united states nuclear regulatory commission · 2020. 12. 5. · maintenance services for nuclear...
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0 UNITED STATES NUCLEAR REGULATORY COMMISSION
Z0 WASHINGTON, D. C. 20555
August 23, 1990
Docket Nos. 50-269, 50-270, 50-287 50-369, 50-370, 50-413, 50-414
LICENSEE: Duke Power Company
FACILITIES: Oconee Nuclear Station, Units 1, 2 and 3 McGuire Nuclear Station, Units 1 and 2 Catawba Nuclear Station, Units I and 2
SUbJECT: SUMMARY OF JULY 16, 1990 INTERFACE MEETING WITH DUKE POWER COMPANY
On July 16, 1990, the NRC staff met at the general office of the Duke Power Company (Duke) in Charlotte, NC to discuss licensing and regulatory issues. This meeting was part of a continuing series of meetings held three times annually. Representatives of the Duke corporate office, the three Duke nuclear stations, NRC Resident Inspection staff and NRR participated in the meeting. An agenda of the meeting is included as Enclosure 1.
After opening remarks, Duke made a presentation on initiatives undertaken in the Duke Quality Assurance (QA) Programs. The presentation covered QA performance assessment, training initiatives, Self Initiated Technical Audit program process and status, and enhancements to the QA verification process. The next presentation discussed the Transmission Department (TD) organization relationship to station management and TD training, procedures and work control system.
Following those presentations, a representative from the NRC Office of Enforcement made a presentation on the enforcement policy in the area of maintenance violations. He indicated that escalated enforcement could be taken for severity level I, II, or III violations that were caused by maintenance program deficiencies which could have been prevented by proper implementation of the Commission's Revised Policy Statement on the Maintenance of Nuclear Power Plants. Such enforcement actions would be submitted to the Commission for review. The process by which the region recommends severity levels and civil penalties remains unchanged. During the presentation, Duke requested that the NRC allow licensees an opportunity to make an additional presentation after the initial enforcement conference, if changes to the original severity level or civil penalty are made.
The Catawba Station Manager then presented an analysis of the unavailability rate for the Catawba Auxiliary Feedwater system. Following a presentation on the status of the Duke Design Basis Documentation program, the NRC made a presentation on the background and status of revisions to the approved source term.
9009040C)48 90823 PDR ADOCK 05000269 - -- ___ PDC
- 2 - August 23, 1990
Future revisions are not expected to significantly affect currently licensed plants and are not expected to result in changes in the size of Emergency Planning Zones.
At the conclusion of the meeting, a tour was taken of the Duke System Dispatchers center and the Catawba/McGuire Crisis Management Center. The participants then briefly met in three groups to discuss plant-specific issues relating to Oconee, McGuire and Catawba.
Meeting participants are listed in Enclosure 2. Handouts used during the presentation are provided in Enclosure 3.
Leonard A. Wiens, Project Manager Project Directorate 11-3 Division of Reactor Projects I/II
Enclosures: As stated
cc/w enclosures: See next page
Db Docket File OGC NRC PDR E. Jordan Local PDR NRC Participants (See Enclosure 2) F. Maraglia ACRS (10) J. Partlow R. Borchardt PDII-3 R/F D. Matthews L. Wiens
OFC . :PDII-3 PM:PDII-3 D:P& NAME EIngram LWiens DMat hews DATE 1 / 90 f/9i/90 /go/0
OFFICIAL RECORD COPY Document Name: DUKE INTERFACE MEETING SUMMARY
Duke Power Company Catawba Nuclear Station McGuire Nuclear Station Oconee Nuclear Station
cc: A.V. Carr, Esq. North Carolina Electric Membership Duke Power Company 3400 Sumner Boulevard 422 South Church Street P.O. Box 27306 Charlotte, North Carolina Raleigh, North Caroline 27611
J. Michael McGarry, III, Esq. Saluda River Electric Cooperative, Bishop, Cook, Purcell and Reynolds Inc. 1400 L Street, N.W. P.O. Box 929 Washington, D.C. 20005 Laurens, South Carolina 29360
North Carolina MPA-1 Senior Resident Inspector Suite 600 Route 2, Box 179N 3100 Smoketree Ct. York, South Carolina 29745 P.O. Box 29513 Raleigh, North Carolina 27626-0513 Regional Administrator, Region II
U.S. Nuclear Regulatory Commission Ms. S. S. Kilborn 101 Marietta Street, N.W., Suite 2900 Area Manager, Mid-South Area Atlanta, Georgia 30323
ESSD Projects Westinghouse Electric Corp. Mr. Heyward G. Shealy, Chief MNC West Tower - Bay 239 Bureau of Radiological health P.O. Box 355 South Carolina Department of Health Pittsburgh, Pennsylvaria 15230 and Environmental Control
2600 Bull Street County Manager of York County Columbia, South Carolina 29201 York County Courthouse York, South Carolina 29745 Ms. Karen E. Long
Assistant Attorney General Richard P. Wilson N.C. Department of Justice Assistant Attorney General P.O. Box 692 S.C. Attorney General's Office Raleigh, North Carolina 27602 P.O. Box 11549 Columbia, South Carolina 29211 Mr. Robert G. Morgan
Nuclear Production Department Piedmont Municipal Power Agency Duke Power Company 121 Village Drive P.O. Box 33189 Greer, South Caroline 29651 Charlotte, North Carolina 28241
Mr. Alan R. Herdt, Chief Dr. John M. Barry Project Branch #3 Department of Environmental Health U.S. Nuclear Regulatory Commission Pecklenburg County 101 Marietta Street, N.W., Suite 2900 1200 Blythe Boulevard Atlanta, Georgia 30323 Charlotte, North Carolina 28203
Duke Power Company -2
cc: County Manager of Mecklenburg County Honorable James M. Phinney 720 East Fourth Street County Supervisor of Oconee County Charlotte, North Carolina 28202 Walhalla, South Carolina 29621
Mr. J. S. Warren Mr.- Paul Guill Duke Power Company Duke Power Company Nuclear Production Department P.O. box 33189 P.O. Box 33189 422 South Church Street Charlotte, North Carolina 28242 Charlotte, North Carolina 29621
Senior Resident Inspector Mr. H. B. Tucker, Vice President c/o U.S. Nuclear Regulatory Commission Nuclear Production Department 12700 Hagers Ferry Road Duke Power Company Huntersville, North Carolina 28078 P.O. Box 1007
Charlotte, North Carolina 28201-1007 Senior Resident Inspector U.S. Nuclear Regulatory Commission Route 2, Box 610 Seneca, South Carolina 27611-7687
Mr. Dayne H. Brown, Director Department of Environmental,
Health and Natural Resources Division of Radiation Protection P.O. Box 27687 Raleigh, North Carolina 27611-7687
Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Division Suite 525 1700 Rockville Pike Rockville, Maryland 20852
Manager, LIS NUS Corporation 2536 Countryside Boulevard Clearwater, Florida
Office of Intergovernmental Relations 116 West Jones Street Raleigh, North Carolina 27603
Enclosure 1
Duke/NRC Interface Meeting July 16, 1990
Wachovia Center/WC-2669 Charlotte, N.C.
8:30 Coffee
9:00 Introductions/Opening Remarks Mike Tuckman
9:15 Quality Assurance John Frye Program Initiatives Doug Franks
10:15 Break
10:30 Transmission Department Roy Holmes Interface Jeff Ashe
11:30 Design Basis Documentation Jack Peele Program Status
12:00 Catawba Emergency Feedwater Pump Tony Owen
12:15 Lunch
1:15 NRC Presentation Dave Matthews
2:15 Corporate Office Tour Mike Tuckman
o NPD
o erisis Management Center
o Dispatch Center
3:15 Adjourn
Enclosure 2
ATTENDEES
NAME ORGANIZATION
L. Wiens NRC/NRR/PDII-3 T. Cooper NRC/RI/McGuire W. Orders NRC/SRI/Catawba D. Hood NRC/NRR/PDI1-3 D. Matthews NRC/NRR J. Frye Duke/QA/Audit L. Davison Duke/QA/General Office B. Dolin Duke/Design Eng./Catawba D. Murdock Duke/DE/McGuire R. Wilkinson Duke/NPD/Planning & Consulting D. Franks Duke/QA/McGuire G. Grier Duke/QA/G.O. J. Peele Duke/Design Eng./Oconee B. Futrell Duke/NPD/Nuc Safety Assurance B. Gill Duke/NPD/Regulatory Compliance R. Morgan Duke/NPU/Regulatory Compliance S. Ninh NRC/RI/McGuire F. Rinaldi NRC/NRR/PD1l-3 O K. Jabbour NRC/NRR P. Skinner NRC/SRI/Oconee M. Tuckman Duke/NPD/Nuclear Support B. Miller NRC/RII/Project Engineer H. Tucker Duke/NPD/G.O. P. Nardoci Duke/NPD/Regulatory Compliance P. Guill Duke/NPD/NSA W. Scott NRC/NRR/Performance
Evaluation Branch J. Ashe Duke/Trans/EM&C L. Tatum Duke/Trans/EM&C R. Holmes Duke/Trans/EM&C J. Hicks Duke/Trans/VP E. LeGette Duke/Oconee/Compliance W. Troskoski NRC/Office of Enforcement
AGENDA
Opening ReMarks
- Jim Hicks, Uice President Transmission
Transmission Department Organization
- Roy Holmes, Manager Transmission EMC
Training, Procedures, & Work Control Systems
- Jeff Ashe, Manager Plant Support
Closing ReMarks
- Jim Hicks, Uice President Transmission
Open The Floor For Questions
Why Is There A Transmission Organization
How Is Transmission Organized
What Transmission Does In Nuclear Plants
Plans To Strengthen Transmission Service
To Nuclear Plants
Transmission Department
U P Trasmission
Transmission mmmm Department Review Committee
Employee Relations Administration Line & Safety & Services Maintenance &
Construction
.o Electrical
Operations Maintenance & Engineer Construction
Transmission Department
EMC Division
Manager
EMC Division
District Manager District Manager District Manager Manager Manager EMC EMC EMC EMC EMC
Charlotte Greenville Greensboro Electrical Supt. Plant Maint.
Manager Plant Support
Transmission Department
EMC Division
Charlotte District
Greensboro District
Greenville District
District Manager
EMC
Supervisor
Planning
District District EngieerEngne. Superintendent Superintendent Superintendent
Relaying Nhr Meter Test Steel Breakers Batteries Controls Meter & Instr. Foundation Cable Transformers
Computer Control House Aux. Systems Capacitors Maintenance
Doble Testing Switchgear
Paint
Transmission Department
EMC Division
Plant Maintenance Section
Manager
EMC
Plant Maintenance
Engineer
Superintendent Superintendent Manager
Plant Support
Generator Motor Nuclear Station Generator Testing Bus Support Engineers
Excitation Systems
Maintenance Services For Nuclear Plants
- Breakers - 600 volt to 500,000 volt
a Motors - 4160 and 6900 volt
* Protective Relaying - 600 to 500,000 volt Systems
* Transformers - 600 volt to 500,000 volt
Power Transformers
* Metering and Instrumentation - Electrical Systems
* Generators - Turbine and Diesels
* Phase Bus - 600 volt and above
NUCLEAR PRODUCTION TRANSMISSION
DEPARTMENT DEPARTMENT
Station Manager
Manager Plant
Maintenance
Superintendent
of
Maintenance
Transmission -------------------------------------
Superintendent
Manager
Maintenance
Engineering
Services Supervisor Supervisor
Technical Station ------------------ support Support
Assistant
I. TRANSMISSION DEPARTMENT EMPLOYEE TRAINING AND QUALIFICATION PROGRAM
* Approach Used
" Program Revisions
" ETQS Program Layout
II. PROCEDURES
* Upgrade
- Non Class iE
III. WORX CONTROL SYSTEMS
TRAINING SYSTEMS DEVELOPMENT MODEL
ANALYSIS DESIGN DEVELOPMENT IMPLEMENTATION
EVALUATION
* 0 JOB ANALYSIS
* DEVELOP.TASK LISTING * PERFORM JOB SURVEY
* DETERMINE TASK RATINGS (FREQUENCY, DIFFICULTY
EMPLOYEE TRAINING AND QUALIFICATION AND IMPORTANCE)
SYSTEM (ETQS) PROGRAM REVISIONS T
*VERIFY TASK LISTINGS *IDENTI FY SKILLS &, KNOWLEDGES
I_ TRAINING ANALYSIS * GROUP SKILLS AND KNOWLEDGES
INPO 86-18 * IDENTIFY SETTINGS FOR TRAINING * REVIEW WITH PRODUCTION
GENERAL EMPLOYEE SUPPORT DEPARTMENT TRAINING (GET)
COMMON SKILLS I & KNOWLEDGES
INITIALTRANSMISSION PROGRAM DEVELOPED
T & Q GUIDES
TASKS DETERMINED TO REQUIRE CLASSROOM PRODUCTION SUPPORT TASKS DETERMINED OR LAB TRAINING DEPARTMENT DEVELOPED TO REQUIRE
ON-THE-JOB CLASSROOM TRAINING TRAINING
EXISTING EMPLOYEES ARE ASSESSED AND PLACED INTO THE PROGRAM AT THE
CORRECT LEVEL
TRANSMISSION DEPARTMENT ETQS PROGRAM
Pftimental Technician *wat uniMath Modfle For: Relay and Meter Of
Technician On-%
Funamental Electuiclan Introduction Duty Area
For Specific 1kailng For all employees Bus Motor or Includes Admln., Breaker Switchgear Safety, General Knowledge aDo T1 Tools and Equipment Generator
Electronics
FUniamental Mechangc I iy Area Pr .. specem wralning
Or For Crane, Ro0Wi0 aIR And Steel Crews IOl13~l~l
XEY POINTS
Organization Changes
* Matrix to Superintendent of Maintenance and
Maintenace Engineering Services Onsite
* Locate Field Crews Onsite
* Onsite Procedure Writing
- Enhance Information Flow
* UP Improved Focus On Transmission Activities
ETQS Program
* Fully Accredited
* Production Support Department Guidance and Support
" Classroom Training Starting 7-16-90
Enclosure 3
DESIGN BASIS DOCUMENTATION PROGRAM STATUS
NRC/DUKE INTERFACE MEETING JULY 16, 1990
B L PEELE DIVISION PROJECT MANAGER DESIGN ENGINEERING DEPARTMENT
DESIGN BASIS DOCUMENTATION * PROGRAM STATUS
AGENDA
1) NEED FOR PROGRAM
2) SCOPE AND SCHEDULE
3) CURRENT STATUS
4) DB DOCUMENTS
5) INVOLVEMENT WITH INDUSTRY
6) NUMARC DB GUIDELINES
7) WORKSHOP
8) QUESTIONS OR COMMENTS
Duke Power/Design Engineering Dept.
Transition: New Construction --. Station Support
Catawba 2 C. 0. - 8/86
TOPFORM - 3/87 (The Overall Plan for Organizational Review of Mods)
TOPFORM Refined - 2/88
DE Site Offices - 4/88
DE Project Organization - 11/88
Design Basis Documentation Report - 5/89
eEngineered Solutions to Problems
a50.59 Evals. of Mods.
*Operability Evals.
DESIGN BASIS DOCUMENTATION
* Design Requirements
* Required Operating Modes
* System Descriptions
* NRC Commitments
DUKE SITA *More productive audits/responses
*Better system design basis understandirg
Better able to identify generic issues
DBD Pilots
Oconee - Emergency Feedwater System (EFW)
McGuire - Emergency Diesel Generator Starting Air System (VG)
Catawba - Nuclear Service Water Pump Structure
DBD Project Management
Quality Design Nuclear Assurance Engineering Production
Lead Dept.
G oon Technical Engineering Oconee General Nclea ce Nuclear Services Support Project Office Nuclear
Station Division Division Station
Mechanical Electrical Civil
* Review DBD Specs. * Prepare & Transmit DBD Specs. * Review DBD & TAC * Normal Document Audit - 1989 Scope Identified * Initiate and Resolve PIRs * SITA Audit Lead - Coordinate Remaining . Initiate LERs
Scope Annually * Revise Procedures * Prepare & Transmit Test
Acceptance Criteria Drawings * Initiate and Resolve PIRs
Same For McGuire and Catawba Nuclear Stations
Estimate of DBD Systems and Structures Scope
Criteria - Nuclear Safety Related, Technical Specification, or other selected systems
Mech Systems Elect Systems Civil Structures
Oconee 45 26 6
McGuire 61 34 3
Catawba 60 34 3
Total DBD 166 94 12 Total Plant 291 167
DBD Prioritization
* Risk Significance / Recent Experience
* Plant Testing Trends (performance degradation, wear, fouling, etc.)
* NRC Generic Issues
* INPO SOERs
DBD Schedule
Oconee Systems & Structures 13/year
McGuire Systems & Structures 16/year
Catawba Systems & Structures 16/year
Total 45/year
Project Completion - 1995
* DBD CURRENT STATUS (JUNE 1990)
CATAWBA MCGUIRE OCONEE
COMPLETED 2 4 2
NDERWAY 10 8 10
STILL TO START 5 4 4
TOTAL SCHEDULED 17 16 16
Relationship of DBD to Other Documents
1OCFR Tech. FSAR Codes Duke Gds Specs SAR SER & Caics Corres. Stands
LL I
Plant, Systems & Structures Dwgs
Smry Specifications Dwgs
Design Design Vendor Computei NPD Dwgs Specs Docs Lists Proced
0i
4Typical Documentation Reviewed for DBD
1OCFR Duke Drawings FSAR PIR / LERs SER Valve / Equipment Lists Standard Review Plan I & C List Branch Technical Positions System Descriptions Tech. Specs. Current NSM Packages Duke Nuclear Guides Fire Protection Safe Shutdown Licensing Correspondence Review Manual ANS Standards Fire Protection Review Manual ANSI Standards Response to TMI Concerns t E Standards Response to NUREG-0588 IEE Standards Plant Environmental Parameters SITA Audit Findings Manual INPO SOERs EQRI Manual NSSS Correspondence Testing Correspondence Files - Station Task Force(testing) Specifications - IWP/IWV Code (ASME Section XI) Calculations - IWP/IWV Manual Manufacturer Drawings and - NPD Directives on Retest
Manuals - Station Procedures and Retest List
- Design Studies on Testing
DESIGN BASES HIERARCHY
PLANT DB
SYSTEM DB
SYSTEM DC
EQUIPMENT DC
DB = DESIGN BASES
DC = DESIGN CRITERIA
Page 4
SECTION 10.0 INTRODUCTION *Boundary and Scope
*System Purpose
*Format and Use
SECTION 20.0 DESIGN BASES AND CRITERIA
*ONLY safety-related and regulatory required system and equipment design bases.
PIP PROCESS INVOKED IF VIOLATED
SECTION 30.0 SYSTEM/STRUCTURE DESCRIPTIONS
*Description of safety and nonsafety functions
*Nonsafety-related and nonregulatory required design bases
FIGURE 1. OUTLINE OF SPECIFICATION SECTIONS
corm 45O69 (R 10-98)
System Design Bases/Objectives
Design Basis: The VG system shall supply control air at sufficient pressure to keep the emergency diesel generator running (Reference section 20.1.2 of specification no. MCS-1609.VG-00-0001).
Objective: Verify that a control air pressure of no less than 90 psig and no greater than 135 psig is maintained, after the diesel starts, while the emergency diesel generator is running for 24 hours (Tech. Spec. 4.8.1.1.2e(8)). The starting air compressors shall be available to start during this test.
Test Frequency: The control air test shall be performed with the same frequency as the emergency diesel start test.
Operability: If a diesel fails this test, then it shall be declared inoperable.
Test Acceptance Criteria
Test/Measurement Reference Document Acceptable Value Including Tolerance
ontrol air pressure TT/OB/9100/300 90 < P < 135 psig
Tech. Spec. 4.8.1.1.2e (8)
2/15/89 letter from JR Hilley to F Schubert
DUKE POWER COMPANY QA COND 1
McGuire Nuclear Station, Units 1 & 2 Design Basis/Test Acceptance Criteria Emergency Diesel Generator Control Air
OSN/DTE &AdL - INS/TE._.A C /f __________ ------ CHK/DTEt~ i;I-qN/T4D~d-.C
CUK/DTE____ __ - 4,. INS/DTE s
C :I REVISIONS DSN R DE CD
NO - REVISIONS DSN CHKIAPR OTE C/E ELE M/N DWG NO MCDB-1609-VG.S002-O1 TREV 0
WEja(m tcs!W .VG-0l
F33/35 -- R 21/23
P~ LINE PURIFIER l/BATMOSPHERE
61/65 115/117 7Yn1 AIR [NLET HIR RN FILTER AS/BI
STARTING AIR DRYER Al81 AFTERCOOLER AIR 62/66 TANK Al/ RlI/Bl COMPRESSOR Al/BI
83/84 VOLUME TANK A/B
DIESEL VI BLACKOUT CONTROL AIR ENGINE HEAD3ER HEADER
A/B 939 91034NOTE Z CONTROL AIR FILTER A/B 79/80
77/78 90/92 n18/20
34/36 "41 RN
63/67 ZZ/Z4
-- vATMOSPHERE 64/68 LINE 116/118 1I1
PUIIRA2/82 AIR INLET PURIFAIER AZ/BZ IR RN FILTER AZ/BZ STARTING AIR DRYER R2/82 AFTERCOOLER AIR
TANK A2/B2 R2/B2 COMPRESSOR AZ/BZ
NOTES u
1. EACH UNIT HAS TWO DIESEL ENGINES (A AND B). EACH ENGINE HAS TWO STARTING AIR SUBSYSTEMS (AS SHOWN ABOVE). BOTH R AND B SUBSYSTEMS EQUIPMENT TAG NUMBERS ARE DISPLAYED.
Z. SOLENOID VALVES VGSVSI6/5170.5161/5171.5162/5172 AND 5163/5173 ARE LOCATED ON THE CONTROL AIR HEADER. SEE IC DETAILS MC-1499-VG3 AND MC-2499-VG3. TYPICAL FOR UNITS I AND 2
LE= ooty 1o1 Colme IS AI 911 FLOW ODViKA. DUK -ME - -- -- -_
Ll lEVI 0puLe L t So-w .P_ _CGUIRE PDSaAR STATION
- I-- -- --- SUM"FIRT
VALt -E I -wo -e DIESEL GENERATOR ENGINE mJK IUOIE -9200"M HC-1609-4.0 VG SYSTEM CUNIT I)O
(IHC-69-4.0 VG SYSTEM UNIT 21SRN R SYSTE ve)
RELIEF VALVE assIRE(661 v19 ETWE i s _e_____ SFLOV DIC ORMNOL
.1 REVISIONm Mg o nDGN C F -. 1 - 1
Figure 1. Terminology Relationships
0 & M Procedures
Configuration Instructions
Management Other
Other Controlled Physical Plant Documents
Design Control
Design Bases Calculatlions Specs. Reg. Req'mis Analyses Drawings
Other Dsgn Re Evaluations 1_Usts
DsignDesign Design Design Design Input Process Output
Documents
Discrepancy FIGURE 2. Design Basis Discrepancy
Safety N Resolution Process Concern?
Operability Y Reportability Evaluation Evaluation
Oper. N N Rep. Issue? Issue?
Y Y
Take Tech Spec Complete Report NRC or other action DB3 Activity to NRC Enforcement
Policy
Final Evaluation
Closeout
KEY POLICY PROPOSALS
OPERABILITY * Evaluate at deliberate pace * Presumption of operability
REPORTABILITY * Presumption of conformity * Combine related items in single LER
ENFORCEMENT * No violations
USE OF SOURCE TERM IN REGULATION CURRENT SITING REQUIREMENTS
SITING REGULATION IS 10 CFR 100.
PART 100 REQUIRES THAT EVERY REACTOR SITE DEFINE:
1) AN EXCLUSION AREA - NO RESIDENTS, CONTROLLED BY APPLICANT
2) LOW POPULATION ZONE (LPZ) - "LOW" DENSITY OF RESIDENTS PERMITTED - NEAREST DENSELY POPULATED CENTER
AT LEAST 1 1/3 TIMES LPZ OUTER RADIUS.
PART 100 ASSUMES EXISTENCE OF LOW-LEAKAGE CONTAINMENT.
CALCULATED DOSES AT EAB AND LPZ MUST MEET PART 100 GUIDELINES (25 REM WHOLE BODY AND 300 REM THYROID) FOR 2 HOUR AND 30 DAY PERIODS, RESPECTIVELY.
1
USE OF SOURCE TERM IN REGULATION CURRENT SITING PRACTICE
* FISSION PRODUCT RELEASE IS DERIVED FROM TID-14844 (1962), AND PRESENTLY GIVEN IN REG. GUIDES 1.3 AND 1.4
- 100 PERCENT OF NOBLE GASES - 50 PERCENT OF IODINE (HALF OF THIS IS THEN
ASSUMED TO PLATE OUT IN CONTAINMENT) - INSTANTANEOUS APPEARANCE - IODINE CHEMISTRY GIVEN (LARGELY 12)
* CONTAINMENT IS ASSUMED TO LEAK AT MAXIMUM LEAK RATE ALLOWED IN TECH. SPECS.
* FISSION PRODUCT CLEANUP SYSTEMS (SPRAYS, FILTERS) EVALUATED CONSERVATIVELY.
* DOSES CALCULATED USING CONSERVATIVE SITE METEOROLOGY.
2
WHAT CAN WE DO WITH WHAT WE HAVE LEARNED AND WHY?
CURRENT SET OF REGULATIONS AND GUIDANCE HAS SERVED WELL TO SET CERTAIN PLANT DESIGN AND SITE PARAMETERS.
TID-14844 DID NOT ORIGINALLY CONTEMPLATE CREDIT FOR THE USE OF FISSION PRODUCT CLEANUP SYSTEMS.
AS THE SIZE OF PLANTS INCREASED, HOWEVER, FISSION PRODUCT CLEANUP SYSTEMS BECAME NECESSARY TO KEEP EXCLUSION AREAS FROM BECOMING VERY LARGE AND RELIANCE ON SUCH SYSTEMS INCREASED.
AS CURRENTLY APPLIED, PART 100 AND ASSOCIATED REGULATORY GUIDES PRIMARILY INFLUENCE PLANT DESIGN AND INFLUENCE SITING TO A MUCH LESS EXTENT (SITING GOVERNED BY REG. GUIDE 4.7).
FURTHER, PART 100 DOES NOT ADDRESS THE ISSUE OF CONTAINMENT FAILURE WHICH IS THE PRIMARY CONTRIBUTOR TO RISK.
3
WHAT CAN WE DO WITH WHAT WE HAVE LEARNED AND WHY?
(CONTINUED)
* HOWEVER, CURRENT PRACTICE DOESN'T INCLUDE UPDATED UNDERSTANDING OF SOURCE TERM FORM, CONTENT, AND BEHAVIOR AND RESULTS IN DESIGNERS INCLUDING DESIGN FEATURES THAT MAY NOT BE IN THE DIRECTION OF ENHANCED SAFETY.
* NEW DESIGNS UNDER REVIEW.
* THEREFORE, THE STAFF IS CONSIDERING CHANGES TO CURRENT PRACTICE FOR FUTURE LWRs THAT WOULD:
- GIVE DESIGNERS MORE FLEXIBILITY TO DEVELOP DESIGNS WITH SAFETY FEATURES THAT ENHANCE SAFETY BY UTILIZING REALISTIC SOURCE TERM ASSUMPTIONS, AND
- MORE DIRECTLY ADDRESS ACCEPTABLE SITE PARAMETERS.
4
OPTIONS FOR IMPROVEMENT TO CURRENT PRACTICE
* CONTINUE CASE-BY-CASE REVIEW (E.G., PER SECY-90-16 FOR ABWR):
- DESIGN CERTIFICATION PROCESS.
* TECHNICAL UPDATE:
- UPDATE TID, R.G.s, SRP TO REFLECT LATEST UNDERSTANDING OF SOURCE TERM AND ASSOCIATED METHODOLOGY, BUT NO RULE CHANGE.
* DECOUPLING:
- UPDATE REGULATIONS AND GUIDANCE TO STATE SEVERE ACCIDENT DESIGN CONSIDERATIONS AND SITE PARAMETERS.
5
PRELIMINARY RECOMMENDATIONS - STEP 1 TECHNICAL UPDATE
UPDATE TID, REG. GUIDES 1.3 AND 1.4 AND CORRESPONDING SRP SECTIONS TO RECOGNIZE CURRENT UNDERSTANDING OF SOURCE TERM:
- TIMING OF RELEASE - FORM AND CONTENT OF FPs.
RETAIN 10 CFR 100 DOSE GUIDELINES AND SITING GUIDANCE CONTAINED IN REG. GUIDE 4.7.
RETAIN CURRENT CONTAINMENT DESIGN BASIS (LOCA) AND ASSUMPTIONS, BUT EVALUATE CONTAINMENT PERFORMANCE UNDER LIKELY SEVERE ACCIDENT CONDITIONS.
CHANGES WOULD BE MADE TO SUPPORT EVOLUTIONARY LWR REVIEW.
APPLICATION OF THESE CHANGES TO EXISTING PLANTS NEEDS TO BE CONSIDERED.
6
PRELIMINARY RECOMMENDATIONS - STEP 2 DECOUPLING
EVALUATE FURTHER THE BENEFITS, DISADVANTAGES, AND SCOPE OF DECOUPLING PLANT DESIGN AND SITING FOR FUTURE LWRs. SPECIFICALLY LOOK AT:
- MODIFYING 10 CFR 100 TO SPECIFY ACCEPTABLE SITE PARAMETERS AND TO REMOVE REQUIREMENT FOR CALCULATION OF DOSE, AND
- MODIFYING 10 CFR 50 TO SPECIFY ACCEPTABLE PLANT DESIGN PERFORMANCE AND FEATURES (SUCH AS CONTAINMENT LEAK RATE AND FISSION PRODUCT CLEANUP SYSTEMS) CONSIDERING SEVERE ACCIDENTS.
7
QUALITY ASSURANCE VERIFICATION FUNCTION
Quality Assurance Performance Assessment
Training Initiatives
Self Initiated Technical Audits
Verification Process Improvements
Quality Assurance Performance Assessment
QA Department Testing
Resource Operations Alelorc Modifications Allocation
M0, aintenance \Rad Protection
UALITY ASSURANCE VERIFICATION FUNCTION
Recent Enhancements
Location based
Management comment
SALP "influence"
Verification Managers' responsibility
QUALITY ASSURANCE. VERIFICATION FUNCTION
QAPA Strengths
* Large data base
* In-house information
* Management input * Objectivity/subjectivity
* Sensitive to significance - * SALP reconciliation
*UALITY ASSURANCE VERIFICATION FUNCTIO
Verification Specialist Training * Basic Nuclear Operator [30 weeks] * Introduction to System Specifics
[8 weeks] * Specialized Technical Training * Performance Based Auditing * Other Available Training
* Simulator demonstrations *Continuing management
*Continuing special ization\ traininag
*UALITY.ASSURANCE VERIFICATION FUNCTIO
Self-Initiated Technical Audits (SITA)
* Background
* Process
* Participants
*UALITY ASSURANCE VERIFICATION FUNCTION
SITA
Low Pressure Service Water (Oconee) Diesel Generator Starting Air (McGuire)
Shared Essential 600 Volt Motor Control Centers of Essential Auxiliary Power
Systems (Catawba) Emergency Power Distribution System
and Emergency Switching Logic --- */ / (conee)
Control Area Ventilation and Chilled Water Systems (McGuire)
SSURANCE VERIFICATION
SITA
Some of the Results...
*UALITY ASSURANCE VERIFICATION FUNCTION
SITA-The Future
June 18, 1990-High Pressure Injection System (Oconee)
December 10, 1990-Auxiliary Feedwater System (Catawba)
Enhancements to the Verification Process
Technical Improvements
Partnerships
Performance based approach
QUALITY ASSURANCE VERIFICATION FUNCTION
Technical Experts as Audit Team Members through Other Departments
Design Engineers
Analytical Chemists
Senior Reactor Operators
Fire Protection Engineers
RadWaste Engineers
Nvuclear Engineers
,-Health Physici~sts
Environmental Enaineers
* ALITY ASSURANCE VERIFICATION FUNCTIO
Technical Expertise Within QA
* SRO assigned to Surveillance at Oconee * Superintendent of Maintenance assigned
to Audits * Security specialist assigned to Audits * Extensive training program
*UALITY ASSURANCE VERIFICATION F
Audit Partnership
* Why SUCCESS g
* How
Results Surveillance
QUALITY ASSURANCE VERIFICATION FUNCTION
Performance-Based Approach
* Training - by John Johnson
of JETS
Performance-Based Approach
* Audits and Surveillances
DUKE/NRC INTERFACE MEETING JULY 16, 1990
CATAWBA NUCLEAR STATION AUXILIARY FEEDWATER UNAVAILABILITY
INTRODUCTION
- DUKE / NRC MEETING JUNE 18, 1990
- HIGH AUXILIARY FEEDWATER SYSTEM UNAVAILABILITY
- INPO GUIDANCE CAN BE LOOSELY INTERPRETED
- DETAILED AND CONSCIENTIOUS TRACKING
- PLANNED VS UNPLANNED
SAFETY SYSTEM PERFORMANCE AUXILIARY FEEDWATER SYSTEM
(1/89 - 12/89)
14 14 MEDIAN 14- 0.013
12
_10
8-8
CNS-1 = .082 5 CNS-2 = .074
4- 3 2
2- 1 1 1
00.01 0.02 0.03 0.04 0.05 0.06 0.07 0.08
sum of components unavailability/number of trains
UNAVALABIU1Y sum of unavailable hours for the sstem (hours system required) x (number of trains)
AUXILIARY FEEDWATER SYSTEM UNAVAILABLE HOURS FOR 1989
PLANNED UNPLANNED 2,000
1,790.6
O
'1,500
1,174.9
1,000LaJ
610.9 569.1
500 261.1
103.5 57.6 74.5 2.2 18.4 34.8 87.1 38.3 60.4
I I I I I I I I I I II c (fo cn Cn cn c cn on n 0n cn c . cn V
AUXILIARY FEEDWATER SYSTEM UNAVAILABLE HOURS FOR 1989
PLANNED UNPLANNED 2,ooo
1,790.6
C Ei 1,500
1,174.9
2 1,000
500 261.1
60.4
D
I C1J c I
C.3 C-3 C-lC,
AUXILIARY FEEDWATER SYSTEM UNAVAILABLE HOURS
THIRD QUARTER 1989 - FIRST QUARTER 1990
PLANNED UNPLANNED 1,400
1,203.7 1,200 1,101.0
a 1,000
n800
00
400261.1
200
11.0 0--y
I I w Ln an cnn
AUXILIARY FEEDWATER SYSTEM TOTAL UNAVAILABLE HOURS
THIRD QUARTER 1989 - FIRST QUARTER 1990
6% OTHER 12% FLUSH
11% PULL TST
6% TESTING
20% MNT
45% SUPPORT
CLAM FLUSHING (12% UNAVAILABILITY)
- NUCLEAR SERVICE WATER PROBLEM
- TRACKED SEPARATELY FROM SUPPORT SYSTEM
- SHORT TERM AND LONG TERM CORRECTIVE ACTIONS
MODIFICATIONS
RAW WATER TASK FORCE
CORRECTIVE MAINTENANCE (20% UNAVAILABILITY)
- USUALLY LARGEST CONTRIBUTOR To UNPLANNED UNAVAILABILITY
- INCLUDES ESTIMATED UNAVAILABILITY HOURS
- GOVERNOR VALVE STEM CORROSION
- SA-2 AND SA-5 STROKE TIME
- GOVERNOR OIL PRESSURE
- TRIP AND THROTTLE VALVE TORQUE SWITCH
SUPPORT SYSTEMS (45% UNAVAILABILITY)
NUCLEAR SERVICE WATER (RN) AND COMPONENT COOLING (KC)
- RN PUMP LUBE STRAINER MODIFICATIONS
- CHEMICAL FLUSH AND 'B' TRAIN PUMP PACKING
- KC HEAT EXCHANGER CLEANING
- RN PUMP 2A INOP DURING UNIT 1 OUTAGE
- NUMEROUS INOPERABILITIES OF LESS THAN 50 HOURS
VARIOUS TESTING (17% TOTAL UNAVAILABILITY)
- PERIODIC TS TESTS (6%)
OPERATIONS MONTHLY
PERFORMANCE QUARTERLY (IWP)
INCREASED FREQUENCY DUE To OPERABILITY CONCERNS
- GOVERNOR VALVE STEM PULL TEST (11%)
VALVE STEM CORROSION
INITIALLY PERFORMED WEEKLY
CURRENTLY MONTHLY
OTHER CATEGORY (6% UNAVAILABILITY)
- ONLINE MODIFICATIONS (2%)
GOVERNOR VALVE DRAIN LINE
SA-2 AND SA-5 STROKE TIME
- AUXILIARY FEEDWATER PUMP BEARING COOLDOWN (2%)
SA-2 AND SA-5 LEAKAGE
- PREVENTIVE MAINTENANCE (2%)
AUXILIARY FEEDWATER SYSTEM TOTAL UNAVAILABLE HOURS
THIRD QUARTER 1989 - FIRST QUARTER 1990
,1,400O
O1.200
1,00039
0 8000
D 2400
200
0I- I CL OM in) z z (nl z
p 0 CL 0
7)1 :D m in-a
SUMMARY
- CATAWBA'S AUXILIARY FEEDWATER UNAVAILABILITY WAS POOR
- IMPROVEMENTS ALREADY APPARENT BASED UPON STATION EFFORTS
- FUTURE UNAVAILABILITY PROJECTIONS
CLAM FLUSH
PUMP TESTING
CORRECTIVE MAINTENANCE
SUPPORT SYSTEMS
GOVERNOR VALVE STEM PULL TEST
BEARING COOLDOWN
MODIFICATIONS
AUXILIARY FEEDWATER SYSTEM PROJECTED UNAVAILABLE HOURS
THIRD QUARTER 1989 - FIRST QUARTER 1990
,1,400
U1,200
C
-r 1,000
800- PROJECTED
600- CURRENT
z 400
200
0
p:0 0
H- m
SAFETY SYSTEM PERFORMANCE AUXILIARY FEEDWATER SYSTEM
(1/89 - 12/89)
14 14 MEDiN 14
12- CNS-1 = .026 CNS-2 = .023
10
8 8- gPROJECE
CURR 6 5 5
4 4 4
2 2
0.01 0.02 0.03 0.04 0.05 0.06 0.07 0.08 sum of components unavailabilify/number of trains
UNAVAlIABILTY = sum of unavailable hours for the system (hours system required) x (number of trains)