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INTRODUCTION TO THE ASME Boiler Pressure Vessel Code:

2. SECTION III EVOLUTION. First Published in 1963Transition from ASA to USAS to ANSI1971 Edition, Nuclear Power Plant Component2007 Edition, ASME B

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INTRODUCTION TO THE ASME Boiler Pressure Vessel Code:

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    1. INTRODUCTION TO THE ASME Boiler & Pressure Vessel Code: SECTION III, DIVISION 1 Nuclear Power Plant Components BY Marcus N. Bressler, PE mbresslerpe@juno.com 05/13/2008

    2. 2

    3. 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. 4 REFERENCED SECTIONS SECTION II - Materials SECTION V - Nondestructive Examination SECTION IX - Welding And Brazing Qualification

    5. 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

    6. 6

    7. 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. 8 INTERPRETATIONS Publication Used as reference Cannot change Code requirements Volume 58, July 1, 2008

    9. 9 MANDATORY APPENDICES Publication Numbering Uses Roman Numeral System

    10. 10 NONMANDATORY APPENDICES Coverage and Use Numbering Uses Alphabetic Capital Letters, but Try not to Use those that are aqkso Roman Numerals

    11. 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. 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. 13 COMMON TERMINOLOGY (contd) Component Piping System Part Appurtenance Piping Subassembly Support NPT Code Symbol Stamp

    14. 14 COMMON TERMINOLOGY (contd) 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. 15 COMMON TERMINOLOGY (contd) 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. 16 COMMON TERMINOLOGY (contd) 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. 17 COMMON TERMINOLOGY (contd) 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. 18 COMMON TERMINOLOGY (contd) Inspection Performed by an ANI Examinations Performed by Qualified Personnel Nondestructive Examinations Radiography Magnetic Particle Eddy Current Ultrasonic Liquid Penetrant Visual

    19. 19 COMMON TERMINOLOGY (contd) Testing Hydrostatic Pressure Test Pneumatic Pressure Test Registered Professional Engineer Certifies Design Input Documents Certifies Design Output Documents Certifies Overpressure Protection Report

    20. 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. 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. 22 SECTION III - SUBSECTION NCA (contd) 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. 23 SECTION III - SUBSECTION NCA (contd) 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. 24 SECTION III - SUBSECTION NCA (contd) NCA - 2000 - CLASSIFICATION NCA-2140 LIMITS AND LOADINGS Design Operating Testing

    25. 25 SECTION III - SUBSECTION NCA (contd) NCA - 2000 - CLASSIFICATION (contd) 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. 26 SECTION III - SUBSECTION NCA (contd) NCA - 2000 - CLASSIFICATION (contd) 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. 27 SECTION III - SUBSECTION NCA (contd) NCA - 2000 - CLASSIFICATION (contd) 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. 28 SECTION III - SUBSECTION NCA (contd) NCA - 2000 - CLASSIFICATION (contd) 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. 29 SECTION III - SUBSECTION NCA (contd) NCA - 3000 DUTIES AND RESPONSIBILITIES Subcontracted Services, Calibration and Welding - The Owner (NCA-3200) Receives N-Certificate Holders 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. 30 SECTION III - SUBSECTION NCA (contd) NCA - 3000 Duties and Responsibilities (contd) 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. 31 SECTION III - SUBSECTION NCA (contd) NCA - 3000 DUTIES AND RESPONSIBILITIES (contd) N-Certificate Holder (NCA-3500) (contd) Verifies All Activities Have Been Performed Receives Owners 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. 32 SECTION III - SUBSECTION NCA (contd) NCA - 3000 DUTIES AND RESPONSIBILITIES (contd) 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 RPEs Certifying the Documents May be From the Same Organizations, But Must Be Independent The Engineering Organization, 1973 -1976

    33. 33 SECTION III - SUBSECTION NCA (contd) NCA - 3000 Duties And Responsibilities (contd) 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. 34 SECTION III - SUBSECTION NCA (contd) NCA - 3000 Duties And Responsibilities (contd) The NA Certificate Holder (NCA-3700) (contd) Verifies All Activities Have Been Performed 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. 35 SECTION III - SUBSECTION NCA (contd) NCA - 3000 DUTIES AND RESPONSIBILITIES (contd) 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 MOs Qualifies MOs and Suppliers of Services May have Responsibility for Part Design such as Component and Piping Supports

    36. 36 SECTION III - SUBSECTION NCA (contd) NCA - 3000 DUTIES AND RESPONSIBILITIES (contd) The NPT Certificate Holder (contd) 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, Authorizes Stamping Fabricator Stamps Nameplate With NPT Stamp Other Duties And Responsibilities Listed In NCA-3620

    37. 37 SECTION III - SUBSECTION NCA (contd) NCA - 3000 DUTIES AND RESPONSIBILITIES (contd) 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 65tf6t6565tf6t65

    38. 38 SECTION III - SUBSECTION NCA (contd) 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. 39 SECTION III - SUBSECTION NCA (contd) 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. 40 SECTION III - SUBSECTION NCA (contd) NCA - 5000 AUTHORIZED INSPECTION (contd) 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. 41 SECTION III - SUBSECTION NCA (contd) NCA - 5000 AUTHORIZED INSPECTION (contd) Satisfied With Nondestructive Examination (NDE) Procedures and Qualification Of NDE Personnel Witnesses Pressure Tests Certifies Compliance With The Code

    42. 42 SECTION III - SUBSECTION NCA (contd) NCA - 5000 AUTHORIZED INSPECTION (contd) 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. 43 SECTION III - SUBSECTION NCA (contd) 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. 44 SECTION III - SUBSECTION NCA (contd) NCA-8000 STAMPING (contd) 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. 45 SECTION III - SUBSECTION NCA (contd) NCA - 9000 GLOSSARY OF TERMS Definitions used in Divisions 1 and 2 of Section III

    46. 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) ; Containment Vessels, 16 t Pumps, 4t

    47. 47 SUBSECTION NB - CLASS 1 (contd) NB - 1100 (contd) Task Group On Attachments Attachments Pressure Retaining Non-Pressure Retaining Structural Non-Structural Introduced In All Subsections NB-2190

    48. 48 SUBSECTION NB - CLASS 1 (contd) 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. 49 SUBSECTION NB - CLASS 1 (contd) NB - 2000 MATERIAL (contd) 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. 50 SUBSECTION NB - CLASS 1 (contd) NB - 2000 MATERIAL (contd) 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. 51 SUBSECTION NB - CLASS 1 (contd) NB - 2000 MATERIAL (contd) 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. 52 SUBSECTION NB - CLASS 1 (contd) 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. 53 SUBSECTION NB - CLASS 1 (contd) NB - 3000 DESIGN (contd) Design Based on Maximum Shear Stress Theory of Failure Design Stress Intensities Used for Design

    54. 54 SUBSECTION NB - CLASS 1 (contd) NB - 3000 DESIGN (contd) 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. 55 SUBSECTION NB - CLASS 1 (contd) NB - 3000 DESIGN (contd) 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. 56 SUBSECTION NB - CLASS 1 (contd) NB - 3000 DESIGN (contd) 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. 57 SUBSECTION NB - CLASS 1 (contd) NB - 3000 DESIGN (contd) 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. 58 SUBSECTION NB - CLASS 1 (contd) NB - 3000 DESIGN (contd) 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. 59 SUBSECTION NB - CLASS 1 (contd) NB - 3000 DESIGN (contd) 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. 60 SUBSECTION NB - CLASS 1 (contd) 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 Categories Used to Define Weld Locations & Establish NDE Rules

    61. 61 SUBSECTION NB - CLASS 1 (contd) NB - 4000 FABRICATION AND INSTALLATION (contd) 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. 62 SUBSECTION NB - CLASS 1 (contd) 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. 63 SUBSECTION NB - CLASS 1 (contd) NB - 5000 EXAMINATION (contd) 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. 64 SUBSECTION NB - CLASS 1 (contd) 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. 65 SUBSECTION NB - CLASS 1 (contd) 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. 66 SUBSECTION NB - CLASS 1 (contd) 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 Owners Review of the Design Report Performed and Documented All NX-8000 Articles Refer You Back To NCA-8000

    67. 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. 68 SUBSECTION NC - CLASS 2 (contd) 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. 69 SUBSECTION NC - CLASS 2 (contd) NC - 3000 DESIGN (contd) 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. 70 SUBSECTION NC - CLASS 2 (contd) 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. 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. 72 SUBSECTION ND - CLASS 3 (contd) 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. 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. 74 SUBSECTION NE (contd) 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. 75 SUBSECTION NE (contd) 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. 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. 77 SUBSECTION NF (contd) 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. 78 SUBSECTION NF (contd) 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. 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. 80 SUBSECTION NG CORE SUPPORT STRUCTURES (contd) NG - 3000 DESIGN Design 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 FABRICATION Almost Identical To Class 1 Rules Choice Of Weld Detail Determines Quality Factor

    81. 81 SUBSECTION NG CORE SUPPORT STRUCTURES (contd) NG - 5000 EXAMINATION More Ultrasonic And Visual Examination Used Code Permits Designer To Define Joints As A Requirement For Examination NG - 8000 CERTIFICATION Rules 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. 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. 83 PART IV ASME 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. 84 PART IV ASME NUCLEAR ACCREDITATION (contd) Types Of Certificates Certificate of Accreditation Owners 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

    85. 85 PART IV ASME NUCLEAR ACCREDITATION (contd) Types Of Certificates (contd) 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

    86. 86 PART IV ASME NUCLEAR ACCREDITATION (contd) Terms of Certificates All Certificates are Issued for 3 years Issuance and Renewal of Certificates Owners 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

    87. 87 PART IV ASME NUCLEAR ACCREDITATION (contd) 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

    88. 88 PART IV ASME NUCLEAR ACCREDITATION (contd) Accreditation Process (contd) 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

    89. 89 PART IV ASME NUCLEAR ACCREDITATION (contd) Accreditation Process (contd) 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

    90. 90 PART IV ASME NUCLEAR ACCREDITATION (contd) Accreditation Process (contd) 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

    91. 91 PART IV ASME NUCLEAR ACCREDITATION (contd) Accreditation Process (contd) Scope of Survey (contd) 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

    92. 92 PART IV ASME NUCLEAR ACCREDITATION (contd) Accreditation Process (contd) Contractual Requirements With AIA All Certificates Other Than QSC Require Agreement With AIA AIA Provides Third Party Inspection Services With One or More ANIs, 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

    93. 93 PART IV ASME NUCLEAR ACCREDITATION (contd) 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

    94. 94 PART II ASME NUCLEAR ACCREDITATION (contd) New Developments In ASME Accreditation Accreditation of AIAs The Code Moved To Add Part 4 To N626, And It Was Approved In The 1992 Edition. Applied to Nuclear AIAs Nuclear AIAs Were First Accredited In 1993 QAI-1-1995 Added Part 5, Which Requires Accreditation Of Non Nuclear AIAs SC-NA First Handled Part 4 Nuclear AIA Accreditation

    95. 95 PART II ASME NUCLEAR ACCREDITATION (contd) 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

    96. 96 PART II ASME NUCLEAR ACCREDITATION (contd) New Developments In ASME Accreditation (contd) 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

    97. 97 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

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