asme iii introduction npp components

INTRODUCTION TO THE ASMEBoiler & Pressure Vessel Code:

SECTION III, DIVISION 1

Nuclear Power Plant

Components BY

Marcus N. Bressler, PE [email protected]

05/13/2008

2

SECTION III EVOLUTION

First Published in 1963

Transition from ASA to USAS to ANSI

1971 Edition, Nuclear Power Plant Component

2007 Edition, ASME B & P V Code

Code Publication Cycle

3

PRIMARY NUCLEAR SECTIONS

Section III, Nuclear Plant Components Division 1 - Metallic Components Division 2 - Concrete Containment Vessels Division 3 - Nuclear Packaging (NUPACK)

Section XI, Inservice Inspection of Nuclear Coolant Systems Division 1 - Rules for Inspection and Testing of Components of

Light-Water Cooled Plants Division 2 - Rules for Inspection and Testing of Components of

Gas-Cooled Plants (Inactive, in Process of Rewriting) Division 3 - Rules for Inspection and Testing of Components of

Liquid Metal Cooled Plants (Inactive)

4

REFERENCED SECTIONS

SECTION II - Materials

SECTION V - Nondestructive Examination

SECTION IX - Welding And Brazing Qualification

5

U.S. REGULATORY ISSUES

The ASME Code as Law

Synopsis of B&PV Laws, Rules and Regulations

The Enforcement Authorities (States and Provinces)

The U.S Nuclear Regulatory Commission (The Regulatory Authority)

US Code of Federal Regulations (CFR)

10 CFR 50.55a

7

ASME NUCLEAR CODE CASES

Publication in Supplements, Four per Year

Dual Numbering: e.g. Case N-155-2 (1792-2)

Fiberglass Reinforced Thermosetting Resin Pipe Section III, Division 1, Class 3

NRC Acceptability of Code Cases

8

INTERPRETATIONS

Publication

Used as reference

Cannot change Code requirements

Volume 58, July 1, 2008

9

MANDATORY APPENDICES

Publication

Numbering

Uses Roman Numeral System

10

NONMANDATORY APPENDICES

Coverage and Use

Numbering

Uses Alphabetic Capital Letters, but Try not to Use

those that are aqkso Roman Numerals

11

APPLICABILITY OF SECTION III AND XI RULES

COMMON USE OF BOTH SECTIONS DUTIES AND RESPONSIBILITIES OF PARTIES PARTIES INVOLVED

Owner N -Type Certificate Holder QSC Certificate Holder

Authorized Inspection Agency (AIA)

Authorized Nuclear Inspector Supervisor (ANIS) Authorized Nuclear Inspector (ANI) Enforcement Authority Regulatory Authority

12

COMMON TERMINOLOGY

Owner

Construction

ASME Certificate Of Authorization

Manufacturer (N-Certificate Holder)

Installer (NA-Certificate Holder)

Fabricator (NPT-Certificate Holder)

Authorized Nuclear Inspector (ANI)

13

COMMON TERMINOLOGY (cont’d)

Component

Piping System

Part

Appurtenance

Piping Subassembly

Support

NPT Code Symbol Stamp

14


NA Code Symbol Stamp

Material Seamless Or Welded Without Filler Metal Added

Welded With Filler Metal Added (NPT-Stamp)

Data Report Form

Design Specification Basis For Construction

Certified By Registered Professional Engineer

Provided By Owner or Designee

15


Design Report Provided by N-Certificate Holder

Design Calculations and Stress Analysis

When required, Certified by RPE

Design Output Drawings Design Drawings

Correlated With Design Reports

Load Capacity Data Sheets

Design Report Summaries

16


ASME Survey Team for N-Type Certificates

Team Leader

Team Member

National Board Rep

ANIS

ANI

Observers (When Assigned) [Have No Vote]

Enforcement Authority (Invited)

Regulatory Authority (Invited)

17


ASME Survey Team for Material Organizations Team Leader & Team Member

Observers (When Assigned) [Have No Vote}

Unannounced Audits for Material Organizations Team Leader Only

18


Inspection Performed by an ANI

Examinations Performed by Qualified Personnel Nondestructive Examinations

Radiography

Magnetic Particle Eddy Current Ultrasonic

Liquid Penetrant

Visual

19


Testing

Hydrostatic Pressure Test

Pneumatic Pressure Test

Registered Professional Engineer Certifies Design Input Documents

Certifies Design Output Documents

Certifies Overpressure Protection Report

20

GENERAL REQUIREMENTS OF SECTION III

Subsection NCA

General Requirements

Covers Both Division 1 and Division 2

Division 3 has Subsection WA, some references to NCA

Describes Qualifications

Lists Duties and Responsibilities

Referenced by Other Subsections

21

SECTION III - SUBSECTION NCA

NCA - 1100 SCOPE Applies to New Construction

Provides Exclusions

Valve Operators, Controllers

Pump Impellers, Drivers

Intervening Elements

Instruments and Fluid Filled Tubing

Instrument, Control and Sampling Piping

22

SECTION III - SUBSECTION NCA (cont’d)

NCA - 1140 Effective Code Prior to Winter 1977 Addenda

Contract Date Establishes Code of Record

Winter 1977 Addenda

Code Effective Date Set by Owner

Must be Listed in Design Specification

Duplicate and Replicate Plants

Three year Window, NRC Provided for Five Years

Winter 1981 Addenda

Existing Materials

23


NCA - 2000 CLASSIFICATION Code Does Not Classify Classification Guidance Provided by

State or Federal Authorities 10CFR50.55a Regulatory Guide 1.26 (RG 1.26) NRC Standard Review Plans American Nuclear Society

Section III Provides Construction Rules for Each Class Multiple Class Components or Optional Use of Classes Listed in the Design Specification

24


NCA - 2000 - CLASSIFICATIONNCA-2140 LIMITS AND LOADINGS

Design

Operating

Testing

25


NCA - 2000 - CLASSIFICATION (cont’d) Included in RG 1.26 and 10 CFR 50.55a

Quality Group A

Class 1 Components (NB) Reactor Pressure Vessel

Pressurizer Vessel (PWR)

Reactor Coolant Pumps

Steam Generators (PWR)

Reactor Coolant Piping

Line Valves

Safety Valves

26


NCA - 2000 - CLASSIFICATION (cont’d) Class 2 Components Important to Safety (RG 1.26 QG B)

Emergency Core Cooling Post Accident Heat Removal Post Accident Fission Product Removal Includes Vessels, Pumps, Valves, Piping, Storage Tanks, and Supports

Class 3 Components Needed for Operation (RG 1.26 QG C) Cooling Water Systems Auxiliary Feedwater Systems Includes Vessels, Pumps, Valves, Piping, Storage Tanks, and Supports

27


NCA - 2000 - CLASSIFICATION (cont’d) Class MC Components (Subsection MC)

Containment Vessel Penetration Assemblies Does not Include Piping, Pumps and Valves Piping through Containment Must be Class 1 or Class 2

Subsection NF - Supports Plate and Shell Type Linear Type Standard Supports Support Class is the Class of the Component Supported

28


NCA - 2000 - CLASSIFICATION (cont’d) Subsection NG (Class CS)

Core Support Structures

Reactor Vessel Internals

Subsection NH

Elevated Temperature Components

Service Temperature Over 8000F

Refers to Subsection NB

No Fracture Toughness Rules

29


NCA - 3000 DUTIES AND RESPONSIBILITIES Subcontracted Services, Calibration and Welding -

The Owner (NCA-3200) Receives N-Certificate Holder’s Design Report

Reviews Design Report

Compares to Design Specification Requirements

Provides Documentation of this Review as the

“Owners Review of the Design Report”

Many Other Duties and Responsibilities Assigned by Section III (NCA-3220)

30


NCA - 3000 Duties and Responsibilities (cont’d) The N-Certificate Holder (NCA-3500)

Agreement with an AIA Documents Quality Assurance (QA) Program Files a QA Manual Obtains a Certificate of Authorization Responsible for Component Meeting all Code Requirements Prepares and Certifies Design Report Stress Analysis of Parts and Appurtenances Reconciliation of Drawing Changes

Provides Design Report to ANI and Owner Buys Material from Material Organizations Qualifies MOs and Suppliers of Services

31


NCA - 3000 DUTIES AND RESPONSIBILITIES (cont’d) N-Certificate Holder (NCA-3500) (cont’d)

Verifies All Activities Have Been Performed

Receives Owner’s Review of the Design Report and Submits to ANI

Collects all Data, Including Certification of Materials

Prepares Data Report Form, Signs, and Presents it to ANI

ANI Accepts Data Package, Certifies Data Report Form, Authorizes Stamping

Manufacturer Stamps Nameplate

Ships Component

Other Duties, and Responsibilities Listed in NCA-3520

32


NCA - 3000 DUTIES AND RESPONSIBILITIES (cont’d)

The Registered Professional Engineer Certifies Design Specification (NCA-3255)

Certifies Design Report (NCA-3555)

Recertifies Revisions to Documents

Responsible for Accuracy and Completeness, Maintains Qualifications as Described in N626.3 - 1993 and Appendix XXIII (1996 Addenda)

The RPE’s Certifying the Documents May be From the Same Organizations, But Must Be Independent

The Engineering Organization, 1973 -1976

33


NCA - 3000 Duties And Responsibilities (cont’d) The NA Certificate Holder (NCA-3700)

Agreement with an AIA

Document QA Program

Files QA Manual

Obtains Certificate of Authorization

Responsible for Assembly and Joining and Meeting the Applicable Requirements of the Code

Not Responsible for Design

Buys Material from Accredited MOs

Qualifies MOs and Suppliers of Services

34


NCA - 3000 Duties And Responsibilities (cont’d) The NA Certificate Holder (NCA-3700) (cont’d)


Performs System Pressure Test

Collects All Data, Including Certification of Materials

Prepares N-5 Data Report Form, Signs, Submits to ANI

ANI Accepts Data Package, Certifies Data Report Form,

Authorizes Stamping

Installer Stamps Nameplate With “NA” Stamp

Other Duties and Responsibilities Listed in NCA-3720.

N-Certificate Holder Taking Overall Responsibility for the Piping System Also Certifies the N-5 Data Report Form, and Stamps the System With An “N” Stamp. This Requirement Was Added in the Summer 1975 Addenda

35


NCA - 3000 DUTIES AND RESPONSIBILITIES (cont’d)

The NPT Certificate Holder Agreement With AIA

Documents and Files QA Program and Manual Obtains a Certificate of Authorization Not Responsible for Design Fabricates Parts, Appurtenances, and Material Welded with Filler Metal Responsible for Meeting Applicable Code Requirements Buys Material from Accredited MO’s Qualifies MOs and Suppliers of Services May have Responsibility for Part Design such as Component and Piping

Supports

36


NCA - 3000 DUTIES AND RESPONSIBILITIES (cont’d) The NPT Certificate Holder (cont’d)


Performs Shop Pressure Test

Collects All Data, Including Certification Of Material

Prepares Appropriate Data Report Form (N-2, NPP-1, NF-1), Signs, Submits To ANI

ANI Accepts Data Package, Certifies Data Report Form, Authorizes Stamping

Fabricator Stamps Nameplate With “NPT” Stamp

Other Duties And Responsibilities Listed In NCA-3620

37


NCA - 3000 DUTIES AND RESPONSIBILITIES (cont’d) NCA-3800 Material Organizations (No AIA Involvement)

Document Quality System Program

Obtain Certificate of Accreditation

Alternatively, Be Qualified By Each Organization That Buys Material

Quality System Certificate (QSC) Holder Subject To Two Unannounced Audits Between Renewal Surveys

Changes to Manual Must Be Approved By ASME Before They Are Implemented

Qualified Material Supplier Cannot Qualify Another Material Supplier

Other Duties And Responsibilities Listed In NCA-3820

Changes Made In 1994 Addenda. Code Case N-483-2

NB/NC/ND/NE/NF/NG/NH – 2610 Major Revision

38


NCA - 4000 QUALITY ASSURANCE QA Program Required For All Organizations

First Required as QC In Winter 1967 Addenda

10CFR50 Appendix B Required QA In 1970

NQA-1-1979 Approved By Code in the Winter 1982 Addenda

Previous Accepted Edition Is NQA-1-1989, With 1a-1989,1b-1991 And 1c-1992 Addenda. NRC and NCA 2006 Addenda approved NQA-1-1994 Edition. NRC and SGGR Reviewing NQA-1-2004, and NQA-1-2008

Code Takes Some Exceptions

39


NCA - 5000 AUTHORIZED INSPECTION Third Party Inspection

The Authorized Nuclear Inspector

Duties And Responsibilities Listed In NCA-5220

The Authorized Inspection Agency

The N626 Documents N626.0-1974 \

N626.1-1975 > Combined Into N626 In 1985

N626.2-1976 /

40


NCA - 5000 AUTHORIZED INSPECTION (cont’d) N626 Committee Reorganized As Qualifications For Authorized Inspection

The N626 Code And Addenda Published As QAI-1-1995

Approved By Section III In 1996 Addenda

Included Part 5 Which Requires Accreditation of Non-Nuclear AIA

ANI Monitors QA Program

Verifies Compliance With Code

Verifies Design Specification And Design Report Are Available And Certified

Verifies Code Compliance Of Materials

Qualification Of Welding Procedure Specifications And Of Welders

41


NCA - 5000 AUTHORIZED INSPECTION (cont’d) Satisfied With Nondestructive Examination (NDE) Procedures

and Qualification Of NDE Personnel

Witnesses Pressure Tests

Certifies Compliance With The Code

42


NCA - 5000 AUTHORIZED INSPECTION (cont’d) The Authorized Nuclear Inspector Supervisor

Supervises One Or More ANIs Reviews And Accepts QA Manual Prior To Initial Survey Reviews And Accepts Changes To QA Manual During Three Years Between

Surveys Changes Cannot Be Implemented Prior To Acceptance By ANIS Audits Material Manufacturing And Supplying Activities Annually Evaluates ANI Performance Twice/Year Evaluates Status Of QA Program

ANIS And ANI Participate In ASME Initial And Renewal Surveys

43

SECTION III - SUBSECTION NCA (cont’d) NCA-8000 STAMPING

Requirements For Accreditation Authorization To Use Stamps Agreement With AIA Scopes Of Authorization Extension To Other Locations Table NCA-8100-1

Accredited Activities Code Symbols Applied Data Report Forms

44


NCA-8000 STAMPING (cont’d)Accreditation Process

Renewal Of Authorization

Requirements For Nameplates

Requirements For Stamping

Items Supplied Without Stamping

Code Data Report Forms Shown In Appendix V

Guidelines For Completion

45


NCA - 9000 GLOSSARY OF TERMS

Definitions used in Divisions 1 and 2 of Section III

46

SUBSECTION NB - CLASS 1

NB - 1100 GENERAL REQUIREMENTS Scope Limitations

Temperature Limits

Boundaries Of Jurisdiction First Circumferential Weld Face Of Flange Face Of Threads

Rules For Attachments Vessels, 2.5 (R x t)½ ; Containment Vessels, 16 t

Pumps, 4t

47

SUBSECTION NB - CLASS 1 (cont’d)

NB - 1100 (cont’d) Task Group On Attachments Attachments

Pressure RetainingNon-Pressure RetainingStructuralNon-Structural

Introduced In All Subsections NB-2190

48


NB - 2000 MATERIAL Limited In Number Carbon & Low Alloy Steel to 700 F (370C) Austenitic And High Alloy Steels To 800 F (425C) Material Must Be Certified Material Must Be Traceable Including Welding Material Test Performed On Material Coupons Plates for Pressure Vessels and All Plates 2” Thick And Greater Must Be Examined

Ultrasonically Repairs to Material Are Limited According To Product Form Material Inspection Is Based On Product Form

49


NB - 2000 MATERIAL (cont’d) Demonstrate Toughness

Charpy “V” - Notch (Cv) Test

Original Requirements Similar To Section VIII

Required 15 To 30 ft-lb Absorbed Energy For Ferritic Material

35 ft-lb For Bolting Material

Pressure Test Performed At 60 F Above (Cv) Test Temperature

50

SUBSECTION NB - CLASS 1 (cont’d) NB - 2000 MATERIAL (cont’d)

Introduced Drop-Weight Test (DWT) Described In ASTM E 208-64 Summer 1972 Addenda Changes Tested at Lower And Lower Temperatures Until Both Specimens

Exhibited “Break” NDT Temp = (Temp No Break - 10F) Run Set Of Charpies At NDT + 60 F All Three Cv Specimens Must Exhibit 50 ft-lb and 35 MLE

(MLE = Mils Lateral Expansion, 1 mil = 0.001”)

RTNDT = (CVT - 60 F)

51


NB - 2000 MATERIAL (cont’d) Adopted E208-85 and E208-91

Brittle Weld Can Only Be Made In One Pass Reduced NDT By ~250 F

% Shear Fracture reporting was dropped in Summer 1985

Addenda For Piping, Pumps and Valves With t => 2-1/2 in. (75 mm)

RTNDT = (Cv - 100F) For t < 2-1/2 in., Cv is Tested At Lowest Service

Temperature and Acceptance Is Based On MLE Typical Charpy Curve

52


NB - 3000 DESIGN Design Of Vessels - NB-3200, NB-3300 Design Rules Different For Each Type Of Component

NB - 3200 - Design By Analysis NB - 3300 - Vessels NB - 3400 - Pumps NB - 3500 - Valves NB - 3600 - Piping

Design Pressure and Temperature used to Size Vessel by Formula Design By Analysis Only Method For Class 1 Pressure Vessels Reinforcement of Openings is Determined By Formulas

53


NB - 3000 DESIGN (cont’d)

Design Based on Maximum Shear Stress Theory of Failure

Design Stress Intensities Used for Design

54


NB - 3000 DESIGN (cont’d) Stress Categories and Limits of Stress Intensity

for Design Conditions Figure NB-3221-1- Primary and Secondary Stresses for Design

Conditions

For Level A and B Conditions

55


NB - 3000 DESIGN (cont’d) Permitted Stress Analysis

Elastic Analysis

Plastic Analysis

Elastic - Plastic Analysis

Experimental Stress Analysis

Check For Need Of Fatigue Analysis Certification Of Design Report By RPE Is Required Acceptability Requirements Are Listed In NB-3211 Fracture Mechanics Evaluation May Be Required Classification of Stress Intensity

56


NB - 3000 DESIGN (cont’d) Design Of Pumps NB - 3400

Rules Apply To All Parts Except Pump Shafts And Impellers, Non-Structural Internals, Seal Packages

Permitted Design Design By Analysis or Experimental Stress Analysis

Casing Wall Thickness Designed As a Vessel With Diameter Equal to Maximum Distance From One Chamber To The Other

Other Parts Designed By Formulas Inlet and Outlets Are Reinforced Pump Shafts May Be Designed To Appendix S Pump Internals To Appendix U

57


NB - 3000 DESIGN (cont’d) Design Of Valves NB - 3500

Minimum Thickness Based On Pressure Temperature Rating For

Standard Rating Valves Listed In ASME B16.34

Interpolated For Non listed Pressure Rating Valves

Standard Design Rules Modified Design By Analysis As Shown In NB-3530

Through NB-3550

Alternative Design Rules Design By Analysis NB - 3200

Experimental Stress Analysis

58



Design Of Valves NB - 3500

Parts Of Valves May Be Designed To Rules of NB-3540

Pressure Relief Valve Design Rules Are Listed In NB-3590

Small valves, NPS 1 and less

59



Design Of Piping NB - 3600 Piping Is Designed By A Set Of Rules-Combination Of Design By

Formula and Design By Analysis

The Design By Formula Approach Is As Conservative As Design By

Analysis, Even If Somewhat Complicated

Design By Analysis Is Still Allowed

If Allowable Stress Limits Are Exceeded, Design Can Be Accepted

If It Meets The Requirements Of NB-3200

Branch Connections Must Be Reinforced; Design Is By Formula

60


NB - 4000 FABRICATION AND INSTALLATION Class 1 Fabrication Rules Have Severe Restrictions For Fabrication of

Components Must Bend Cold Formed Plate To Qualified Procedure To Determine Effect On

Toughness. If Toughness Is Reduced, Material Must Be Procured With Higher Toughness Requirements

Weld Joint Design Is Generally Limited Full Penetration Butt Welds Out-Of-Roundness Is Limited Fit-Up Tolerances Are Limited Smooth Contours/Adequate Radii Required At Discontinuities

Weld Joint CategoriesUsed to Define Weld Locations & Establish NDE Rules

61


NB - 4000 FABRICATION AND INSTALLATION (cont’d) Welding Procedure And Welder Qualification Are Given In Section IX Surface Condition Of Welds Must Be Suitable For Interpretation Of NDE

And Must Not Mask Indications That Would Show In Final Radiographs Owner Must Provide Accessibility For Section XI Inservice Inspection Of

Welds Post weld Heat Treatment (PWHT) Is Required For Many Materials And

Thicknesses Weld Repair Of Material Defects Are Covered By NB-2500 Weld Repair Of Welds Are Covered By NB-4400 Repairs Without PWHT Are Covered By NB-4600

62


NB - 5000 EXAMINATION – See Figure 40 - 1 Procedures For NDE Are Given In Section V Section V Only Covers Methodology Requirements For Examination Are Covered In NB-5200 Acceptance Standards Are Listed In NB-5300 Qualification Of NDE Personnel Is In NB-5500, In Lieu Of NQA-1, Supplement

2S2 NB-5112 Required Demonstration Of All NDE Procedures To The Satisfaction

Of the ANI Material 2 in And Greater (>51mm), Cut Edges NDE by MT or PT Final Longitudinal and Circumferential Weld Joints Must Be RT examined, and

Weld Surface And Adjacent Base Material 1/2 in (13mm) Must Be Surface Examined

63


NB - 5000 EXAMINATION (cont’d) Ultrasonic (UT) Examination Generally Not Permitted.

When Allowed, Section III Rules Apply

Preservice Examination Has Been Added To Section III

All Personnel Performing NDE Are Required To Be Qualified, Trained,

And Tested. The Reports Of All Examinations Must Be Maintained.

Even Visual Examination Must Meet All Requirements.

64


NB - 6000 TESTING Completed Components Are Pressure Tested With Water To 1.25

Design Pressure. Hydrostatic Testing Is Normally Performed In The Shop, At Ambient Temperature

Test Loads Are The Pressure Loading, The Weight Of Test Fluid, And The Component Dead Weight

If Hydrostatic Test Cannot Be Performed, Pneumatic Testing At 1.1 PD is Acceptable

Testing Requirements Vary By Component

Inactive Valves Designed By Rules Are Hydrostatically Tested In Accordance With ANSI B16.34.

65


NB-7000 PROTECTION AGAINST OVERPRESSURE Section III Provides Rules For The Prevention Of Overpressure

of Nuclear Components A Component Can Be Completed Without These Overpressure

Protection Devices, but they Must Be installed as Part of the Nuclear System

The Rules Are Similar For Classes 1, 2, And 3 Systems Overpressure Protection Reports Are Required and They Must

Be Certified By An RPE Rules Are Provided For Both Reclosing And Nonreclosing

Pressure Relief Devices

66


NB-8000 CERTIFICATION AND STAMPING Before An N-Certificate Holder Can Certify A Data Report And

Apply the Code Symbol Stamp To The Nameplate, He Must Verify

That All Code Requirements, Including The Pressure Test, Have

Been Done Design Report Must Be Prepared and Certified By An RPE Owner’s Review of the Design Report Performed and Documented All NX-8000 Articles Refer You Back To NCA-8000

67

SUBSECTION NC - CLASS 2

NC - 2000 MATERIAL Rules For Class 2 Material Are Similar To Class 1 More Materials Are Available In Section II, Part D, Subpart 1,

Tables 1A, 1B and 3 Plates Over 2 in (51mm) Are Not Subject To UT Examination Impact Testing Is Required But Acceptance Standards Are Lower Dropweight Test To Show That The Lowest Service Metal Temperature

Is Satisfied In Accordance With Appendix R Is Alternate Test Many More Materials Are Exempted From Toughness Testing

68

SUBSECTION NC - CLASS 2 (cont’d)

NC - 3000 DESIGN Design of Pumps

Generally Use Formulas Based On Vessel Design. For Some Portions Of

Pumps, Any Method Proven Satisfactory May Be Used

Design of Valves

Generally Designed to Pressure-Temperature Rating Of ANSI B16.34

Design of Piping

Designed Using Simplified Formulas And System Analysis

Similar To ANSI B31.1 Design

69

SUBSECTION NC - CLASS 2 (cont’d)

NC - 3000 DESIGN (cont’d)

Atmospheric Storage Tanks

Designed By Formulas

Based On API Standard 2000

Foundations Based On API 650

0 - 15 PSI Storage Tanks

Designed By Formula

Based On API Standard 620

These Rules Were Adopted In The Winter 1971 Addenda

70

SUBSECTION NC - CLASS 2 (cont’d) NC - 4000 FABRICATION AND INSTALLATION

Rules Are Very Similar to Class 1 Details of Construction Less Restrictive Storage Tank Fabrication Rules Are More Restrictive than API Standards Qualification of Weld Procedures And Welders Are Same As Class 1

Requirements For PWHT Less Stringent

NC - 5000 EXAMINATION Longitudinal And Circumferential Welds Require RT Surface Examination Of These Welds Is Not Required Personnel Qualifications For NDE Are The Same As Class 1 Penetration Welds Only Require RT When They Are Butt Welds

71

SUBSECTION ND - CLASS 3

ND - 2000 MATERIALS More Materials Available

Testing Is In Accordance With Material Specifications

Design Spec. Must State Whether Impact Testing Is Required

Only Cv Testing Is Required

More Exemptions From Testing

ND - 3000 DESIGN Same As For Class 2

Design By Analysis Alternative Not Available For Vessels

Weld Joint Efficiency Factors Used In Formulas When NDE Is Reduced

72

SUBSECTION ND - CLASS 3 (cont’d)

ND - 4000 FABRICATION More Options Available for Fabrication Details

Welding And PWHT Rules Same As For Class 2

ND - 5000 - EXAMINATION All Butt Welds Are Not Required To Be RT Examined In Full

Spot Radiography Permitted With Reduced Weld Joint Efficiency

NDE Based On Material Size

Construction Is More Economical

Personnel Qualification Same As Class 1

73

SUBSECTION NE NE - 2000 - MATERIAL

Requirements For Materials Are Almost The Same As For Class 2

Impact Testing Is Required For All Containment Vessel Materials

Drop-weight Test Required Only For Material Over 2-1/2 in (64mm)

The Lowest Service Temperature Difference Between TNDT And Cv

Temperature Is 30 F

Appendix R Referenced In The Winter 1980 Addenda. Provides A Factor “A” Which Is Added To TNDT To Establish The LST. It Is 30 F Up To 2-1/2 in.,

And Increases With Material Thickness t.

74

SUBSECTION NE (cont’d)

NE - 3000 DESIGN

Containment Vessels Are Designed By Analysis Except For Some Small Pressure Parts

Allowable Stress Intensities Are 10% Higher Than For Class 2, Due To Fact that No Overpressure Protection Devices Are Allowed

Materials Are Limited To Those For Class 1 With Some Additions

Design Stress Intensity Tables Of Appendix I - 10.0 Deleted In The 1991 Addenda, Published In Section II, Part D, Subpart 1, Tables 1A, 1B, and 3, Same As Class 2

The 10% Increased Factor Added To Formulas

75

SUBSECTION NE (cont’d)

NE - 4000 FABRICATION Same As Class 2, But All Nozzle Opening Assemblies Must Be PWHT

Before Installation In the Vessel

NE - 5000 EXAMINATION Slightly More Restrictive Than For Class 2 Vessels

NE - 6000 TESTING Due To Size, The Pressure Test Is Pneumatic

Weld Inspection For Leakage Is Generally Verified By An Integrated Leak Rate Test

76

SUBSECTION NF NF - 2000 MATERIAL

Rules For Materials Are Similar to Class 2 Supports Are Classified According To The Class Of The Component

They Support Materials Are Listed In Tables 1A, 1B, 2A, 2B, 3 and 4 of Section II Part

D Additional Materials For Supports Were Listed In Code Case 1644, Now

In Code Cases N-71 and N-249 Design Specification Must State Whether Or Not Impact Testing Is

Required. If It Is, Only Cv Testing Is Required In The 1991 Addenda, Impact Test Exemption Curves Were Added To

NF

77

SUBSECTION NF (cont’d)

NF - 3000 DESIGN Plate And Shell Type Supports

Maximum Shear Stress Theory

Supports Skirts, Saddles, Biaxial Stress

Linear Type Supports

Originally In Appendix XIII, then XVII; Now In NF-3300

Based on AISC Specification

Standard Supports Can be Both Plate and Shell or Linear Type Design

78

SUBSECTION NF (cont’d) NF - 4000 FABRICATION

Rules Are Similar To Class 2 But Less Restrictive

NF - 5000 EXAMINATION Depends On Class Of Component Being Supported More Lenient Than Rules For The Supported Component More Extensive Visual Examination

GENERAL COMMENTS Supports Fabricated By Welding Are NPT Stamped. If Specified to The

1998 Edition, 1999 Addenda, Stamping Is Not Required

Standard Supports Supplied As Material (NF-1214) Can Be Supplied With Certificates Of Compliance (Up to 1998 Addenda)

79

SUBSECTION NG CORE SUPPORT STRUCTURES

NG - 2000 MATERIALS

Core Support Structures Are Internal Structural Components,

Not Pressure Retaining

Rules For Materials Almost Like Class 1

Impact Testing Is Different, Material 2 in (51mm) And Under Is

Accepted By MLE

Material Over 2 in. Tested for RTNDT, Like Class 1

80

SUBSECTION NG CORE SUPPORT STRUCTURES (cont’d)

NG - 3000 DESIGNDesign By Analysis And Maximum Shear Stress Theory

Allowable Stress Limits Different From Class 1

Based On A Factor On Yield Strength Or Ultimate Tensile

Strength At Temperature

Quality Factor On Stress And Fatigue Factor Are Determined By Joint Design And Amount Of NDE

NG - 4000 FABRICATIONAlmost Identical To Class 1 Rules

Choice Of Weld Detail Determines Quality Factor

81

SUBSECTION NG CORE SUPPORT STRUCTURES (cont’d)

NG - 5000 EXAMINATIONMore Ultrasonic And Visual Examination Used

Code Permits Designer To Define Joints As A Requirement For Examination

NG - 8000 CERTIFICATIONRules Were Changed So That Core Support Structures Receive

An “N” Stamp. Thus, N Certificate Holder Responsible For Structural Integrity and Meeting All Section III Requirements

Code Class is “CS”

82

SUBSECTION NH ELEVATED TEPERATURE SERVICE

CODE CASES N - 47 THROUGH N – 51

These Cases Were 1332 through 1336 before 1977

Edition

Incorporated As Subsection NH In the 1995 Addenda

Cases Expired Six Months After Publication of NH

83

PART IVASME NUCLEAR ACCREDITATION

Service Provided By ASME

Organization Applies to ASME For Accreditation To

Perform Activities In Compliance With The Rules Of

Section III

Requirements Are Detailed In NCA - 8000

Evaluation Performed By Survey Teams

Results Of Survey Are Reported to The Subcommittee

On Nuclear Accreditation(SC-NA)

SC-NA Approves Team Report And Awards Certificates

Staff Issues Certificates Upon Payment Of Invoice

84

PART IVASME NUCLEAR ACCREDITATION (cont’d)

Types Of Certificates Certificate of Accreditation

Owner’s Certificate Agreement with AIA Completes N-3 Data Report Form

Corporate Certificates Can be Extended to Other Sites Agreement with AIA Code Symbol Stamps Not Provided

Replaced Interim Letter on July 1, 1998

Quality System Certificates Material Organizations Manufacturing and/or Supplying Material No Agreement With AIA No Welded Fabrication Permitted Weld Repairs of Material per NX-2500 is Permitted

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Types Of Certificates (cont’d)N Certificate Holder – Components (Includes Piping Systems)

NA Certificate Holder – Shop and Field Installation

NPT Certificate Holder - Parts, Piping Subassemblies, Appurtenances

NV Certificate Holder - Pressure Relief Devices, Safety Valves

NS Certificate Holder - Supports (Beginning with 1999 Addenda)

Scopes Can Describe Activities Performed At Other Locations Corporate Certificates Can Be Extended To Other Sites Scopes Can Permit Manufacture Or Supply Of Material All Require Agreement With AIA Utilities Can Get N-Type Certificates For a Nuclear Plant Site

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Terms of Certificates All Certificates are Issued for 3 years

Issuance and Renewal of Certificates Owner’s Certificates

A Construction Permit or Docket Date Issued by USNRC is Prerequisite Renewal is by Mail Application must be Made 90 days in Advance of Expiration

Other Certificates Application for Initial Certificate When Ready for Survey Renewal Application Required at least 6 Months Before Expiration Deposit Must be Submitted With Application

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Accreditation Process Same For Initial Issuance and For Renewal

Initial Application Made After ANIS or a Consultant (for QSC) is Satisfied with Readiness

Process Differs for Various Certificates

Owners Certificate Initial Application Results in an Interview

ASME Interview Team: ASME Team Leader, AIA Representative and Jurisdictional Authority or National Board Representative

QA Program Can Be 10CRF50 Appendix B

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Accreditation Process (cont’d) Quality System Certificates

Application Results In a Scheduled Survey

Survey Team

Team Leader

Team Member

Recommendation For Issuance Or Renewal Subject To

Approval By SC-NA And Payment Of Invoice

Fee Includes At Least 2 Unannounced Audits By A Single Team Member

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Accreditation Process (cont’d) Certificates Of Authorization

Application Results In Scheduled Survey

Survey Team

Team Leader

Team Member

National Board Representative

ANIS And ANI

Jurisdictional Authority and Regulatory Authority Invited Approval By SC-NA And Payment of Invoice is Required

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Accreditation Process (cont’d) Scope of Survey

Issuance or Renewal Of Certificates Is Accomplished By Completing A Successful Survey Performed By An ASME Team, Including

Review For Approval Of The QA Manual

Acceptance Of A Demonstration Which Implements The program

Receiving A Favorable Team Recommendation

Successful Completion Of SC-NA Ballot Process

Notification By Staff And Submittal Of Invoices

Payment Of Invoices And Cost Of Code Symbol Stamps

Receipt Of Certificates

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Accreditation Process (cont’d) Scope of Survey (cont’d)

Failure Of A Renewal Survey Would Require A Resurvey, With Potential Loss Of the Certificates During The Appeal Process

Due Process Permits Extension Of Certificates If All Required Steps Are Met

Survey Can Only Be Aborted by Request of Applicant

ASME Staff Must Be Notified and Has to Approve

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Accreditation Process (cont’d) Contractual Requirements With AIA

All Certificates Other Than QSC Require Agreement With AIA

AIA Provides Third Party Inspection Services With One or More ANI’s, Supervised by an ANIS

Survey Participation ANI and ANIS Participate in Survey

ANIS Participates in Review/Acceptance of Final Version of QA Manual

Observers Can Be Part of Team, As It Is Necessary to Train SC-NA Members and Alternates, New Candidates for ANI, and New Candidates for ASME Team Members

Observers Have No Vote on The Team

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QSC Certificates Manual Revisions Manual Revisions Between Surveys Must Be Submitted To ASME

For Review And Acceptance By A Member Of The Survey Team

Manual Revisions Should Not Be Implemented Until Approved By ASME

QSC Applicants Pay For 2.6 Unannounced Audits During The Three Year Term Of The Certificates. Twenty Percent Of The MOs Will Be Subjected At Random To A Third Unannounced Audit

All Changes To The Manual Are Subject To Verification During The Audits And Surveys

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PART IIASME NUCLEAR ACCREDITATION (cont’d)

New Developments In ASME Accreditation

Accreditation of AIA’s

The Code Moved To Add Part 4 To N626, And It Was Approved In The

1992 Edition. Applied to Nuclear AIAs

Nuclear AIA’s Were First Accredited In 1993

QAI-1-1995 Added Part 5, Which Requires Accreditation Of Non Nuclear

AIA’s

SC-NA First Handled Part 4 Nuclear AIA Accreditation

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New Developments In ASME Accreditation Board First Established As The Advisory Board On Accreditation

and Certification (BAC) June 1993 Changed To Supervisory Board On Accreditation,

Registration And Certification (BARC) Today It Is The Board On Conformity Assessment (BCA) N626 Committee Moved From Board Nuclear Codes And

Standards To BCA N626 Committee Now QAI, Committee On Qualification For

Authorized Inspection AIA Accreditation Now Under QAI Committee

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New Developments In ASME Accreditation (cont’d) The NS Certificate - See Figure 27-1 - Audience Handout

Agreement With AIA

Limited To Piping And Standard Supports

Stamping Of Welded Supports Was Introduced In The Winter 1975 Addenda

The NS Certificate Introduced 1998 Edition, 1999 Addenda

Eliminates Standard Supports Supplied As Material Under NF-1214

Permits Design Responsibility

Permits Welded Fabrication

Stamping Of Welded Supports Is Not Required

New Certificate Of Conformance, Form NS-1

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CONCLUSION Presentation Included History And Philosophy Of ASME Section III

Limitation In Time Prevented In-Depth Coverage

Assumed Audience Had Some Knowledge Of Nuclear Code

Courses Available Through ASME Continuing Education Institute

Lack Of New Nuclear Plants In US Has Not Slowed Development Of Section III

Standard Has Gained Acceptance Of World Nuclear Community

Participation Includes Canada, Japan, Korean, Spanish, South African, UK, And Russian Members And Globalization Is Proceeding