ASMECodes2

INTRODUCTION TO THE ASMEBoiler & Pressure Vessel Code:

SECTION III, DIVISION 1Nuclear Power Plant

ComponentsBY

Marcus N. Bressler, PE [email protected]

05/13/2008

mailto:[email protected]

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

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PRIMARY NUCLEAR SECTIONSSection III, Nuclear Plant Components

Division 1 - Metallic ComponentsDivision 2 - Concrete Containment VesselsDivision 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 PlantsDivision 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)

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REFERENCED SECTIONS

SECTION II - Materials

SECTION V - Nondestructive Examination

SECTION IX - Welding And Brazing Qualification

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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

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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

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INTERPRETATIONS

Publication

Used as reference

Cannot change Code requirements

Volume 58, July 1, 2008

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MANDATORY APPENDICES

Publication

Numbering

Uses Roman Numeral System

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NONMANDATORY APPENDICES

Coverage and Use

Numbering

Uses Alphabetic Capital Letters, but Try not to Use those that are aqkso Roman Numerals

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APPLICABILITY OF SECTION III AND XI RULES

COMMON USE OF BOTH SECTIONSDUTIES AND RESPONSIBILITIES OF PARTIESPARTIES INVOLVED

OwnerN -Type Certificate HolderQSC Certificate HolderAuthorized Inspection Agency (AIA)

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

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COMMON TERMINOLOGY

Owner

Construction

ASME Certificate Of Authorization

Manufacturer (N-Certificate Holder)

Installer (NA-Certificate Holder)

Fabricator (NPT-Certificate Holder)

Authorized Nuclear Inspector (ANI)

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COMMON TERMINOLOGY (cont’d)

Component

Piping System

Part

Appurtenance

Piping Subassembly

Support

NPT Code Symbol Stamp

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NA Code Symbol Stamp

MaterialSeamless Or Welded Without Filler Metal Added

Welded With Filler Metal Added (NPT-Stamp)

Data Report Form

Design SpecificationBasis For Construction

Certified By Registered Professional Engineer

Provided By Owner or Designee

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COMMON TERMINOLOGY (cont’d)Design Report

Provided by N-Certificate Holder

Design Calculations and Stress Analysis

When required, Certified by RPE

Design Output DrawingsDesign Drawings

Correlated With Design Reports

Load Capacity Data Sheets

Design Report Summaries

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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)

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ASME Survey Team for Material OrganizationsTeam Leader & Team Member

Observers (When Assigned) [Have No Vote}

Unannounced Audits for Material OrganizationsTeam Leader Only

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COMMON TERMINOLOGY (cont’d)Inspection

Performed by an ANI

ExaminationsPerformed by Qualified PersonnelNondestructive Examinations

RadiographyMagnetic ParticleEddy Current UltrasonicLiquid PenetrantVisual

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Testing

Hydrostatic Pressure Test

Pneumatic Pressure Test

Registered Professional EngineerCertifies Design Input Documents

Certifies Design Output Documents

Certifies Overpressure Protection Report

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GENERAL REQUIREMENTS OF SECTION III

Subsection NCAGeneral 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

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SECTION III - SUBSECTION NCA

NCA - 1100 SCOPEApplies to New Construction

Provides ExclusionsValve Operators, Controllers

Pump Impellers, Drivers

Intervening Elements

Instruments and Fluid Filled Tubing

Instrument, Control and Sampling Piping

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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 OwnerMust be Listed in Design Specification

Duplicate and Replicate Plants

Three year Window, NRC Provided for Five Years

Winter 1981 Addenda Existing Materials

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SECTION III - SUBSECTION NCA (cont’d)

NCA - 2000 �LASSIFICATIONCOde Does Not ClassifyClassification Guidance Provided by

Stat% or Federal Authorities10CFR50.55aRegulatory Guide 1.26 (RG 1.26)NRC Standard Review PlansAmerican Nuclear Society

Section III Provides Construction Rules for Each ClassMultiple Class Components or Optional Use of ClassesListed in the Design Specification

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NCA - 2000 - CLASSIFICATIONNCA-2140 LIMITS AND LOADINGS

Design

Operating

Testing

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

Quality Group A

Class 1 Components (NB) Reactor Pressure VesselPressurizer Vessel (PWR)Reactor Coolant PumpsSteam Generators (PWR)Reactor Coolant PipingLine ValvesSafety Valves

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

Emergency Core CoolingPost Accident Heat RemovalPost Accident Fission Product RemovalIncludes Vessels, Pumps, Valves, Piping, Storage Tanks, and Supports

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

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

Containment VesselPenetration AssembliesDoes not Include Piping, Pumps and ValvesPiping through Containment Must be Class 1 or Class 2

Subsection NF - SupportsPlate and Shell TypeLinear TypeStandard SupportsSupport Class is the Class of the Component Supported

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

Core Support Structures

Reactor Vessel Internals

Subsection NHElevated Temperature Components

Service Temperature Over 8000F

Refers to Subsection NB

No Fracture Toughness Rules

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NCA - 3000 DUTIES AND RESPONSIBILITIESSubcontracted 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)

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

Agreement with an AIADocuments Quality Assurance (QA) ProgramFiles a QA ManualObtains a Certificate of AuthorizationResponsible for Component Meeting all Code Requirements Prepares and Certifies Design ReportStress Analysis of Parts and AppurtenancesReconciliation of Drawing ChangesProvides Design Report to ANI and Owner Buys Material from Material OrganizationsQualifies MOs and Suppliers of Services

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

Verifies All Activities Have Been PerformedReceives Owner’s Review of the Design Report and Submits to ANICollects all Data, Including Certification of MaterialsPrepares Data Report Form, Signs, and Presents it to ANIANI Accepts Data Package, Certifies Data Report Form, AuthorizesStampingManufacturer Stamps NameplateShips ComponentOther Duties, and Responsibilities Listed in NCA-3520

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SECTION III - SUBSECTION NCA (cont’d)NCA - 3000 DUTIES AND RESPONSIBILITIES (cont’d)

The Registered Professional EngineerCertifies Design Specification (NCA-3255)Certifies Design Report (NCA-3555)Recertifies Revisions to DocumentsResponsible 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 IndependentThe Engineering Organization, 1973 -1976

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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

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SECTION III - SUBSECTION NCA (cont’d)NCA - 3000 Duties And Responsibilities (cont’d)

The NA Certificate Holder (NCA-3700) (cont’d)Verifies All Activities Have Been PerformedPerforms System Pressure TestCollects All Data, Including Certification of MaterialsPrepares N-5 Data Report Form, Signs, Submits to ANIANI Accepts Data Package, Certifies Data Report Form,Authorizes StampingInstaller Stamps Nameplate With “NA” StampOther 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

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NCA - 3000 DUTIES AND RESPONSIBILITIES (cont’d)

The NPT Certificate Holder Agreement With AIA

Documents and Files QA Program and ManualObtains a Certificate of AuthorizationNot Responsible for DesignFabricates Parts, Appurtenances, and Material Welded with Filler MetalResponsible for Meeting Applicable Code RequirementsBuys Material from Accredited MO’sQualifies MOs and Suppliers of ServicesMay have Responsibility for Part Design such as Component and Piping Supports

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SECTION III - SUBSECTION NCA (cont’d)NCA - 3000 DUTIES AND RESPONSIBILITIES (cont’d)

The NPT Certificate Holder (cont’d)Verifies All Activities Have Been Performed

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, AuthorizesStamping

Fabricator Stamps Nameplate With “NPT” Stamp

Other Duties And Responsibilities Listed In NCA-3620

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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

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NCA - 4000 QUALITY ASSURANCEQA 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

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NCA - 5000 AUTHORIZED INSPECTIONThird Party Inspection

The Authorized Nuclear Inspector

Duties And Responsibilities Listed In NCA-5220

The Authorized Inspection Agency

The N626 DocumentsN626.0-1974 \

N626.1-1975 > Combined Into N626 In 1985

N626.2-1976 /

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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

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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

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

Supervises One Or More ANIsReviews And Accepts QA Manual Prior To Initial SurveyReviews And Accepts Changes To QA Manual During Three Years Between SurveysChanges Cannot Be Implemented Prior To Acceptance By ANISAudits Material Manufacturing And Supplying Activities AnnuallyEvaluates ANI Performance Twice/YearEvaluates Status Of QA Program

ANIS And ANI Participate In ASME Initial And Renewal Surveys

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NCA-8000 STAMPINGRequirements For AccreditationAuthorization To Use StampsAgreement With AIAScopes Of AuthorizationExtension To Other LocationsTable NCA-8100-1

Accredited ActivitiesCode Symbols AppliedData Report Forms

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NCA-8000 STAMPING (cont’d)Accreditation Process

Renewal Of Authorization

Requirements For Nameplates

Requirements For Stamping

Items Supplied Without Stamping

Code Data Report FormsShown In Appendix V

Guidelines For Completion

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NCA - 9000 GLOSSARY OF TERMS

Definitions used in Divisions 1 and 2 of Section III

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SUBSECTION NB - CLASS 1NB - 1100 GENERAL REQUIREMENTS

ScopeLimitations

Temperature Limits

Boundaries Of JurisdictionFirst Circumferential WeldFace Of FlangeFace Of Threads

Rules For AttachmentsVessels, 2.5 (R x t)½ ; Containment Vessels, 16 tPumps, 4t

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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

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NB - 2000 MATERIALLimited In NumberCarbon & Low Alloy Steel to 700 F (370C)Austenitic And High Alloy Steels To 800 F (425C)Material Must Be CertifiedMaterial Must Be Traceable Including Welding MaterialTest Performed On Material CouponsPlates for Pressure Vessels and All Plates 2” Thick And Greater Must Be ExaminedUltrasonicallyRepairs to Material Are Limited According To Product FormMaterial Inspection Is Based On Product Form

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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

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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 ChangesTested at Lower And Lower Temperatures Until Both SpecimensExhibited “Break”

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

(MLE = Mils Lateral Expansion, 1 mil = 0.001”)RTNDT = (CVT - 60 F)

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

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

% Shear Fracture reporting was dropped in Summer 1985 AddendaFor 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 ServiceTemperature and Acceptance Is Based On MLETypical Charpy Curve

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

NB - 3200 - Design By AnalysisNB - 3300 - VesselsNB - 3400 - PumpsNB - 3500 - ValvesNB - 3600 - Piping

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

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NB - 3000 DESIGN (cont’d)

Design Based on Maximum Shear Stress Theory of Failure

Design Stress Intensities Used for Design

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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

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

Elastic AnalysisPlastic AnalysisElastic - Plastic AnalysisExperimental Stress Analysis

Check For Need Of Fatigue AnalysisCertification Of Design Report By RPE Is RequiredAcceptability Requirements Are Listed In NB-3211Fracture Mechanics Evaluation May Be RequiredClassification of Stress Intensity

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SUBSECTION NB - CLASS 1 (cont’d)NB - 3000 DESIGN (cont’d)

Design Of Pumps NB - 3400Rules Apply To All Parts Except

Pump Shafts And Impellers, Non-Structural Internals, Seal PackagesPermitted Design

Design By Analysis or Experimental Stress AnalysisCasing Wall Thickness

Designed As a Vessel With Diameter Equal to Maximum DistanceFrom One Chamber To The Other

Other Parts Designed By FormulasInlet and Outlets Are ReinforcedPump Shafts May Be Designed To Appendix SPump Internals To Appendix U

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SUBSECTION NB - CLASS 1 (cont’d)NB - 3000 DESIGN (cont’d)

Design Of Valves NB - 3500Mynimum Thickness

Based On Pressure Temperature Rating ForStandard Rating Valves Listed In ASME B16.34Interpolated For Non listed Pressure Rating Valves

Standard Design RulesModified Design By Analysis As Shown In NB-3530Through NB-3550

Alternative Design RulesDesign By Analysis NB - 3200Experimental Stress Analysis

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Design Of Valves NB - 3500Parts 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

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Design Of Piping NB - 3600Piping 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

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SUBSECTION NB - CLASS 1 (cont’d)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 RequirementsWeld Joint Design Is Generally Limited Full Penetration Butt WeldsOut-Of-Roundness Is LimitedFit-Up Tolerances Are LimitedSmooth Contours/Adequate Radii Required At Discontinuities

Weld Joint CategoriesUsed to Define Weld Locations & Establish NDE Rules

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SUBSECTION NB - CLASS 1 (cont’d)NB - 4000 FABRICATION AND INSTALLATION (cont’d)

Welding Procedure And Welder Qualification Are Given In Section IXSurface Condition Of Welds Must Be Suitable For Interpretation Of NDE And Must Not Mask Indications That Would Show In Final RadiographsOwner Must Provide Accessibility For Section XI Inservice Inspection Of WeldsPost weld Heat Treatment (PWHT) Is Required For Many Materials And ThicknessesWeld Repair Of Material Defects Are Covered By NB-2500Weld Repair Of Welds Are Covered By NB-4400Repairs Without PWHT Are Covered By NB-4600

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SUBSECTION NB - CLASS 1 (cont’d)NB - 5000 EXAMINATION – See Figure 40 - 1

Procedures For NDE Are Given In Section VSection V Only Covers MethodologyRequirements For Examination Are Covered In NB-5200Acceptance Standards Are Listed In NB-5300Qualification Of NDE Personnel Is In NB-5500, In Lieu Of NQA-1, Supplement 2S2NB-5112 Required Demonstration Of All NDE Procedures To The Satisfaction Of the ANIMaterial 2 in And Greater (>51mm), Cut Edges NDE by MT or PTFinal 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.

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SUBSECTION NB - CLASS 1 (cont’d)NB - 6000 TESTING

Completed Components Are Pressure Tested With Water To 1.25Design Pressure. Hydrostatic Testing Is Normally Performed In The Shop, At Ambient TemperatureTest 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 OVERPRESSURESection III Provides Rules For The Prevention Of Overpressure of Nuclear ComponentsA Component Can Be Completed Without These Overpressure Protection Devices, but they Must Be installed as Part of the Nuclear SystemThe Rules Are Similar For Classes 1, 2, And 3 SystemsOverpressure 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 STAMPINGBefore 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 RPEOwner’s Review of the Design Report Performed and DocumentedAll NX-8000 Articles Refer You Back To NCA-8000

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SUBSECTION NC - CLASS 2

NC - 2000 MATERIALRules For Class 2 Material Are Similar To Class 1More Materials Are Available In Section II, Part D, Subpart 1,Tables 1A, 1B and 3Plates Over 2 in (51mm) Are Not Subject To UT ExaminationImpact Testing Is Required But Acceptance Standards Are LowerDropweight 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 ValvesGenerally Designed to Pressure-Temperature Rating Of ANSI B16.34

Design of PipingDesigned 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 1Details of Construction Less RestrictiveStorage Tank Fabrication Rules Are More Restrictive than API StandardsQualification of Weld Procedures And Welders Are Same As Class 1

Requirements For PWHT Less Stringent

NC - 5000 EXAMINATIONLongitudinal And Circumferential Welds Require RTSurface Examination Of These Welds Is Not RequiredPersonnel Qualifications For NDE Are The Same As Class 1Penetration 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 DESIGNSame 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 FABRICATIONMore Options Available for Fabrication Details

Welding And PWHT Rules Same As For Class 2

ND - 5000 - EXAMINATIONAll 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 NENE - 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 AFactor “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 DESIGNContainment 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 FABRICATIONSame As Class 2, But All Nozzle Opening Assemblies Must Be PWHT Before Installation In the Vessel

NE - 5000 EXAMINATIONSlightly More Restrictive Than For Class 2 Vessels

NE - 6000 TESTINGDue To Size, The Pressure Test Is Pneumatic

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

76

SUBSECTION NFNF - 2000 MATERIAL

Rules For Materials Are Similar to Class 2Supports Are Classified According To The Class Of The Component They SupportMaterials Are Listed In Tables 1A, 1B, 2A, 2B, 3 and 4 of Section II Part DAdditional Materials For Supports Were Listed In Code Case 1644,Now In Code Cases N-71 and N-249Design Specification Must State Whether Or Not Impact Testing IsRequired. If It Is, Only Cv Testing Is RequiredIn 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 EXAMINATIONDepends On Class Of Component Being SupportedMore Lenient Than Rules For The Supported ComponentMore Extensive Visual Examination

GENERAL COMMENTSSupports 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 TheoryAllowable Stress Limits Different From Class 1Based On A Factor On Yield Strength Or Ultimate TensileStrength At TemperatureQuality Factor On Stress And Fatigue Factor Are Determined By Joint Design And Amount Of NDE

NG - 4000 FABRICATIONAlmost Identical To Class 1 RulesChoice Of Weld Detail Determines Quality Factor

81

SUBSECTION NG CORE SUPPORT STRUCTURES (cont’d)

NG - 5000 EXAMINATIONMore Ultrasonic And Visual Examination UsedCode 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 ToPerform Activities In Compliance With The Rules OfSection 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 CertificatesCertificate of Accreditation

Owner’s CertificateAgreement with AIACompletes N-3 Data Report Form

Corporate CertificatesCan be Extended to Other SitesAgreement with AIA Code Symbol Stamps Not Provided

Replaced Interim Letter on July 1, 1998

Quality System CertificatesMaterial Organizations Manufacturing and/or Supplying MaterialNo Agreement With AIANo Welded Fabrication PermittedWeld 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 InstallationNPT Certificate Holder - Parts, Piping Subassemblies, AppurtenancesNV Certificate Holder - Pressure Relief Devices, Safety ValvesNS Certificate Holder - Supports (Beginning with 1999 Addenda)

Scopes Can Describe Activities Performed At Other LocationsCorporate Certificates Can Be Extended To Other SitesScopes Can Permit Manufacture Or Supply Of MaterialAll Require Agreement With AIAUtilities Can Get N-Type Certificates For a Nuclear Plant Site

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Terms of CertificatesAll Certificates are Issued for 3 years

Issuance and Renewal of CertificatesOwner’s Certificates

A Construction Permit or Docket Date Issued by USNRC is PrerequisiteRenewal is by MailApplication must be Made 90 days in Advance of Expiration

Other CertificatesApplication for Initial Certificate When Ready for SurveyRenewal Application Required at least 6 Months Before ExpirationDeposit Must be Submitted With Application

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Accreditation ProcessSame For Initial Issuance and For Renewal

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

Process Differs for Various Certificates

Owners CertificateInitial 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 TeamTeam 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 TeamTeam Leader

Team Member

National Board Representative

ANIS And ANI

Jurisdictional Authority and Regulatory Authority InvitedApproval 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 ParticipationANI and ANIS Participate in SurveyANIS Participates in Review/Acceptance of Final Version of QA ManualObservers 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 MembersObservers Have No Vote on The Team

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QSC Certificates Manual RevisionsManual 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 TheAudits 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 The1992 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 AccreditationBoard 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 BCAN626 Committee Now QAI, Committee On Qualification For Authorized InspectionAIA 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 AIALimited To Piping And Standard SupportsStamping Of Welded Supports Was Introduced In The Winter 1975 AddendaThe NS Certificate Introduced 1998 Edition, 1999 AddendaEliminates Standard Supports Supplied As Material Under NF-1214Permits Design ResponsibilityPermits Welded FabricationStamping Of Welded Supports Is Not RequiredNew Certificate Of Conformance, Form NS-1

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CONCLUSIONPresentation 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

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