J. D. Woodard Executive Vice President

Southern Nuclear Operating Company. Inc. 40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201

Tel 205.992.5086

SOUTHERN k

COMPANY Energy to Serve Your World'

July 23, 2001

LCV- 1545

Docket No.: 50-425

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555

Ladies and Gentlemen:

VOGTLE ELECTRIC GENERATING PLANT INSERVICE INSPECTION SUMMARY REPORT

Southern Nuclear Operating Company (SNC) submits herein the "Owner's Report for Inservice Inspections (Form NIS-1)" for inservice inspection activities conducted at

Vogtle Electric Generating Plant, Unit 2 (VEGP-2) during its Spring 2001 maintenance/refueling outage. Paragraph IWA-6230 of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, 1989 Edition, requires submittal of the enclosed report. The supporting documentation, e.g., examination records, equipment and material certifications, etc., from which the enclosed "Owner's Report for Inservice Inspections (Form NIS-1)" was compiled is

available for review upon request at the plant site.

In addition, "Owner's Reports for Repair and Replacements (Form NIS-2)" are included in the enclosed report for repairs and/or replacements of piping and components that were documented and completed at VEGP-2 from the end of the previous maintenance/refueling outage (Fall 1999) through the Spring 2001

maintenance/refueling outage. Any attachments, e.g., code data reports, etc., that are referenced in the completed NIS-2 forms will be made available for review upon request at the plant site.

A discussion on the examination of steam generator tubes performed during the Spring 2001 maintenance/refueling outage is included in the enclosed VEGP-2 "Owner's Report for Inservice Inspections (Form NIS-1)." That discussion constitutes the report required by VEGP Technical Specification 5.6.10.b to be submitted to the NRC within 12 months following completion of the steam generator

U. S. Nuclear Regulatory Commission LCV- 1545 Page Two

tube examinations. As a result, a separate submittal will not be made to the NRC on steam generator tubes examined during the subject outage.

None of the steam generator tubes required plugging as a result of the examinations performed during the Spring 2001 maintenance/refueling outage at VEGP-2. Pursuant to the requirements of VEGP Technical Specification 5.6.10.a, a report was submitted to the NRC within 15 days of the completion of the steam generator tubing examinations and indicated that none of the steam generator tubes required plugging during the subject outage. SNC letter LCV-1536 dated May 2, 2001, transmitted the VEGP Technical Specification-required 15-day report to the NRC.

In addition to components already identified in current requests for relief, seven (7) Class 1 and 2 piping and equipment welds had limited volumetric examination coverage. The affected welds included the following:

Class 1 Equipment - Reactor Coolant System 21201-V6-002-W17 - Pressurizer (PZR) Safety Nozzle-to-Safe End, 21201-V6-002-W18 - PZR Safety Nozzle-to-Safe End, 21201-V6-002-W19 - PZR Safety Nozzle-to-Safe End, and 21201-V6-002-W20 - PZR Relief Nozzle-to-Safe End.

Class 1 Piping - Reactor Coolant System 21201-058-7 - 6" Elbow-to-Flange.

Class 2 Piping - Containment Spray System 21206-005-1 - 8" Flange-to-Pipe, and 21206-006-1 - 8" Flange-to-Pipe.

Physical limitations due to the geometric configuration of the welded area prevented full ultrasonic examination coverage for each of the affected welds. As a result of the physical limitations, the examination coverage was limited to less than ninety percent (<90%). ASME Section XI Code Case N-460, as approved by the NRC in NRC Regulatory Guide 1.147, allows Code acceptance when the reduction in examination coverage is less than ten percent (<10%). Each of the welds identified above was examined using surface means, e.g., liquid penetrant, and the Code-required surface examination coverage was achieved. Because it is impractical to achieve the Coderequired volumetric examination coverage for the affected welds due to the geometric configuration of the welded areas, request(s) for relief from the ASME Section XI Code requirements will be submitted to the NRC, as allowed by 10 CFR 50.55a, for review and approval.

U. S. Nuclear Regulatory Commission LCV-1545 Page Three

In addition to the inservice inspection of Class 1, 2, and 3 components and supports

during the VEGP-2 Spring 2001 maintenance/refueling outage, Class MC (IWE) and

CC (IWL) containment examinations and tests were performed prior to and/or during

the subject outage in response to the September 9, 1996, NRC rulemaking to 10 CFR

50.55a. That rulemaking invoked the requirements of Subsections IWE and IWL to

the 1992 Edition of ASME Section XI with 1992 Addenda (as amended by the NRC).

The containment examinations and tests performed during the VEGP-2 Spring 2001

maintenance/refueling outage were performed in accordance with the requirements of

the 1992 Edition of ASME Section XI with 1992 Addenda (as amended by the NRC)

except where relief has been granted by the NRC. They were performed by either

SNC or vendor personnel and included, but were not limited to, the containment liner

plate general visual examination, tendon tests, containment concrete examinations,

and examinations of bolting, seals, and gaskets of disassembled components. Details

on the examinations and tests performed, conditions observed, and their resolution are

provided in the enclosed "Owner's Report for Inservice Inspections." The Class MC

and CC containment examinations and tests required by the rulemaking to 10 CFR

50.55a to be completed by September 9, 2001, were completed during the VEGP-2 Spring 2001 maintenance/refueling outage.

The signed original and four copies of the "Owner's Report for Inservice Inspections

(Form NIS-1)" for ISI activities conducted during the Spring 2001

maintenance/refueling outage at VEGP-2 are provided for your review. Two copies

of the subject report are being provided to the Regional Administrator for NRC Region II.

Should there be any questions in this regard, please contact this office.

Sincerely,

J. D. Woodard

JDW/JAE/

Enclosure: "Owner's Report for Inservice Inspections (Form NIS-1)" for VEGP-2 Eighth Maintenance/Refueling Outage (2R8), Spring 2001

U. S. Nuclear Regulatory Commission LCV-1545 Page Four

xc: Southern Nuclear Operating Company Mr. J. B. Beasley, Jr. (w/o enclosure) Mr. J. T. Gasser (w/o enclosure) Mr. M. Sheibani (w/enclosure) SNC Document Management (w/enclosure)

U. S. Nuclear Regulatory Commission Mr. R. R. Assa, Project Manager, NRR (w/o enclosure) Mr. L. A. Reyes, Regional Administrator (w/ 2 enclosures) Mr. J. Zeiler, Senior Resident Inspector (w/enclosure)

Vogtle Electric Generating Plant Unit 2

Eighth Maintenance/Refueling Outage (2R8) Owner's Report for Inservice Inspection

Southern Nuclear Operating Company the southern electric system

OWNER'S REPORT FOR INSERVICE INSPECTIONS

for the

EIGHTH MAINTENANCE/REFUELING OUTAGE

of

VOGTLE ELECTRIC GENERATING PLANT, UNIT 2 (7821 River Road, P. 0. Box 1600, Waynesboro, Georgia 30830)

COMMERCIAL OPERATION DATE: May 20, 1989

DOCUMENT COMPLETION DATE: June 2001

Prepared by

SOUTHERN NUCLEAR OPERATING COMPANY (40 Inverness Center Parkway, P. O. Box 1295, Birmingham, Alabama 35201)

as LICENSEE AND OPERATING AGENT

for

GEORGIA POWER COMPANY (241 Ralph McGill Boulevard, N.E., P. O. Box 4545, Atlanta, Georgia 30308-3374)

as OWNER

TABLE OF CONTENTS Page

Introduction 1-1

ASME Form NIS-1 with Abstract - ASME Class 1 and 2 2-1

ASME Class 3, MC, and CC Examinations and Tests 3-1

Augmented Inspections 4-1

Examination Summary Listings

Introduction to Summary Listings 5-1

ASME Class 1

Equipment Examinations 6-1 Piping Examinations 7-1

ASME Class 2

Equipment Examinations 8-1 Piping Examinations 9-1

Supports

Introduction and Equipment Support Examinations 10-1 Introduction and Piping Support Examinations 11-1

Snubber Functional Examinations

Introduction to Snubber Functional Testing and Results 12-1

Pressure Tests 13-1

Indication Notification Forms 14-1

NIS-2 Forms 15-1

i

LIST OF ABBREVIATIONS

ACC Acceptable AD Anchor/Darling AFW Auxiliary Feedwater System Al GPC Action Item (followed by unique no. denoting Action Item number) ANII Authorized Nuclear Inservice Inspector ASME American Society of Mechanical Engineers ASNT American Society for Nondestructive Testing ASTM American Society for Testing and Materials BC Branch Connection CCSS Centrifugally Cast Stainless Steel CCW Component Cooling Water CE Combustion Engineering CH Closure Head CR Condition Report CS Containment Spray CVCS Chemical and Volume Control System DS Downstream ET Eddy Current Examination EVAL Evaluation FAC Flow-Accelerated Corrosion (may also be referred to as "erosion/corrosion") FB Flange Bolting FNR FAC Notification Report FW Feedwater System FSAR VEGP Final Safety Analysis Report (includes updates thereto) GEO Geometric Indications GPC Georgia Power Company HHSI High Head Safety Injection HL Hanger Lug HX Heat Exchanger HYD Hydraulic Snubber IEN NRC Information Notice (may also be shown as "IN" followed by unique no. denoting notice

number) ILRT Integrated Leakage Rate Test IND Indication INF Indication Notification Form ISI Inservice Inspection IST Inservice Testing ID Inside Diameter IR Inside Radius LB Large Bore LD Longitudinal Seam Weld Extending Downstream LD-I Longitudinal Seam Weld Downstream Inside of Elbow LLRT Local Leakage Rate Test LMT Lambert, MacGill and Thomas LU Longitudinal Seam Weld Extending Upstream LU-O Longitudinal Seam Weld Upstream on Outside of Elbow MECH Mechanical Snubber MS Main Steam System MT Magnetic Particle Examination NCI Nonconformance Item NDE Nondestructive Examination

ii

LIST OF ABBREVIATIONS - (continued)

NI NRC NRC-B NRI NSCW OR PL PM PR PROF PS PSA PSI PT RCS RCP RHR RI RLW RL RPV RR RWST SAT "SB SCS SI SSI SNC SUP T&C TDAFW TS UNSAT US UT VEGP

VT W

iii

No Indication United States Nuclear Regulatory Commission NRC Bulletin (followed by unique no. denoting Bulletin number) No Recordable Indication Nuclear Service Cooling Water System Outside Radius Pipe Lug Paul-Munroe ENERTECH Pipe Restraint Profile Pipe Support Pacific Scientific Preservice Inspection Liquid Penetrant Examination Reactor Coolant System Reactor Coolant Pump Residual Heat Removal System Recordable Indication Refracted Longitudinal Wave Restraint Lug Reactor Pressure Vessel Relief Request (followed by unique no. denoting relief request number) Refueling Water Storage Tank Satisfactory Examination Results Small Bore Southern Company Services Safety Injection System Sonics Systems International Southern Nuclear Operating Company Supplemental Data Thickness and Contour Turbine Driven Auxiliary Feedwater (Pump) VEGP Technical Specification Unsatisfactory Examination Results Upstream Ultrasonic Examination Vogtle Electric Generating Plant (common unless followed by "-1" or "-2" to designate a specific plant unit) Visual Examination Westinghouse

INTRODUCTION

This report documents the examinations and tests performed at Vogtle Electric Generating Plant, Unit 2 (VEGP-2) between November 3, 1999 (date of last examination performed during the seventh maintenance/refueling outage, 2R7) and May 1, 2001 (date of last examination performed during the eighth maintenance/refueling outage, 2R8) to meet the requirements of Article IWA-6000 of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, 1989 Edition (Code). In addition, a sunmmary of the following augmented examinations are included in this report:

"* VEGP Technical Specification 5.5.9 - Steam Generator Tube Inspections,

"* VEGP Technical Requirement 13.7.2 - Snubber Visual Inspections and Functional Tests,

"* United States Nuclear Regulatory Commission (NRC) Bulletin 88-09 - Thimble Tube Thinning in Westinghouse Reactors,

"* Westinghouse Technical Bulletin NSD-TD-90-02 - BMI Conduit Guide Tube Leaks,

"* GPC Action Item 87-0131 - Cracking in Stagnant Borated Water Piping Welds, and

"* Balance of Plant Examinations for Flow-Accelerated Corrosion.

This report also addresses Code-applicable repairs and/or replacements, which were documented since the last maintenance/refueling outage at VEGP-2 through the completion of the eight maintenance/refueling outage in May 2001. The Owner's Reports for Repairs and Replacements (Forn NIS-2) are included herein.

In addition to the examination of Class 1, 2, and 3 piping and components and other components, e.g., flux thimble tubes, as an "augmented" scope, Class MC and CC components associated with containment were also examined. These examinations were performed in accordance with the requirements of the 1992 Edition of ASME Section XI with 1992 Addenda (as amended by 10 CFR 50.55a) except where relief has been granted by the NRC. These examinations were performed in response to the rulemaking to 10 CFR 50.55a that became effective September 9, 1996 (Ref. Federal Register Notice 61 FR 41303).

1-1

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules

1. Owner: Georgia Power Company, 241 Ralph McGill Blvd., N. E. P. 0. Box 4545, Atlanta, Georgia 30308-3374

2. Plant: Vogtle Electric Generating Plant, 7821 River Road P. 0. Box 1600, Waynesboro, Georgia 30830

3. Plant Unit: Two

4. Owner Certification of Authorization: N/A

5. Commercial Service Date: May 20, 1989

6. National Board Number for Unit: N/A

7. Components Inspected:

Component or Manufacturer or Manufacturer or Installer State or Province National Board Appurtenance Installer and Address Serial Number Number Number Reactor Combustion Eng. 7372 N/A 22004 Pressure Vessel Inc.,

Chattanooga, TN

Steam Westinghouse Elec., GBGT 1984 (S/N 77743), N/A 36, Generators 1, 2 Tampa, FL GBGT 1983 (S/N 77745), 35, and 3, GBGT 1982 (S/N 77742) 34 respectively

Pressurizer Westinghouse Elec., 77749 N/A 24 Pensacola, FL

Selected Piping, Pullman Power 1201, 1204 & 1206 N/A N/A Components, Products, and Supports Williamsport, PA

2-1

FORM NIS-I (Back)

8. Examination Dates: November 3, 1999 to May 1, 2001

9. Inspection Period Identification: First Period of Second Inspection Interval

10. Inspection Interval Identification: Second Inspection Interval

11. Applicable Edition of Section XI 1989 Addenda None

12. Date/Revision of Inspection Plan: February 28, 2001 / Revision 4

13. Abstract of Examinations and Tests. Include a list of examinations and tests and a statement concerning status of work required for the Inspection Plan. (See Abstract and Examination Summary Listings)

14. Abstract of Results of Examinations and Tests. (See Abstract)

15. Abstract of Corrective Measures. (See Abstract)

We certify that a) the statements made in this report are correct, b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section XI, and c) corrective measures taken conform to the rules of the ASME Code, Section XI.

Certificate of Authorization No. (if applicable) N/A Expiration Date N/A

Date: gL _ 20.04 Signed: Southern Nuclear Operating By: Company, Inc. for

Georgia Power Company Owner

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Georgia and employed by The Hartford Steam Boiler Inspection and Insurance Company of One State Street, Hartford, CT 06102 have inspected the components described in this Owner's Report during the period November 3, 1999, to May 1, 2001, and state that to the best of my knowledge and belief, the Owner has performed examinations and tests and taken corrective measures described in this Owner's Report in accordance with the Inspection Plan and as required of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, tests, and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

/•_7 Commission: 6A 203 "InspecrsSnature National Board, State, Province, and Endorsements

Date: e. - -7 9 200/

2-2

ABSTRACT - ASME CLASS 1 AND 2

Introduction/Status

The ASME Boiler and Pressure Vessel Code, Section XI, 1989 Edition (Code), is the applicable code for conducting inservice inspection activities during the second ten-year inspection interval at VEGP-2. Examinations and tests required by the Code are scheduled in accordance with "Inspection Program B" as defined in Code paragraphs IWB2412 and IWC-2412. This "Owner's Report for Inservice Inspection" is for those first inspection period examinations and tests which were performed between November 3, 1999 (date of last examination performed during the seventh maintenance/refueling outage, 2R7) and May 1, 2001 (date of last examination performed during the eighth maintenance/refueling outage, 2R8). The Code required percentage of examinations and tests scheduled for the first inspection period were completed during 2R8.

By Federal Register Notice 64 FR 51370 dated September 22, 1999, 1OCFR50.55a(g)(6)(ii)(C), Implementation of Appendix VIII to ASME Section XI, was incorporated into the rule to expedite implementation of Appendix VIII. The Supplements of Appendix VIII of Section XI, ASME Boiler and Pressure Vessel Code, 1995 Edition with the 1996 Addenda, have been implemented in accordance with the applicable schedule.

In addition to the summary of inservice inspection activities, this report addresses Code-applicable repairs and replacements documented at VEGP-2 since 2R7 through the end of 2R8. The Owner's Reports for Repairs or Replacements (Form NIS-2) are provided herein.

It should be noted that Authorized Nuclear Inservice Inspector (ANII) inspection services were provided for those examinations and tests required by the Code. ASME Section XI examinations and tests are itemized in the applicable sections by reference to Examination Category. Examinations that do not meet the Code-required coverage either reference request(s) for relief or indicate that additional relief is required.

Class I Examinations

Selected Class 1 components were examined by Southern Nuclear Operating Company (SNC) personnel utilizing ultrasonic testing (UT), dye penetrant testing (PT), magnetic particle testing (MT), and visual testing (VT) methods, as applicable. Specific components and examination areas are itemized in the applicable portions of this document. A summary of those components examined are listed below:

"* Steam Generator Inner Radii, "* RPV Closure Head, "* RPV Closure Head Studs, Nuts and Washers, "* Pressurizer Shell, Nozzle and Safe-End Welds, "* Piping Welds, and "* Valve and Piping Flange Bolting.

During the scope of VEGP-2 examinations conducted, no Class 1 components were observed to have either reportable ultrasonic, liquid penetrant, magnetic particle or visual indications.

In addition to components already identified in current requests for relief, one piping weld and four equipment welds had limited volumetric coverage during ultrasonic examinations because of physical limitations due to the geometric configuration of the welded areas. In order for adequate ASME Section XI Code-required examination coverage to be attained, more than ninety percent (90%) of the required volume must be examined as addressed in ASIMIE Code Case N-460. The subject code case has been approved for use in NRC Regulatory Guide 1.147. It is impractical to achieve the ASME Section XI Code-required volumetric examination coverage due to the geometric configuration of the welded area. Relief from the ASME Section XI Code requirements will be requested from the NRC for the affected welds through the relief request process as allowed by 10 CFR 50.55a. The applicable welds are indicated

2-3

by "Relief Request Required" in the Class 1 weld tables. Each of the affected welds was examined using surface means, e.g., liquid penetrant, and the Code-required surface examination coverage was achieved.

The Eddy Current (ET) examinations of steam generator tubing, as required by VEGP Technical Specification 5.5.9, were performed by Westinghouse and are discussed in the "Augmented Examinations" portion of this document.

Class I Pressure Test

Table IWB-2500-1, Examination Category B-P, of ASME Section XI requires the performance of-a system leakage

test (IWB-5221) each maintenance/refueling outage. This system leakage test (LT-1) was performed prior to plant

startup following the maintenance/refueling outage. These visual examinations revealed minor leakage and boron

residue at mechanical connections and one through-wall pressure boundary leak. These leakage conditions were corrected.

The one through-wall pressure boundary leak was located on the leak-off line (3/8 inch diameter) of valve 2HV8701B. Design Change Package (DCP) 00-V2N0017 was implemented during the 2R8 maintenance/refueling

outage. This DCP utilized the existing leak-off connection near the bonnet connection of valve 2HV8701B and routed it to the existing thermal bypass line (3/4 inch diameter). The purpose of the design change was to route the

leak-off line to the existing bypass line in such a manner that this flowpath could be used to preclude the potential

for pressure-locking of double disk gate valve 2HV8701B. In order to correct this leakage condition, valve 2HV8701B was repacked with packing below the leak-off line and the piping installed by the DCP was removed.

Subparagraph IWA-5242(a) of ASME Section XI requires removal of insulation from pressure-retaining bolted

connections for VT-2 examination during system pressure testing for systems borated for the purposes of controlling

reactivity. Relief was requested (Ref.: Request for Relief RR-26) from this Code requirement and subsequently approved as documented by NRC letters dated October 24, 1997, for Class 1 components and December 31, 1998, for Class 2 and 3 components. The approved alternative allows insulation to be removed and connections to be

examined while they are at atmospheric or static pressures. With the insulation removed a direct visual examination is performed to detect previously occurring leakage through the presence of boric acid crystals.

The test boundary of the system leakage test includes both Class I and Class 2 components. The Class 2 components

comprise part of the reactor coolant pressure boundary but are not required to be classified as Class 1 per

1OCFR50.55a(c)(2). The frequency for removal of insulation and direct visual examination for Class 1 pressureretaining bolted connections is once each refueling outage (refer to Table IWB-2500-1, Exanmination Category B-P)

and, as such, those activities occurred during the 2R8 maintenance/refueling outage.

The frequency for removal of insulation and direct visual examination for Class 2 pressure-retaining bolted

connections is once each inspection period (refer to Table IWC-2500-1, Examination Category C-H). For the first inspection period those activities were scheduled and performed either before or during the seventh maintenance/refueling outage (2R7).

Class 2 Examinations

Selected Class 2 components were examined utilizing MT, PT, and UT, as applicable. Specific components and

examination areas are itemized in the applicable portions of this report document. A summary of those components

examined are listed below:

"• Steam Generator Nozzle Welds, and "• Piping Welds.

During the scope of VEGP-2 manual examinations conducted, no Class 2 components were observed to have either "reportable ultrasonic, liquid penetrant, or magnetic particle indications.

2-4

In addition to components already identified in current requests for relief, two piping welds had limited volumetric coverage during ultrasonic examinations because of physical limitations due to the geometric configuration of the welded areas. In order for adequate ASME Section XI Code-required examination coverage to be attained, more than ninety percent (90%) of the required volume must be examined as addressed in ASMIE Code Case N-460. The subject code case has been approved for use in NRC Regulatory Guide 1.147. It is impractical to achieve the ASME Section XI Code-required volumetric examination coverage due to the geometric configuration of the welded area. Relief from the ASME Section XI Code requirements will be requested from the NRC for the affected welds through the relief request process as allowed by 10 CFR 50.55a. The applicable welds are indicated by "Relief Request Required" in the Class 2 weld tables. Each of the affected welds was examined using surface means, e.g., liquid penetrant, and the Code-required surface examination coverage was achieved.

Class 2 Pressure Tests

Table IWC-2500-1, Examination Category C-H, of ASME Section XI requires system pressure testing each inspection period. The specific system pressure tests performed are itemized in the "Pressure Tests" portion of this report document. The visual examinations performed during these system pressure tests found only minor leakage at mechanical joints such as valve stem packing and at flanged connections. These leaks were either corrected or evaluated and determined acceptable for continued system operation.

Subparagraph IWA-5242(a) of ASME Section XI requires removal of insulation from pressure-retaining bolted connections for VT-2 examination during system pressure testing for systems borated for the purposes of controlling reactivity. Relief was requested from this Code requirement and subsequently approved as documented by NRC letters dated October 24, 1997, for Class 1 components and December 31, 1998, for Class 2 and 3 components. The approved alternative allows insulation to be removed and connections to be examined while they are at atmospheric or static pressures. With the insulation removed a direct visual examination is performed to detect previously occurring leakage through the presence of boric acid crystals. This approved alternative was implemented on applicable pressure-retaining bolted connections.

Class 1 and 2 Component Supports

No examinations were scheduled nor performed during the 2R8 maintenance/refueling outage.

2-5

ASME CLASS 3. MC. AND CC EXAMINATIONS AND TESTS

"Class 3 Supports and Integral Attachments

No examinations were scheduled nor performed during the 2R8 maintenance/refueling outage.

Class 3 Pressure Tests

No Class 3 Pressure Tests were scheduled nor performed during the 2R8 maintenance/refueling outage.

Class MC Containment Examinations and Tests (IWE)

Category E-A, Containment Surfaces

During the VEGP-2 Spring 2001 maintenance/refueling outage, containment examinations were performed in response to the NRC rulemaking to 10 CFR 50.55a in which the requirements of Subsections IWE and IWL to the

1992 Edition of ASME Section XI with 1992 Addenda were invoked. A general visual examination of the VEGP-2

containment liner, a Class MC component as defined in Subsection IWE to the Code, was performed by SNC

personnel during the outage. The examination was performed using VEGP procedure 84303-C, Revision 0, "Containment Liner General Visual Examination". Personnel performing the general visual examination of the

containment liner plate were qualified in accordance with VEGP procedure 85001-C, Revision 10, "Qualification of

Inspection, Examination, and Testing Personnel". The examination was performed under the guidance of a

Registered Professional Engineer. Optical aids such as flashlights and binoculars were used when performing the general visual examination that included both direct and indirect, i.e., remote, visual examination methods.

One hundred thirty-five anomalies were identified during 2R8 and were recorded on an Anomaly Data Sheet as

"required by procedure 84303-C. That procedure defines an anomaly as a deviation or departure from the normal or

common order, form, or rule with evidence of degradation that may affect either the containment structural integrity

or leak tightness. The VEGP-2 containment liner was examined for evidence of flaking, blistering, peeling, discoloration, cracking, wear, pitting, excessive corrosion, arc strikes, gouges, surface discontinuities, dents, and

other signs of surface irregularities and distress. Of these anomalies, there were twenty-six indications of rust, forty

eight indications of bare metal, twelve indications of depressions, and forty-nine indications of arc strikes were observed. All anomalies were evaluated as cosmetic in nature only and not affecting the structural integrity of the containment liner plate. SCS letter SG-18218 dated February 28, 2001, provided an "Engineering Evaluation" as allowed by the ASME Section XI Code. That letter, which is available at the plant site for review upon request, provides the justification for evaluation of arc strike areas that meet specific thickness criteria from the inspection and repair requirements referenced in section 1.9.94 of the updated VEGP FSAR.

Category E-B, Pressure-Retaining Welds

The rulemaking contains a modification that makes examinations of Subsection IWE, Category E-B optional. SNC has chosen to not examine category E-B welds at VEGP.

Category E-C, Containment Surfaces Requiring Augmented Examination

Any surface areas likely to experience accelerated degradation and aging, should such areas exist, need to be

identified. Such areas (if identified) require the performance of augmented examinations as defined in Examination

Category E-C. There are no existing areas in VEGP-2 requiring Category E-C examination.

Category E-D, Seals, Gaskets, and Moisture Barriers

The rulemaking contains a modification that makes examinations of Subsection IWE, Category E-D optional. SNC

has chosen to implement Request for Relief (RR)-E-1 to allow leak tightness to be verified by 10 CFR 50, Appendix

3-1

J Type B testing (LLRT). The NRC approved SNC's use of RR-E-1 in its June 16, 2000, letter to SNC. The Type B test results, along with the Type C test results, will be reported to the NRC in the Integrated Leakage Rate Test (Type A test) report as required by 10 CFR 50 Appendix J.

Category E-F, Pressure-Retaining Dissimilar Metal Welds

The rulemaking contains a modification that makes examinations of Subsection IWE, Category E-F optional. SNC has chosen to not examine category E-F welds at VEGP.

Category E-G, Pressure-Retaining Bolting

One hundred percent (100%) of the accessible containment boundary and pressure-retaining bolting (bolts and studs) are to be examined during the interval using a VT-1 examination method. All of the visible surfaces are required to be examined when the bolting is not disassembled. Approximately 34% of the penetration bolting listed in Table 2.2 of the VEGP Containment Inservice Inspection Program Plan was examined during the outage (2R8). These examinations were accomplished using Surveillance 84303-201 and Inspection Report (IR) #24483. The penetrations examined using this IR included the following:

2-1818-H3-P16 2-1818-H3-P10 2-1818-H3-P32 2-1818-H3-P53 2-1818-H3-P15 2-1818-H3-P09 2-1818-H3-P30 2-1818-H3-P49 2-1818-H3-P14 2-1818-H3-P58 2-1818-H3-P56 2-1818-H3-P48 2-1818-H3-P12 2-1818-H3-P57 2-1818-H3-P54 2-1818-H3-P47 2-1818-H3-P46 2-1818-H3-P45 2-1818-H3-P33 2-1818-H3-P31 2-1818-H3-P29

All examinations of the bolting for these twenty-one penetrations were completed with satisfactory results.

All IWE examinations have been completed for VEGP-2 that are required by the rulemaking to 1OCFR50.55a to be completed by September 9, 2001.

Class CC Containment Examinations and Tests (IWL)

During the VEGP-1 and 2 Spring 2000 In-Service Tendon Inspection, containment examinations were performed in response to the NRC rulemaking to 1OCFR 50.55a in which the requirements of Subsections IWE and IWL to the 1992 Edition of ASME Section XI with 1992 Addenda were invoked. The general visual examination of the reinforced concrete and the post-tensioning systems of Class CC components, was performed during the tendon surveillance by a vendor qualified under criteria specified by the 1992 Edition and 1992 Addenda of ASME Section XI. The baseline inspection was conducted per IWL to allow on-going monitoring of the containment condition. The IWL general visual inspection was performed under the guidance of a Registered Professional Engineer. Light meters, flashlights, feeler gauges, and an optical comparator were used when performing the general visual examination that included both direct and indirect visual examination methods. The subject examination was repeated during VEGP-2 Outage 2R8 because the visual examination of the concrete containment was not performed "during a refueling outage" as required by NRC Regulatory Guide 1.163.

During the visual examination, two conditions were noted that required an engineering evaluation from SCS. It was necessary for SCS to determine if the conditions would require a detailed inspection. The first condition was an indication of metal exposure, which was later determined to be rebar-chairs, a support used to hold rebar in place while the concrete is being poured. The second concern was the areas of spalling on the edge of the containment buttresses. SCS letter SG-16802 dated March 5, 1999, provided an Engineering Evaluation Report as described in

IWL-3300 for two concrete spalls and also included the initial concrete repair procedure for these two areas. Spall is

defined as a fragment, usually in the shape of a flake, detached from a larger mass by a blow, by the action of

weather, pressure or expansion within the large mass. SCS' response was documented in their letter SG-17640 dated

May 25, 2000, to SNC. It was noted that both indications were non-structural in nature and had no considerable effect on the structural integrity of containment.

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During the containment concrete examinations, inclusive of tendon testing, and in response to lOCFR50.55a(b)(2)(ix), the following information is provided by SNC:

No adverse conditions were identified during the examination and test of the containment concrete, including tendons, which involve the additional requirements of 1OCFR50.55a(b)(2)(ix), Paragraphs A, B, C, and E. With regard to lOCFR50.55a(b)(2)(ix), Paragraph D, there were areas identified where grease leakage was observed on the containment concrete surfaces. A detailed examination was performed by the test vendor and is included in its final report submitted to SNC. That report is available for review upon request at the VEGP plant site. The amount of grease leakage observed was less than the excessive grease leakage reporting threshold value of seven (7) gallons as specified in Enclosure 2 to SNC letter LCV-1307 dated April 5, 1999, that was submitted to the NRC for review and approval. The subject document requested relief from the regulatory requirements of 10CFR50.55a(b)(2)(ix), Paragraphs A and D, relative to the reporting of grease leakage to the NRC in the "ISI Summary Report", otherwise referred to as the "Owner's Report for Inservice Inspection (Form NIS-1)". Excessive grease leakage, i.e., grease leakage in excess of 7 gallons, as it pertains to VEGP is reported to the NRC pursuant to the requirements of VEGP Technical Specification 5.6.9. The NRC reviewed and approved the SNC request for relief pertaining to the reporting of grease leakage and was documented in its June 16, 2000, letter to SNC. Based on the foregoing information, reporting of excessive grease leakage is not required to be addressed in this report due to the NRC approval of the SNC request for relief. No report was filed in response to VEGP Technical Specification 5.6.9 since the observed grease leakage was less than 7 gallons. The actual leakage observed during the VEGP-2 containment concrete examination was 89 ounces (0.70 gallons).

All IWL examinations have been completed for VEGP-2 that are required by the rulemaking to 10CFR50.55a to be completed by September 9, 2001.

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AUGMENTED INSPECTIONS

VEGP Technical Requirements Manual - TR 13.7.2 Snubbers

Visual Inspections

VEGP Technical Requirements Manual (TRM) Technical Requirement (TR) 13.7.2, Technical Requirement Surveillance (TRS) 13.7.2.1 requires each snubber to be visually examined. During the VEGP-2 seventh maintenance/refueling outage, (2R7), one of the snubbers that comprise the total snubber population was found to have unsatisfactory visual examination results. Based upon Table 13.7.2-2, Note 3 in the VEGP TRM, the next visual examination interval remains 36 months, which coincides with the performance of the visual examinations being required during the VEGP-2 ninth maintenance/refueling outage (2R9). Therefore, visual examination of snubbers was not required during the eighth VEGP-2 maintenance/refueling outage (2R8).

Functional Testing

VEGP TR 13.7.2, TRS 13.7.2.3 also requires functional testing of snubbers. The snubbers were categorized into six types as follows:

Type I Pacific-Scientific mechanical snubbers (Models PSA-1/4 and PSA- 1/2) Type II Pacific-Scientific mechanical snubbers (Models PSA-1, PSA-3, and PSA-10) Type III Pacific-Scientific mechanical snubbers (Model PSA-35 and PSA-100) Type IV Anchor/Darling mechanical snubbers (Model series AD-40 through AD-500) Type V Anchor/Darling mechanical snubbers (Model series AD-1600 through AD-12500) Type VI Paul-Munroe ENERTECH 1000 kip steam generator hydraulic snubbers.

Each snubber type was functionally tested utilizing a test plan (as detailed in VEGP TRM 13.7.2.3 in accordance with Table 13.7.2-4) which requires that an initial representative random sample of ten percent (10%) of the population to be functionally tested. The result of the functional testing of the snubber types is as follows:

Snubber Type I II HI IV V VI Total Total Population 21 59 26 236 111 8 461 10% Initial Representative Sample 3 6 3 24 12 1 49 Quantity Failed in Previous Outage 4 0 0 1 1 * 0 6 Total Original Outage Test Scope 7 6 3 25 13 1 55 Total Tested Which Passed Acceptance Criteria 8 6 3 26 35 1 79 Total Tested Which Failed Acceptance Criteria 0 1 0 0 2 0 3 Expanded or Additional Snubbers Tested during Outage 1 1 0 1 24 0 27 (Details Provided Below) Total Tested 8 7 3 26 37 1 82

Expanded or Additional Snubbers Tested during Outage

Type I Scope increased by one due to visually observed condition at 2-1201-239-HOOI. Type II Scope increased by one due to location adjacent to Type V failed snubber

2-1301-015-H004. Type III There were no scope additions for this type snubber. Type IV Scope increased by one due to visually observed condition at 2-1301-168-H012. Type V *Scope increased by one due to Condition Report (CR) #1999001715 identified during 2R7. Scope

increased by twelve due to failure of Type V snubber 2-1301-015-H004 and one additional Type II due to location adjacent to failed snubber. Scope increased by twelve due to failure of 2-1301-106H005.

Type VI There were no scope additions for this type snubber.

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Functional Test Failure Analysis

In accordance with VEGP TR 13.7.2, Table 13.7.2-4, paragraph 4, engineering evaluations were performed by Southern Company Services (SCS) for the one (1) Type II snubber and the two (2) Type V snubbers that failed functional testing. The engineering evaluations were performed in order to determine the cause(s) of the failures and to determine if the piping systems to which the failed snubbers were attached were adversely affected. The affected piping systems to which the failed snubbers were attached were returned to their approved design configuration by replacing the failed snubbers with known operable snubbers. The following is a listing of snubbers and the correspondence associated with the engineering evaluations that are available at the plant site for review upon request.

Type Affected Snubber(s) Applicable SCS Evaluation Letter/Date Condition Report Number V 2-1301-015-H004 SG-18366, 04/10/2001 2001000714 II 2-1301-094-H002 SG-18410, 04/26/2001 2001000979 V 2-1301-106-H005 SG-18414, 04/26/2001 2001000986

The specific Types I through VI snubbers that were functionally tested in response to VEGP TR 13.7.2 are itemized in the Snubber Functional Testing Listings of this report document.

GPC Action Item No. 87-0131 - Stagnant Borated Water Systems Cracking

As a result of generic concerns of pipe cracking in stagnant borated water systems in pressurized water reactors, several welds in Class 2 piping systems were examined in response to GPC Action Item No. 87-0131. Nondestructive examination methods utilized included ultrasonic and/or liquid penetrant examination techniques. "Welds were examined in the Safety Injection and Containment Spray systems. No reportable indications were observed.

The examinations are itemized in the Class 2 Piping section of this report.

Balance of Plant Examinations For Flow-Accelerated Corrosion

Ultrasonic thickness examinations were performed on selected components (fittings, piping, and equipment) in the Condensate, Heater Drain, Heater Vent, Main Feedwater, Turbine Drain, Main Steam, Steam Generator Blowdown, Extraction Steam, and Turbine Drive Steam systems. In all, seventy-one (71) large-bore components were ultrasonically examined during the 2R8 maintenance/refueling outage. Of the seventy-one large-bore components ultrasonically examined, twenty-six (26) were due to the re-examination of previously examined components and forty-five (45) were examined for the first time. In addition, twenty-one (21) small-bore (<2" NPS) ultrasonic examinations were performed on selected portions of small-bore pipe lines and visual examinations were performed on the inside surface of two (2) drain tanks. The ultrasonic examination of large and small-bore components was performed using SNC procedure UT-V-466, Rev. 6, "Ultrasonic Flow-Accelerated Corrosion Examination Procedure". The visual examination of the two drain tanks was performed using SNC procedure VT-V-715, Rev. 2, "Visual Examination (VT-1)".

Eighteen (18) large-bore components were identified to have wall thickness measurements that indicated possible wear due to flow-accelerated corrosion (FAC). The affected components had wall thickness readings that were at or below the "Action Level" wall thickness value assigned to each of the components. The "Action Level" value is defined as the wall thickness which is fifty percent (50%) of the difference between the nominal wall and Code minimum wall. The examination results for sixteen of these large-bore components were reported by SNC Inspection and Testing Services (ITS) to VEGP Engineering Support by means of FAC Notification Reports (FNRs) which are available at the plant site for review. One FNR was subsequently determined to not be required due to the

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component not actually being below its "Action Level" value. The examination results of the other two below "Action Level" components were reviewed by the site FAC Engineer and it was determined that no FNR was required due to the wall thinning not being significant. SCS engineering personnel were requested by the site FAC Engineer to perform an expedited evaluation to determine the continued acceptability of each below "Action Level" component for which an FNR had been initiated. The continued acceptability of small-bore components was determined by the site FAC Engineer. The following is a listing of correspondence associated with the engineering evaluations that are available at the plant site for review upon request:

Affected Component FNR Number/Date SCS Eval. Letter No./Date Type and System 21304031-14-P014 F01V2001, SG-18362, 14" Pipe Section, 04/10/01 04/11/01 Heater Drain System 21304004-12-R032HD28 F01V2002, SG-18373, 6"xl2" Expander, 04/10/01 04/13/01 Heater Drain System 21304123-12-R034 F01V2003, SG-18373, 6"xl 2" Expander, 04/10/01 04/13/01 Heater Drain System 21305-E4-021 F01V2004, SG-18380, 6A FW Heater Shell Wall 04/11/01 04/14/01 Main Feedwater System 21305-E4-022 F01V2005, SG-18380, 6B FW Heater Shell Wall 04/11/01 04/14/01 Main Feedwater System 21305055-16-POll F01V2006, SG-18381, 16" Pipe Section, 04/12/01 04/20/01 Main Feedwater System 21304031-14-POlO F01V2007, SG-18386, 14" Pipe Section, 04/13/01 04/19/01 Heater Drain System 21304031-14-P006 F01V2008, SG-18386, 14" Pipe Section, 04/13/01 04/19/01 Heater Drain System 21305547-34-P017 F01V2009, SG-18391, 34" Pipe Section, 04/17/01 04/20/01 Main Feedwater System 21305055-24-PO07MFW15 FO1V2010, SG-18398, 24" Pipe Section, 04/17/01 04/23/01 Main Feedwater System 21305055-16-EO12MFW17 FO1V2011, SG-18381, 16" Elbow, 04/16/01 04/20/01 Main Feedwater System Downstream Ext. of F01V2012, SG-18391, 21305547-34-E018 04/17/01 04/20/01 34" Elbow, Main Feedwater System Upstream Ext. of F01V2013, SG-18413, 21305055-24-E004 04/20/01 04/26/01 24" Elbow, Main Feedwater System

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Affected Component FNR Number/Date SCS Eval. Letter No./Date Type and System Downstream Ext. of F01V2014, N/A - Determined Not 21304021-30-E029 04/23/01 Below "Action Level" 30" Elbow, Heater Drain System 21305061-16-P018 F01V2015, SG-18412, 16" Pipe Section, 04/23/01 04/24/01 Main Feedwater System Upstream Ext. of F01V2016, SG-18422, 21305547-34-EO20CND18 04/24/01 04/26/01 34" Elbow, Main Feedwater System Downstream Ext. of N/A - FNR Determined Not N/A 21305029-24-R013, Required 30"x24" Reducer, Condensate System 21305157-6-P004, N/A - FNR Determined Not N/A 6" Pipe Section, Required Main Feedwater System

Examination results concerning each of the affected components were evaluated by SCS and it was determined that immediate corrective action was appropriate for two components. Portions of components 21305-E4-021 and 21305-E4-022 (i.e., FW Heaters 6A and 6B Shell Walls) were determined to be below acceptable wall thickness and were subsequently replaced. An additional four of the above components were determined to have significant wear and are being scheduled for replacement during the next maintenance/refueling outage, i.e., 2R9. This includes components 21304004-12-R032HD28, 21304123-12-R034, 21305055-16-POl1, and 21305055-16-EO12MFW17. All other large-bore components were determined to be acceptable for continued service for at least two more fuel cycles and no other corrective action was deemed necessary. In regards to small-bore examination results, five small-bore lines showed signs of wear significant enough to require immediate action during the maintenance/refueling outage. This included portions of four steam drain lines and a feedwater heater vent line. This small-bore piping was subsequently replaced. No other corrective actions were required or taken in regards to Flow-Accelerated Corrosion examinations during the 2R8 outage.

NRC Bulletin 88-09 - Thimble Tube Thinning in Westinghouse Reactors

In response to NRC concerns of thinning in Bottom-Mounted Instrumentation (BMI) flux thimbles in Westinghouse reactors, eddy current examination of the fifty-eight (58) flux thimbles was performed during the eighth maintenance/refueling outage at VEGP-2. The purpose of the examinations was to detect and size indications of possible wear on the outer diameter of the flux thimbles. The examination of the flux thimbles was performed by Westinghouse in accordance with their procedure MP 2.3.1 GAE/GBE-2, "Thimble Tube Eddy Current Inspection at Vogtle Units 1 and 2".

An evaluation was performed by Westinghouse using WCAP-12866, "Bottom Mounted Instrumentation Flux Thimble Wear", on BMI flux thimbles which were found to have indications of wear after the eighth fuel cycle. The evaluation indicates that that the 2R8 data and the projected wear on all thimbles for 2R9 and 2R1 0 is within the allowable limit of 80% specified in WCAP-12866. There was no need for repositioning the flux thimbles or capping at the seal table location.

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In determining the projected wear data for 2R9 and 2R10, the 2R8 values were adjusted up based on the previous data from 2R6 and 2R7. Normally the maximum value of the last 3 cycles is used for this projection, however there were several tubes where the 2R8 data did not correlate with the previous outages. In these instances the larger value from the last two outages that was closest to the 2R8 data was used. This adjustment was performed based on a Westinghouse engineering judgement call.

The evaluation was transmitted to the plant site in Westinghouse letter GP-17252 dated April 25, 2001, for Flux Thimble Eddy Current Data Evaluation and is available at the plant site for review upon request.

Westinghouse Technical Bulletin NSD-TD-90-02 - BMI Conduit Guide Tube Leaks

In accordance with the recommendations in Westinghouse Technical Bulletin NSD-TD-90-02, the BMI conduit (flux thimbles) guide tubes were visually examined for any signs of leakage. The examination was performed by SNC personnel. There were no signs of cracks, pitting, or other signs of degradation to the BMI conduit guide tubes. The inspection was performed under MWO 20002019.

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Technical Specification 5.5.9 - Steam Generator Tube Inspections

NOTE

The following discussion on the steam generator tubing inspections, in addition to fulfilling the reporting requirements of ASME Section XI for Inservice Inspection activities, constitutes the report required by VEGP Technical Specification 5.6.10.b to be submitted to the NRC within twelve (12) months following completion of the steam generator tube inspections. Accordingly, a separate submittal is not being made to the NRC on the inspection of the steam generator tubes performed during the eighth maintenance/refueling outage (2R8) at VEGP-2.

Introduction

During 2R8, the Steam Generator Maintenance Services Group of the Westinghouse Nuclear Services Division performed eddy current testing of two Westinghouse Model F steam generators in parallel from April 18, 2001, through April 24, 2001. One hundred percent (100%) of the active tubes from two steam generators, i.e., Steam Generators 2 and 3, were inspected rather than only one steam generator as required by VEGP Technical Specification Table 5.5.9. The extent of the examinations and their results are summarized in Table I (refer to pages 4-15 to 4-18) including the location and the accumulative number of previously plugged steam generator tubes. Although Steam Generators 1 and 4 were not examined during 2R8, Table I provides information for those steam generators as well.

Tables II & III (refer to pages 4-19 and 4-20) identify the steam generator tubes with indications by location and percent of wall thickness penetration for Steam Generators 2 and 3, respectively. Information is provided only for the steam generators examined during 2R8.

Applicable procedures, personnel qualifications, material and equipment certifications, sign-off sheets, and supporting data, etc., can be found in Westinghouse Electric Company Nuclear Service Division Steam Generator Maintenance Services Field Service Report, MRS-FSR-1091-GBE, "Steam Generator Eddy Current Inspection ", which is available at the plant site for review upon request.

Tube Inspection Plan

Bobbin Inspection Plan

Steam generator tube inspections conducted during 2R8 met or exceeded the recommendations made in the EPRI PWR Steam Generator Examination Guidelines, EPRI TR-107569-V1R5, which were adopted by SNC for steam generator tube inspections. The VEGP inspection plan requires that 100% of the tube population be inspected from two steam generators each outage rather than twenty percent (20%) of the tube population from four steam generators each cycle or forty percent (40%) of the tube population from two steam generators each cycle. This plan offers the advantage of a shorter inspection interval in order to achieve complete steam generator tube inspection and offers an improved sensitivity to degradation mechanisms that might be initiating within a particular steam generator. Each of the tubes examined was tested full length.

Motorized Rotating Pancake Coil (MRPC) Inspection Plan

The inspection program outlined in the VEGP response to NRC Generic Letter 95-03, "Circumferential Cracking of Steam Generator Tubes", was met or exceeded during 2R8. During 2R8, the MRPC inspection plan for Steam Generators 2 and 3 for top-of-tubesheet circumferential cracking exceeded the minimum requirements specified in Revision 5 of the EPRI guidelines on steam generator tubing inspection. Approximately 64% of the tube population in each of the two steam generators were inspected. The MRPC inspections typically were conducted at the top of the tubesheet in a region approximately three inches above to three inches below the top of the tubesheet. The PlusPoint probe was used to conduct the inspections. Special-interest MRPC inspections were performed at hot leg and

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cold leg distorted bobbin (possible flaw) indications using the 0.560 inch diameter Plus-Point probe. The VEGP plans include inspecting twenty percent (20%) of the hot leg freespan straight length and U-bend dings> 5 volts identified by the bobbin probe utilizing the Plus-Point probe.

In response to the lessons learned from the tube rupture event at Indian Point 2, VEGP utilized a dual frequency (high/mid frequency) probe to ensure the data quality for the detection of Primary Water Stress Corrosion Cracking (PWSCC) in the low row U-bends was adequate. Presently, there are no published industry criteria for data quality and signal-to-noise (S/N) ratio. An evaluation of the S/N ratio was performed by Westinghouse on the low row U-bends and the S/N ratio was found to be acceptable for steam generators 2 and 3. A similar study, with acceptable results, was performed on SGs 2 and 3 on VEGP-1 during 1R9. The VEGP-2 review is documented in Westinghouse letter SGO-01-35 dated May 15, 2001.

Inspection Plan Implementation

To summarize the bobbin inspection plan, active tubes, row 3 and higher, were inspected with a Westinghouse 0.560-inch diameter probe throughout their entire length. The rows 1 and 2 straight lengths were tested using a 0.560-inch diameter probe.

The top of tubesheet and special interest examinations were performed with .560/115 +Point Probes at 900 rotations per minute (rpm). Approximately 60% of the rows 1 and 2 U-bend area RPC examinations were performed with High Frequency/Mid Range +Point RPC Probes. After the completion of the bobbin inspection program, special interest MRPC inspections were performed to better characterize indications in the steam generators. Disposition of tubes for which special interest MRPC was performed confnrmed that these indications did not represent serviceinduced degradation.

The Eddy Current inspection program was conducted in accordance with Westinghouse Field Procedure MRS 2.4.2 GPC-3 Rev. 8, Eddy Current Inspection of Preservice and Inservice Heat Exchanger Tubing. Inspection probes used were in accordance with Probe Authorization Rev. 1 and test configurations and acquisition rates were in accordance with the Eddy Current ACTS Sheets GBE-01-101 (Bobbin), GBE-02-101 (TSH and Special Interest RPC), GBE-03101 (Low Row Bobbin), GBE-04-101 (2 Coil U-bend RPC), GBE-05-101 (permeability), and GBE-06-101 (permeability, special interest and restrictions).

Per ACTS GBE-01-101, the bobbin inspection plan withdrawal rate was 40 inches per second and the test frequencies were 630 kilohertz (kHz), 320 kHz, 160 kHz, and 10 kHz. Per ACTS GBE-03-101, the bobbin withdrawal rate was 24 inches per second for low-row bobbin tube inspections. Per ACTS GBE-02-101, the withdrawal rate for the TSH and Special Interest Plus-Point RPC inspection plan was 0.4 inch per second and the test frequencies were 600 kHz, 300 kHz, 200 kHz, 100 kHz, and 20 kHz. Per ACTS GBE-04-101, the specifications for the low row U-bends 2 coil +Point Exam, the inspections are specified. ACTS GBE-05-101 and ACTS GBE-06-101 were written to facilitate the inspection of locations masked by permeability. Each probe, along with its inspection plan, corresponding ACTS number, and the EPRI Guidelines, Appendix H qualifications, is listed on the Probe Authorization dated March 27, 2001.

All tubes on the inspection plan were tested to their required extent. Special interest examinations (191 total) were required in all channelheads. Bobbin examinations were performed with Replaceable Probe Heads (RPH) mounted on WA-RLLC probe conduit. Row 1 and 2 U-bend RPC examinations were examined with a special order two coil high frequency / mid-range (HF/MR) probe. Four U-bends that would not pass the two coil probe head were tested with a standard one coil probe head.

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Inspection Summary Table

The above extents met or exceeded the inspection plan. In some cases, either the required minimum extent was exceeded or additional tubes were tested.

Data Evaluation

Data collection was performed by Westinghouse using the ROSA and TC6700 tester. Data was sent from the site via a data transmission line (T-1) in the ANSER format to the Westinghouse Waltz Mill, Pennsylvania facility. Westinghouse and its subcontractors performed the primary analysis of the eddy current data using Automated Data Screening (ADS) and ST2000 software for Data Management. Framatome performed the secondary analysis of the eddy current data. Resolutions were performed jointly by Westinghouse and Framatome at the Waltz Mill facility. All analysis was performed using ANSER Software. SNC site-specific Data Analysis Guidelines and procedure MRS 2.4.2 GPC-37, Revision 6, "Steam Generator Eddy Current Data Analysis Techniques for Vogtle Units 1 and 2", were used to perform the analysis.

Analysts were required to complete a training session and then were tested on their performance. The analyst training meets the requirements of the EPRI PWR Steam Generator Examination Guidelines, EPRI TR-107569VIR5, which included training tapes, test tapes, and a training manual for SNC. Analysts are required to pass an exam prior to analyzing any new data. One Westinghouse analyst did not pass the required exam and was rejected. Prior to the start of data acquisition a complete history review was performed of all baseline data for VEGP-2 to minimize the impact history lookups would have on the analysis schedule.

The primary analysis was performed off-site by Westinghouse at their Waltz Mill Facility. Secondary analysis was also performed off-site by Framatome at their Lynchburg and Benicia facilities. Remote analysis was accomplished using T-1 lines to communicate between the plant site and the remote locations. Data management was performed off-site with reports being generated on-site via the T- 1 lines. A SNC Level III was located at the Waltz Mill site to facilitate the resolution of eddy current data and performed the duties of the independent qualified data analyst (QDA). In addition, SNC QDA performed random samples of test data to ensure the EPRI requirements were being followed. In addition, all comparison reports between the primary and secondary analysis were verified by the SNC QDA.

The bobbiniMRPC inspections conducted during 2R8 identified no pluggable indications in Steam Generator 2 or 3. The following table summarizes the indications found by stating the number of tubes in which each type of indication was found.

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Type and Extent of Inspection SG 2 SG 3 Bobbin Full Length TEH through TEC 5132 5137 Bobbin 7H through TEC 1 3 Bobbin 7C through TEC 486 485 Bobbin 7C through TEH 244 245 Bobbin 7H through TEH 243 243 +PointTM RPC TSH +/- 3" 3598 3613 +PointTM RPC U-bend, Row 1 -(HF/MR) 73 71 +PointTM RPC U-bend, Row 1 0 2 +PointTM RPC U-bend, Row 2 (HF/MR) 71 72 +PointTM RPC U-bend, Row 2 1 1 +PointTM RPC U-bend, Row 3 (HF/MR) 0 1 +PointTM RPC Special Interest, HL 35* 107* +PointTM RPC Special Interest, CL 7 28* +PointTM RPC Special Interest, U-bend 8 6 * -- Reflects tubes with multiple Special Interest Inspections.

Indication Summary Table

Number of Tubes per Indication Size Steam Generator (S/G)

S/G 2 S/G 3 40% and greater wall 0 0 thickness penetration 30-39% wall thickness 3 0 penetration 20-29% wall thickness 8 3 penetration Less than 20% wall 39 26 thickness penetration Possible Loose Part Wear 0 4 Manufacturing Buff Marks (total tubes) 1139 948 Dent or Ding (total tubes) 200 277

It should be noted that the above table is based on the largest indication per tube. Tubes with multiple indications had only the largest indication counted.

More details regarding indication distributions can be found in the maps, which follow the steam generator tubing inspection discussion.

Degradation Assessment

Prior to maintenance/refueling outage 2R8, VEGP performed a degradation assessment as required by the provisions of Nuclear Energy Institute (NEI) guideline NEI 97-06 and Revision 5 of the EPRI guidelines for steam generator tube inspection. The purpose of the degradation assessment was to ensure that the appropriate nondestructive examination (NDE) techniques and personnel would be used during eddy current testing at VEGP. The degradation assessment provides assurances that the NDE techniques used are appropriate for detection and measurement performance to support growth rates, repair criteria, and structural limits for the degradation mechanisms.

Degradation mechanisms were grouped into categories according to their likelihood of occurrence. The categories include: active mechanisms for degradation previously found in the VEGP steam generators, relevant mechanisms for degradation found in similar plants with the same tubing material and similar design features, and potential mechanisms for degradation not found in similar plants but not judged to have a meaningful potential to occur based on historical or laboratory data. Other degradation mechanisms judged to be non-relevant for Westinghouse Model F steam generators were addressed in the assessment A subgroup included in the assessment identified the process applied to resolve potential indication signals in order to classify the signals for disposition relative to leaving the tube inservice or repairing the indications.

The only observed degradation mechanism at VEGP is anti-vibration bar (AVB) wear. As defined by the EPRI guidelines, the AVB wear observed at VEGP is not considered an active damage mechanism. The VEGP inspection plan requires the use of the bobbin probe to test all tubes in contact with the AVBs for the SGs tested that outage. The VEGP inspection plan is more conservative than the EPRI guidelines. Potential degradation mechanisms included in the assessment are Outside Diameter Stress Corrosion Cracking (ODSCC) and PWSCC which have been detected in thermally treated tubing in European plants. The VEGP inspection plan includes MRPC inspections at the top of tubesheet expansion region and at the small radius U-bends for detection of stress corrosion cracking (SCC). The assessment also concluded that the likelihood of initiation of both ODSCC and PWSCC at either the top of tubesheet expansion region and the small radius U-bends is considered low for VEGP.

Non-relevant degradation mechanisms include those degradation mechanisms observed in other steam generators with differing materials of construction and manufacturing practices. In general, these mechanisms are associated

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with drilled-hole carbon steel tube support plates (TSP). The VEGP TSPs are broached, quatrefoil tube holes with stainless steel TSPs. The likelihood of initiation of these degradation mechanisms at VEGP is considered remote.

In response to the lessons learned from the tube rupture event at Indian Point 2, VEGP utilized a dual frequency (high/mid frequency) probe to ensure the data quality for the detection of PWSCC in the low row U-bends was adequate. Based upon our acceptable S/N measurements and the difficulty encountered while trying to push the double headed high/mid frequency probe through the row 1 tubes, it was determined that enough data was collected with the high/mid frequency probes to accept the single headed (mid-frequency) probe data. Approximately 60% of the total row 1 and 2 U-bends were examined with the high/mid frequency probe.

For each degradation mechanism identified, the assessment specified the probe(s) to be used during inspection, the detection qualification including techniques sheet and estimated probability of detection (POD) information, the inspection sample plan, and the basis for expanding the inspection, if required. The degradation assessment also included information supporting the sizing qualification (when sizing is applied) including technique sheet and uncertainty data.

Condition Monitoring

There were no steam generator tubes identified during 2R8 that challenged the structural integrity recommendations of NRC Regulatory Guide 1.121. Furthermore, there were no tubes that required in-situ leakage testing or pressure testing. The only tube degradation mechanism observed at VEGP-2 during 2R8 was tube mechanical wear at AVB and Baffle Plate intersections. The AVB wear observed during 2R8 was consistent with the historical performance and structural expectations as projected in the degradation assessment report. No tubes were found to have experienced excessive AVB wear. Based upon the results of the Wear Projection Technology, tube stabilization will not be required in either generator until after the end of plant life (38 years allowing for 20 year life extension). The VEGP-2 pre-outage degradation assessment identified a structural limit of approximately twenty-four percent (24%) (remaining wall thickness) for AVB wear which satisfies the requirements of NRC Regulatory Guide 1.121. The following table lists indications seen after final disposition during the inspection. Only AVE percent wear indications are representative of a tube degradation in the VEGP steam generators.

2R8 Indications/Signals Condition S/G 2 S/G 3 AVB AVB % Wear Indications 95 43 BLG Oversize Tube Diameter 11 33 DFI Freespan indication (+Pt confirmed) 0 0 DFS Benign Freespan Signal 134 145 DNG Freespan Ding 132 187 DNI Distorted Ding/Dent Indication 0 0 DNS DNI cleared by +Pt (+Pt confirmed) 1 0 DNT Dents (TSP, Baffle, TS) 129 218 DSI TSP Indication (+Pt confirmed) 0 0 DSS DSI History Cleared 37 28

MBM Manufacturing Buff Marks 1788 1588 MMB Multiple MBMs 10 0 PCT Bobbin Sizing 95 43 PLP Possible Loose Part 0 4 PVN Permeability Variation 8 1

4-10

VOGTLE 2R8 AVB WEAR INDICATION SUMMARY

S/G # IND # Ž 40% Max. % Depth 2 cycle 95% A 2 95 0 37 3.46 3 43 0 27 2.11

Degradation Mechanisms

As defined in the degradation assessment, indications were categorized as observed, relevant, and non-relevant based upon their likelihood of occurrence. The AVB indications observed during 2R8 were consistent with expectations. For the ninety-five (95) indications reported in Steam Generator 2 and forty-three (43) indications reported in Steam Generator 3, none exhibit per cycle growth rates in excess of the 95% cumulative distribution allowance (11.7%) on the basis of prior cycle and documented in the Degradation Assessment Report. Forty-four (44) "new" indications, none > 16% in depth of penetration, were reported: this number was adjusted downward to 5 after lookups from the 2R6 data for new indications. None of the AVB wear indications were found to challenge tube integrity requirements and condition monitoring requirements are satisfied for these indications.

Foreign objects have been reported at VEGP-2 in prior inspections. Five PLP indications have been reported in SG 3 for 2R8. Those in the neighborhood of Row (R) 41 and Column (C) 25 are believed to be associated with a strap identified by visual examination in 2R7; loose parts evaluation indicated that no excessive wear was anticipated. A PLP signal was reported at SG 3 R21/C58-TSH+0.15"; no indication of wear is associated with this location. A visual inspection of this area did not indicate the presence of a PLP due to no definition of shape. The area identified appeared to be a scale bridge. If there is a PLP at this location, it is covered with scale that will prevent any relative motion or drag force.

There were no indications of outside diameter (OD) pitting or transition zone stress corrosion cracking detected. These degradation modes have not been observed in US Model F SGs with thermally treated tubes.

U-bend PWSCC, ODSCC related to the presence of freespan dings or support plate level dents, and sludge pile ODSCC are degradation mechanisms that have not been observed in similar SGs but are considered on a contingency basis should such indications be detected. There were no indications attributable to any of these mechanisms at VEGP-2 during 2R8. The likelihood of occurrence of these indications have the lowest probability of occurrence in the Westinghouse Model F design steam generators.

Indications reported in the VEGP-2 steam generators include manufacturing burnish marks and benign indications. The signals associated with these categories do not represent in-service degradation. The locations of these signals were carefully monitored for change from baseline or initial condition. In addition, approximately 191 other locations were re-examined with the Plus-Point probe because of questions concerning the nature of their bobbin signal. All these locations were confirmed to exhibit characteristics that were not indicative of tube degradation.

All straight tube section dents (Ž_5 volts) in both SG 2 and 3 were examined with Plus-Point probes. Also, twenty percent of the U-bend dents Ž_ 5 volts were examined with a Plus-Point probe. All of the locations tested in both S/Gs were reported as No Detectable Degradation (NDD). The dings and dents in Model F SGs do not result from TSP corrosion, because the 405 stainless steel plate quatrefoil tube hole design is unlikely to support in-service denting. There were no indications for the dents and dings other than the change in geometry and no degradation was detected.

AVB Wear Projection Technology-based Assessment

The Wear Projection Technology's Outage-Follow Mode application supporting the VEGP-2 2R8 Outage provided daily, and cumulative, confirmation that there was no wear site data obtained during the outage which indicated a need for tube stabilization (or tube plugging during this outage). Further, a near-worst-case interpretation of the largest (worst case) tube / AVB wear site increment (of 16% between 2R6 and 2R8) was evaluated. This evaluation

4-11

indicated that, for this near-limit-case scenario, the margin relative to requiring stabilization at expected end-ofoperation (with a 20 year Plant-Life-including life extension) is more than 38 years. Westinghouse concluded that the tube U-bend wear degradation mode is presently not strongly progressing in VEGP-2 Steam Generators 2 and 3.

Operational Assessment

NEI 97-06 requires that a "Forward Looking" operational assessment be performed. This assessment must establish if observed degradations mechanisms will continue to meet tube structural and leakage integrity requirements at the end of the upcoming cycle. This is calculated by adding growth rates and NDE uncertainty to the largest flaw left in service (the maximum indication that can be left in service is 39%). Performing this calculation using a 95% Confidence Limit (CL) the projected AVB wear at 2R9, when SG 1 and 4 are next inspected is 39% + 14.8% + 4.3%, or 58.1% Through-Wall (TW). For 2R10, the calculation for SG 2 and 3 is 39% + 14.5% + 4.3%, or 57.8% TW. This is below the structural limit of 75.75% TW identified in the Degradation Assessment, therefore tube integrity is demonstrated and operational assessment requirements are met for two-cycle inspection intervals.

The above evaluation is conservative based on the following:

1) The growth rate for the inspection period ending at 2R6 was used. The 2R6 data was used as a conservative measure since the observed growth rates were negative for end of 2R8.

2) Generally, the largest growth rates do not occur at the largest indications left in service. 3) Largest wear assumed to be left in service was 39%.

The 2R8 growth rates for the AVB indications were, on the average, slightly negative. SG 3 had a more negative average change that did SG 2. The general implication of this is that there is little or no growth to the AVE indications as a population. As addressed in the Condition Monitoring Operational Assessment (CMOA), this negative growth rate can be attributed to slight differences (still acceptable tolerances) between the standards used in the inspections. In summary, based on the CMOA evaluation, the negative average growth rates observed for AVB indications during 2R8 imply little or no average growth in the population charted.

The projected wear using the observed data for 2R8 would be significantly less. The end of cycle (EOC) wear for 2R10 in SG 2 is 43.2% TW. The EOC wear for 2R10 in SG 3 is 32.2% TW. The EOC wear for 2R9 in SG 1 is 42.2% TW and EOC for 2R9 in SG 4 is 5 1.0% TW. These values using the observed 2R8 data are significantly less than the conservative calculations above using 2R6 growth rates and maximum allowable wear for return to service.

The projection used at 2R7 for SGs 1 and 4 employed a 15.1% growth allowance. Therefore the 2R7 projection for 2R9 remains the most conservative for these SGs. These projections predict maximum wear depths well below the structural limit of 75.75% TW identified in the Degradation Assessment; thus, tube integrity is demonstrated and the operational assessment requirements are met for two cycle inspection intervals.

AVB wear is the only systematic degradation mechanism that has been observed at VEGP-2. Based on application of conservative prior AVE wear growth rates, the condition of the VEGP-2 SG tubes has been analyzed with respect to continued operability of the SGs until the end of Cycle 10, without exceeding the structural integrity recommendations of draft Reg. Guide 1.121. Conservative projection of the AVE wear in SGs 2 and 3 to EOC1O indicates that all structural criteria will continue to be satisfied until the next planned inspection for each SG. Similarly, based on the current data from 2R8, projections for SGs 1 and 4 to EOC9 indicate that all structural criteria will continue to be satisfied for these SGs as well until their next inspection at 2R9. The conclusion for SGs 1 and 4 will be re-evaluated based on the data from 2R9.

4-12

Visual Inspection

A visual inspection of the tubesheet was performed of plugged tube ends to identify signs of leakage. There were no signs of visible leakage from plugged tubes. Westinghouse procedure MRS-SSP-1 102-GAE/GBE, "Visual Inspection of Mechanical Plugs for Vogtle Site", was used to inspect the tube plugs.

Mechanical Plugging

As noted above, there were no tubes required to be plugged in steam generators 2 or 3.

By letter LCV-1536, dated May 2, 2001, SNC notified the NRC pursuant to VEGP Technical Specification 5.6.10.a and reported that no tubes were plugged in SG 2 or 3 during 2R8.

VEGP-2 Outage 2R8 Plugging Summary

SG2 SG3 Tubes plugged this outage 0 0 Tubes previously plugged 7 1 Total plugged tubes 7 1

4-13

Maps

1. Steam Generator 2 - Bobbin Inspection Plan - Cold Leg (page 4-21)

2. Steam Generator 2 - Bobbin Inspection Plan - Hot Leg (page 4-22)

3. Steam Generator 2 - Tubesheet +PT Inspection Plan- Hot Leg (page 4-23)

4. Steam Generator 2 - UB +PT Inspection Plan (page 4-24)

5. Steam Generator 2 - Bobbin Test Extents (Actual) (pages 4-25 and 4-26)

6. Steam Generator 2 - +PT Tests Extents (Actual) (pages 4-27 and 4-28)

7. Steam Generator 3 - Bobbin Test Program - Cold Leg (page 4-29)

8. Steam Generator 3 - Bobbin Test Program - Hot Leg (page 4-30)

9. Steam Generator 3 - Tubesheet +PT Inspection Plan- Hot Leg (page 4-3 1)

10. Steam Generator 3 - UB +PT Inspection Plan (page 4-32)

11. Steam Generator 3 - Bobbin Test Extents (Actual) (pages 4-33 and 4-34)

12. Steam Generator 3 - +PT Test Extents (Actual) (pages 4-35 and 4-36)

4-14

TABLE I

Steam Generator 1

Total No. of Tubes:

No. of Tubes Inspected:

No. of Tubes Degraded:

No. of Tubes Defective:

No. of Tubes Plugged Prior to Outage 2R8:

No. of Tubes Plugged during Outage 2R8:

Total No. of Tubes Plugged:

Overall Percentage of Tubes Plugged:

5,626

5,622

N/A

N/A

4

N/A

4 (plugs located at Row 1, Colunm 1; Row 27, Column 42; Row 54, Column 35; and Row 48, Column 26)

0.07%

4-15

TABLE I (continued)

Steam Generator 2

Total No. of Tubes:

No. of Tubes Inspected:

No. of Tubes Degraded:

No. of Tubes Defective:

No. of Tubes Plugged Prior to Outage 2R8:

No. of Tubes Plugged during Outage 2R8:

Total No. of Tubes Plugged:

Overall Percentage of Tubes Plugged:

5,626

5,619

11

0

7

0

7 (plugs located at Row 2, Column 48; Row 5, Column 48; Row 16, Column 103; Row 48, Column 98; Row 53, Column 86; Row 50, Column 67; and Row 51, Column 32)

0.12%

4-16

TABLE I (continued)

Steam Generator 3

Total No. of Tubes:

No. of Tubes Inspected:

No. of Tubes Degraded:

No. of Tubes Defective:

No. of Tubes Plugged Prior to Outage 2R8:

No. of Tubes Plugged during Outage 2R8:

Total No. of Tubes Plugged:

Overall Percentage of Tubes Plugged:

5,626

5,625

3

0

1

0

1 (plug located at Row 25, Column 102)

0.02%

4-17

TABLE I (continued)

Steam Generator 4

Total No. of Tubes:

No. of Tubes Inspected:

No. of Tubes Degraded:

No. of Tubes Defective:

No. of Tubes Plugged Prior to Outage 2R8:

No. of Tubes Plugged during Outage 2R8:

Total No. of Tubes Plugged:

Overall Percentage of Tubes Plugged:

5,626

5,609

N/A

N/A

17

N/A

17 (plugs located at Row 48, Column 25; Row 3, Column 35; Row 12, Column 36; Row 57, Column 46; Row 8, Column 56; Row 52, Column 56; Row 16, Column 57; Row 51, Column 59; Row 48, Column 64; Row 23, Column 67; Row 51, Column 73; Row 22, Column 90; Row 24, Column 93; Row 57, Column 45; Row 50, Column 67; Row 57, Column 44; and Row 44, Column 21).

0.30%

4-18

TABLE H

Steam Generator 2

Row Column Reference Point Distance from Wall Thickness Plugged (Note 1) Ref. (in.) Penetration (%) (Y/N)

(Note 2)

42 19 AV3 -.03 11 N 43 20 AV2 -.26 13 N 54 38 AV4 .00 15 N 38 39 AV5 -. 17 22 N 39 43 AV3 .00 19 N 39 44 AV5 .00 13 N 40 48 AV4 .00 22 N 59 56 AV4 .26 12 N 40 58 AV5 .00 33 N 43 64 AVI .00 17 N 52 71 AV4 .00 37 N 44 72 AV5 .00 12 N 51 72 AV3 .00 11 N 40 73 AV5 .00 17 N 43 73 AV4 .00 21 N 52 73 AV4 .00 36 N 38 74 AV2 .00 15 N 42 74 AV2 .00 28 N 49 74 AV3 .20 20 N 51 74 AV3 .11 16 N 57 79 AV3 .00 9 N 38 81 AV6 .00 12 N 51 87 AV5 .00 29 N 39 88 AV4 .00 18 N 42 88 AV2 .00 12 N 53 88 AV5 .06 18 N 50 89 AV5 -. 11 13 N 51 89 AV5 .06 29 N 53 90 AV6 .00 9 N 49 91 AV2 .00 22 N 28 115 AV6 .00 19 N

The above information is based on the largest indication observed for the respective tube during the eighth maintenance/refueling outage at VEGP-2.

Note 1: Reference Point Location Description

Note 2:

TSH, TSC - Top of Tubesheet Hot and Cold BPH, BPC - Baffle Plate Hot and Cold #H, #C - (# = Number) of Support Plate Hot and Cold, e.g., 2H, 2C AVI, AV2, AV3, AV4, AV5, AV6 - Anti-vibration Bars

Unless indicated otherwise, distance is above Reference Point. A negative number, e.g., -2.00, indicates that the distance is below the Reference Point.

4-19

TABLE HI

Steam Generator 3

Row Column Reference Point Distance from Wall Thickness Plugged (Note 1) Ref. (in.) Penetration (%) (Y/N)

(Note 2)

32 12 AV5 .00 19 N

34 13 AV5 .14 20 N

38 15 AVI .00 14 N

32 16 AV2 .00 14 N

41 19 AV4 .00 12 N

42 19 AV5 -.49 11 N

42 20 AV4 .00 13 N

43 21 AV2 .06 11 N

44 21 AV2 .00 15 N 45 22 AV3 .12 15 N 44 23 AV3 .19 11 N

45 23 AV3 .19 15 N

47 24 AV4 .00 18 N

47 25 AV2 .00 14 N

48 25 AV6 -.03 9 N

50 29 AV4 .00 11 N

51 31 AV6 .00 11 N

48 37 AV3 .14 13 N

54 38 AV5 .00 13 N

57 48 AV6 .03 13 N

57 49 AV4 -.08 10 N

58 49 AV6 -.08 16 N

42 53 AV4 -.27 9 N 39 72 AV3 .25 16 N

41 77 AV4 .36 22 N

57 78 AV2 .00 10 N 56 82 AV3 .00 27 N

42 104 AV6 -.05 10 N

40 106 AVI .52 10 N

The above information is based on the largest indication observed for the respective tube during the eighth maintenance/refueling outage at VEGP-2.

(1) See Note 1, page 4-19.

(2) See Note 2, page 4-19.

4-20

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LU D

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In

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0 00 . +. + , * .... ....

-e"0 + e . ++ = l . + . 0 ..................................... o ..............

... .... .............. . . . ..... ... ...... .... ....... ... .. ............................... 0 9 + . . .. .._.. . . . 0 I I I I ' I I I 1 e l e l l p " l

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)+ .... .... .... ... . . .. . ..... .... ...... ...... ... .... .. Co °) ... .. I... .. ...... . .. ... .... .... .... .... .... ..... .... ... .~ ... .... ..... .... --...- ... .. .. 00 .. ........ .... .... .... .... .... .. .OO. .... .... ..... .... . .. .... .... .. . . ... . . . . . 0 S... . .... . ...... . . ..... + ... :;Ios

oo ... t .. . . . : ... : + .... ..... .... •..o o... 0 ... ..... . ... . . ... .:: [ : t.. .. . . . . . . .f. . . . ooi : :.. . . ! : _: : . . . . t . . . . . . . . .. . .. .. .t .^ 0 0 .. ' " .. . . . . . . . . . .o . . . . t . . . . t . . . . . . . .. . . . . . . . .. . . . . ..o O Ef 0+ + + .... .. .. + + ....0 o• : :: :: • . . . .. .... .... .... .... .. . • ..... : : : : :.... . .... .... ....... 00 ... .... .. ......... .. I: ::.... .. .... . .......... .... ... I ..... ..... .. .... .... ... ... .. ..... .. .. SE

S 0 0 . . . . . . ." . . . . . . . . . . . . . ; ' ; , ; ; ; . . . . .. -.

001 ii i I0 I i i i i ~ i i I I ~ I I I I I ~ l

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005

00

S.. .. .. ...l l . .... .. ... .......... . .... ... . l ..o "0 ., , ::,.~ e :: + ::+ ::: :: : '::: : .:: -:: -: + -: :::: ::== :::: :::•:,::L0 0

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. - : : ... .

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00 .. .. . .. . . . . I - [ : = : : : = = . = = + .... •: =.. ...

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3808d Id+ u0 JH O9 H1I/1 Hl HqnOUH1 380d d- 8fl A.H @Z9'

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d 3i9 c -fl esA SIN3IX3 Q0L17dVLJ0o id+ QN•8-fl • - OS

) )

( ( (

Augmented ASME Sect. XI Examination Component or Weld No.] Calibration Exam

Item No./Cat. Requirement Description Exam Procedure Block(s) Sheet No(s). Results Remarks

See Note A See Note B See Note C See Note D See Note E See Note F See Note G See Note H

NOTES:

A. The ASME Section XI Item No. and Category of the examination area are listed in this colunmn.

B. The implementing document e.g., VEGP Technical Specifications, NRC Bulletin, etc., requiring performance of augmented examinations is referenced here.

C. Each examination area is listed in this column. The component or weld number typically is similar to the drawing number, e.g., weld number 21201-005-8 is found on drawing number ISI-21201-005.

D. This column lists the applicable NDE procedures used for the examination.

E. This column lists the calibration block(s) that was/were used.

F. This column references the examination data sheet(s) which records exam data, examiners, and any pertinent remarks.

G. The results of the examinations are indicated in this column. The absence of indications is indicated in the column as "NI" or "SAT". The presence of nonrelevant indications or indications which are less than the recording level is indicated in the column as "NRI". The presence of indications deemed recordable (per NDE procedure) are indicated in the column as "RI" or "UNSAT" and are explained in the remarks column of the summary table.

H. The remarks column is used to describe any pertinent features of the examination such as limitations, INFs, etc. Refer to INF section in this report for their disposition.

FIGURE 1. EXPLANATION OF SUMMARY TABLE FORMAT

5-1

(

VEGP-2 EIGHTH MAINTENANCE / REFUELING OUTAGE CLASS I EQUIPMENT EXAMINATIONS

AS ME SECTION XI ITEM NO./CAT.

AUGMENTED EXAMINATION REQUIREMENT(S)

COMPONENT OR WELD NO. / DESCRIPTION

EXAMINATION PROCEDURE(S)

CALIBRATION BLOCK(S)

EXAM SHEET NO(S). RESULTS REMARKS

VT-1 PER RR-6

VT-1 PER RR-6

TS 5.5.9

TS 5.5.9

21201 -B6-002-IR-01

INLET NOZZLE INNER RADIUS

21201 -B6-002-1 R-02 OUTLET NOZZLE INNER RADIUS

21201 -86-002-T01

TUBING - ENTIRE LENGTH OF SELECTED TUBES

21201 -B6-003-T01

TUBING - ENTIRE LENGTH OF SELECTED TUBES

B3.140

B-D

B3.140

B-D

B 16.20

B-Q

B16.20

B-Q

B6.30 B-G-1

B6.30

B-G-1

B6.30

B-G-1

B6.30

B-G-1

B6.30

B-G-1

B6.30

B-G-1

VT-V-715

VT-V-715

MT-V-505

UT-V-482

MT-V-505

UT-V-482

MT-V-505

UT-V-482

MT-V-505

UT-V-482

MT-V-505

UT-V-482

MT-V-505

UT-V-482

S01V2V045 SAT

S01V2V046 SAT

419A

419A

419A

419A

419A

419A

S0lV2M001 NRI

S01V2U326 NRI

S01 V2M002 NRI

S01V2U327 NRI

S01 V2M003 NRI

SOIV2U328 NRI

S01 V2M004 NRI

S01V2U329 NRI

S01 V2M009 NRI

S01V2U330 NRI

S01 V2M010 RI

SOlV2U331 NRI

N/A

N/A

SEE AUGMENTED SUMMARY SECTION FOR DETAILS AND RESULTS.

SEE AUGMENTED SUMMARY SECTION FOR DETAILS AND RESULTS.

N/A

N/A

N/A

N/A

N/A

MT RI / CODE ACCEPTABLE.

6-1

(

21201 -V6-001 -801

CLOSURE HEAD STUDS

21201 -V6-001 -802

CLOSURE HEAD STUDS

21201-V6-001--B03

CLOSURE HEAD STUDS

21201 -V6-001 -804

CLOSURE HEAD STUDS

21201-V6-001 -B05

CLOSURE HEAD STUDS

21201-V6-001-B06

CLOSURE HEAD STUDS

(

VEGP-2 EIGHTH MAINTENANCE / REFUELING OUTAGE

CLASS 1 EQUIPMENT EXAMINATIONS

ASME SECTION XI ITEM NO./CAT.

AUGMENTED EXAMINATION REQUIREMENT(S)

B6.30

B-G-1

B6.30 B-G-1

B6.30 B-G-1

B6.30

B-G-1

B6.30

B-G-1

B6.30

B-G-1

B6.30

B-G-1

B6.30

B-G-1

B6.30

B-G-1

B6.30 B-G-1

COMPONENT OR WELD NO. / DESCRIPTION

21201-V6-001-B07

CLOSURE HEAD STUDS

21201-V6-001-B08

CLOSURE HEAD STUDS

21201-V6-001-B09

CLOSURE HEAD STUDS

21201-V6-001-B10

CLOSURE HEAD STUDS

21201-V6-001-B11

CLOSURE HEAD STUDS

21201-V6-001-B12

CLOSURE HEAD STUDS

21201-V6-001-B13

CLOSURE HEAD STUDS

21201-V6-001-B14

CLOSURE HEAD STUDS

21201-V6-001-B15

CLOSURE HEAD STUDS

21201-V6-001-B16

CLOSURE HEAD STUDS

EXAMINATION PROCEDURE(S)

MT-V-505

UT-V-482

MT-V-505

UT-V-482

MT-V-505

UT-V-482

MT-V-505

UT-V-482

MT-V-505

UT-V-482

MT-V-505

UT-V-482

MT-V-505

UT-V-482

MT-V-505

UT-V-482

MT-V-505

UT-V-482

MT-V-505

UT-V-482

CALIBRATION BLOCK(S)

419A

419A

419A

419A

419A

419A

419A

419A

419A

419A

EXAM SHEET NO(S).

S01 V2M01 1

S01V2U332

RESULTS

NRI

NRI

S01 V2M005 NRI

S01V2U333 NRI

S01V2M006 NRI

SOIV2U334 NRI

S01V2M007 NRI

S01V2U335 NRI

S01V2M008 NRI

S01V2U336 NRI

S01 V2M012 NRI

S01V2U350 NRI

S01V2M013 NRI

S01V2U351 NRI

S01 V2M014 NRI

S01V2U352 NRI

S01 V2M015 NRI

S01V2U353 NRI

S01 V2M016 NRI

S01V2U354 NRI

6-2

(

REMARKS

N/A

N/A

N/A

N/A

N/A

N/A

N/A

N/A

N/A

N/A

(

VEGP-2 EIGHTH MAINTENANCE / REFUELING OUTAGE

CLASS 1 EQUIPMENT EXAMINATIONS

ASME SECTION XI ITEM NO./CAT.

B6.30 B-G-1

AUGMENTED EXAMINATION REQUIREMENT(S)

COMPONENT OR WELD NO. / DESCRIPTION

212014-6-001 -B317 CLOSURE HEAD STUDS

EXAMINATION PROCEDURE(S)

MT-V-505

UT-V-482

CALIBRATION BLOCK(S)

419A

EXAM SHEET NO(S).

S01 V2M01 7

S01 V2U355

FSAR 5.3.3.7

B6.30

B-G-1

B 13.10

B-N-I

B6.10

B-G-1

B6.10

B-G-1

B6.10 B-G-1

B6.10 B-G-1

B6.10

B-G-1

B6.10

B-G-1

B6.10 B-G-1

B6.10

B-G-1

21201 -V6-001 -118

CLOSURE HEAD STUDS

21201-V6-001-102

VESSEL CLOSURE HEAD INTERIOR

21201-V6-001-NO1

CLOSURE HEAD NUTS

21201 -V6-001 -N02

CLOSURE HEAD NUTS

21201 -V6-001 -N03

CLOSURE HEAD NUTS

21201-V6-001-N04

CLOSURE HEAD NUTS

21201 -V6-001 -N05

CLOSURE HEAD NUTS

21201 -V6-001 -N06

CLOSURE HEAD NUTS

21201 -V6-001 -N07

CLOSURE HEAD NUTS

21201 -V6-001 -N08

CLOSURE HEAD NUTS

MT-V-505

UT-V-482

VT-V-735

419A

VT-V-715

VT-V-715

VT-V-715

VT-V-715

VT-V-715

VT-V-715

VT-V-715

VT-V-715

S01 V2M018 NRI

S01V2U356 NRI

S01V2V006 SAT

S01V2V009 SAT

S01V2V010 SAT

S01V2V011 SAT

S01V2V012 SAT

S01V2V013 SAT

S01V2V014 SAT

S01V2V015 SAT

S01V2V023 SAT

6-3

(

RESULTS

NRI

NRI

REMARKS

N/A

VT-1 PER RR-5

VT-1 PER RR-5

VT-1 PER RR-5

VT-1 PER RR-5

VT-1 PER RR-5

VT-1 PER RR-5

VT-1 PER RR-5

VT-1 PER RR-5

N/A

N/A

N/A

N/A

N/A

N/A

N/A

N/A

N/A

N/A

il

( (

VEGP-2 EIGHTH MAINTENANCE/ REFUELING OUTAGE

CLASS 1 EQUIPMENT EXAMINATIONS

ASME AUGMENTEDSECTION XI EXAMINATION ITEM NO./CAT. REQUIREMENT(S)

COMPONENT OR WELD NO. / DESCRIPTION

EXAMINATION CALIBRATION PROCEDURE(S) BLOCK(S)

EXAM SHEET NO(S). RESULTS

B6.10

B-G-1

B6.10

B-G-1

B6.10

B-G-1

86.10 B-G-1

B6.10 B-G-1

B6.10

B-G-1

B6.10

B-G-1

B6.10 B-G-1

B6.10

B-G-1

B6.10

B-G-1

B6.50

B-G-1

B6.50

B-G-1

VT-i PER RR-5

VT-1 PER RR-5

VT-I PER RR-5

VT-i PER RR-5

VT-i PER RR-5

VT-I PER RR-5

VT-I PER RR-5

VT-I PER RR-5

VT-I PER RR-5

VT-i PER RR-5

REMARKS

21201 -V6-001 -N09

CLOSURE HEAD NUTS

21201 -46-001 -N 10

CLOSURE HEAD NUTS

21201 -46-001 -N 1I

CLOSURE HEAD NUTS

21201 -V6-001 -N12

CLOSURE HEAD NUTS

21201 -V6-001 -N13

CLOSURE HEAD NUTS

21201-V6-001 -N 14

CLOSURE HEAD NUTS

21201 -46-001 -N 15

CLOSURE HEAD NUTS

21201 -46-001 -N16

CLOSURE HEAD NUTS

21201-V6-001-N17

CLOSURE HEAD NUTS

21201 -V6-001-N18

CLOSURE HEAD NUTS

21201 -V6-001 -S01

CLOSURE WASHERS

21201 -V6-001-S02

CLOSURE WASHERS

VT-V-71 5

VT-V-715

VT-V-715

VT-V-715

VT-V-715

VT-V-715

VT-V-715

VT-V-715

VT-V-715

VT-V-715

VT-V-71 5

VT-V-715

S0l1V2V024

S0l1V2V025

S01'V2V026

S01 V2V031

S01'V2V032

S01 V2V033

S01'V2V034

S01 V2V035

S01 V2V036

S01 V2V037

S01V2V016

S01V2V017

SAT

SAT

SAT

SAT

SAT

SAT

SAT

SAT

SAT

SAT

SAT

SAT

N/A

N/A

N/A

N/A

N/A

N/A

N/A

N/A

N/A

N/A

N/A

N/A

6-4

ASME AUGMENTED SECTION XI EXAMINATION ITEM NO./CAT. REQUIREMENT(S)

B6.50

B-G-1

B6.50

B-G-1

B6.50

B-G-1

B6.50

B-G-1

B6.50

B-G-1

B6.50

B-G-1

B6.50 B-G-1

B6.50

B-G-1

B6.50

B-G-1

B6.50

B-G-1

B6.50

B-G-1

B6.50 B-G-1

COMPONENT OR WELD NO. / DESCRIPTION

21201-V6-001 -S03

CLOSURE WASHERS

21201 -V6-001 -S04

CLOSURE WASHERS

21201 -V6-001 -S05

CLOSURE WASHERS

21201-V6-001-S06

CLOSURE WASHERS

21201 -V6-001 -S07

CLOSURE WASHERS

21201-V6-001-S08

CLOSURE WASHERS

21201-V6-001-S09

CLOSURE WASHERS

21201-V6-001-S10

CLOSURE WASHERS

21201 -V6-001 -Sl$

CLOSURE WASHERS

21201-V6-001-S12

CLOSURE WASHERS

21201-V6-001 -S 13

CLOSURE WASHERS

21201 -V6-001-S14

CLOSURE WASHERS

VEGP-2 EIGHTH MAINTENANCE / REFUELING OUTAGE

CLASS 1 EQUIPMENT EXAMINATIONS

EXAMINATION CALIBRATION EXAM S PROCEDURE(S) BLOCK(S) NO(S).

VT-V-715 S01 V2VC

VT-V-715 S01 V2V(

VT-V-715 S01 V2VC

VT-V-715 S01V2V(

VT-V-715 S01 V2V(

VT-V-715 S01 V2V(

VT-V-715 S01 V2V(

VT-V-715 S01 V2V(

VT-V-715 S01 V2V(

VT-V-715 S01 V2V(

VT-V-715 S01 V2V(

VT-V-715 S01 V2V(

HEET

318

319

320

321

)22

027

028

029

030

038

339

040

6-5

(

RESULTS

SAT

SAT

SAT

SAT

SAT

SAT

SAT

SAT

SAT

SAT

SAT

SAT

REMARKS

N/A

N/A

N/A

N/A

N/A

N/A

N/A

N/A

N/A

N/A

N/A

N/A

i.

(

VEGP-2 EIGHTH MAINTENANCE / REFUELING OUTAGE CLASS I EQUIPMENT EXAMINATIONS

ASME SECTION XI ITEM NO./CAT.

AUGMENTED EXAMINATION REQUIREMENT(S)

COMPONENT OR WELD NO. / DESCRIPTION

EXAMINATION PROCEDURE(S)

CALIBRATION BLOCK(S)

EXAM SHEET NO(S). RESULTS REMARKS

B6.50 B-G-1

B6.50 B-G-1

B6.50

B-G-1

B6.50

B-G-1

NRC BULL. 88-09

WTECH BULL NS

B3.120

B-D

B3.120

B-D

B2.11

B-B

21201-V6-001-SI5

CLOSURE WASHERS

21201-V6-001-S16

CLOSURE WASHERS

21201-V6-001-S17

CLOSURE WASHERS

21201-V6-001 -S18

CLOSURE WASHERS

21201-V6-001-TO1 - T58

INCORE FLUX THIMBLE TUBES

21201-V6-001-T01-OD - T58-OD

THIMBLE TUBE GUIDE TUBES

21201 -V6-002-IR-01

6" SAFETY NOZZLE INNER RADIUS

21201 -V6-002-IR-04

6" RELIEF NOZZLE INNER RADIUS

21201 -V6-002-WO1

UPPER HEAD TO UPPER SHELL WELD

VT-V-715

VT-V-715

VT-V-715

VT-V-715

VENDOR

VENDOR

UT-V-416

UT-V-416

UT-V-411

S01V2V041 SAT

S01V2V042 SAT

51 V2V043 SAT

S01V2V044 SAT

N/A

N/A

N/A

N/A

SEE AUGMENTED SUMMARY SECTION FOR DETAILS AND RESULTS.

SEE AUGMENTED SUMMARY SECTION FOR DETAILS AND RESULTS.

411A

411A

403A, 411A

S01V2U423 NRI

SO1V2U424 NRI

S01V2U435 SOlV2U437

SOIV2U438

S01V2U439

S01V2U440

S01V2U441

S01V2U442

S01V2U443

N/A

N/A

NRI NRI

NRI NRI

NRI

NRI

NRI

NRI

UT SCANS LIMITED / RR-7.

6-6

(

C (

VEGP-2 EIGHTH MAINTENANCE / REFUELING OUTAGE CLASS 1 EQUIPMENT EXAMINATIONS

ASME SECTION XI ITEM NO.ICAT.

AUGMENTED EXAMINATION REQUIREMENT(S)

B2.12

B-B

MT PER RR-7B3.110

B-D

MT PER RR-7B3.110 B-D

MT PER RR-7B3.1 10 B-D

B5.40

B-F

COMPONENT OR WELD NO. I DESCRIPTION

21201 -V6-002-W06

UPPER SHELL LONGITUDINAL WELD

21201 -V6-002-W1 0

UPPER HEAD TO 6" SAFETY NOZZLE WELD

21201 -V6-002-W1 I

UPPER HEAD TO 6" SAFETY NOZZLE WELD

21201 -V6-002-W1 6

14" SURGE NOZZLE WELD TO LOWER HEAD

21201 -V6-002-W1 7

6" SAFETY NOZZLE TO SAFE END WELD

EXAMINATION PROCEDURE(S)

UT-V-411

MT-V-505 UT-V-411

MT-V-505

UT-V-411

MT-V-505

UT-V-411

PT-V-605

UT-V-404

CALIBRATION BLOCK(S)

403A

411A

411A

411A

324A, 355A

RESULTS

NRI

NRI

NRI

NRI

EXAM SHEET NO(S).

S01V2U431

S01V2U432

SOlV2U433

S01V2U434

S01 V2M019

S01V2U367

S01V2U368

S01V2U369

S01 V2U370

S01V2M020

S01 V2U363

S01 V2U364

S01V2U365

SO1V2U366

S01 V2M021

S01V2U372

S01V2U373

SO1V2U374

S01V2U375

S01V2P025

S01V2U390

S01V2U391

S01 V2U392

SO1V2U393

S01V2U394

S01V2U395

S01V2U396

S01V2U397

REMARKS

UT SCANS LIMITED / CODE CASE N-460 (>90%).

UT SCANS LIMITED / RR-7.

UT SCANS LIMITED / RR-7.

UT SCANS LIMITED / RR-7.

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

6-7

UT SCANS LIMITED / RELIEF REQUEST REQUIRED.

(

VEGP-2 EIGHTH MAINTENANCE / REFUELING OUTAGE

CLASS 1 EQUIPMENT EXAMINATIONS

ASME SECTION XI ITEM NO./CAT.

AUGMENTED EXAMINATION REQUIREMENT(S)

COMPONENT OR WELD NO. / DESCRIPTION

EXAMINATION PROCEDURE(S)

CALIBRATION BLOCK(S)

EXAM SHEET NO(S). RESULTS REMARKS

21201 -V6-002-W1 8

6" SAFETY NOZZLE TO SAFE END WELD

21201 -V6-002-W1 9

6" SAFETY NOZZLE TO SAFE END

21201 -V6-002-W20

6" RELIEF NOZZLE TO SAFE END WELD

PT-V-605

UT-V-404

PT-V-605

UT-V-404

PT-V-605

UT-V-404

324A, 355A

324A, 355A

324A, 355A

B5.40

B-F

S01V2P026

S01V2U398

S01V2U401

S01V2U404

S01V2U407

S01V2U410

S01V2U413

S01V2U416

S01V2U419

S01V2P027

S01V2U399

S01V2U402

S01V2U405

S01 V2U408

S01V2U411

S01V2U414

S01V2U417

S01V2U420

S01V2P028

S01V2U400

S01V2U403

SO1V2U406

S01V2U409

S01V2U412

S01V2U415

S01V2U418

S01V2U421

UT SCANS LIMITED / RELIEF REQUEST REQUIRED.

PT RI / CODE ACCEPTABLE. UT SCANS LIMITED / RELIEF REQUEST REQUIRED.

UT SCANS LIMITED / RELIEF REQUEST REQUIRED.

6-8

(

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

RI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

B5.40

B-F

B5.40

B-F

(

VEGP-2 EIGHTH MAINTENANCE/ REFUELING OUTAGE

CLASS I EQUIPMENT EXAMINATIONS

ASME SECTION XI ITEM NO./CAT.

AUGMENTED EXAMINATION REQUIREMENT(S)

COMPONENT OR WELD NO. / DESCRIPTION

EXAMINATION PROCEDURE(S)

CALIBRATION BLOCK(S)

EXAM SHEET NO(S). RESULTS REMARKS

21201 -V6-002-W22

14" SAFE END WELD TO SURGE NOZZLE

B5.40 B-F

PT-V-605

UT-V-404315A, 357A N/AS01V2P020

S01V2U357

S01V2U358

S01V2U359

S01V2U360

S01V2U361

S01V2U362

NRI NRI

NRI

NRI

NRI

NRI

NRI

6-9

(

VEGP- 2 EIGHTH MAINTENANCE / REFUELING OUTAGE

CLASS 1 PIPING EXAMINATIONS

ASME SECTION XI ITEM NO./CAT.

B9.11 B-J

AUGMENTED EXAMINATION REQUIREMENT(S)

COMPONENT OR WELD NO. I DESCRIPTION

21201-053-6

14" PIPE TO SAFE END

21201-056-1

6" SAFE END TO ELBOW

21201-057-1

6" SAFE END TO ELBOW

21201-058-1

6" SAFE END TO ELBOW

21201-058-7

6" ELBOW TO FLANGE

B9.11

B-J

B9.11 B-J

B9.11

B-J

B9.11

B-J

B7.50

B-G-2

B7.70

B-G-2

B9.11

B-J

B9.11

B-J

21201-058-7 FB

6" FLANGE BOLT ASSEMBLY FOR

21201 -PSV-801 OA

21201 PSV801 OA

VALVE BOLTING (ISI-21201-058)

21201-059-1

6" SAFE END TO ELBOW

21201-059-11

6" PIPE TO TEE

EXAMINATION PROCEDURE(S)

PT-V-605 UT-V-481

PT-V-605

UT-V-481

PT-V-605

UT-V-481

PT-V-605

UT-V-481

PT-V-605

UT-V-481

VT-V-715

VT-V-715

PT-V-605 UT-V-481

PT-V-605 UT-V-481

CALIBRATION BLOCK(S)

315A

304A, 324A

304A, 324A

304A, 324A

304A

EXAM SHEET NO(S).

S01V2P021 NRI S01V2U376 NRI

S01V2P018 S01V2U380

S01V2U381

S01V2P019

S01V2U386 S01V2U387

S01V2P016 S01V2U384

S0lV2U385

S01V2PO17

S01V2U388

S01V2U389

S01V2V004 SAT

S01V2V003 SAT

304A, 324A

304A, 348A

S01V2P012 S01V2U382 S01V2U383

S01V2P022

S01V2U427

S01V2U428

NRI NRI

RI

NRI

NRI

NRI

NRI NRI

RI

NRI

NRI

NRI

RESULTS REMARKS

N/A

UT RI / GEOMETRY.

N/A

UT RI / GEOMETRY.

UT SCANS LIMITED / RELIEF REQUEST REQUIRED.

EXAMINED IN PLACE UNDER TENSION.

EXAMINED IN PLACE UNDER TENSION.

UT RI / GEOMETRY.

N/A

NRI NRI RI

NRI

NRI

NRI

7-1

( (

C

ASME AUGMENTED SECTION XI EXAMINATION ITEM NO./CAT. REQUIREMENT(S)

B9.21

B-J

B9.21

B-J

B9.21

B-J

B9.21

B-J

B9.21

B-J

B9.11

B-J

B9.11

B-J

B9.21

B-J

B9.21

B-J

B9.21

B-J

B9.21

B-J

C (

COMPONENT OR WELD NO. / DESCRIPTION

21201-059-14

3" REDUCER TO ELBOW

21201-059-15

3" ELBOW TO ELBOW

21201-059-17

3" PIPE TO VALVE

21201-059-18

3" VALVE TO PIPE

21201-059-21

3" PIPE TO VALVE

21201-060-1

6" TEE TO PIPE

21201-060-2

6" PIPE TO REDUCER

21201-060-3

3" REDUCER TO ELBOW

21201-060-4

3" ELBOW TO ELBOW

21201-060-5

3" ELBOW TO PIPE

21201-060-6

3" PIPE TO VALVE

VEGP- 2 EIGHTH MAINTENANCE / REFUELING OUTAGE

CLASS 1 PIPING EXAMINATIONS

EXAMINATION CALIBRATION EXAM SHEET PROCEDURE(S) BLOCK(S) NO(S).

PT-V-605 S01V2P029

PT-V-605 S01V2P030

PT-V-605 S01V2P013

PT-V-605 S01V2P014

PT-V-605 S01V2P015

PT-V-605 304A S01V2P023

UT-V-481 S01V2U425

PT-V-605 304A S01V2P024

UT-V-481 S01V2U426

PT-V-605 S01V2P031

PT-V-605 S01V2P032

PT-V-605 S01V2P033

PT-V-605 S01V2P034

RESULTS

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

NRI

7-2

REMARKS

N/A

N/A

N/A

N/A

N/A

UT SCANS LIMITED I CODE CASE N-460 (>90%).

N/A

N/A

N/A

N/A

N/A

C

VEGP- 2 EIGHTH MAINTENANCE / REFUELING OUTAGE CLASS I PIPING EXAMINATIONS

ASME SECTION XI ITEM NO./CAT.

AUGMENTED EXAMINATION REQUIREMENT(S)

COMPONENT OR WELD NO. / DESCRIPTION

EXAMINATION PROCEDURE(S)

CALIBRATION BLOCK(S)

EXAM SHEET NO(S). RESULTS REMARKS

21201-060-7

3" VALVE TO PIPE

21201-060-10

3" PIPE TO VALVE

21204U6079

VALVE BOLTING (ISI-21204-124)

PT-V-605

PT-V-605

VT-V-715

S01V2P035 NRI

S01V2P036 NRI

S01V2V005 SAT

N/A

N/A

EXAMINED IN PLACE UNDER TENSION.

7-3

(

B9.21 B-J

B9.21 B-J

B7.70 B-G-2

VEGP- 2 EIGHTH MAINTENANCE / REFUELING OUTAGE CLASS 2 EQUIPMENT EXAMINATIONS

ASME SECTION XI ITEM NO.ICAT.

C2.21

C-B

AUGMENTED EXAMINATION REQUIREMENT(S)

COMPONENT OR WELD NO. I DESCRIPTION

212011-B6-001-W18

32" STEAM OUTLET NOZZLE TO UPPER HEAD WELD

EXAMINATION CALIBRATION PROCEDURE(S) BLOCK(S)

MT-V-505 409A

UT-V-411

EXAM SHEET NO(S).

S01V2M023

RESULTS

NRI

REMARKS

SURFACE ONLY. VOLUMETRIC PERFORMED 2R7.

8-1

VEGP- 2 EIGHTH MAINTENANCE / REFUELING OUTAGE

CLASS 2 PIPING EXAMINATIONS

ASME SECTION XI ITEM NO.ICAT.

C5.11

C-F-1

AUGMENTED EXAMINATION REQUIREMENT(S)

A[ 87-0131

Al 87-0131C5.11

C-F-1

C5.11

C-F-1

C5.11

C-F-1

C5.11

C-F-1

Al 87-0131

A[ 87-0131

A[ 87-0131

Al 87-0131C5.11 C-F-1

C5.11 C-F-1

Al 87-0131

COMPONENT OR WELD NO. / DESCRIPTION

21204-008-3

8" PIPE TO ELBOW

21204-008-4

8" ELBOW TO PIPE

21204-011-6

6" PIPE TO TEE

21204-012-10

8" ELBOW TO PIPE

21206-005-1

8" FLANGE TO PIPE

21206-005-2

8" PIPE TO ELBOW

21206-006-1

8" FLANGE TO PIPE

EXAMINATION CALIBRATION PROCEDURE(S) BLOCK(S)

PT-V-605 UT-V-481

PT-V-605

UT-V-481

PT-V-605

UT-V-481

PT-V-605

UT-V-481

PT-V-605

UT-V-481

PT-V-605

UT-V-481

PT-V-605

UT-V-481

414A

414A

337A

414A

414A

414A

414A

EXAM SHEET NO(S).

S01V2P001

S01V2U 302

S01V2U303

S01V2P002

S01V2U304

S01V2U305

S01V2P008

S01V2U307

S01V2U308

S0lV2P011

S01V2U306

S0lV2U322

S01V2P007

S01V2U314

S01V2U319

S01V2U320

S01V2U321

S01V2P006

S01V2U317

S01V2U318

S01V2P003

S01V2U315

S0lV2U316

S01V2U323

RESULTS REMARKS

NRI

NRI

T&C

NRI

NRI

T&C

NRI

NRI

T&C

NRI

NRI

T&C

NRI

NRI

NRI

NRI

T&C

NRI

NRI

T&C

NRI

NRI

T&C

NRI

N/A

N/A

N/A

N/A

UT SCANS LIMITED / RELIEF REQUEST REQUIRED.

N/A

UT SCANS LIMITED / RELIEF REQUEST REQUIRED.

9-1

VEGP- 2 EIGHTH MAINTENANCE / REFUELING OUTAGE

CLASS 2 PIPING EXAMINATIONS

ASME SECTION XI ITEM NO./CAT.

C5.11

C-F-1

C5.11

C-F-1

C3.20 C-C

C3.20 C-C

AUGMENTED EXAMINATION REQUIREMENT(S)

Al 87-0131

Al 87-0131

COMPONENT OR WELD NO. I DESCRIPTION

21206-006-2

8" PIPE TO ELBOW

21206-006-3

8" ELBOW TO PIPE

21206-006-18

SUPPORT H008

21206-006-41

SUPPORT H015

EXAMINATION CALIBRATION PROCEDURE(S) BLOCK(S)

PT-V-605

UT-V-481

PT-V-605

UT-V-481

PT-V-605

PT-V-605

414A

414A

EXAM SHEET NO(S).

S01V2P004

S01V2U312

S01V2U313

S01V2P005

S01V2U309

S01V2U310

RESULTS REMARKS

NRI

NRI

T&C

NRI

NRI

T&C

S01V2P010 NI

S01V2P009 NRI

N/A

N/A

N/A

N/A

9-2

C ( I,

ASME Sect. Support No. & Examination Exam XI Cat. ISI Class Description. Procedures Sheet No. Results Remarks

See Note A See Note B See Note C See Note D See Note E See Note F See Note G

NOTES:

A. The ASME Section XI category designation for the equipment support is listed in this column.

B. The ASME Section XI class no., e.g., 1, 2, or 3, for the system on which the equipment support being examined is listed in this column.

C. The equipment support number and support description are listed in this column.

D. This column lists the applicable NDE procedure(s) used during the examination. When a class 3 support lists VT-V-715 (VT-1) in addition to VT-V-735 (VT-3), the class 3 support also received a VT-1 on the integral attachment per IWD-2500-1 and Code Case N-509 (RR-20).

E. This column references the examination data sheet(s) which serve to document the examination and lists the examiner, any pertinent remarks, etc.

F. The results of the examinations are indicated in this column.

G. The remarks column is used to describe any pertinent features of the examination such as limitations, reportable results, INFs, etc. Refer to INF section in this report for their disposition.

FIGURE 2. EXPLANATION OF EQUIPMENT SUPPORT SUMMARY TABLE FORMAT

10-1

EQUIPMENT SUPPORT EXAMINATIONS

No equipment support examinations were performed during the 2R8 maintenance/refueling outage.

10-2

( ( I

ASME Sect. Support No. & Examination Exam

XI Cat. ISI Class NPS (In.) Description Procedure(s) Sheet No. Results Remarks

See Note A See Note B See Note C See Note D See Note E See Note F See Note G See Note H

NOTES:

A. The ASME Section XI category designation for the piping support is listed in this column.

B. The ASME Section XI class no., e.g., 1, 2, 3, for the system on which the piping support being examined is listed in this column.

C. This column indicates the nominal pipe size in inches for the piping on which the piping support is being examined.

D. The piping support number and support description are listed in this column.

E. This column lists the applicable NDE procedure(s) used during the examination. When a class 3 support lists VT-V-715 (VT-1) in addition to

VT-V-735 (VT-3), the class 3 support also received a VT-1 on the integral attachment per IWD-2500-1 and Code Case N-509 (RR-20).

F. This column references the data sheet(s) which serve to document the examination and list the examiner, any pertinent remarks, etc.

G. The results of the examinations are indicated in this column.

H. The remarks column is used to describe any pertinent features of the examination such as limitations, reportable results, INFs, etc. Refer to INF section in this

report for their disposition.

FIGURE 3. EXPLANATION OF PIPING SUPPORT SUMMARY TABLE FORMAT

11-1

PIPING SUPPORT EXAMINATIONS

No piping support examinations were performed during the 2R8 maintenance/refueling outage.

11-2

Snubber Mfgr/Size

See Note C

Scope Examined

See Note D

A. The unique tag number for the snubber being examined is listed in this column.

B. The ASME Section XI class no., e.g., 1, 2, 3, for the system on which the snubberbeing examined is listed in this column.

C. This column lists the name of the manufacturer of any snubbers functionally tested and the size of the snubber, e.g., PSA-1/4. Manufacturer designations are abbreviated and can be found in the List of Abbreviations.

D. This column lists the scope of examination in which the snubber is functionally tested, i.e., original scope or expanded scope. Snubbers included in the expanded scope of examination are generally as a result of other snubber functional test failures.

E. The results of the functional test of the snubber tested is listed in this column.

FIGURE 4. EXPLANATION OF SNUBBER FUNCTIONAL TEST RESULTS SUMMARY TABLE FORMAT

12-1

Tag Number

See Note A

ISI Class

See Note B

NOTES:

Results

See Note E

TAG NUMBER 21201-239-H001

21204-057-H019

21208-047-H604

21217-073-H623

21305-063-H1004

21305-063-H004E

22402-022-11004

22402-023-H003

VEGP-2 EIGHTH MAINTENANCE/REFUELING OUTAGE SNUBBER FUNCTIONAL TESTS

TYPE I SNUBBERS

SNUBBER SCOPE ISI CLASS MFGR/SIZE EXAMINED RE 2 PSA-1/2 EXPANDED PA,

2 PSA-1/2 PREV FAILURE PA

1 PSA-1/2 PREV FAILURE PA

3 PSA-1/4 ORIGINAL PA

- PSA-1/2 PREV FAILURE PA

- PSA-1/2 PREV FAILURE PA

PSA-1/4 ORIGINAL PA

PSA-1/4 ORIGINAL PA

SULTS SS

SS

SS

SS

SS

SS

SS

SS

TYPE II SNUBBERS

TAG NUMBER 21201-030-H608

21201-030-H611

21206-005-11008

21208-001-H026

21301-015-H007

21301-094-H002

21305-155-H003

ISI CLASS 1

1

2

1

2

SNUBBER MFGR/SIZE PSA-3

PSA-3

PSA-3

PSA-3

PSA-3

PSA-10

PSA-3

SCOPE EXAMINED ORIGINAL

ORIGINAL

ORIGINAL

ORIGINAL

ORIGINAL

EXPANDED

ORIGINAL

TYPE Ill SNUBBERS

TAG NUMBER 21201-053-11005

21204-126-H020

21305-056-H022B

ISI CLASS 1

SNUBBER MFGR/SIZE PSA-35

PSA-35

PSA-35

SCOPE EXAMINED ORIGINAL

ORIGINAL

ORIGINAL

12-2

RESULTS PASS

PASS

PASS

PASS

PASS

FAILED

PASS

RESULTS PASS

PASS

PASS

VEGP-2 EIGHTH MAINTENANCE/REFUELING OUTAGE SNUBBER FUNCTIONAL TESTS

(continued)

TYPE IV SNUBBERS

TAG NUMBER 21201-014-H641

21201-051-H006

21201-106-HOOI

21202-231-H030

21204-192-HOOI

21208-007-H002

21208-008-H025

21208-011-H045

21208-055-H046

21208-225-H004

21217-071-H628A

21301-118-H011

21301-121-H004

21301-127-H024

21301-128-H006

21301-129-HO16

21301-136-H003

21301-137-H004

21301-139-H003

21301-168-HOOI

21301-168-HO12

21301-213-H003

21302-108-H005

21302-109-HO13

21302-109-HO15

21302-110-H019

ISI CLASS 2

1

2

2

1

2

2

2

2

3

2

2

2

2

2

2

2

2

2

2

2

2

2

SNUBBER MFGR/SIZE AD-41

AD-41

AD-71

AD-153

AD-503

AD-501

AD-73

AD-41

AD-153

AD-41

AD-41

AD-151

AD-43

AD-503

AD-501

AD-151

AD-71

AD-151L

AD-71

AD-41

AD-73

AD-73

AD-503

AD-503

AD-501

AD-501

SCOPE EXAMINED ORIGINAL

ORIGINAL

ORIGINAL

ORIGINAL

ORIGINAL

ORIGINAL

ORIGINAL

ORIGINAL

ORIGINAL

PREV. FAILURE

ORIGINAL

ORIGINAL

ORIGINAL

ORIGINAL

ORIGINAL

ORIGINAL

ORIGINAL

ORIGINAL

ORIGINAL

ORIGINAL

EXPANDED

ORIGINAL

ORIGINAL

ORIGINAL

ORIGINAL

ORIGINAL

12-3

RESULTS PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

VEGP-2 EIGHTH MAINTENANCE/REFUELING OUTAGE SNUBBER FUNCTIONAL TESTS

(continued)

TYPE V SNUBBERS

12-4

TAG N UMBER 21201-064-11614A

21201-064-H614B

21201-064-11625

21202-004-H073

21204-023-HOOI

21204-023-11005

21204-023-H009

21204-024-H038

21204-025-H006

21204-043-H013

21204-125-H007

21205-007-H019

21208-008-H018

21301-014-H005

21301-015-H004

21301-104-H004

21301-104-11005

21301-104-11006

21301-105-11002

21301-105-1-1003

21301-105-11006

21301-106-11002

21301-106-11005

21301-106-11006

21301-107-11004

21301-107-11005

ISI CLASS

3

1

1

1

1

1

1

1

2

2

2

2

2

2

2

2

2

2

2

2

2

2

2

SNUBBER MFGR/SIZE AD-1603

AD-1603

AD-1601

AD-1601

AD-5501

AD-1603

AD-1601

AD-1601

AD-1601

AD-1601

AD-5501

AD-1603

AD-1603

AD-1603

AD-1603

AD-5501

AD-5501

AD-5501

AD-5503

AD-12501

AD-5501

AD-5503

AD-5501

AD-5501

AD-5501

AD-5501

SCOPE EXAMINED ORIGINAL

EXPANDED

EXPANDED

ORIGINAL

ORIGINAL

EXPANDED

ORIGINAL

EXPANDED

EXPANDED

EXPANDED

EXPANDED

ORIGINAL

EXPANDED

EXPANDED

ORIGINAL

EXPANDED

EXPANDED

EXPANDED

ORIGINAL

CR#199901715

EXPANDED

EXPANDED

EXPANDED

EXPANDED

ORIGINAL

EXPANDED

RESULTS PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

FAILED

PASS

PASS

PASS

PASS

PASS

PASS

PASS

FAILED

PASS

PASS

PASS

VEGP-2 EIGHTH MAINTENANCE/REFUELING OUTAGE SNUBBER FUNCTIONAL TESTS

(continued)

TYPE V SNUBBERS (continued)

TAG NUMBER 21301-107-H006

21302-109-H018

21302-109-H024

21302-110-HO13

21305-058-H003

21305-058-HOO5

21305-060-1-1003

21305-060-HG005

21305-062-H006

21305-064-H006

22403-036-H601

ISI CLASS 2

2

2

2

2

2

2

2

2

2

SNUBBER MFGR/SIZE AD-5501

AD-1603

AD-1603

AD-1601

AD-12501

AD-12501

AD-12501

AD-12501

AD-12501

AD-12501

AD-1601

SCOPE EXAMINED EXPANDED

ORIGINAL

EXPANDED

ORIGINAL

EXPANDED

ORIGINAL

EXPANDED

EXPANDED

ORIGINAL

EXPANDED

EXPANDED

TYPE VI SNUBBERS

SNUBBER MFGR/SIZE

SCOPE EXAMINED

212011-B6-002-S08 2

RESULTS PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

PASS

TAG NTTMRE•R TSI CTA~Sq

PM-25701

RESULTS

ORIGINAL PASS

12-5

NUMBER ISI CLASS

SYSTEM PRESSURE TESTS

The following pressure tests were included in the scope of the eighth maintenance/refueling outage (2R8) at VEGP-2. These pressure tests included system inservice tests and system leakage tests. No functional tests or hydrostatic tests were performed during 2R8. Boundaries for the pressure tests that were performed during 2R8 are described in the VEGP-2 Inservice Inspection Plan - Second 10-Year Interval document. Examination results are discussed in the applicable sections of this report document. The examination data for these pressure tests is available at the plant site for review upon request.

System Inservice Test Schedule (ITs)

System Leakage Test Schedule (LT)

LT Exam. Test Description

B-PI Class 1 System Leakage Test

NOTE 1: Most portions of this pressure test boundary were examined prior to the end of the seventh maintenance/refueling outage. The remaining portions were examined after the end of the seventh maintenance/refueling outage after the incorporation of a design change (DCP-V2NO056) which replaced the positive displacement charging pump with a centrifugal-type normal charging pump.

13-1

INDICATION NOTIFICATION FORMS

No Indication Notification Forms were required during the 2R8 maintenance/refueling outage.

14-1

OWNER'S REPORTS FOR REPAIRS OR REPLACEMENTS (FORM NIS-2)

The following Owner's Reports for Repairs or Replacements (Form NIS-2) are provided for work activities documented at VEGP-2 since the last maintenance/refueling outage (2R7) through the completion of the eighth maintenance/refueling outage (2R8) in May 2001. Reports are identified by their respective traveler number which is denoted on each of the NIS-2 reports. The originals of the NIS-2 reports are filed with their respective traveler packages at the plant site. Only those NIS-2 reports applicable to VEGP-2 are included in this report document. Any attachments, e.g., code data reports, etc., referenced in the NIS-2 reports will be made available for review upon request at the plant site.

The NIS-2 reports for the following travelers are included herein:

96236 99138 99181 99224 99264 99282 96348 99139 99189** 99226 99265 99283 99050 99140 99190** 99227 99266 99285 99051 99141 99191 99228 99267 00015 99052 99142 99202 99229 99271 00087 99115 99143 99204 99232 99272 00090

99124 99144 99209 99233 99273 00139 99125 99145 99210 99257 99274 00141

99127 99146 99211 99258 99275 00157

99128 99148 99218 99259 99276 00193 99129 99149 99219 99260 99277 01003

99130** 99150** 99221 99261 99278 01011 99131 99170 99222** 99262 99279 99133 99179** 99223 99263 99280

"**These travelers are certified on the same NIS-2 report:

99130 is certified with 99222, 99150 is certified with 99179, and 99189 is certified with 99190.

15-1

ORIGINAL FORM NIS-2 OW 4ER'S REPORT FOR REPAIRS OR REPLACEMENTS

As F ,quired By The Provisions Of The ASME Code Section Xl

Traveler # 96-236

1. Owner Georgia Power CompFny Name

333 Piedmont Avenue, Atlanta GA.

2. Plant Voqtle Electric Generatina Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Namr-e

4. Identification Of System

Date

Sheet

Unit

MWO #

9/12/96

I of

2

29601768 Repair Organization P.O. No., Job No., etc.

Plant Voutle Address

1208 / Chemical and Volume Control Sv sten5. (a) Applicable Construction Code ASME SEC II1 1977 Edition, Winter 1977 Addenda, N-249-1 Code Case

(b)Applicable Edition of section XI Utilities For Repairs Or Replacements 1983

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTUR NATIONAL " REPAIRED, ASME CODE OF OF E', BOARD OTHER YEAR REPLACED OR STAMPED COMPONENT MANUFACTURER SERP L NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO)

PULLMAN NI.A N/A V2-1208-066-HO19 19d8o REPLACEMENT YES PIPE POWER •14 e/'1 SUPPORT PR UCT,-,q

7. Description Of Work Snubber Ar-43. S&W 402 was replaced with AD-43, SIN 258 to support surveillance testing.

8. Test Conducted: NIA

Hydrostatic ] Pneumatic[] Nominal Operating Pressure[] Other [] Pressure N/A PSI Test Temp. NiA OF

We certify that the statements made in th. report are correct and this rules of the ASME Code, Section XI.

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commtss-ion issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georgia arid employed by Hartford Steam boiler Insnection and Insurance Co of a C. nneticu have inspected the components described in this Owner's Report during the period • , , to -, - o , and state that to ýhe best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

s�-1

By signing this certificate, neither !he Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any nner for any personal injury or property damage or a loss of any kind arising from or connected with this ýi Commissions 9A0o3

"Ineor's Signature National Board, State, Provi:.:- and Endorsements

Date /_ 200

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI

Traveler

I Owner

2 Plant

flsrn/. Din.,.. fla.,.a....

Name 333 Piedmont Avenue. Atlanta GA

Voati. Electtlc Generatino Piau,

Wa*nasbr-O. CA 102l8aAddress

3 Work Performed ByL % Maintenance

Date I1, -A % sheet____________

unit_

Repair Organization P.O. No., Job No., etc.

P/anf VefiftName Address

4 identification Of Systm \ \ ~ d\~ ~~'~ ~ ImA kAC-'ý 5 ali Applicable Construction Code.ASME SEC i•1 .EEdition, Witeor 1•t Addenda, N-249-. Code Case

fb) Applicable Edition Of Section XI Utilities For Repairs Or Replacernents 19.U

I idenlafication Of Components Repairs Or Replaced And Replacement Components

%&ME NAME MANUFACTURER NATIONAL REPAIRED, ASME COOE or OF SERIAL eo7o OmE YEAR R0AEt.•.D OR STAMPED _.______ENT MANUFACTURER NO. NO. IDENTIFICATION GMT RAYCS OR NO

Puolman Po,•,t WA -\ Xl\ 9 j Pope Support Products NWA W/A \rc -, ýA6 _- "f,•Q 98 Repnl_€emen.t

7. Description Of Work Snubbi

8. Tests Conducted: WNAIW

.Serlal#

Hydrostatic:: Pneumatic: Nominal Operating Pressure0 OtherZ Pressum PSI Test Temp. _ F

CERTIFICATE OF COMPLANCE - V, " We certify that the statements made in the report are correct and this e-.o\ r. :- conforms to the rules of the ASME Code, Section XL

repair or replacement

Type Code Symbol Stamp.

Certificate of Atlthýation No.

AI'IQIUVW OT • u~r,,NMsNlAN1A Date

O....... r. ....... -'"; mI'+ " '

WA

WI' xpiraton UDat

Date . . nao -

was re laced wth AD - 1 Serial 0 Lt 1 -1

WA72/]+

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid conmission issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Gworala and employed by Harfford Steam Boiler Inspecctlon and Insurance Co. of Hartford, Connectlicut have inspected the components described in this Owner's Report during the period I&-7-1-. to. JL-Wo60 -, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owner's Report in accordance with the requirements of the ASME Code, Section XL

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable In any manner for any personal Injury or property damage or a loss of any kind arising from or connected with this inspection. ,

Comriss.ons GA 701

Nauonal Board, State, Province and EndorsementsDate

Voatle Ef tife Commune PLa,.#

. - . ....... •rlT1

i

,ý, 4- - -,a -ý. ctc",-,rea

I r ¸

Owner or Owner's Desi - -a ,

,99(-Zol----- "• Ybl

AD- I

v_

'ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

1. Owner Southern NuclearOperating Company Name

40 Invemess Center Parkway, Birmingham, AL

2. Plant Vogte Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler # 99050

09/15/99

Of

2

29900308 Repair Organization P.O. No., Job No., etc.

Plant VoctleAddress

4. Identification Of System 1208 / Chemical and Volume Control

5. (a) Applicable Construction Code ASME SEC III 1974 Edition, Summer 1975 (b)Applicable Edition of section Xi Utilities For Repairs Or Replacements 19M

6. Identification Of Components Repairs Or Replacement Components

system

Addenda, NIA

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) VALVE ROCKWELL BX844 N/A 2-1208-U4-483 1985 REPLACEMENT YES

INTERNATIONAL

7. Description Of Work Performed locking tack weld on valve caD to body connection per WPCS 990050.

8. Test Conducted: Hydrostatic [] Pneumatic[] Nominal Operating Pressure[E] NIA Other E Pressure N/A PSi Test Temp. N/A 9F

CERTIFICATE OF COMPLIANCE

We certify that the statements made In the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed Owne or Ownr ' TDate IT 19 Owner or Owner's Designee,Tti

Date //-/9 19 010

4l

Code Case

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford, Connecticut have inspected the components described In this Owner's Report during the period 01/21/99 to //- Jq-L t , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report in accordance with the requirements of the ASME Code, Section Xi.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this

Ins ACti " •A-2L/aý- L Commissions__ ____

Inspector's Signature / National Board, State, Province and Endorsements

ORIGINAL. FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xi

Traveler # 99051

1. Owner Southem Nuclear Operating CompanyName

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogte Electric Generating Plant

Waynesboro, GA 30830Address

3. Work Performed by Nuclear Operations MaintenanceName

Date

Sheet

Unit

03/23/00

1 Of 3

2

MWO # WO# 29900499, PO# 7038022 and PO# 7038895 Repair Organization P.O. No., Job No., etc.

Plant Vogtle Address

4. Identification Of System 1201 / Reactor Coolant System

5. (a) Applicable Construction Code ASME SEC IIl 1971 Edition, Winter 1972 (b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989

Addenda, N/A

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) SAFETY CROSBY VALVE N60446-02- N/A 2PSV-8OOB 1978 REPLACEMENT YES

VALVE & GAGE CO. 0028

7. Description Of Work Valve was re=laced. The reolacement valve was purchased under PO 7038022 from Union Electric's, Plant Callowav as S/N N60446-00-0028. The setooint pressure for this valve was changed by Crosby Valve & Gaoe Company under PO 7038895 in accordance with DCP 97-V2N0009. CrosbV Valve & Gaae Company assigned SIN N60446-02-0028 to this valve uoon completion of the setnoint chance. A copy of Form NV- i for the original serial numbered replacement valve is attached.

8. Test Conducted: WA-

Hydrostatic [] Pneumatic[l Nominal Operating Pressure[x' Other [] Pressure NIA PSI Test Temp. N/A

Date 7- 120

I

Code Case

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section XI. Repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No. a A

Owner or Owner's Desinee, Title 7

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Geoomia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticui have Inspected the components described In this Owner's Report during the periodQIl . to owAriJA.a, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report In accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any man for any personal injury or property damage or a loss of any kind arising from or connected with this inspepton. /J/

_______________ __.____- ___ Commissions (•4ppJ' "Inspec)6r's Signature National Board, State, Province and Endorsements

2000•

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

1. Owner Southern Nuclear Operating CompanyName

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations MaintenanceName

4. Identification Of System

Date

Sheet

Unit

Traveler # 99052

03/30/00

Of 3

2

MWO # WO# 29900499, PO# 7038220 and PO# 7038895 Repair Organization P.O. No., Job No., etc.

Plant Vogtle Address

1201 / Reactor Coolant System

5. (a) Applicable Construction Code ASME SEC III 1971 Edition, Winter 1972 (b)Applicable Edition of Section Xi Utilized For Repairs Or Replacements 19L9

Addenda, N/A Code Case

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) SAFETY CROSBY VALVE N60446-02- N/A 2PSV-801IA 1978 REPLACEMENT YES VALVE & GAGE CO. 0006

7. Description Of Work Valve was replaced. The replacement valve was purchased under PO 7038220 from Union Electric's, Plant Callowav as S/N N60446-00-0006. The setooint pressure for this valve was changed by Crosby Valve & Gace Company under PO 7038895 in accordance with DCP 97-V2NO009. Crosby Valve & Gage Company assgqned S/N N60446-02-0006 to this valve upon completion of the setpoint chance. The valve nozzle, disc insert and spindle assembly were also replaced durino this modification. A cony of Form NV-1 for the oriomnin~ _.rrinl

8. Test Conducted: MAD

61II1I�

Hydrostatic [ PneumaticE Nominal Operating Pressure'X Other ] Pressure N/A PSI Test Temp. N/A 2F

I

CERTIFICATE OF COMPLIANCE

We certify that the statements made In the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section XI. Repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No. _ror__,__seeTtl_

Signed ~ )l~J-~, ae' 1 20 &o~ Ow-ner -or `Owner's Designlee, Ttie -

CERTIFICATE OF INSERVICE INSPECTION

1, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford, Connecticut have inspected the components described In this Owner's Report during the period 01/25/99 to 7-/L-x -, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore,. neither the Inspector nor his employer shall be liable In any mann for any personal Injury or property damage or a loss of any kind arising from or connected with this

VY//,&' s_.x. ,_... Commissions _ A__ 3__ "lnspectssig;nature National Board, State, Province and Endorsements

Date 7-...(" 20 oOe•

soindle assembly were also replaced dunna this modification A cony of Forin NV-1 for the nrini, / sF,_Z" 2EWkWa-U.

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

1. Owner Southern NuclearOperating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogde Elecfrc Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler # 99115

08112J99

! of 3

2

29901418 Repair Organization P.O. No., Job No., etc.

Plant VogUeAddress

4. Identification Of System 1202/NuclearService Cooling Water

6. (a) Applicable Construction Code ASME SEC III 1974 Edition, Winter 1975 (b)Applicable Edition of section Xl Utilities For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

System

Addenda, N/A Code Case

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) VALVE CROSBY VALVE N67951-00-0011 N/A 2PSV-11744 1999 REPLACEMENT YES

& GAGE CO.

7. Description Of Work Safety relief valveS/N N67951-00-0003 was replaced with S/N N67951-00-001 1. A copy of Form NV-I for the replacement valve is attached,

8. Test Conducted: Hydrostatic [] Pneumatic[] Nominal Operating Pressurerx NWA [] Other Fl Pressure NIA PSI Test Temp. N/A OF

CERTIFICATE OF COMPUANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization No. NIA Expiration Date N/A

Signed " 64 ,. ,•") J- Date }iu 19 q9 Owner or Owner's Designee, TitleL/

4 i'CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Geormia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford, Connecticut have inspected the components described in this Owner's Report during the period 04/21/99 to 9.j-0-7-9 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in an manner for any perxe al injury or property damage or a loss of any kind arising from or connected with this ins ion. Commissions . g4S,7

Inspectors Signature 7 Nationdl Board, State, Province and Endorsements

Date Z' •7 19

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

1. Owner Southern Nuclear Operating CompanyName

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler # 99124

02/25/00

Of 5

2

29901684Repair Organization P.O. No., Job No., etc.

Plant VogtleAddress

4. Identification Of System 12081 Chemical and Volume Control System

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 Addenda, N/A Code Case (b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 1989 Code Case N-416-1

6. Identification Of Components Repairs Or Replacement Components

I I. I ______________ I

7. Description Of Work Installed piping modifications per DCP 97-V2NO056. The modification included installation of orifice 2FO-10133 and a olobe valve (2-1208-U4-150). Copies of Form N-2 for the flow orifice (SIN 98P-91447) and Form NPV-1 for the olobe valve (SIN B3995) are attached,

8. Test Conducted: N/Al

Hydrostatic[] PneumaticE Nominal Operating Pressureg]Code Case N-416-1 Other R Pressure N/A PSI Test Temp. N/A 2F

Date ____-__ Zg_

'I

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO)

1208 PIPING SOUTHERN N/A N/A 2J3-1208-501-01 1999 REPLACEMENT NO SYSTEM NUCLEAR

IOPERA TING QQ-

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT Conforms to the rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization No. N/A Expiration Date F. :;2 W,4 N/A

Signed aYý _ Date atsO Owner or Owner's Designee, Tl1t%

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Ggooi.a and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticut have inspected the components described in this Owner's Report during the period 06/14/99 to j09- C)- ) - , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any onal Injury or property damage or a loss of any kind arising from or connected with this Ins~ton. _ _ _ _ _ __ _

I ionspeco 's " Commissions C alBog S Inpco' intrrNatinlBo ard, State, Province and Endorsements

-ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

Traveler # 99125

1. Owner Southern Nuclear Operating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Wavnesboro, GA 30830Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO#

02t28/00

_ _ _ _ _ Of _

2

29901681 and 29901683 Repair Organization P.O. No., Job No., etc.

Plant VogSte Address

4. Identification Of System 1208 / Chemical and Volume Control System

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 Addenda, N/A Code Case

(b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989 Code Case N-416-1

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) 1208 PIPING SOUTHERN N/A N/A 2K3-1208-003-01 1999 REPLACEMENT NO

SYSTEM NUCLEAR

7. Description Of Work Installed Diping modifications eer DCP 97-V2NO056. This modification includes the installation of a flow orifice 2F0-10 124. fabricated under Section XI Traveler# 99132 and WO# 29901681.

8. Test Conducted: WAD

C

Hydrostatic [ Other E

Pneumatic[] Nominal Operating Pressure[K]Code Case N-416-1 Pressure WA PSI Test Temp. N/A OF

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT Conforms to the rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization No. N/A Expiration Date• l-N/A

Signed "N, Date ____,__ _

Owner or Owner's Designfee, TItI'-

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticut have Inspected the components described In this Owner's Report during the period 06114199 to 3.-ZZ- op O, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal Injury or property damage or a loss of any kind arising from or connected with this Insection. 9 " d.7 ln ,cf_!•j / , Commissions _ _ _ _ _ _ _ _

Inspector's Signature/ Nationial Board, State, Province and Endorsements

Date OkZZ-00

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xi

1. Owner Southern Nuclear Operating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830Address

Traveler # 99127

03/07/00Date

Sheet I Of 3

Unit

MWO#

3. Work Performed by Nuclear Operations Maintenance Name

2

29901682 Repair Organization P.O. No., Job No., etc.

Plant VogqteAddress

4. Identification Of System 1208 / Chemical and Volume Control System

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 Addenda, N/A (b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 1989 Code Case N-416-1

6. Identification Of Components Repairs Or Replacement Components

Code Case

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) 1208 PIPING SOUTHERN N/A N/A 2K3-1208-123-01 1999 REPLACEMENT NO

SYSTEM NUCLEAR OPERATING QQ

7. Description Of Work Installed piping modifications per DCP 97-V2NO056. This modification included the installation of various pipe fittinos tccommainstallation of the new charoino pumo as well as 2" drain valve (2-1208-X4- 6071A conyof Form NPV-1 for this valve S/N C2499 is attached.

8. Test Conducted: NIAE

cAý

Hydrostatic [] Pneumatic[] Nominal Operating Pressure[X]Code Case N-4116-1 Other F1 Pressure NIA PSI Test Temp. NIA 'F

CERTIFICATE OF COMPLIANCE

We certify that the statements made In the report are correct and this REPLACEMENT Conforms to the rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization.No. N/A Expiration Date N/A

Signed " ,1' J'i1kha-# Y n I Date 7 ) • 200, Owner or Owner's Designee, Title

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Insoection and Insurance Co. of Hartford. Connecticut have Inspected the components described In this Owner's Report during the period 0_114/99 to e,4-0-5-00_, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be lipble in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this In n Commissions 1A 4197

Inspector's Signaturoe National Board, State, Province and Endorsements

Date s 0-!5 20 40

!

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

1. Owner Southern Nuclear Operating Company Name

40 Invemess Center Parkway, Birmingham, AL

2. Plant Vogte Electric Generating Plant

Waynesboro, GA 30830Address

3. Work Performed by Nuclear Operations Maintenance

Date

Sheet

Unit

MWO #

Name

Traveler # 99128

03/03/00

Of

2

29901732 Repair Organization P.O. No., Job No., etc.

Plant Voctle

Address

4. Identification Of System 1208 / Chemical and Volume Control System

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 Addenda, N/A Code Case (b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989 Code Case N-416-1

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) 1208 PIPING SOUTHERN N/A N/A 2K3-1208-003-01 1999 REPLACEMENT NO

SYSTEM NUCLEAR 2K3-1208-003-03 OPERATING Q, 2K3-120R-09q-O1

7. Description Of Work Installed pininG modifications oer DCP 97-V2NO056. This modification included the installation of varinus nin,fittinas to accommodate installation of the new charaina Dump.

8. Test Conducted: WAJ

Hydrostatic r- Pneumatic[] Nominal Operating Pressure[Z]Code Case N-416-1 Other El Pressure N/A PSI Test Temp. N/A QF

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georaia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Harford. Connecticyu have inspected the components described in this Owner's Report during the period 06/14/99 to p5-ol/.. 600, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable In any manner for any p~r~onal injury or property damage or a loss of any kind arising from or connected with this Insl:to - Co sn -- "=44tg- • • •••-- Commissions 1,4- 4"'97

National Board, State, Province and Endorsements

2o

-EInspector's Signature e'

Date /3_ - t•/

v

Sw • r

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

Traveler # 99129

1. Owner Southern Nuclear Operating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Voptle Electric Generating Plant

Waynesboro, GA 30830Address

Date

Sheet

Unit

MWO #

3. Work Performed by Nuclear Operations Maintenance Name

02122/00

I Of

2

29901624 and 29902725 Repair Organization P.O. No., Job No., etc.

Plant VogUeAddress

4. Identification Of System 1208 / Chemicai and Volume Control System

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 Addenda, N/A (b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 19" Code Case N-416-1

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) 1208 PIPING SOUTHERN N/A N/A 2K3-1208-144-01 1999 REPLACEMENT NO

SYSTEM NUCLEAR OPERA TING QO

7. Description Of Work Installed eiia modifications per DCP 97-V2N056. The modification included installation of orifice plate 2F010123 which was fabricated under Traveler# 99221: the addition of a pressure indicator 2PI-8474: and the shortenino of the oump discharae spool.

8. Test Conducted: WAfl

Hydrostatic ] Pneumatic[] Nominal Operating Pressure[' Code Case N-416-1 Other 1] Pressure N/A PSI Test Temp. N/A 2F

Code Case

CERTIFICATE OF COMPLIANCE

We certify that the statements made In the report are correct and this REPLACEMENT Conforms to the rules of the ASME Code, Section Xi. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorlzatign No. N/A Expiration Date N/A

Signed Ti• Date "--'- D Owner or Owner's Designee, Title V

CERTIFICATE OF INSERVICE INSPECTION

1, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Insoection and Insurance Co. of Hartford, Connecticui have Inspected the components described in this Owner's Report during the period ,0621/)99 to _"- 9 -O , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report In accordance with the requirements of the ASME Code, Section Xi.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for anyrprsonai injury or property damage or a loss of any kind arising from or connected with this "Ins"pinq Commissions ,A V9 7

Inspector's Signetu National Board, State, Province and Endorsements DateA

ORIGINAL' FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

Traveler # 99222 and 99130

1. Owner Southern NuclearOperating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Voctle Electric Generatinq Plant

Waynesboro, GA 30830Address

3. Work Performed by Nuclear Operations Maintenance Name

4. Identification Of System

Date

Sheet

Unit

MWO #

11/30/99

1 Of I

2

29901625 and 29902725 Repair Organization P.O. No., Job No., etc.

Plant Vogtle Address

1208 / Chemical and Volume Control System

5. (a) Applicable Construction Code ASMESECIII 1977 Edition, Winter1977 Addenda, N/A Code Case (b)Appllcable Edition of Section XI Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) NO.

1208 PULLMAN N/A N/A 2K3-1208-146-01 1988 REPLACEMENT YES PIPING POWER

I YTnM PRODUCTS T

7. Description Of Work Fabricated and installed orfice plate 2F010122 with new boltino materials. Also, installed a sockolet on line 1208-154-4" per DCP 97-V2NO049.

8. Test Conducted: WAD

c

��.1

Hydrostatic [] Pneumatic[] Nominal Operating PressureFrI Other [] Pressure N/A PSI Test Temp. WA

.3

CERTIFICATE OF COMPUANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed / Oneo Owe' DesineeDate 1 /l 19 Owne orOnrsDsineil

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georqia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticu• have inspected the components described in this Owner's Report during the period 021/9 to 0a2 L - , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report In accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any peirsonal injury or property damage or a loss of any kind arising from or connected with this

djcX, - Commissions • I--7 Inspector's Signature V " National 3oard, State, Province and Endorsements

Date _02 - &d_ _JwA

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

Traveler # 99131

1. Owner Southern Nuclear Operating Company Name

40 Invemess Center Parkway, Birmingham, AL

2. Plant Vogtie Electric Generating Plant

Waynesboro, GA 30830Address

Date

Sheet

Unit

MWO #

3. Work Performed by Nuclear Operations Maintenance Name

02/22100

I Of 3

2

29901685 Repair Organization P.O. No., Job No., etc.

Plant VoqtleAddress

4. Identification Of System 1217 / Auxiliary Component Cooling Water System

5. (a) Applicable Construction Code ASME SEC IIl 1977 Edition, Winter 1977 Addenda, N/A (b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 19§1 Code Case N-416-1

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) 1217 PIPING SOUTHERN N/A N/A 2K3-1217-182-02 1999 REPLACEMENT NO

SYSTEM NUCLEAR 2K3-1217-183-03 OPERA TING CO. 2K3-1217-184-01

2K3-1217-186-01

7. Description Of Work Installed DIino modifications oer DCP 97-V2NO056. Modifications include the installation of a 1-1/2" olobe valve. A copy of Form NPV-1 for this valve &W HO50ABJ is attached.

8. Test Conducted: WAE-

Hydrostatic R Pneumatic[] Nominal Operating PressurefZCode Case N-416-1 Other F1 Pressure NIA PSI Test Temp. NIA 2F

'3

Code Case

CERTIFICATE OF COMPLIANCE

We certify that the statements made In the report are correct and this REPLACEMENT Conforms to the rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorizaton No. N/A Expiration Date NIA Signed IAa QDate "___..______

Owner or Owner's Designee, Titlf 90

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georqia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford, Connecticut have Inspected the components described in this Owner's Report during the period 06/14/99 to 4- /-4-o , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report In accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in anyannr for any/,"rsonal Injury or property damage or a loss of any kind arising from or connected with this

ins I Commissionsc4tio 7 Inspector's Signaturi National Board, State, Province and Endorsements

Date_ _ _ _ _ _

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

Traveler # 991331. Owner Southern Nuclear Operating Company

Name 40 Inverness Center Parkway, Birmingharn, AL

2. Plant Vo10e Electic Generating Plant

Waynesboro, GA 30830 Address

Dats

Sheet

Unit

MWO #

03/03100

I Of

2

29901732 Repair Organization P.O. No., Joi No., eatc.

3. Work Performed by Nuclear Operations Maintenance Plant Vogfie

Name Address 4. Identification Of System 1204 / Safety Injection System 5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 Addenda, N/A Code Case (b)Appllcable Edition of Section X1 Utilized For Repairs Or Replacements 198I" Code Case N-416-1

6. Identification Of Components Repairs Or Replacement Components

7. Description Of Work Installed oionOa modifications Per DCp 97-V2NO056. This mldifiction included the installation of a tee in line 1204-057-3' to loin line 1208-003-3'.

8. Test Conducted: N/A

Hydrostatic [3 PneumaticE] Nominal Operating Preseureg]Code Case N-416-1 Other [] Pressure N/A PSI Test Temp. N/A OF

CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georo2L and employed by Hartford Steam Boiler Inspection and Insurance Co. of H have Inspected the components described In this Owner's Report during the period__ Q1AW . to - o_-Z.C_, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report In accordance with the requirements of the ASME Code, Section XI. 0.. •-- -- .

sign.ng mis certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the Iminatlons and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall liable in any manner for any perso7 Injury or property damage or a loss of any kind arising from or connected with this ~cIon. Ar-A' Commissions 6;4.19/- 7

National Board, State, Province and EndorsementsAv �j

uste 20 bol

ORIGINALFORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

1. Owner Southern Nuclear Operating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Voglie Electic Generating Plant

Waynesboro, GA 30830Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler # 99138

02/16/00

I Of

2

29901687 Repair Organization P.O. No., Job No., etc.

Plant VogUeAddress

4. Identification Of System 1208 / Chemical and Volume Control

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 (b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

System

Addenda, N/A

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) 1208 PIPE SOUTHERN N/A N/A V2-1208-0O3-H606 1999 REPLACEMENT NO SUPPORT NUCLEAR

OPRTING CO.I

7. Description Of Work Installed Pice support per DCP 97-V2NO056.

8. Test Conducted: Hydrostatic [] PneumatlcEJ- Nominal Operating PressureE[ WA [] Other [ Pressure N/A PSI Test Temp. WA QF

CERTIFICATE OF COMPLIANCE

We certify that the statements made In the report are correct and this REPLACEMENT Conforms to the rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authori1tio No. N/A Expiration Date N/A

Signed 1 2 I Date _____"_,,_c.___

Owner or Owner's Designee, Tooe 20 $t) O3-1"-CO

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georcia and employed by Hartford Steam Boiler Insoection and Insurance Co. of Hartford nnecti have Inspected the components described in this Owner's Report during the period__.Q9 A ___ to " , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report In accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal Injury or property damage or a loss of any kind arising from or connected with this

ZA.~ ý ý& Commissions G4 4/97 Inspector's Signaturdr National Board, State, Province and Endorsements

Date 0 - 4•-

I

Code Case

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xi

1. Owner Southern Nuclear Operating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler # 99139

03/03/00

Of

2

29901732Repair Organization P.O. No., Job No., etc.

Plant VogdeAddress

4. Identification Of System 12081 Chemical and Volume Control System

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 Addenda, N/A Code Case (b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) 1208 PIPE SOUTHERN N/A N/A V2-1208-OO3-H605 1999 REPLACEMENT NO SUPPORT NUCLEAR

OPERA TING CO.

7. Description Of Work Installed pipe support per DCP 97-V2N056,

8. Test Conducted: Hydrostatic [] Pneumatic[] Nominal Operating Pressure[] WA [j Other E Pressure WA PSI Test Temp. N/A 2F

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT Conforms to the rules of the ASME Code, Section Xi. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorizatin N7. N/A Expiration Date N/A

Signed or tle Date Owner or Owner's Designee, Title

Date os5- 6/ 20ob

7

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel Inspectors and the State oi Province of Georoia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticut have inspected the components described in this Owner's Report during the period 06/14/99 to t6"-/-oa , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be II ble in any manner for any persoll: injury or property damage or a loss of any kind arising from or connected with this in • .• Ž •-4L. •-• •-Commissions S_ __ _ _

Inspector's Signature National Board, State, Province and Endorsements

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

Traveler # 99140

1. Owner Southern Nuclear Operating Company Name

40 Inverness Center Parkway, Blrminqham, AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

4. Identification Of System

Date

Sheet

Unit

MWO #

03/03100

I Of

2

29901732 Repair Organization P.O. No., Job No., etc.

Plant VodlleAddress

1208 / Chemical and Volume Control System

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 Addenda, N/A (b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989

Code Case

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) 1208 PIPE SOUTHERN N/A N/A V2-1208-003-H607 1999 REPLACEMENT NO SUPPORT NUCLEAR

OPERATING C.

7. Description Of Work Installed pide suoport oar DCP 97-V2NO056,

8. Test Conducted: Hydrostatic [] Pneumatic[] Nominal Operating Pressure[] N/A E] Other [] Pressure N/A PSI Test Temp. N/A 9F

CERTIFICATE OF COMPUANCE We certify that the statements made In the report are correct and this REPLACEMENT Conforms to the

rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

# Certificate of Authorization No. N/A Expiration Date N/A

A) Y '0w Signed or kwn r Date 11n 20 Owner or Owner's Designee,V1

Date _____________

I

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of bolier and Pressure vessel Inspectors and the State oi Province of Georqia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticut have Inspected the components described in this Owner's Report during the period 06/14/99 to Lb5"o/-20t0.3 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xi,

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any persnal injury or property damage or a loss of any kind arising from or connected with this _ _ _ _ _ _ Commissions n __/,9_7_

Inspector's Signature National Board, State, Province and Endorsements

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

Traveler # 99141

1. Owner Southern Nuclear Operating Company Name

40 Inverness Center Parkway, Birmingham. AL

2. Plant Voptle Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

03/03/00

I Of 1

2

29901732 Repair Organization P.O. No., Job No., etc.

Plant VootleAddress

4. Identification Of System 1208 / Chemical and Volume Control System

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 Addenda, N/A (b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 19§.

6. Identification Of Components Repairs Or Replacement Components

Code Case

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) 1208 PIPE SOUTHERN N/A N/A V2-1208-003-H029 1999 REPLACEMENT NO SUPPORT NUCLEAR SOPERATING QO

7. Description Of Work Installed Dioe supoort oer DCP 97-V2NO056,

8. Test Conducted: Hydrostatic [] Pneumatlc-- Nominal Operating Pressure[] N/A FXJ Other rE Pressure N/A PSI Test Temp. N/A F

CERTIFICATE OF COMPMANCE

We certify that the statements made In the report are correct and this REPLACEMENT Conforms to the rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization No. N/A Expiration Date N/A

Signed " . Qý 4 Date 20_ Mner or Owner's Designee, TItle L1

5�O

C-

CERTIFICATE OF INSERVICE INSPECTION

1, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georoia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford, Connecticut have Inspected the components described in this Owner's Report during the period 06/14/-to 1)5- 61.260c and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report In accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable In any manner for any personal injury or property damage or a loss of any kind arising from or connected with this

__ Commissions c;, Isti~on., (I,•/7 "

Inspector's Signature National Board, State, Province and Endorsements

Date 2000- )/

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

1. Owner Southern Nuclear Operating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

4.

5.

6.

Date

Sheet

Unit

MWO #

Traveler # 99142

02/16/00

1 Of 1

2

29901687 Repair Organization P.O. No., Job No., etc.

Plant VogtieAddress

Identification Of System 1208 / Chemical and Volume Control System

(a) Applicable Construction Code ASME SEC Ill 1977 Edition, Winter 1977 Addenda, N/A Code Case (b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 1989

Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) 1208 PIPE SOUTHERN N/A N/A V2-1208-123-H604 1999 REPLACEMENT NO SUPPORT NUCLEAR

OPERA TING C(Q.

7. Description Of Work Installed Pipe support per DCP 97-V2NO056.

8. Test Conducted: Hydrostatic [] Pneumatic[] Nominal Operating Pressure[] NIA Other ] Pressure WA PSI Test Temp. WA 2F

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT Conforms to the rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization No. N/A Expiration Date N/A

SOgnedrnejor ne' Dn I T ke Date _ /,___-__

Owner or (Uner's Designee, T1#e) '4000 1~

I

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georqia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticul have Inspected the components described In this Owner's Report during the period 06/14/99 to -O.-:6..,, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable In any manger for any pars al injury or property damage or a loss of any kind arising from or connected with this Insp:in - , f/1,("

!t- LJ . _ Commissions GX LZ97 Inspector's Signature 9V National Board, State, Province and Endorsements

Date 2ýO -. 260_0

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xi

1. Owner Southern Nuclear Operating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations MaintenanceName

Date

Sheet

Unit

MWO #

Traveler # 99143

02/16/00

I Of 1

2

29901687 Repair Organization P.O. No., Job No., etc.

Plant VoatleAddress

4. Identification Of System 1217 / Auxiliary Component Cooling Wat

5. (a) Applicable Construction Code ASME SEC I/1 1977 Edition, Winter 1977 (b)Applicable Edition of Section Xi Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

er System

Addenda, N/A Code Case

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) 1217 PIPE SOUTHERN N/A N/A V2-1217-182-H601 1999 REPLACEMENT NO SUPPORT NUCLEAR

OPERA TING CO.

7. Description Of Work Installed iDe suDOort per DCP 97-V2NO056,.

8. Test Conducted: Hydrostatic F1 PneumaticE] Nominal Operating Pressure[] N/A [ Other ] Pressure N/A PSI Test Temp. N/A 2F

CERTIFICATE OF COMPUANCE

We certify that the statements made In the report are correct and this REPLACEMENT Conforms to the rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization No. N/A Expiration Date N/A

Signed ,2 1k / . Date "..//•.' -R) Owner or Owner's Designee, Titlo'J

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Insoection and Insurance Co. of Hartford. Connecticut have Inspected the components described In this Owner's Report during the period 06/A1_4/99 to 613- Z4- 00 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report In accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any per Il Injury or property damage or a loss of any kind arising from or connected with this

42~~J AýLOýC; Commissions A~4 0 -7Inspectors Signature f /

Date - 20 -ft. ZQ.O

National Board, State, Province and Endorsements

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

1. Owner Southern Nuclear Operating CompanyName

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Wainesboro, GA 30830Address

3. Work Performed by Nuclear Operations MaintenanceName

Date

Sheet

Unit

MWO #

Traveler # 99144

02/16/00

I Of 1

2

29901687 Repair Organization P.O. No., Job No., etc.

Plant VootleAddress

4. Identification Of System 1217 / Auxiliary Component Cooling Wa

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 (b)Applicable Edition of Section Xi Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

.ter System

Addenda, N/A

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) 1217 PIPE SOUTHERN N/A N/A V2-1217-183-H621 1999 REPLACEMENT NO SUPPORT NUCLEAR

OPERATING CO.

7. Description Of Work Installed pipe suoport per DCP 97-V2N0056.

8. Test Conducted: Hydrostatic [ Pneumatic[] Nominal Operating Pressure[_ NWA RX Other R Pressure N/A PSI Test Temp. WA 2F

CERT1FICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT Conforms to the rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization No. N/A Expiration Date N/A

Signed a 1A4 Date 4& //rp -1 e:a

Owner or Own'er's Designee, Title -a -t 00,.

Code Case

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticul have Inspected the components described in this Owner's Report during the period 06/14/99 to a3-,O-0 -, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any man or for any perspnoI Injury or property damage or a loss of any kind arising from or connected with this a,. 7 commissions -04V?7

Inspector's Signature National Board, State, Province and Endorsements

Date ___________

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

1. Owner Southern Nuclear Operating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtie Electric Generating Plant

Date 0

Sheet 1

Unit

raveler # 99145

2/16/00

Of I

2

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

MWO # 29901687Repair Organization P.O. No., Job No., etc.

Plant Vogtle Address

4. Identification Of System 1208 / Chemical and Volume Control System

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 Addenda, N/A Code Case (b)Appilcable Edition of Section Xl Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO)

1208 PIPE SOUTHERN N/A N/A V2-1208-501-H602 1999 REPLACEMENT NO SUPPORT NUCLEAR

OPERA TING C.

7. Description Of Work Installed pipe suPcort per DCP 97-V2NO056.

8. Test Conducted: Hydrostatic [] PneumaticE] Nominal Operating PressureL] N/A[K Other [ Pressure N/A PSI Test Temp. N/A 2F

CERTIFICATE OF COMPMANCE

We certify that the statements made In the report are correct and this REPLACEMENT Conforms to the

rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization No. N/A Expiration Date N/A

Signed a,., 2f o-4, De ) ))R Owner or Owner's Designee, Title 47 ;Vo-i,.Oj

c111Dk

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georqia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticu have inspected the components described In this Owner's Report during the period 061L4L92 to 10-00 -, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any pe on Injury or property damage or a loss of any kind arising from or connected with this inspe ion.I

_____ _____ mmissions 64i 497nd? inspector' Sinature National Board, State, Province and Endorsements

Date 03-20 -'r2-6

K.-

'1 4

1. Owner Southern Nuclear Operating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830Address

Date

Sheet

Unit

MWO #

02/16/00

I Of 1

2

29901687 Repair Organization P.O. No., Job No., etc.

3. Work Performed by Nuclear Operations Maintenance Name

4. Identification Of System

Plant Vogte Address

1208 / Chemical and Volume Control Svstem

5. (a) Applicable Construction Code ASME SEC li 1977 Edition, Winter 1977 Addenda, N/A (b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

Code Case

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) 1208 PIPE SOUTHERN N/A AVA V2-1208-501-H603 1999 REPLACEMENT NO SUPPORT NUCLEAR

OPERA TING CO.

7. Description Of Work Installed ipe suoo oer DCP 97-V2NO056.

8. Test Conducted: Hydrostatic E] Pneumaticj] Nominal Operating PressureaZ N/A F] Other [] Pressure N/A PSi Test Temp. NIA 9=

CERTIFICATE OF COMPUANCE

We certify that the statements made In the report are correct and this REPLACEMENT Conforms to the rules of the ASME Code, Section Xi. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization No. N/A Expiration Date N/A

Signed Owner oO r C.Dl4 M44i -Date -4;Owner or Owner's Designee, TItl~'6' .

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xi

Traveler # 99146

CERTIFICATE OF INSERVICE INSPECTION

1, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticut have Inspected the components described In this Owner's Report during the periodgfid.12-_ to 1-2, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report in accordance with the requirements of the ASME Code, Section Xi.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personpl-.injury or property damage or a loss of any kind arising from or connected with this

_,.d••i-. i . ,- Commissions 4 V9 Inspector's Signature 0 National Board, State, Province and Endorsements

Date 03 - 4 2

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xi

1. Owner Southern Nuclear Operating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant VogUe Electdc Generating Plant

Waynesboro, GA 30830Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler # 99148

02/16/00

I Of 1

2

29901687 Repair Organization P.O. No., Job No., etc.

Plant VootleAddress

4. Identification Of System 1208 / Chemical and Volume Control

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 (b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 1919

6. Identification Of Components Repairs Or Replacement Components

Systemn

Addenda, N/A

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) 1208 PIPE SOUTHERN N/A N/A V2-1208-123-H603 1999 REPLACEMENT NO SUPPORT NUCLEAR

OPERATIING CQ

7. Description Of Work Installed pipe supoort per DCP 97-V2N0056.

8. Test Conducted: Hydrostatic [] Pneumatic[] Nominal Operating Pressure[] N/A [] Other El Pressure N/A PSI Test Temp. N/A OF

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT Conforms to the rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorlzgtiol No. N/A Expiration Date N/A

Signed )•1ýý) Date _ _ _ 5-3 Owner or Owner's Designee, Title 0 ,4Ou -)7-eO

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georcia and employed by Hartford Steam Boiler Insoection and Insurance Co. of Hartford. Connecticul have Inspected the components described In this Owner's Report during the period_06/14/99 to o-Zo- -, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report In accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described in this Owners Report Furthermore, neither the Inspector nor his employer shall be liable in any manner for any persiqal Injury or property damage or a loss of any kind arising from or connected with this

~cZZ sy4__ý e Commissions (,# 497

Inspector's Signature •/

Date '. -00 4. _

National Board, State, Province and Endorsements

I

Code Case

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xi

1. Owner Southern Nuclear Operating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830Address

3. Work Performed by Nuclear Operations Maintenance Name

Traveler# 99149

Date 02/16/00

Sheet Of

Unit 2

MWO # 29901687 Repair Organization P.O. No., Job No., etc.

Plant VogteAddress

4. Identification Of System 1208 / Chemical and Volume Control System

5. (a) Applicable Construction Code ASME SEC II 1977 Edition, Winter 1977 Addenda, N/A Code Case (b)Applicable Edition of Section Xi Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) 1208 PIPE SOUTHERN N/A N/A V2-1208-501-H601 1999 REPLACEMENT NO SUPPORT NUCLEAR

7. Description Of Work Installed ioe suoort er DCP 97-V2NO056.

8. Test Conducted: Hydrostatic [1 Pneumatic[] Nominal Operating Pressurea] NWA nX Other n] Pressure NIA PSI Test Temp. NIA 2F

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT Conforms to the rules of the ASME Code, Section Xi. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization No. N/A Expiration Date N/A

Signed Ye) e-h & k Date - / ) 46-e- 62.' Owner or Owner's Designee, Titi6' "3 0 - (7-00

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georqia and employed by Hartford Steam Boiler Insoection and Insurance Co. of Hartford. Connecticut have Inspected the components described in this Owner's Report during the period 06/14/99 to p3 -20- on , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report In accordance with the requirements of the ASME Code, Section Xi.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measur"_ .described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any person• lIinjury or property damage or a loss of any kind arising from or connected with this Ins oction. I~i

__ _____ __ _ __ __ommissions e (/97 Inspector's Signature National Board, State, Province and Endorsements

Date Q)A- ,20r

R I

k

#

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

Traveler # 99150199179

1. Owner Southern Nuclear Operating Company Date 1219/99

Name 40 Inverness Center Parkway, Birmingham, Sheet I Of 2

Ala.

2. Plant Vogtle Electric Generating Plant Unit 2

Waynesboro, GA 30830 MWO # 29901719

Address Repair Organization P.O. No., Job No., etc.

3. Work Performed by Nuclear Operations Maintenance Plant Vogtlie

Name Address

4. Identification Of System 12021 NUCLEAR SERVICE COOLING WATER SYSTEM

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 77 Addenda, N/A Code Case

(b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE

OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO)

PIPING PULLMAN N/A N/A 2K3-1202-187-01 1988 REPLACEMENT YES

SYSTEM POWER - PRODUCTS

PIPING PULLMAN N/A N/A 2K3-1202-222-01 1988 REPLACEMENT YES

SYSTEM POWER PRODUICTS

PIPING PULLMAN N/A N/A 2K3-1202-187-02 1988 REPLACEMENT YES

SYSTEM POWER _pRCIOLUCTS

PIPING PULLMAN N/A N/A 2K3-1202-002-01 1988 REPLACEMENT YES

SYSTEM POWER PROBUCjrTS

PIPING PULLMAN N/A N/A 2K(3-1202-226-01 1988 REPLACEMENT YES

SYSTEM POWER PRODUCTS

PIPING PULLMAN N/A N/A 2K3-1202-187-03 1988 REPLACEMENT YES

SYSTEM POWER I pRODUtCTS

PIPING PULLMAN N/A N/A 2K3-1202-002-02 1988 REPLACEMENT YES

SYSTEM POWER _ Q pRoQIDUTS _

PIPING PULLMAN N/A N/A 2K3-1202-194-01 1988 REPLACEMENT YES

SYSTEM POWER

7. Description Of Replaced exlsting studs and nuts with corrosion resistant material per REA 97-VAA678 at the bolted

Work connections In the following Iocations:.2FE1818A.2HV1806 2FE1818B.2HV1822.2HV2143.2FE2132A.2HV" 1808.2FE-1820A.2HV-1830.2FE-1820B, 2H-12138. 2FE2132B, 2-1202U4-197,2HV-1 1687,21202U4-199. 2HV

11688: blind flanqes near 2FE-1820A,2FE1820B.2HV11687, and flanaed soacer near2-1204-P6-003.

8. Test Conducted: Hydrostatic [] PneumaticZ] Nominal Operating Pressure[

N/A E] Other [] Pressure N/A PSI Test Temp. N/A 2F

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

Section XI Travelers 99150/ 99179 Page 2 of 2

repair or replacement

CERTIFICATE OF COMPUANCE

Conforms to theREPLACEMENTWe certify that the statements made in the report are correct and this rules of the ASME Code, Section Xl.

WAType Code Symbol Stamp

WAExpiration DateCertificate of Authorization No. N/A

Signed 4)a) 4 • 1e )-- . Date Owner or Owner's Designee, Atle

19 !4

."- :J.��'

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georgla and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford, Connecticut have Inspected the components described In this Owner's Report during the period /, - I- 9! to 12-14-w •9?, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be lieale in any manner for any pers o4al injury or property damage or a loss of any kind arising from or connected with this °'Inspeglon"

ns t :;e' J •• Commissions t?-4' 7

Inspector's Signature i National Board, State, Province and Endorsements

Date 1900

'ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

1. Owner Southem NuclearOperating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler # 99170

11/17/99

I Of

2

29901380 Repair Organization P.O. No., Job No., etc.

Plant VootleAddress

4. Identification Of System 1301 / Main Steam System

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 (b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

Addenda, N-249-1 Code Case

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) NO.

PIPE PULLMAN N/A N/A V2-1301-105-HO03 1988 REPLACEMENT YES SUPPORT POWER

PRODUCTS

7. Description Of Work Snubber AD- 12501. serial # 53 was replaced with AD-12501. serial # 23 to supoort surveillance testing.

8. Test Conducted: Hydrostatic f] Pneumatic[ Nominal Operating Pressure[-' N/A [] Other rI Pressure N/A PSI Test Temp. N/A F

CERTIFICATE OF COMPLIANCE

We certify that the statements made In the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A !No. .

Signed•l )( Th -//_f Date I 19 / i_ 9 Owner or Owner's Designee, Tie

Iv c�3�

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georgia and employed by H-arford Steam Boiler Inspection and Insurance Co. of Hartford, Connecticut have inspected the components described In this Owner's Report during the period 06/02/99 to - - and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report In accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any persl I Injury or property damage or a loss of any kind arising from or connected with this

SCommissions 4A (197

Inspector's Signature ' National Board, State, Province and Endorsements

Date 19

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

Traveler # 99181

1. Owner Southern NuclearOperating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830Address

Date 11/23/99

Sheet I Of 2

Unit

MWO #

3. Work Performed by Nuclear Operations Maintenance Name

2

29901721 Repair Organization P.O. No., Job No., etc.

Plant VogtleAddress

4. Identification Of System 1202 /Nuclear Service Cooling Water System

5. (a) Applicable Construction Code ASME SEC //I 1977 Edition, Winter 1977 Addenda, N/A (b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

Code Case

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) NO.

1202 PULLMAN N/A N/A 2K4-1202-188-03 1988 REPLACEMENT YES PIPING POWER 2K4-1202-192-04

SYSTEM PRODUCTS

1202 PULLMAN N/A N/A 2K4-1202-196-05 1988 REPLACEMENT YES PIPING POWER 2K4-1202-138-02

SYSTEM PRODUCTS

1202 PULLMAN N/A N/A 2K4-1202-139-02 1988 REPLACEMENT YES PIPING POWER 2K4-1202-225-03

SYSTEM PRODUCTS

1202 PULLMAN N/A N/A 2K4-1202-223-03 1988 REPLACEMENT YES PIPING POWER 2K4-1202-001-05

SYSTEM PRODUCTS I 1 1

7. Description Of Work Installed reolacement studs and nuts in accordance with REA 97-VAA678 on piing flanges located at the inlet and outlet of Containment Cooling Units 2-1501-A7-001-000: 2-1501-A7-002-000: 2-1501-A7-005-000: 2-1501-A7-

uuuuf••-J'l 'L/UU•'UU, J = r- ¶UL-UUIJII/ Pli~tU If Id(•UUUJ LIJ~lf( III i•d8fCJS IUCd1eU a~[ Zt-dd7: •PI--2224- 2F0 -2222 2F0-2225; 2FE-2227: 2FE-2230- 2F0-2184: 2FE-2186, 2F0-2188- 2FE-2190- 2F0-2228 and2F0-2231 (reference Section XI Traveler numbers 99181 throuah 99188).

8. Test Conducted: NIA

Hydrostatic [] Pneumatic[] Nominal Operating Pressure[] Other F- Pressure NWA PSI Test Temp. N/A

.

ORIGINAL Traveler # 99181

Sheet 2 of 2

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A N o . b a

D t Signed -Date __ __ __ _i 9 Owner or Owner's Designee, Title

Date /_ _ __9 19

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticu; have inspected the components described in this Owner's Report during the period 015/9_ to / 4.-'- ?9 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this

a-., •- ",ZeL ( , Commissions .4 e19 7

Inspector's Signature' National Board, State, Province and Endorsements

1. Owner S

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

Traveler # 99189; 99190

outhern Nuclear Operating Company Date 11/24/99Name

40 Inverness Center Parkway, Birmingham, Ala.

2. Plant Vogtle Electric Generatinl Plant

Waynesboro, GA 30830

Sheet

Unit

MWO #

1Ot 2

2

29901723Address Repair Organizatl

3. Work Performed by Nuclear Operations Maintenance Plant Vo! Name Addre

4. Identification Of System 1202 1 NUCLEAR SERVICE COOLING WATER

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 77 Addenda, (b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components:

on P.O. No., Job No., etc.

gtless

SYSTEM

N/A Code Case

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO)

PIPING PULLMAN N/A N/A 2K7-1202-215-01 1988 REPLACEMENT YES SYSTEM POWER

PRODUCTS PIPING PULLMAN N/A N/A 2K7-1202-099-01 1988 REPLACEMENT YES

SYSTEM POWER PROOU•rT.1 PIPING PULLMAN N/A N/A 2K7-1202-098-01 1988 REPLACEMENT YES SYSTEM POWER

PRODUCTS PIPING PULLMAN N/A N/A 2K7-1202-213-01 1988 REPLACEMENT YES

SYSTEM POWER PRODUCTS

PIPING PULLMAN N/A N/A 2K7-1202-228-01 1988 REPLACEMENT YES SYSTEM POWER

PRODUCTS£ PIPING PULLMAN N/A N/A 2K7-1202-232-01 1988 REPLACEMENT YES

SYSTEM POWER PRODUCTS

PIPING PULLMAN N/A N/A 2K7-1202-098-02 1988 REPLACEMENT YES SYSTEM POWER

_RODUCT_ PIPING PULLMAN N/A N/A 2K7-1202-099-02 1988 REPLACEMENT YES

SYSTEM POWER RODUC•TS

7. Description Of Replaced existing studs and nuts with corrosion resistant material per REA 97-VAA678 at the followin~f Work locations:2HV-8109.2FE-1821A.2HV.1831.2FE-1821B, 2HV1807. 2FE-1819A, 2HV-1823. 2FE=1819B. 2HV-2135.

8. Test Conducted: NIAE

ciMei nv-i moe. 01nv-i io-u. ann4 cl-naas near 0-97of-~J.185: 2-1202-X4-O70:2-1202-U4-184;2.1202-X4.53.

Hydrostatic [] Pneumatic[:] Nominal Operating PressureE] Other [] Pressure N/A PSI Test Temp. NIA

r,

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

Traveler Number - 99189; 99190 Page 2 of 2

CERTIFICATE OF COMPLIANCE

we certify that the statements made in the report are correct and this REPLACEMENT Conforms to the

rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp NIA

Certificate of Authorization No. N/A Expiration Date WA

Signed - '7 n• p- te I 19 :<• Owner or Owhner's Designee, Title

CERTIFICATE OF INSERVICE INSPECTION

1, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford, Connecticut have inspected the components described in this Owner's Report during the period (,- /-9 I to /,?- 0 g-q -, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report In accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this Insectlon'/. 1 -, 4_, ",, Commissions a4 '/97

Inspector's Signature V National Board, State, Province and Endorsements

Date , 19 _

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

Traveler # 99191

1. Owner Southern NuclearOperating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electrc Generating Plant

Waynesboro, GA 30830

Date 11/23/99

Sheet I Of 2

Unit

MWO #Address

3. Work Performed by Nuclear Operations Maintenance Name

2

29901722Repair Organization P.O. No., Job No., etc.

Plant VogteAddress

4. Identification Of System 1202 /Nuclear Service Cooling Water System

5. (a) Applicable Construction Code ASMESEC#III 1977 Edition, Winter1977 Addenda, (b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) NO.

1202 PULLMAN N/A N/A 2K4-1202-21 1-01 1988 REPLACEMENT YES PIPING POWER 2K4-1202-205-01 SYSTEM PRODUCTS

1202 PULLMAN N/A N/A 2K4-1202-209-02 1988 REPLACEMENT YES PIPING POWER 2K4-1202-212-02

SYSTEM PRODUCTS

1202 PULLMAN N/A N/A 2K4-1202-216-04 1988 REPLACEMENT YES PIPING POWER 2K4-1202-220-04

SYSTEM PRODUCTS

1202 PULLMAN N/A N/A 2K4-1202-229-05 1988 REPLACEMENT YES PIPING POWER 2K4-1202-140-01

SYSTEM PRODUCTS

1202 PULLMAN N/A N/A 2K4-1202-141-01 1988 REPLACEMENT YES PIPING POWER 2K4-1202-231-05

SYSTEM PRODUCTS I I 1 1

7. Description Of Work Installed replacement studs and nuts in accordance with REA 97-VAA678 on piping flanges located at the inlet and outlet of Containment Coolinq Units 2-1501-A7-002-000: 2-1501-A7-003-000: 2-1501-A7-004-000: 2-1501-A7007-01: 2-1501-A7-008-01: 2-151 I-E7-001-000: and 2-1515-A7-002-000. Also replaced bolting in flanges located at 2F0-2210: 2FE-2209: 2FE-2212: 2F0-2214: 2FE-2215 2FE-2218: 2F0-2216:2F0-2219: 2F0-2 185: 2FE-2191

8. Test Conducted: NIAE

and 2F0-2189 (reference Section XI Traveler numbers 99191 through 99200).

2F

N/A Code Case

Hydrostatic [] Pneumatic[] Nominal Operating PressureEl Other [ Pressure NIA PSI Test Temp. N/A

1202 / Nuclear Service

Cooling Water

System

ORIGINAL Traveler # 99191

Sheet 2 of 2

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed ne Ow Date ________ 19T Owner or Owner's Designee, Tidb

Date /42 -0 9

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticui have Inspected the components described In this Owner's Report during the period 6/1 5/99_ to j.-d9o99 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report In accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this

i,:24 Commissions 4A ("/7

Inspector's SNational Board, State, Province and Endorsements

-ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

1. Owner Southern NuclearOperating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtile Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler #

I Of 2

2

29901858

99202

Repair urganization P.O. No., Job No., etc.

Plant Voatle

PAddroates4. Identification Of System 1302 / Auxiliary Feedwater System

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 Adc (b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 1912

6. Identification Of Components Repairs Or Replacement Components

denda, NIA

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED COMPONENT MANUFACTURER I NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) VALVE ANCHOR! E-9001-26-15 N/A 2-1302-U4-043 1980 REPAIR! YES DARLING VALVE REPLACEMENT

7. Description Of Work Valve bonnet was replaced under Traveler# 99202. A copy of Form N-1 for the replacement bonnet is attached Thevle ysaloweld repaired in th nr.r• 1 nrnn ,n-' ao,,',Aseal

8. Test Conducted: NIA[

Hydrostatic 11 Pneumatic[] Nominal Operating Pressureo] Other [I Pressure NIA PSI Test Temp. WA

i

Code Case

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPAIR/REPLACEMENT conforms to the rules of the ASME Code, Section Xl. repair or replacement Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed Owner COn 'sDesneeTi 20 tl Owner orOne'esignee, Title U1

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Geomiap and employed by Hartford Steam Boiler Insoection and Insurance Co. of Hartord. Cnn have Inspected the components described in this Owner's Report during the period 1/15/99 to 0 44 6_(e_, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report In accordance with the requirements of the ASME Code, Section XI. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable In any manner for any sonal Injury or property damage or a loss of any kind arising from or connected with this

I-• Commissions 64 e197 Inspector's Signature National Board, State, Province and Endorsements

ORIGINALFORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

1. Owner Southern NuclearOperating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Voptle Electric Generating Plant

Waynesboro, GA 30830

Date

Sheet

Unit

MWO #Address

3. Work Performed by Nuclear Operations Maintenance Name

Traveler # 99204

12/05/00

1 Of 7

-+- 2. ~L Qý0

29901677 and 29902366 Repair Organization P.O. No., Job No., etc.

Plant Vogtle Address

4. Identification Of System 1208 / Chemical and Volume Control System

5. (a) Applicable Construction Code ASME SEC III 1974 Edition, Summer 1975 Addenda, N/A Code Case

(b)Applicable Edition of section Xl Utilities For Repairs Or Replacements 1989 Code Case N-416-1

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO)

PUMP INGERSOLL- 0398019 N/A ,+-'1208-P4-001 1999 REPLACEMENT YES DRESSER PUMP Z

____C____ co ________lz-oý- 00________

PUMP PENN IRON 129132-1A 1 & 76 & e-1208-P4-001 1998 REPLACEMENT YES PEDESTALS WORKS, INC. 129132-IB2 79 -Z

7. Description Of Work The positive displacement pump was replaced by a centrifuaal normal charging pump per DCP 97- V2NO056. This replacement also includes welding of the suction and discharge nozzle flanges and their bolting to the Dump. Copies of Form NPV-1 for the replacement Pump and NF-1 for the replacement pump pedestals are attached.

8. Test Conducted: Hydrostatic [] PneumaticE] Nominal Operating Pressure [ Code Case N-416-1 N/A j] Other [] Pressure N/A PSI Test Temp. N/A 2F

CERTIFICATE OF COMPLIANCE

We certify that the statements made In the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed- 'L_4-k 1A--- ,2i a ,.i-t.Date /. /• 20 00 Owner or Owner's Designee, Title (-

/

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georaia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connectic have Inspected the components described In this Owner's Report during the period 06/23/99 to , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report In accordance With the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable In any ma er for any personal injury or property damage or a loss of any kind arising from or connected with this InspeI.. -'1/J

______ _,.,______ __ _ Commissions GAo3 Inspedtor-'s-Signature National Board, State, Province and Endorsements

Date /2. // 20 4o

-ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

1. Owner Southern NuclearOperating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler # 99209

12102/99

Of

2

29901923 Repair Organization P.O. No., Job No., etc.

Plant VootleAddress

Identification Of System 2101 / Containment Building System5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977

(b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

Addenda, N/A

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) NO.

EQUIPMENT CHICAGO N/A N/A 2-2101-R2-016 1988 REPAIR NO HATCH BRIDGE AND

IRON

7. Description Of Work Welded load in ramp to equipment hatch barret per DCP 99-V2NO037.

8. Test Conducted: Hydrostatic [] PneumaticE] Nominal Operating PressureR N/A 2] Other ] Pressure N/A PSI Test Temp. N/A F

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPAIR conforms to the rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No. V1_ _ _ _ _ _ _ _ _ __Date

Signed -' po • - Date _I_ Z___ __ 19 q. Owner or Owner's Designee, TItlb

4.

Code Case

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticui have inspected the components described In this Owner's Report during the period 07/21/99 to ,-04 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any pe/sQnal Injury or property damage or a loss of any kind arising from or connected with this _________. /Commissions t;, 4 97

Inspector's Signature 6 National Board, State, Province and Endorsements

Date 42-A3 19

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xi

1. Owner Southern NuclearODeratina ComnanvName

40 Inverness Center Parkwav. Birminaham. AL

2. Plant Vogtle Electric Generatinq Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler #

03/13/00

99210

1Of 3

2

29900185Repair Organization P.O. No., Job No., etc.

Plant Vogte Address

4. Identification Of System 1301 / Main Steam System

5. (a) Applicable Construction Code ASMESEC III 1977 Edition, Winter 1977 (b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

Addenda, N/A

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) VALVE CONTROL 23469-1-3 N/A 2PV3020 1982 REPAIR / YES

COMPONENTS, REPLACEMENT INC.

7. Description Of Work Valve pluo was replaced, Pressure seal area of valve body was waildad and rmachined to r~ctore nfitntm-Ugl

surface. A copy of Form N-2 for the replacement plug is attached.

8. Test Conducted: NA1

0\

Hydrostatic [] Pneumatic[] Nominal Operating Pressure[] Other [] Pressure WA PSI Test Temp. N/A

Code Case

CERT1FICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPAIR/REPLACEMENT conforms to the rules of the ASME Code, Section XI. repair or replacement

Type Coda Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed" x <6 4 L ý t1 ,; t"-'u Date A_/__ _2_ 20 Oe-,

Owner or Owner's Designee•it le-

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georqia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticut have inspected the components described In this Owner's Report during the perlod__Q.•WQ4 to .•ý.3- 0 ) , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report In accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable In any manner for any rmsonal Injury or property damage or a loss of any kind arising from or connected with this - cZ1 Commissions el,+ 4/-17

Inspector's Signature National Board, State, Province and Endorsements

Date , 15 - O- 20__

F

.......

•'

.....

r---"

-.

,r wv_ U

ORIGINAL' FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

1. Owner Southern Nuclear Operating Company Name

40 Inverness Center Parkway, Birmingham. Ala.

2. Plant Vogtie Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

4. Identification Of System

Date

Sheet

Unit

MWO #

Traveler # 99211

5/24/2000

1 Of

2

29900967 Repair Organization P.O. No., Job No., etc.

Plant Vogtle Address

1202 1 NUCLEAR SERVICE COOLING WATER

5. (a) Applicable Construction Code ASME SEC III 1974 Edition, Winter '75 Addenda, N/A Code Case (b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) VALVE Crosby Valve & Gage N67951-00-0003 N/A 2PSV1 1752 1984 REPLACEMENT YES

Co.

N/A N/A N/A Nl/A N/A N/A N/A N/A

7. Description Of Work: Relief valve S/N N67951-00.O008 was replaced with spare relief valve S/N N67951-00-0003 to facilitate valve testing. The replacement valve was oreviouslY installed as 2PSV-11744.

8. Test Conducted: Hydrostatic [] Pneumatic[] Nominal Operating Pressurerx N/A E Other jJ Pressure WNA PSI Test Temp. N/A 2F

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT Conforms to the rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization No. N/A Expiration Date NIA SignedJ/ -V aWA Date 6_

Owner or Owner's Designee, TttL%

I

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel inspectors and the State ol Province of Georgla and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford, Connecticut have inspected the components described in this Owner's Report during the period__ -___- 9!?__ _ to & -Z3- 00 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any per al injury or property damage or a loss of any kind arising from or connected with this inspe'tion I Commissions

Inspector's Signature National Board, State, Province and Endorsements

Date _________

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

1. Owner Southern Nuclear Operatinq ComoanvName

40 Inverness Center Parkway, Birmingham, Ala.

Vogtle Electric Generating Plant

Waynesboro, GA 30830Address

3. Work Performed by Nuclear Operations Maintenance

Name

Date

Sheet

Unit

MWO #

N

Plant Vogtie Address

4. Identification Of System 1202 / NUCLEAR SERVICE COOLING WATER SYSTEM

5. (a) Applicable Construction Code ASME SEC III 1974 Edition, Winter '75 Addenda, N/A Code Case ~ (b)Applicable Edition of Section Xi Utilized For Repairs Or Replacements 1989

$ C6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) VALVE Crosby Valve & Gage N67936-00-0002 N/A 2PSVI 1759 1984 REPLACEMENT YES

Co.

N/A N/A N/A N/A A N/A N/A N/A

7. Description Of Work: Relief valve S/N N67936-00-0003 was replaced with spare relief valve S/N N67936-00-0002 to facilitate valvetesting. The replacement valve was previously installed as 1PSV-11766.

8. Test Conducted: . A =-'- Hydrostatic L] Pneumatic-] Nominal Operating Pressurer9 Other [] Pressure WA PSI Test Temp. N/A

Date

Traveler # 99218

5/24/2000

1 Of

2

29901912 Repair Organization P.O. No., Job No., etc.

2. Plant

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT Conforms to the rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp WA

Certificate of Auth rizaton No. N{A Expiration Date NA

Signed or_ O e i ellnee__ _, Date Tltl__-_-_ Owner or Owner's Designee, Titlif - S 6/ Z

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticut have inspected the components described in this Owner's Report during the period !7-/1 -99 to & -2,3 -6 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xi.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any mnner fon e injury or property damage or a loss of any kind arising from or connected with this

ap tion.Commissions ,4 -/9 7

Inspector's Signature National Board, State, Province and Endorsements

|

1it

|

•

--17.

QF

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xi

1. Owner Southern Nuclear Operating Company

2. Plant

Name 40 Inverness Center Parkway, Birmingham, Ala.

Voatle Electric Generating Plant

Waynesboro, GA 30830Address

3. Work Performed by Nuclear Operations Maintenance

Name

4. Identification Of System

Date

Sheet

Unit

MWO #

Traveler # 99219

5/23/2000

Of

2

29901913 Repair Organization P.O. No., Job No., etc.

Plant VoatleAddress

12081 CHEMICAL VOLUME CONTROL SYSTEM

5. (a) Applicable Construction Code ASME SEC ill 1971 Edition, Winter '72 Addenda, N/A

(b)Applicable Edition of Section Xi Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

Code Case

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO VALVE Crosby Valve & Gage N569000-00- N/A 2PSV8121 1977 REPLACEMENT YES

Co. 0049

N/A N/A N/A N/A NIA N/A N/A N/A

7. Description Of Work: Relief valve SiV N56900-00-0025 was reolaced with spare relief valve SIN N56900-00-0049 to facilitate valve testing. The replacement valve was previously Installed as 1PSV-8121.

8. Test Conducted: N/AmF-

Hydrostatic [] Pneumatic[] Nominal Operating Pressure[-] Other n Pressure N/A PSI Test Temp. N/A

CERTIFICATE OF COMPUANCE

We certify that the statements made In the report are correct and this rules of the ASME Code, Section Xl.

REPLACEMENTrepair or replacement

Conforms to the

Type Code Symbol Stamp

Certificate of Authorizaiony. N/A

Signed-• , r - Date Owner or Owner's Designee, Title J,

Expiration Date

• .so_-, O

I

NIA

N/A

CERTIFICATE OF INSERVICE INSPECTION

1, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georgla and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford, Connecticut have inspected the components described in this Owner's Report during the period t? -m/: -" to ol-,Z- oV , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xi.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any peeeq al injury or property damage or a loss of any kind arising from or connected with this

S .A/•t•Aoc c Commissions aA 7

inspeicor's Signature i/ National Board, State, Province and Endorsements

Date 6 -Z-3 ."760tl

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section Xi

1. Owner Southern Nuclear Operating CompanyName

40 Invemess Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generatino Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler # 99221

05/03/00

I Of 1

2

29900570 Repair Organization P.O. No., Job No., etc.

Plant VootlePlant VootleAddress

4. Identification Of System 1205 / Residual Heat Removal Sy

5. (a) Applicable Construction Code ASMESEC III 1971 Edition, Summer 1972 (b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

stem

Addenda, N/A Code Case

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) HEAT SENTRY 796018 1307 2-1205-P6-002- 1979 REPLACEMENT YES

EXCHANGER EQUIPMENT M01 CORP,

7. Description Of Work Motor heat exchanger end covers and channels were replaced"

8. Test Conducted: Hydrostatic ] Pneumatic[] Nominal Operating PressurefZJ NIA E Other [] Pressure N/A PSI Test Temp. NIA 2F

I

4(1

Erf lhIr.RI E I- CUMPLIANCE We certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section XI. Repair or replacement

Type Code Symbol Stamp NIA

Certificate of Authorization N/A Expiration Date N/A No.

Signed R r 20 De e Owner or Owner's Designee, Title RV

CERTIFICATE OF INSERVICE INSPECTION

1, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inswection and Insurance Co. of Hanford. Connecticu have inspected , the components described in this Owner's Report during the period 01/25/99 to -6-.-. -CO, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be lla le in any manner for any persooI Injury or property damage or a loss of any kind arising from or connected with this

Commissions • a9 n/Ba Inspector's Signat National Board, State, Province and Endorsements Date / 200

I

1. 1. .. .,

1. Owner Southern NuclearOperating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Voatle Electric Generating Plant

Waynesboro, GA 30830Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler # 99223

11/17/99

Of

2

29901501 Repair Organization P.O. No., Job No., etc.

Plant VootleAddress

4. Identification Of System 1501 / Containment Cooling System

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 Add (b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 198f.

6. Identification Of Components Repairs Or Replacement Components

enda, N/A

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) NO.

1501 PULLMAN N/A AL/A 2V4-1501-034-01 1988 REPLACEMENT YES PIPING POWER 2V4-1501-035-01

SYSTEM PRODUCTS

7. Description Of Work Installed replacement studs and nuts on opoino fiances located on Containment Cooler unit 2-1501-A7-006.

8. Test Conducted: Hydrostatic [] Pneumaticl] Nominal Operating PressureN/A [X1 Other El Pressure N/A PSI Test Temp. N/A F

CERTIFICATE OF COMPUANCE

We certify that the statements made In the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed -lk )Y, .) -•,- ý -L7 19ata 71/ ig1 Owner or Owner's Designee, Title U

Code Case

COVI

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georoia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford, Connecticui have inspected the components described in this Owner's Report during the period 09/28/99 to /2- of- 9! , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this in • J • - 4 Commissions SA Z/?

Inspector's Signature National Board, State, Province and Endorsements

Date /.2- 01/ 19

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

/1. Owner S

ORIGi vi FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

Traveler # 99224

'nthern Nuclear Oneratinay Comnanv Date 12/9/99Name

40 Inverness Center Parkway, Birmingham, Ala.

Vog•te Electric Generating Plant

Waynesboro, GA 30830

Sheet

Unit

MWO #

Of 2

2

29801500Address Repair Organization P.O. No., Job No., etc.

3. Work Performed by Nuclear Operations Maintenance Plant Vogtle Name Address

4. Identification Of System 1501 I Containment Air Cooling System

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 77 Addenda, N/A Code Case (b)Applicable Edition of section XI Utilities For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (ES OR NO) HEAT CVI INC. 02A338 1229 2-1501A7-003 1982 REPLACEMENT YES EXCHANGER HEADER

HEAT CVI INC. 024347 1230 2-1501A7-003 1982 REPLACEMENT YES EXCHANGER HEADER

HEAT CVI INC. 02A356 1231 2-1501A7-003 1982 REPLACEMENT YES EXCHANGER HEADER

HEAT CVI INC. 02A364 1232 2-1501A7-003 1982 REPLACEMENT YES EXCHANGER

HEAT CVI INC. 02A365 2-1501A7-003 1982 REPLACEMENT YES EXCHANGER 1233 HEADER

HEAT CVI INC. 02A376 2-1501A7-003 1982 REPLACEMENT YES EXCHANGER 1234 HEADER

7. Description Of Replaced existing studs and nuts with corrosion resistant material per Specification AX4AJ16-123 on Inlet Work outlet manifolds as shown on isometric drawings 2V4-1501-028-01.& 2V4-1501-029-01.

8. Test Conducted: Hydrostatic [] PneumaticE] Nominal Operating Pressure -] NIA nX Other n Pressure NIA PSI Test Temp. N/A QF

2. Plant

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

Traveler Number - 99224 Page 2 of 2

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the

rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization No. WA Expiration Date WA

Signed1A? 1i" ý- , Date ____c-_ 19 g Owner or Owner's Designee, T"le

Date______ 19

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georgla and employed by Hartford Steam boiler Inspection and Insurance Co. of Hartfo Connecticut have Inspected the components described in this Owner's Report during the period 9-a9. 9 to /./- 9 ? , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance With the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable In any manner for any personal Injury or property damage or a loss of any kind arising from or connected with this

Iion . 'A = (I Commissions 6 -4AV19 7

Inspector's Signature National Board, State, Province and Endorsements

ORIGINAL FORM NIS-2 OWNER'S.REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

1. Owner Southern NuclearOperating Company Name

40 Invemess Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Wavnesboro, GA 30830Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler # 99226

11/17/99

I Of 1

2

29900559 Repair Organization P.O. No., Job No., etc.

Plant VoatleAddress

4. Identification Of System 1202 / Nuclear Service Cooling Water

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 (b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

System

Addenda, N/A

7. Description Of Work Installed replacement studs and nuts on piping blind flan•es located on lines 1202-530-8" and 1202-531-8"

8. Test Conducted: Hydrostatic [] Pneumatic[] Nominal Operating Pressure[] NIA E] Other E Pressure WA PSI Test Temp. NIA 2F

CERTIFICATE OF COMPUANCE

We certify that the statements made In the report are correct and this REPLACEMENT conforms to the

rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed 17&'/J•- -k , ,- . Date Ii/1 19 9 Owner or Owner's Designee, TItle U

Code Case

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) NO.

1202 PULLMAN N/A N/A 2K7-1202-228-01 1988 REPLACEMENT YES PIPING POWER 2K7-1202-3281

SYSTEM -PRODUCTS - --- i

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford, Connecticui have Inspected the components described in this Owner's Report during the period 10/04/99 to L2• , , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any p onal injury or property damage or a loss of any kind arising from or connected with this InslectlonV 1 _ in-`La4%ý ,5. 7LJ Commissions CV, LA 7

Inspector's Signature f National Board, State, Province and Endorsements

Date /0?- 0 6 - 9 17 1990

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

1. Owner Southern NuclearOperating CompanyName

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electrc Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler # 99227

12108/99

Of

2

29902563 Repair Organization P.O. No., Job No., etc.

Plant VogtleAddress

4. Identification Of System 1205 / Residual Heat Removal System

5. (a) Applicable Construction Code ASMESECIII 1977 Edition, Winter1977 Addenda, N/A Code Case (b)Applicable Edition of Section Xi Utilized For Repairs Or Replacements 19!2

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) NO.

1205 PIPING PULLMAN N/A N/A 2K3-1205-008-01 1988 REPLACEMENT YES SYSTEM POWER

_______ PRODUC(TS ____ ___ _____ ____ _____

7. Description Of Work Installed reolacement studs and nuts in the piving flanoes located at 2F0-10443.

8. Test Conducted: Hydrostatic ] PneumaticE] Nominal Operating Pressure[] WA [] Other 51 Pressure N/A PSI Test Temp. N/A RF

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed !j/ • V nL Date J ZII57-" 19 9'• Owner or Owner's Designee, TWt -

Date /,,g -Y1 19

I

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of bolier and Pressure vessel Inspectors and the State or Province of Georqia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticut have Inspected the components described In this Owner's Report during the period 10/03/99 to - q , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report In accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described In this Owners Report Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this in I ti ,4- Com m issions 49 l 9 -7

Inspector's Signature 1" , National Board, State, Province and Endorsements

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

Traveler # 99228

1. Owner Southern Nuclear Operating Company

2. Plant

Name 40 Inverness Center Parkway, Birmingham,

Ala.

Vogtle Electric Generating Plant

Waynesboro, GA 30830

Date

Sheet

Unit

MWO #

Address

3. Work Performed by Nuclear Operations MaintenanceName

12f10/99

Of

2

29902566 Repair Organization P.O. No., Job No., etc.

Plant Voatle

Address

4. Identification Of System 12051/ RESIDUAL HEAT REMOVAL SYSTEM

5. (a) Applicable Construction Code ASME SEC Ill 1977 Edition, Winter '77 Addenda, N/A

(b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989

Code Case

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTURER NATIONAL REPAIRED. ASME CODE

OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO)

PIPING Pullman Power NIA N/A 2K3-1208-008-01 1988 REPLACEMENT YES

SYSTEM Company Inc.

NIA N/A N/A N/A N/A NI/A N/A N/A

7. Description Of Replacement of studs and nuts In PpDing flanqes for 2FV-0619. Work

8. Test Conducted: Hydrostatic [] Pneumatic- Nominal Operating Pressure[]

NIA 7X Other 7 Pressure WA PSI Test Temp. NIA

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT Conforms to the

rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp NIA

Certificate of Authorization No. NIA Expiration Date NIA

Signed Y) i Yý., Date -LJ0o 19 q Owner or Owner's Designee, TIt1#

Date /Aý - /3 19 _.

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel inspectors and the State

or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford, Connecticut have

inspected the components described in this Owner's Report during the period /0- 03-99 to / 2-144 9 9 -, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken

corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xi.

By signing this certificate, neither the inspector nor his employer makes any warranty, expressed or Implied, concerning the

examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall

be liable in any manner for any personal Injury or property damage or a loss of any kind arising from or connected with this

Ins n ý Q Commissions &4 42-"7

Inspector's Signature i , National Board, State, Province and Endorsements

ORIGINALFORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

1. Owner Southern NuclearOperating CompanvName

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830Address

3. Work Performed by Nuclear Operations MaintenanceName

Date

Sheet

Unit

MWO #

/

Address

4. Identification Of System 1205 / Residual Heat Removal Sy

5. (a) Applicable Construction Code ASME SEC I/_ 1977 Edition, Winter 1977 (b)Applicable Edition of Section Xi Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

stem

Addenda, l/A Code Case

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) NO.

1205 PIPING PULLMAN N/A AVA 2K3-1205-007-02 1988 REPLACEMENT YES SYSTEM POWER

PRODOICTS

7. Description Of Work Installed replacement studs and nuts in the piping flanoes located at 2FV-0618.

8. Test Conducted: Hydrostatic E] PneumaticE] Nominal Operating Pressure' N/A [ Other [ Pressure N/A PSI Test Temp. N/A F

CERI1FICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed YV• , Date I /'•/i7 19 Owner or Owner's Designee, Title U

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georcia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Ha Cdnnecti ul have Inspected the components described In this Owner's Report during the period 10//9 to eL3 -OZ.-00 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable In any manner for an personal Injury or property damage or a loss of any kind arising from or connected with this • Commissions 7 "£/9

Inspector's SignatuF6 National Board, State, Province and Endorsements

Date 0,802-

Traveler # 99229

12/15/99

Of

2

29902620 Repair Organization P.O. No., Job No., etc.

Plant Voatle

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

1. Owner Southern NuclearOperating CompanyName

40 Inverness Center Parkway, Birminrham. AL

2. Plant Vogtle Electfic Generating Plant

Waynesboro, GA 30830Address

3. Work Performed by Nuclear Operations MaintenanceName

Traveler # 99232

Date 04/03/00

Sheet Of 3

Unit 2

MWO # 29801685 Repair Organization P.O. No., Job No., etc.

Plant Vogtie Address

4. Identification Of System 1201 / Reactor Coolant System

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Summer 1979 Addenda, N/A Code Case (b)Applicable Edition of Section Xi Utilized For Repairs Or Replacements 1982

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) NO.

VALVE GARRETT P-144 N/A 2PV0455A 1984 REPLACEMENT YES

7. Description Of Work Installed replacement valve Duo. A copy of Form N-2 for the reolacement Dlua S/N N96012-38-0027 is attached.

8. Test Conducted: Hydrostatic [] Pneumatic[] Nominal Operating Pressure[X' N/A Other [ Pressure N/A PSI Test Temp. N/A 2F

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No. Signed Date _..__ _ -7 20 00

Owner or (Owner's Designee, Titlet

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georoia and employed by Hartford Steam Boiler Inspection and Insurance Go. of Hartford. Connecticul have inspected the components described In this Owner's Report during the period 10/07/99 to 4.5-01- Z , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report In accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable In any manner for any p" nal injury or property damage or a loss of any kind arising from or connected with this

cj= J)it- ,• Commissions /i4A 41!9 7Inspector's Signature I

Date &. -0/"2

National Board, State, Province and Endorsements

'S'1

fe 0Vi

0o. __

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

1. Owner Southern NuclearOperatinq CompanyName

40 Inverness Center Parkway, Birmingham. AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler # 99233

12107/99

Of 2

2

29900514 Repair Organization P.O. No., Job No., etc.

Plant VoqtleAddress

4. Identification Of System 1302 / Auxiliary Feedwater System

5. (a) Applicable Construction Code ASME SEC III 1974 Edition, Summer 1975 Addenda, N/A Code Case (b)Applicable Edition of Section Xi Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) NO.

VALVE ANCHOR E9001-110-6 N/A 2-1302-U4-120 1983 REPLACEMENT YES DARLING VALVE

rn

7. Description Of Work Installed reolacement valve bonnet. A copy of Form N-2 for the renlacement bonnet is attached.

8. Test Conducted: Hydrostatic [] Pneumaticl] Nominal Operating PressureJ] N/A E Other [ Pressure N/A PSI Test Temp. WA 2F

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed ,• c !J•A . Date L -- / 1 19 7 Owner or Owner's Designee, TItIJ

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance CO. of Hartford. Connecticut have inspected the components described in this Owner's Report during the period 10/10/9 to 12- D9-,?? , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any persIa injury or property damage or a loss of any kind arising from or connected with this I=n 5& Commissions e4 4,17

I.npuCuLr s oSgnature ,

1"2 09 inDate

National Board, State, Province and Endorsements

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

Traveler # 99257

1. Owner Southern Nuclear Operating ComDanvName

40 Inverness Center Parkway, Birmingham. AL

2. Plant Vo0t0e Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance

Name

4. Identification Of System

Date

Sheet

Unit

MWO #

11/29/99

I Of

2

29900436 Repair Organization P.O. No., Job No., etc.

Plant Voctle

Address

12011/ Reac~tor Coola~nt S tern 5. (a) Applicable Construction Code ASME SEC III 1971 Edition, Summer 1972 Addenda, 1484-2 Code Case

(b)Applicable Edition of Section Xi Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) NO.

1201 WESTINGHOUSE 1983 35 2-1201-B6-002 1982 REPLACEMENT YES

7. Description Of Work Installed reolacement bolt and a helical threaded insert on nozte side handhole at the supportolate.

8. Test Conducted: Hydrostatic 0 Pneumatic[] Nominal Operating Pressurez] NIA [ Other ] Pressure N/A PSI Test Temp. NIA QF

CERTIFICATE OF COMPUANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed 2Ow0er or Owner_0 Owner or Owner's Designee, Titleý

I

.. n ir"FI ICA UI" IOINEHVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticut have inspected the components described in this Owner's Report during the period 10/13/99 to 6/0-O , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this Inspetr. S r Commissions CA -,97 inspicto~r's Signature N~lA U, A , re vuuuUI .iusee

Datet9 Province naEndorsements Date !C. -I10 201)

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

1. Owner Southern NuclearOperating CompanyName

40 Inverness Center Parkway, Birmingham. AL

2. Plant Vobtle Electric Generating Plant

Waynesboro, GA 30830Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler # 99258

11/29/99

1 Of

2

29900440 Repair Organization P.O. No., Job No., etc.

Plant VootleAddress

4. Identification Of System 1201 / Reactor Coolant System

5. (a) Applicable Construction Code ASME SEC III 1971 Edition, Summer 1972 A (b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

ddenda, 1484-2 Code Case

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) NO.

1201 WESTINGHOUSE 1982 34 2-1201-B6-003 1982 REPLACEMENT YES

7. Description Of Work Installed replacement bolt on hot lea side secondarm inspection handhole.

8. Test Conducted: Hydrostatic [] PneumaticE] Nominal Operating PressureN/A D Other f] Pressure N/A PSI Test Temp. N/A RF

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed D•k 2, Kh -p-.4 -"/i& Date . )• 19' Owner or Owner's Designee, Title U

Date A2 - 07 19

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticuy have inspected the components described in this Owner's Report during the period 10/99 to 1-2-,79 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal Injury or property damage or a loss of any kind arising from or connected with this insA-n 7/ •2 § Commissions (14 9-19 7

Inspector's SignatureV National Board, State, Province and Endorsements

ORIGINAL

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section Xl

1. Owner Southern NuclearOperating CompanyName

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830Address

3. Work Performed by Nuclear Operations Maintenance

Date

Sheet

Unit

MWO #

Name

4. Identification Of System 1208 / Chemical and Volume Control

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 (b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

Traveler # 99259

11/22/99

1 Of

2

29902743 Repair Organization P.O. No., Job No., etc.

Plant Vootle

Address

System

Addenda, N/A Code Case

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) NO.

1208 PULLMAN N/A N/A 2K4-1208-020-02 1988 REPLACEMENT YES PIPING POWER

SYSTn PRODUCTS I _ _

7. Description Of Work Installed replacement studs and nuts on aioing flanges located at 2FE0157.

8. Test Conducted: Hydrostatic E] PneumaticE] Nominal Operating Pressure[] N/A [g] Other ] Pressure N/A PSI Test Temp. N/A RF

CERTIFICATE OF COMPLIANCE

We certify that the statements made In the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signeder or O e DesigDateee, Tile 199 Owner or Owner's Designee, Tntle C

I

II�

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartord Connecticut have inspected the components described in this Owner's Report during the period 10/15/99 to 1,2-f(,- , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal Injury or property damage or a loss of any kind arising from or connected with this ins ction., __________________,,__._Commissions - 47

Inspector's Signaturet National Board, State, Province and Endorsements

Date /,Ra-I 19 Q

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

1. Owner Southern Nuclear Operating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtie Electric Generatinq Plant

Waynesboro, GA 30830

Traveler # 99260

01/06/00Date

Sheet I Of I

Unit

MWO #Address

3. Work Performed by Nuclear Operations Maintenance Name

2

29902400 Repair Organization P.O. No., Job No., etc.

Plant VogqteAddress

4. Identification Of System 1202 /Nuclear Service Cooling Water System

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 Addenda, (b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 19D9

6. Identification Of Components Repairs Or Replacement Components

N/A Code Case

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT ES OR NO) 1202 PIPING PULLMAN N/A N/A 2K5-1202-031- 1988 REPLACEMENT YES

SYSTEM POWER 01 PRODUCTS

7. Description Of Work Installed replacement studs and nuts in viinn flanoes located at valves 2HV-11605 and 2-1202-U4-031.

8. Test Conducted: Hydrostatic [] PneumaticE] Nominal Operating PressureE[ N/A [] Other [ Pressure N/A PSI Test Temp. N/A RF

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed orDate O ss et Owner or Owner's Designee, Title(I e9-

Date 0-4 - b 2- id 2dfoo

'4

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georaia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticul have Inspected the components described in this Owner's Report during the period 10a/1/_9 to 03-oz-oc- -, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report In accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any persopaI injury or property damage or a loss of any kind arising from or connected with this Ins ction, Commissions GA 4Q7

l Date •)•, -

• Z.

1• 2•O•J%I

National Board, State, Province and EndorsementsInspector's Signature V

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

1. Owner Southern NuclearOperating Company Name

40 Inverness Center Parkway, Binningham, AL

2. Plant VogUe Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

Traveler # 99261

11/17/99IDntn

Sheet I Of _

Unit 2

MWO # 29902934 Repair Organization P.O. No., Job No., etc.

Plant Vogtle Address

4. Identification Of System 1302 / Auxiliary Feedwater System

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 Addenda, N/A Code Case (b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) NO.

1302 PULLMAN N/A N/A 2K2-1302-002-01 1988 REPLACEMENT YES PIPING POWER

SySTE PRODUCTS

7. Description Of Work Installed replacement studs and nuts on bining flangoes located at 2FE5267.

8. Test Conducted: Hydrostatic [] Pneumatic[] Nominal Operating PressureD N/A[] Other F Pressure NIA PSI Test Temp. NIA QF

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed • ),4 6U-Date _ _ __ _ _ 19 Owner or Owner's Designee, Title

I

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georoia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticua have inspected the components described In this Owner's Report during the period 10/18/99 to /,I-lo -- -, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report In accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any pemronal injury or property damage or a loss of any kind arising from or connected with this insl ction. I !/// .",,

:n j 4-:KNA Commissions__ __ __ __ __ __

Inspector's Signature V National Board, State, Province and Endorsements

Date 19

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xi

1. Owner Southern NuclearOperating Company Name

40 Inverness Center Parkway, Birminaham. AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830Address

3. Work Performed by Nuclear Operations Maintenance

Date

Sheet

Unit

MWO #

Name

Traveler # 99262

11/22/99

Of

2

29902933 Repair Organization P.O. No., Job No., etc.

Plant Vont/eAddress

4. Identification Of System 1302 / Auxiliary Feedwater System

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 Addenda, N/A Code Case (b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) 130Z NO. f PULLMAN N/A N/A 2K3-1302-030-01 1988 REPLACEMENT YES

PIPING POWER SYSTEM POUCT_

7. Description Of Work Installed replacement studs and nuts on biDing flanges located at 2FE5286.

8. Test Conducted: Hydrostatic [] PneumatlcE] Nominal Operating PressureE] NIA[] Other [ Pressure NIA PSI Test Temp. NIA 2F

CERTIFICATE OF COMPLIANCE

We certify that the statements made In the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section Xi. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed J'Ji • Date W Q44 19 Owner or Owner's Designee, Title

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticu have inspected the components described In this Owner's Report during the period 10/18. to 0 -O(o--t , and state that to the best of my knowledge and belief, the Owner has performed examinations and takenr corrective measures described in this Owners Report In accordance with the requirements of the ASME Code, Section Xl. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this -- Ins In Isptr I gn Commissions t4 4(q 7

Inspector's Signature INational Board, State, Province and Endorsements

Date 19

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

1. Owner Southern NuclearOperating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Voqtle Electric Generatina Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler # 99263

11/17/99

Of

2

29902935 Repair Organization P.O. No., Job No., etc.

Plant VoatleAddress

4. Identification Of System 1302 / Auxiliary Feedwater System

5. (a) Applicable Construction Code ASME SEC I// 1977 Edition, Winter 1977 Adc (b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

lenda, N/A

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) NO.

1302 PULLMAN N/A N/A 2K2-1302-003-01 1988 REPLACEMENT YES PIPING POWER

RYTF PRODUICTS _______________________

7. Description Of Work Installed replacement studs and nuts on piping flanges located at 2F05284.

8. Test Conducted: Hydrostatic [] Pneumatic[] Nominal Operating PressureE[ N/A j] Other [ Pressure N/A PSI Test Temp. N/A 5F

CERTIFICATE OF COMPUANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed PA ,t D)ate 19 Owner or Owner's Designee, Titlea

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georcia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticut have inspected the components described in this Owner's Report during the period 10/18/99 to _/_2. -02- 1?1 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report In accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any person1.al injury or property damage or a loss of any kind arising from or connected with this • •a - &LG0o Commissions (A C/•9 _

National Board, State, Province and Endorsements

I

Code Case

Inspector's Signature /

Date 1Z -02- 19

J

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

1. Owner Southern NuclearOperating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler # 99264

11/22/99

Of

2

29902932 Repair Organization P.O. No., Job No., etc.

Plant VogteAddress

4. Identification Of System 1302 / Auxiliary Feedwater System

5. (a) Applicable Construction Code ASME SEC I!1 1977 Edition, Winter 1977 Addenda, N/A Code Case (b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) i302- NO.

PULLMAN N/A N/A 2K3-1302-030-01 1988 REPLACEMENT YES PIPING POWER

RYXTEL PRODUCTQS

7. Description Of Work Installed replacement studs and nuts on piping flances located at 2F05282.

8. Test Conducted: Hydrostatic F] Pneumatic[] Nominal Operating PressureN/A [ Other E] Pressure N/A PSI Test Temp. WA QF

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed klavý!L @ Date /24 19 Owner or Owner's Designee, Title J

CERTIFICATE OF INSERVICE INSPECTION

1, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georoia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticui have inspected the components described in this Owner's Report during the period 1018/ to /,Z- 02 - and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report In accordance with the requirements of the ASME Code, Section Xi.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal Injury or property damage or a loss of any kind arising from or connected with this

= npao' In Inatu4-:0 Y Commissions 6A• 49 7 " Inspector'sCommissions National Board, State, Province and Endorsements

19Date /;- - 0.;--

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

1. Owner Southern Nuclear Operating CompanyName

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler # 99265

02/15/00

I Of 1

2

29802330 Repair Organization P.O. No., Job No., etc.

Plant VoatleAddress

4. Identification Of System 1302 / Auxiliary Feedwater System

5. (a) Applicable Construction Code ASME SEC I/I 1974 Edition, Summer 1975 (b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 198

Addenda, N/A

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) VALVE ANCHOR! E-9001-25-1 NIA 3-1302-U4-116 1980 REPLACEMENT YES

DARLING VALVE Co.

7. Description Of Work Installed reDlacement valve disc. A copy of Form N-2 for the reolacement disc is attached.

8. Test Conducted: Hydrostatic E] PneumaticE] Nominal Operating Pressure E] N/A Z Other L Pressure N/A PSI Test Temp. N/A ?F

CERTIFICATE OF COMPUANCE

We certify that the statements made In the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed L) A • L. - Date a/____ __

Owner or Owner's Designee, TRtlW

Date ________

J

Code Case

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of GeoroLa and employed by Hartford Steam Boiler Insoection and Insurance Co. of Hartford. Connecticut have , ingpected the components described in this Owner's Report during the period 10/18/99 to !Y - d .o 0 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable In any manner for any-lr onal Injury or property damage or a loss of any kind arising from or connected with this iCommissions A,44 4197

Inspector's Signature, National Board, State, Province and Endorsements

:ýi1 k APP

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

Traveler # 99266

1. Owner Southern NuclearOperating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electfic Generating Plant

Waynesboro, GA 30830Address

3. Work Performed by Nuclear Operations Maintenance Name

4. Identification Of System

Date

Sheet

Unit

MWO #

03/07/00

1 Of 3

2

29902485 Repair Organization P.O. No., Job No., etc.

Plant Vog•te Address

1203 / Component Coolina Water Svstem

5. (a) Applicable Construction Code ASME SEC III 1974 Edition, Winter 1975 Addenda, N/A Code Case (b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) VALVE FISHER 7785019 6382 2HV-11817 1981 REPLACEMENT YES

CONTROLS CO.

7. Description Of Work Installed replacement retaining dina (S/N 2) in valve. A copy of Form N-2 for the replacement retaining rino is attached. The material channe nf th4 rnnlpI-rnThnt rntnininn rinn7 k. •nnrnvp•rl fnr '•hnrf tnrrn incftllhthn

aooroved by CR# 2000000008,

8. Test Conducted: NIA

Hydrostatic [] PneumaticE] Nominal Operating Pressure[] Other F1 Pressure N/A PSI Test Temp. N/A 2F

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed D'ce4/,,.a ". Dt __-._Date_ __ /_ 20 I Ov~ner or Owner's Designee, Title [. I

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georqia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticu have inspected the components described in this Owner's Report during the period 1___ to 04-jP4-0OO , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report In accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable In any manner for any personal Injury or property damage or a loss of any kind arising from or connected with this Insp Ion _ _ _ _ _ ... . Commissions _ _ _ _ _ _ _ _

Inspector's Signature National Board, State, Province and Endorsements

Date 'A0 (, - 2040

attached. The material rhantia rd tha ranhqn-ament n4faininn rinn, iq qnnrnved for short f- inatAllatinn

ORIGINAL

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section Xl

1. Owner Southern Nuclear Operating Company

2. Plant

Name 40 Inverness Center Parkway, Birmingham,

Ala.

Vogtle Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

4. Identification Of System

Date

Sheet

Unit

MWO #

Traveler # 99267

11t23/99

Of

2

29903046 Repair Organization P.O. No., Job No., etc.

Plant Vogtie

Code Case

Address

12041 SAFETY INJECTION

5. (a) Applicable Construction Code ASME SEC III 1974 Edition, Summer '75 Addenda, N/A (b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) VALVE Rockwell BR140 N/A 2-1204-U4-143 1983 REPAIRED YES

International

N/A N/A N/A N/A N/A N/A N/A N/A

7. Description Of Performed locking tackweld on valve after maintenance. Work

8. Test Conducted: Hydrostatic [] Pneumatic[] Nominal Operating Pressure[ NIA E Other n Pressure WA PSI Test Temp. N/A F

CERTIFICATE OF COMPLIANCE

We certify that the statements made In the report are correct and this REPAIR Conforms to the rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization No. NIA Expiration Date N/A

Signed oýr Owners Date De 2knee 19Te Owner or Owner's Designee, TIt~e,#

/

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticut have inspected the components described in this Owner's Report during the period /0-0/. -q to Z?-0"7- 9- , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report In accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable In any manner for any personal injury or property damage or a loss of any kind arising from or connected with this 1• 1' jý,- Commissions 4;A 4-/9 7

Inspector's Signature National Board, State, Province and Endorsements

Date_________q_91

1204 / SAFETY INJECTION

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xi

1. Owner Southern NuclearOperating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtie Electric Generating Plant

Waynesboro, GA 30830Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler # 99271

01/03/00

I Of 3

2

29903124 Repair Organization P.O. No., Job No., etc.

Plant Vootle

Address4. Identification Of System 1202 / Nuclear Service Cooling Wate

5. (a) Applicable Construction Code ASME SEC II! 1974 Edition, Winter 1975 (b)Applicable Edition of Section Xi Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

r System

Addenda, N/A Code Case

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) VALVE CROSBY VALVE N67936-00- N/A 2PSV-11766 1997 REPLACEMENT YES

& GAGE CO. 0005

7. Description Of Work Installed replacement valve. A copy of Form NV- 1 for the reolacement valve is attached.

8. Test Conducted: Hydrostatic [] Pneumatic[] Nominal Operating PressureXN/A [] Other[] Pressure N/A PSI Test Temp. N/A OF

CERTIFICATE OF COMPLIANCE

We certify that the statements made In the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed 'JŽ,j4 k C - Date q' -tJ- Z- e' Owner or Owner's Designee, TItl i - ÷

S~AP I I-Ah UP ........... I..S...T.ONCERTIF;ICIIATE• OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co, of Hartford. Connecticut have Jnspected the components described in this Owner's Report during the period 10/20/99 to 0#1o3,_ -, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report in accordance with the requirements of the ASME Code, Section Xi.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any per nal injury or property damage or a loss of any kind arising from or connected with this ins ction. Commissions A4• JQ,7

-National 1oard, State, Province and Endorsements

ce\oO

Inspector's Signature ,/

Date 04 1 -43 -. Ai

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

1. Owner Southern NuclearOperating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Voftie Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #Repair Organization P.O. No., Job No., etc.

Plant VogtleAddress

4. Identification Of System 1205 / Residual Heat Removal System

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 Addenda, N/A Code Case

(b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) NO.

1205 PULLMAN N/A N/A 2K3-1205-006-01 1988 REPLACEMENT YES PIPING POWER

SYSTEM PRODUCTS __

7. Description Of Work Installed replacement studs and nuts on piping flances located 2FE061 1.

8. Test Conducted: Hydrostatic ] Pneumatic[] Nominal Operating Pressure[] NIA[•] Other F] Pressure NIA PSI Test Temp. N/A F

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed "•a- fiV 4,4_. Date Ii " 19 '71 Owner or Owner's Designee, Tltlq(

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticut have Inspected the components described In this Owner's Report during the period 10/21/29 to Z, -9, , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal Injury or property damage or a loss of any kind arising from or connected with this

_ _ _ _ Commissions aA V/97

Inspector's SIgnatur&1' National Board, State, Province and Endorsements

Date 19

Traveler # 99272

11/17/99

Of 1

2

29902568

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

1. Owner Southern NuclearOperating Company Name

40 Inverness Center Parkwav. Birminaham. AL

2. Plant Vogtle Electdc Generating Plant

Waynesboro, GA 30830Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler # 99273

12/16/99

I Of 1

2

29902622 Repair Organization P.O. No., Job No., etc.

Plant VootleAddress

4. Identification Of System 1205 / Residual Heat Removal Sy,

5. (a) Applicable Construction Code ASME SEC I _I 1977 Edition, Winter 1977 (b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

stem

Addenda, N/A Code Case

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) NO.

1205 PIPING PULLMAN N/A N/A 2K3-1205-009-01 1988 REPLACEMENT YES SYSTEM POWER

PRODUCTS

7. Description Of Work Installed reolacement studs and nuts in the oinina flanaes located at 2FE-0618.

8. Test Conducted: Hydrostatic [] Pneumatic[] Nominal Operating Pressure[] N/A n] Other n] Pressure NIA PSI Test Temp. NIA OF

CERTIFICATE OF COMPUANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No. _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _

Signed Date i/s)

Owner or Owner's Designee, Title F /-)0<

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Insoection and Insurance Co. of Hartford. Connecticui have Inspected the components described in this Owner's Report during the period 10/21/99 to 0.3-,• 2-00 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any perst=nl Injury or property damage or a loss of any kind arising from or connected with this !Insaction./s

J , • ---•, c a4.• = \ 4 . Commissions (:4 09 7

Inspector's Signature a National Board, State, Province and Endorsements

Date 0.3- o 2- - " X zo

SORIGINAL

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions of The ASME Code Section Xi

Traveler # 99274

1. Owner Southern Nuclear Operating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830Address

Date

Sheet

Unit

MWO #

3. Work Performed by Nuclear Operations Maintenance Name

08/15/00

! Of 3

2

29901788 Repair Organization P.O. No., Job No., etc.

Plant Vootle

Address

4. Identification Of System 1208 / Chemical arnd Volume Control System

5. (a) Applicable Construction Code ASME SEC Ill 1974 Edition, N/A (b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

Addenda, N/A

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE

OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED COMPONENT MANUFACTURER NO. NO. IDENT1FICATION BUILT REPLACEMENT (YES OR NO)

VALVE FISHER 9318722 2628 2FV-0121 1985 REPLACEMENT YES CONTROLS CO.

7. Description Of Work Valve vlua was reolaced. A covy of Form N-2 for the reolacement valve p"uo is attached.

8. Test Conducted: Hydrostatic E] Pneumatic[] Nominal Operating Pressure[] NIA [] Other fl Pressure NIA PSI Test Temp. N/A 9F

CERTIFICATE OF COMPUANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the

rules of the ASME Code, Section Xl. Repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed " V/'1 oi• - Date 20 Owner or Owner's Designee, Title/

Code Case

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticu have Inspected the components described In this Owner's Report during the period__Q10Q20l9 to R. od , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable In any manner for any personal Injury or property damage or a lose of any kInd arising from or connected with this

___________••___•_____•_•ommissions -. -4. .-23 Inspecjlr's Signature National Board, State, Province and Endorsements

Date •-.Tp 20400

ORIGINAL

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section Xl

Traveler # 99275

1. Owner Southern NuclearOperating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vootle Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet I

Unit

MWO #

11/17/99

Of 3

2

29802005 Repair Organization P.O. No., Job No., etc.

Plant VogSte Address

4. Identification Of System 1208 / Chemnlcal and Volume Control System

5. (a) Applicable Construction Code ASME SEC I11 1977 Edition, Winter 1977 Addenda, N/A

(b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) NO.

VALVE FISHER 5945210 2938 2HV-8149A 1978 REPLACEMENT YES CONTROLS CO.

7. Description Of Work Installed replacement plug assenmbly in valve. This replacement activity was not reviewed by the ANIII or Quality Control prior to implementaton as documented by condition report number4099e5S9. A copy of Form N-2 for therevid•LeInaF LJIU I,• •IIantIg. p w a-__ ____,

8. Test Conducted: NtAn

Hydrostatic [] Pneumatic[] Nominal Operating PressureL] Other F1 Pressure N/A PSI Test Temp. N/A 2F

Date "5-WS

Code Case

CERTIFICATE OF COMPLIANCE

We certify that the statements made In the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Owner or Owner's Designee, Title

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georola and employed by Hartford Steam Boiler Insoection and Insurance Co. of Hartford. Connecticu have inspected the components described In this Owner's Report during the period to - 1,5 _- W , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective medsures described In this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any perp al Injury or property damage or a loss of any kind arising from or connected with this ins lction.I ins~c . I -J " I 1A-• \ ý Commissions !ýa 4L97

Inspector's Signature V National Board, State, Province and Endorsements

IQe•I/Yl I•'•:1 <"

'ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

1. Owner Southern Nuclear~perating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtie Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler # 99276

11/16/99

I Of /

2

29902034 Repair Organization P.O. No., Job No., etc.

Plant VoqtleAddress

4. Identification Of System 1208 / Chemical and Volume Control

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 (b)Appllcable Edition of Section Xl Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

I System

Addenda, N/A

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) NO.

1208 PULLMAN NIA N/A 2K3-1208-116-01 1988 REPLACEMENT YES PIPING POWER

RYTE PROPUCTS ________ _____

7. Description Of Work Installed replacement studs and nuts on piping flanges located at 2FE01 11.

8. Test Conducted: Hydrostatic [] Pneumaticr' Nominal Operating Pressurel] N/A nX Other Rl Pressure N/A PSI Test Temp. N/A 1F

CERTIFICATE OF COMPLIANCE

We certify that the statements made In the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

____, _tle A._Da

Signed Owner or Owner's Designee, Title -1

Date 1; - 4 7, 19

Code Case

CERTIFICATE OF INSERVICE INSPECTION

1, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticut have inspected the components described In this Owner's Report during the period 10/21/99 to /0 - ?- , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report In accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable In any manner for any personal injury or property damage or a loss of any kind arising from or connected with this

IscosSn at N naorSPCommissions 64 4197 Inspector's Slgnaturif National Board, State, Province and Endorsements

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

1. Owner Southem NuclearOperating CompanyName

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogt/e Electric Generating Plant

Wavnesboro, GA 30830Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler # 99277

11/22/99

Of

2

29902742 Repair Organization P.O. No., Job No., etc.

Plant VoatleAddress

4. Identification Of System 1208 / Chemical and Volume Control

5. (a) Applicable Construction Code ASME SEC/III 1977 Edition, Winter 1977 (b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

System

Addenda, N/A

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) NO.

1208 PULLMAN N/A N/A 2J4-1208-037-01 1988 REPLACEMENT YES PIPING POWER

SYSTE PRODUCTS

7. Description Of Work Installed repLacement studs and nuts on piping flanges located at 2FE0156.

8. Test Conducted: Hydrostatic ] Pneumatic[] Nominal Operating PressureN/A [] Other R Pressure N/A PSI Test Temp. N/A 2F

CERTIFICATE OF COMPUANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed -AZ;a A 4 M Date iJ/ Q9. 19 i' Owner or Owner's Designee, TltleG

Code Case

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georqia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticui have Inspected the components described In this Owner's Report during the period_ 1024/9 to 1.2-0 2 -9 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corfective measures described In this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any 7ersonal injury or property damage or a loss of any kind arising from or connected with this in ectn Commissions t '

Inspector's Signature National Board, State, Province and Endorsements

Date /2-02- 19

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

Traveler # 99278

1. Owner Southern Nuclear Operating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

01/23/01

] Of 1

2

29902632 Repair Organization P.O. No., Job No., etc.

Plant VogtleAddress

4. Identification Of System 1208 / Chemical and Volume Control System

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 (b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

Addenda, N/A

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) 1208 PIPING PULLMAN N/A N/A 2K3-1208-055-01 1989 REPLACEMENT YES

SYSTEM POWER PRODUCTS

7. Description Of Work Installed replacement studs and nuts on opiing flanges at inlet to letdown reheat exchanger 2-1208-E6-007.

8. Test Conducted: Hydrostatic [] Pneumatic[] Nominal Operating PressureE] N/A []j Other l Pressure N/A PSI Test Temp. N/A F

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT Conforms to the rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorizati ntN. N/A Expiration Date N/A

Signed oY)r Owners Date Title0 Owner or Owner's Designee, Thite

Date I - ,s,2-

Code Case

961CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticut have Inspected the components described in this Owner's Report during the period 10/26/00 to /-A.r-a/ , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner r any personal Injury or property damage or a loss of any kind arising from or connected with this

__nsp _on. ____--,-, _____Commissions GA 20

"Inspector'SSignature National Board, State, Province and Endorsements

2001

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

1. Owner Southern Nuclear Operatng CompanyName

40 Invemess Center Parkway, Birmingham, AL

2. Plant Vogde Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler #

04/06/01

99279

Of

2

29902633

Repair Organization P.O. No., Job No., etc.

Plant Vogtie Address

S.... .. . . . . . A _._ , st_-4. Identification Of System 1208U/ Chlemical and Volume Control

5. (a) Applicable Construction Code ASME SEC III 1974 Edition, Winter 1975

(b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

Addenda, N/A

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO)

HEAT JOSEPH OAT 2322-4B 1055 2-1208-E6-003 1978 REPLACEMENT YES

EXCHANGER CORPORATION

7. Description Of Work Installed replacement studs and nuts on letdown heat exchanger head in accordance with MDC# 99-V2M062.

8. Test Conducted: Hydrostatic ] PneumaticE[] Nominal Operating Pressure[] N/A [] Other F] Pressure N/A PSI Test Temp. N/A OF

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT Conforms to the

rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization No. N/A Expiration Date N/A

Signed Nk• or -.- e r.. Date 12 20 r-> o r or Owner's Designee, Ttle

20 0/

I

Code Case

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel inspectors and the State or

Province of Georaia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Harfforci Connectcut have

inspected the components described in this Owner's Report during the period 10/27/00

to /4-e" -01 -, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the

examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall

be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this insqction. , - ,

22M Commiissions 4'4L7National Board, :Sate, Province and EndorsementsInspector's Signature

Date

Z I

Systemn

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xi

1. Owner Southern NuclearOperating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations MaintenanceName

Date

Sheet

Unit

MWO #

Traveler # 99280

12/08/99

1 Of 1

2

29902741 Repair Organization P.O. No., Job No., etc.

Plant VogqteAddress

4. Identification Of System 1208 / Chemical and Volume Control

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 (b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

I System

Addenda, N/A Code Case

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) NO.

1208 PULLMAN N/A N/A 2K4-1208-041-01 1988 REPLACEMENT YES PIPING POWER

SYSTEM I PROU_ _

7. Description Of Work Installed replacement studs and nuts on gibina flanaes at 2FE-0154.

8. Test Conducted: Hydrostatic [] Pneumatlc[E Nominal Operating PressureEr NA fX] Other E Pressure N/A PSI Test Temp. N/A 9F

CERTIFICATE OF COMPLIANCE

We certify that the statements made In the report are correct and this REPLACEMENT conforms to the

rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed k"/JL 1 Y}t % Date 19 q

Owner or Owner's Designee, Title [/ --

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticut

have inspected the components described in this Owner's Report during the period 2 to 9 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section XL.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any gersonal Injury or property damage or a loss of any kind arising from or connected with this "ýd Ipts lg r Commissions 5*c10

Inspector's Signatur.J Natiofiai Board, State, Province and Endorsements

Date 12- 1-3 19 4-9

I

•System

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

1. Owner Southern NuclearOperating CompanyName

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler # 99282

11/08/99

Of

2

29903364 Repair Organization P.O. No., Job No., etc.

Plant VotileAddress

4. Identification Of System 1501 / Containment Cooling System

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 Add (b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

ends, N/A

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) NO.

1501 PULLMAN N/A N/A 2V4-1501-038-01 1988 REPLACEMENT YES PIPING POWER

SyTM PRODUCTS ________ _____

7. Description Of Work Installed replacement nut on cooler2-1501-A7-008-000 outlet header fRance saddle support.

8. Test Conducted: Hydrostatic E] Pneumatic[] Nominal Operating PressureE] N/A [] Other [] Pressure N/A PSi Test Temp. WA QF

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.n n n1

Signed kI r ý1~~ ~kDate II 0 19 ct

Date _ _/- I/ __ _ 19 99

V

Code Case

V

CERTIFICATE OF INSERVICE INSPECTION

1, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticut have inspected the components described In this Owner's Report during the period 11/08/99 to 11-19'-492 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report In accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described In this Owners Report Furthermore, neither the Inspector nor his employer shall be liable In any manner for any personal Injury or property damage or a loss of any kind arising from or connected with this Ins n. 1 <. ,n A I Commissions 8,4 0 -97

Inspector's Signatur4V National Board, State, Province and Endorsements

ORIGINAL. FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

1. Owner Southern NuclearOperating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant VogUe Electric Generating Plant

Waynesboro, GA 30830Address

3. Work Performed by Nuclear Operations MaintenanceName

Date

Sheet

Unit

MWO #

Traveler # 99283

11/08/99

1 Of _

2

29903363 Repair Organization P.O. No., Job No., etc.

Plant Vopt/eAddress

4. Identification Of System 1501 / Containment Cooling System

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 Add (b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

enda, N/A

NAME NAME MANUFACTUR NATIONAL REPAIRED, ASME CODE OF OF ER BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER SERIAL NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) NO.

1501 PULLMAN N/A NIA 2V4-1501-033-01 1988 REPLACEMENT YES PIPING POWER

SYSTEM PRODUCTS

7. Description Of Work Installed replacement nut on cooler2-1501-A 7-005-000 outIet header flange saddlQe sunDOrt.

8. Test Conducted: Hydrostatic Fl Pneumatlc[] Nominal Operating Pressure[] NIA [J Other [] Pressure NIA PSI Test Temp. NIA 2F

CERTIFICATE OF COMPUANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section Xi. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A N.o Signed -wPner or OnesDieeTt, Date it 19q

O;wn;1er or` Owner's Designee, Tltlh[j

Code Case

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georola and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. ConnecticuA have Inspected the components described In this Owner's Report during the period 11/08/99 to I - 9 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report In accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable In any manner for any p"M Injury or property damage or a loss of any kind arising from or connected with this

pAV _ Commissions 3A V9 7 Inspector's Signature National Board, State, Province and Endorsements

Date 19 .9..

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

1. Owner Southern NuclearOperating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

Traveler # 99285

03/09/00Date

Sheet I Of

Unit

MWO #

I

2

29903481 Repair Organization P.O. No., Job No., etc.

Plant VogSte Address

4. Identification Of System 1217/1 Auxiliary Component Cooling Water System

5. (a) Applicable Construction Code ASME SEC Ill 1977 Edition, Winter 1977 Addenda, N/A (b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 1989 Code Case N-416-1

6. Identification Of Components Repairs Or Replacement Components

Code Case

- & L

7. Description Of Work A weld on line 2-1217-183-1.12 had to be to be cut out and rewelded to facilitate piping instlation under DCP97-V2NO056. Pressure test performed in coniunction with Section XI Traveler# 99131 under WO# 29901685.

8. Test Conducted: WADl

Hydrostatic ] Pneumatic[] Nominal Operating Pressure[X] Code Case N-416-1 Other E1 Pressure NIA PSI Test Temp. NIA 9F

Date o Vo-6 o20_

]

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODEOF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO)

1217PIPING PULLMAN N/A N/A 2K3-1217-183-03 1987 REPAIR YES SYSTEM POWER

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPAIR conforms to the rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No. _ _ _ _ _ _ _ _

Signed ek2)A,4•',\- 1 Date 3/ I • 20

Owner or Owner's Deslgnee,nItle/"

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticui have Inspected the components described in this Owner's Report during the period 11/16/99 to 0 -,jo 0 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal Injury or property damage or a loss of any kind arising from or connected with this

4?Ln jdiLS( Commissions de •4°• 7

Inspector's Signature L/ National Board, State, Province and Endorsements

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xi

.1

1. Owner Southern Nuclear Operating CompanyName

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler # 00015

05/17/00

I Of 3

2

20000132 Repair Organization P.O. No., Job No., etc.

Plant VogUeAddress

4. Identification Of System 1301 / Main Steam System

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 (b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

Addenda, N/A

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) VALVE CONTROL 23469-1-4 N/A 2PV-3030 1982 REPLACEMENT YES

COMPONENTS INC_

7. Description Of Work Valve pluo was replaced. A copV of Form N-2 for the replacement valve Dlu is attached.

8. Test Conducted: Hydrostatic [] Pneumatic[] Nominal Operating PressureDNWAE] Other E] Pressure WA PSI Test Temp. NIA 2F

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section Xl. Repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No.

Signed %k- 2 ,.. ) 7 P) , Date -/ Vj 2000 Owner or Owner's Designee,'Title d

Code Case

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georoia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticut have inspected the components described In this Owner's Report during the period 02/29/00 to _, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this

.151=4 Commissions 5,4 ý;47 Inspector's Signature National Board, State, Province and Endorsements

Date 0

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

Traveler # 00087

1. Owner Southern Nuclear Operating CompanyName

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations MaintenanceName

Date

Sheet

Unit

MWO #

09/05/00

Of

2

20001127Repair Organization P.O. No., Job No., etc.

Plant Vogtie Address

4. Identification Of System 2101 / Containment Building System

5. (a) Applicable Construction Code ASME SEC III 1975 Edition, Winter 1975 Addenda, N/A (b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 192_

Code Case

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO)

CONTAIN- WALSH N/A N/A 2-2101- 1988 REPLACEMENT NO MENT CONSTRUCTION CNMTBLDG

BUILDING CO.

7. Description Of Work Concrete was replaced around the grease vents.

8. Test Conducted: Hydrostatic ] Pneumatic'] Nominal Operating PressureDl N/A [] Other E Pressure N/A PSI Test Temp. N/A 2F

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the

rules of the ASME Code, Section XI. Repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A No._..... ._ _

Signed , 2ol Owner or Owners Designee, Title IJ

Date 9-/A-- 20 00

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Insoection and Insurance Co. of Hartford. Connecticut have inspected the components described in this Owner's Report during the period 06/21/00 to 9 - Ar"-o. , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable In any maq er for any personal injury or property damage or a loss of any kind arising from or connected with this Ins_ ection._&4__ _ _ _ Commissions 6A 7 0 3

Inspedtor's Signature National Board, State, Province and Endorsements

Date q -/A--, 20 0 0

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required ByThe Provisions Of The ASME Code Section Xl

Traveler # 00090

1. Owner Southern Nuclear Operating CompanyName

40 Inverness Center Parkway. Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

02/08/01

_ _ _ Of 1

2

20001032 Repair Organization P.O. No., Job No., etc.

Plant VogtleAddress

4. Identification Of System 1902 ( Waste Processing System - Gas

5. (a) Applicable Construction Code ASME SEC III 1974 Edition, Summer 1976 Addenda, N/A

(b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

Code Case

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) HEAT AMETEK 78H-104 255 2-1902-C6-002 1978 REPLACEMENT YES

EXCHANGER SCHUTTE &

7. Description Of Work Installed replacement studs and nuts on heat exchanger head.

8. Test Conducted: Hydrostatic ] PneumaticE] Nominal Operating Pressure[] N/A [] Other [] Pressure N/A PSI Test Temp. N/A QF

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT Conforms to the rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization No. N/A Expiration Date N/A

Signed /_ Oe r " _ ow nr s Date DQin T 20 nl Owner or Owner's Designee, TIN

Date -- 1- 20ý

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticut have inspected the components described In this Owner's Report during the period 07/18/00 to 1-2i-/ •l , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any man er for any personal injury or property damage or a loss of any kind arising from or connected with this

Commissions CA 2 63'

Insp9-tor's Signature National Board, State, Province and Endorsements

20 0 /

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

Traveler # 00139

1. Owner Southern Nuclear Operating CompanyName

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtfe Electfic Generating Plant

Waynesboro, GA 30830Address

Date

Sheet

Unit

MWO #

3. Work Performed by Nuclear Operations Maintenance Name

04/03/01

_ _ _ _ Of

2

20001879 Repair Organization P.O. No., Job No., etc.

Plant Vo0tie

Address

4. Identification Of System 1202 / Nuclear Service Cooling Water System

6. (a) Applicable Construction Code ASME SEC III 1974 Edition, Winter 1975 Addenda, N/A

(b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

Code Case

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) RELIEF CROSBY N67951-00-0001 N/A 2PSV-11746 1984 REPLACEMENT YES VALVE

7. Description Of Work Relief valve SAV N67951-00-0007 was removed for inservce testinf and was replaced by relief valve S/V N6795100-0001. Relief valve S1N 67951-00-0001 was originally instalied as 1PSV-11744. removed under MWO# 10001472 and returned to warehouse stock as a spare.

8. Test Conducted: Hydrostatic ] Pneumatic[] Nominal Operating Pressure[•] N/AD Other [] Pressure N/A PSI Test Temp. N/A OF

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code, Section Xl. Repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization No. N/A Expiration Date N/A

Signed .On orOwnersesinere Date ,Titloe 20 0

I owner or Owner's Designee, Title ~' I

Date 20 - -0

I

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford, Connecticut have inspected the components described in this Owner's Report during the period 11/02/00 to 4 - 6 ( _, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspeion• insp,9•/,on - ,•"• 'OI 4 Commissions ($ "

Inspector's Signature National Board, State, Prbvince and Endorsements

E¸

!

20 cl

/

1. Owner Southern Nuclear Operating Company Name

40 Invemess Center Parkway, Birmingham, AL

2. Plant Vogtile Electric Generating Plant

Wavnesboro, GA 30830

Date

Sheet

Unit

MWO #Address

3. Work Performed by Nuclear Operations Maintenance Name

Traveler # 00141

02/21/01

Of

2

20001880 Repair Organization P.O. No., Job No., etc.

Plant Vogtie

Address

4. Identification Of System 1202 / Nuclear Service Cooling Water System

5. (a) Applicable Construction Code ASME SEC III 1974 Edition, Winter 1975 Addenda, N/A

(b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO)

RELIEF CROSBY N67951-00- N/A 2PSV-11752 1984 REPLACEMENT YES

VALVE 0006

7. Description Of Work Relief valve S/N N67936-00-0003 was removed for inservice testing and was replaced by relief valve S'N N67936-00-0006. Relief valve SIN 67936-00-0006 was orfinally installed as 1PSV- 11752, removed under MWO# 10000136, and returned to warehouse stock as a spare.

8. Test Conducted: NIA-

A'

Hydrostatic [] Pneumatic[] Nominal Operating Pressure[l Other [] Pressure N/A PSI Test Temp. N/A

Date 20 �li

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

Code Case

gF

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT conforms to the

rules of the ASME Code, Section XI. Repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization N/A Expiration Date N/A

No.

Signed . J ') . .-- A,'n• , Date -/z-/ 20 O0 _)Owner or Owner's Designee, Title IJ

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel Inspectors and the State or Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticut

have Inspected the components described in this Owner's Report during the period 11/16/00

to ,1--- ) / , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken

corrective measures described In this Owners Report In accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the

examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable In any manner for any personal Injury or property damage or a loss of any kind arising from or connected with this

_n_______ _________ Commissions e$4,;e . Inspectorfs Signature National Board, State, Province and Endorsements

r-'. ,•"

Date 20 .0/_

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

Traveler # 00157

1. Owner Souther Nuclear Operating CompanyName

40 Inverness Center Parkway, Birmingham, AL

2. Plant Voglie Eectric Generating Plant

Waynesbom, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO#

04/06/01

1 Of 1

2

29902633 Repair Organization P.O. No., Job No., etc.

Plant Vodtle

Address

4. Identification Of System 1208 / Chemical and Volume Control System

5. (a) Applicable Construction Code ASME SEC III 1977 Edition, Winter 1977 Addenda, N/A

(b)Applicable Edition of Section Xl Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

Code Case

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE

OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO)

1208 PIPING PULLMAN N/A N/A 2K3-1208-055-01 1989 REPLACEMENT YES

SYSTEM POWER 2K3-1208-066-01 PRODUCTS

7. Description Of Work Installed replacement studs and nuts on piping flanges at the tube side inlet and outlet to letdown exchanoer 2-1208E6-003.

8. Test Conducted: Hydrostatic [] Pneumatic[] Nominal Operating Pressure[:]

N/A f] Other [] Pressure N/A PSI Test Temp. N/A OF

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT Conforms to the

rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization No. N/A Expiration Date N/A S . I . .Mc•n• , rae ____________

Signed -V\..----Mr Date q .,_ 20

7 Owner or Owner's Designee, Title

Date 72 - / -&/

t

CERTIFICATE OF INSERVILIP•ON mNmu iur

1, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel inspectors and the State or

Province of Georqia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford, Connecticut have

inspected the components described in this Owner's Report during the period 12/06/00

to '0"4-1-61J , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken

corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the

examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall

be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this

inspe on. /J6'v2~.-w-,t_. //'•lJ/,j'a'rJ• L, Commissions 6' /6.!

National Board, State, Province and EndorsementsInsdctor's Signature

20

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xl

Traveler # 00193

1. Owner Southern Nuclear Operating Company Name

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830 Address

Date

Sheet

Unit

MWO #

3. Work Performed by Nuclear Operations Maintenance Name

02/09/01

1 Of 3

+" Z c/ao'

20000453 Repair Organization P.O. No., Job No., etc.

Plant Voatle

Address

4. Identification Of System 1204 / Safety Injection System

5. (a) Applicable Construction Code ASME SEC III 1974 Edition, Summer 1974

(b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989

Addenda, N/A

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE

OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO)

HEAT SENTRY 786103 1279 Ae1204-P6-003- 1978 REPLACEMENT YES

EXCHANGER EQUIPMENT "- M01

HEAT SENTRY 786104 1280 Jf1204-P6-003- 1978 REPLACEMENT YES

EXCHANGER EQUIPMENT A- M01

7. Description Of Work Installed replacement water boxes (plenums) on motor heat exchanaers per REA 98-VAA600. Copy of Form N-2

for the replacement water boxes is attached S/N 1279-1. 1279-2. 1280-1 and 1280-2. The bolts on these heat

exchanoers were also replaced.

8. Test Conducted: NIAL

Hydrostatic [:] Pneumatic[-] Nominal operating Pressure[9] Other [] Pressure N/A PSI Test Temp. N/A

Date � /9 20 � I

I

Code Case

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT Conforms to the

rules of the ASME Code, Section XI. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorizatlo5g No. N/A Expiration Date N/A

Signed Owe r Oi Date ,20 L)

Owner or Owner's Designee, TIO

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel Inspectors and the State or

Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford, Connecticbi have

inspected the components described In this Owner's Report during the period 12/15/00

to V- I/r - , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken

corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the

examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall

be liable in any mar er for any personal Injury or property damage or a loss of any kind arising from or connected with this

_________________,,_r_-.- Commissions GA ,63 "Insoeepor's Signature National Board, State, Province and Endorsements

20. 0/Date -23- 19)

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section XI

Traveler# 01003

1. Owner Southern Nuclear Operating Company DateName

40 Inverness Center Parkway, Birmingham, AL Sheet

2. Plant Vogtle Electric Generating Plant

Waynesboro, GA 30830 Address

3. Work Performed by Nuclear Operations Maintenance Name

Unit

MWO #

03/01/01

1 Of 3

2

20000451 Repair Organization P.O. No., Job No., etc.

Plant Vogtle Address

4. Identification Of System 1208 / Chemical and Volume Control System

5. (a) Applicable Construction Code ASME SEC III 1971 Edition, Summer 1972 Addenda, N/A

(b)Applicable Edition of Section Xi Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO)

HEAT SENTRY 78100 1276 2-1208-P6-002- 1978 REPLACEMENT YES

EXCHANGER EQUIPMENT M01 CORP.

HEAT SENTRY 78101 1277 2-1208-P6-002- 1978 REPLACEMENT YES

EXCHANGER EQUIPMENT M01 I - I CORP

7. Description Of Work Installed replacement water boxes (plenums) on motor heat exchanoers Per REA 98-VAA600. Copy of Form N-2 for the replacement water boxes is attached SIN 1276-1. 1276-2. 1277-1 and 1277-2.

8. Test Conducted: NIAf-

Hydrostatic [] Pneumatlc[] Nominal Operating Pressure[Z] Other [] Pressure N/A PSI Test Temp. N/A

Date ,-?-A-,

Code Case

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT Conforms to the

rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization No. N/A Expiration Date N/A

Signed 7 O D Aeign . 5 cod I Date I a 2o ( Owner or Owiner's De~ignee, Title 1,51) 114,/& 4, 1V (dC/(c,p

CERTIFICATE OF INSERVICE INSPECTION

1, the undersigned, holding a valid commission Issued by the national Board of boiler and Pressure vessel Inspectors and the State or

Province of Georgia and employed by Hartford Steam Boiler Inspection and Insurance Co. of Hartford. Connecticut have

Inspected the components described In this Owner's Report during the period 01/09/01

to - f, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken

corrective measures described in this Owners Report In accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the

examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall

be liable in any mann for any personal Injury or property damage or a loss of any kind arising from or connected with this

SCommissions . A os "Inspec6r's Signature National Board, State, Province and Endorsements

2041

ORIGINAL FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required By The Provisions Of The ASME Code Section Xi

1. Owner Southern Nuclear Operating CompanyName

40 Inverness Center Parkway, Birmingham, AL

2. Plant Vogtde Electric Generating Plant

Waynesboro, GA 30830Address

3. Work Performed by Nuclear Operations Maintenance Name

Date

Sheet

Unit

MWO #

Traveler #

04/03/01

01011

I Of 3

20000454Repair Organization P.O. No., Job No., etc.

Plant Vogtfe Address

4. Identification Of System 1204 / Safety Injection System

5. (a) Applicable Construction Code ASME SEC III 1974 Edition, Summer 1974 (b)Applicable Edition of Section XI Utilized For Repairs Or Replacements 1989

6. Identification Of Components Repairs Or Replacement Components

Addenda, N/A

NAME NAME MANUFACTURER NATIONAL REPAIRED, ASME CODE OF OF SERIAL BOARD OTHER YEAR REPLACED OR STAMPED

COMPONENT MANUFACTURER NO. NO. IDENTIFICATION BUILT REPLACEMENT (YES OR NO) HEAT SENTRY 786102 1278 1204-P6-04-MOl 1978 REPLACEMENT YES

EXCHANGER EQUIPMENT ?CORP. _ _ _ _ ___ _

HEAT SENTRY 786105 1281 X1204-P6-004-M01 1978 REPLACEMENT YES EXCHANGER EQUIPMENT I - CORP. _ _ _,1_ _

7. Description Of Work Installed replacement water boxes (plenums) on motor heat exchangers Mer REA 98-VAA600. Copy of Form N-2 for the replacement water boxes is attached S/IN 1278-1. 1278-2. 1281-1 and 1281-2.

8. Test Conducted: N/A

Hydrostatic [] Pneumatic[-] Nominal Operating Pressure[Z Other [] Pressure N/A PSI Test Temp. N/A

Code Case

OF

CERTIFICATE OF COMPLIANCE

We certify that the statements made in the report are correct and this REPLACEMENT Conforms to the rules of the ASME Code, Section Xl. repair or replacement

Type Code Symbol Stamp N/A

Certificate of Authorization No. N/A Expiration Date N/A

Signed Ow owDate ner's 20 D T Q? Ownier or Owner's Designee, Title J

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the national Board of boiler and Pressure vessel inspectors and the State or Province of Geomia and employed by Hartford Steam Botler Inspection and Insurance Co. of Hartford Connecticut have insperted the components described in this Owner's Report during the period 01/29/01 to -7- 1 ) ,. and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this insp-'tion. /

42'JA',, ,ý Commissions A/•7 Inspector's Signature National Board, State, Province and Endorsements

Date I*- 7'-, / 20