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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
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
COMMON TERMINOLOGY (cont’d)
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
COMMON TERMINOLOGY (cont’d)
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
COMMON TERMINOLOGY (cont’d)
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
COMMON TERMINOLOGY (cont’d)
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
COMMON TERMINOLOGY (cont’d)
Inspection Performed by an ANI
Examinations Performed by Qualified Personnel Nondestructive Examinations
Radiography
Magnetic Particle Eddy Current Ultrasonic
Liquid Penetrant
Visual
19
COMMON TERMINOLOGY (cont’d)
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
SECTION III - SUBSECTION NCA (cont’d)
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
SECTION III - SUBSECTION NCA (cont’d)
NCA - 2000 - CLASSIFICATIONNCA-2140 LIMITS AND LOADINGS
Design
Operating
Testing
25
SECTION III - SUBSECTION NCA (cont’d)
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
SECTION III - SUBSECTION NCA (cont’d)
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
SECTION III - SUBSECTION NCA (cont’d)
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
SECTION III - SUBSECTION NCA (cont’d)
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
SECTION III - SUBSECTION NCA (cont’d)
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
SECTION III - SUBSECTION NCA (cont’d)
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
SECTION III - SUBSECTION NCA (cont’d)
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
SECTION III - SUBSECTION NCA (cont’d)
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
SECTION III - SUBSECTION NCA (cont’d)
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
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 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
SECTION III - SUBSECTION NCA (cont’d)
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
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, Authorizes Stamping
Fabricator Stamps Nameplate With “NPT” Stamp
Other Duties And Responsibilities Listed In NCA-3620
37
SECTION III - SUBSECTION NCA (cont’d)
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
SECTION III - SUBSECTION NCA (cont’d)
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
SECTION III - SUBSECTION NCA (cont’d)
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
SECTION III - SUBSECTION NCA (cont’d)
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
SECTION III - SUBSECTION NCA (cont’d)
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
SECTION III - SUBSECTION NCA (cont’d)
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
SECTION III - SUBSECTION NCA (cont’d)
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
SECTION III - SUBSECTION NCA (cont’d)
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
SUBSECTION NB - CLASS 1 (cont’d)
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
SUBSECTION NB - CLASS 1 (cont’d)
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
SUBSECTION NB - CLASS 1 (cont’d)
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
SUBSECTION NB - CLASS 1 (cont’d)
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
SUBSECTION NB - CLASS 1 (cont’d)
NB - 3000 DESIGN (cont’d)
Design Based on Maximum Shear Stress Theory of Failure
Design Stress Intensities Used for Design
54
SUBSECTION NB - CLASS 1 (cont’d)
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
SUBSECTION NB - CLASS 1 (cont’d)
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
SUBSECTION NB - CLASS 1 (cont’d)
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
SUBSECTION NB - CLASS 1 (cont’d)
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
SUBSECTION NB - CLASS 1 (cont’d)
NB - 3000 DESIGN (cont’d)
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
SUBSECTION NB - CLASS 1 (cont’d)
NB - 3000 DESIGN (cont’d)
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
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 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
SUBSECTION NB - CLASS 1 (cont’d)
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
SUBSECTION NB - CLASS 1 (cont’d)
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
SUBSECTION NB - CLASS 1 (cont’d)
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
SUBSECTION NB - CLASS 1 (cont’d)
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
SUBSECTION NB - CLASS 1 (cont’d)
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
SUBSECTION NB - CLASS 1 (cont’d)
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
85
PART IVASME NUCLEAR ACCREDITATION (cont’d)
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
86
PART IVASME NUCLEAR ACCREDITATION (cont’d)
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
87
PART IVASME NUCLEAR ACCREDITATION (cont’d)
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
PART IVASME NUCLEAR ACCREDITATION (cont’d)
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
89
PART IVASME NUCLEAR ACCREDITATION (cont’d)
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
90
PART IVASME NUCLEAR ACCREDITATION (cont’d)
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
91
PART IVASME NUCLEAR ACCREDITATION (cont’d)
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
92
PART IVASME NUCLEAR ACCREDITATION (cont’d)
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
93
PART IVASME NUCLEAR ACCREDITATION (cont’d)
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
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
95
PART IIASME NUCLEAR ACCREDITATION (cont’d)
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
PART IIASME NUCLEAR ACCREDITATION (cont’d)
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
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