Title: INTRODUCTION TO THE ASME Boiler & Pressure Vessel
1INTRODUCTION TO THE ASMEBoiler Pressure Vessel
Code
- SECTION III, DIVISION 1
- Nuclear Power Plant
- Components
-
BY - Marcus N. Bressler, PE
-
mbresslerpe_at_juno.com -
05/13/2008 -
2SECTION 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
3PRIMARY 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)
4REFERENCED SECTIONS
- SECTION II - Materials
- SECTION V - Nondestructive Examination
- SECTION IX - Welding And Brazing Qualification
5U.S. REGULATORY ISSUES
- The ASME Code as Law
- Synopsis of BPV 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(No Transcript)
7ASME 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
-
8INTERPRETATIONS
- Publication
- Used as reference
- Cannot change Code requirements
- Volume 58, July 1, 2008
9MANDATORY APPENDICES
- Publication
- Numbering
- Uses Roman Numeral System
10NONMANDATORY APPENDICES
- Coverage and Use
- Numbering
- Uses Alphabetic Capital Letters, but Try not to
Use those that are aqkso Roman Numerals
11APPLICABILITY 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
12COMMON TERMINOLOGY
- Owner
- Construction
- ASME Certificate Of Authorization
- Manufacturer (N-Certificate Holder)
- Installer (NA-Certificate Holder)
- Fabricator (NPT-Certificate Holder)
- Authorized Nuclear Inspector (ANI)
13COMMON TERMINOLOGY (contd)
- Component
- Piping System
- Part
- Appurtenance
- Piping Subassembly
- Support
- NPT Code Symbol Stamp
14COMMON 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
15COMMON 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
16COMMON 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)
17COMMON 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
18COMMON TERMINOLOGY (contd)
- Inspection
- Performed by an ANI
- Examinations
- Performed by Qualified Personnel
- Nondestructive Examinations
- Radiography
- Magnetic Particle
- Eddy Current
- Ultrasonic
- Liquid Penetrant
- Visual
19COMMON TERMINOLOGY (contd)
- Testing
- Hydrostatic Pressure Test
- Pneumatic Pressure Test
- Registered Professional Engineer
- Certifies Design Input Documents
- Certifies Design Output Documents
- Certifies Overpressure Protection Report
20GENERAL 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
21SECTION 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
22SECTION 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
23SECTION 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
24SECTION III - SUBSECTION NCA (contd)
- NCA - 2000 - CLASSIFICATION
- NCA-2140 LIMITS AND LOADINGS
- Design
- Operating
- Testing
25SECTION 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
26SECTION 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
27SECTION 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
28SECTION 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
29SECTION 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)
30SECTION 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
31SECTION 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
32SECTION 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
33SECTION 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
34SECTION 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
35SECTION 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
36SECTION 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
37SECTION 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
38SECTION 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
39SECTION 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 gt Combined Into N626 In 1985
- N626.2-1976 /
40SECTION 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
41SECTION 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
42SECTION 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
43SECTION 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
44SECTION 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
45SECTION III - SUBSECTION NCA (contd)
- NCA - 9000 GLOSSARY OF TERMS
- Definitions used in Divisions 1 and 2 of Section
III
46SUBSECTION 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
47SUBSECTION 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
48SUBSECTION 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
-
49SUBSECTION 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
50SUBSECTION 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)
51SUBSECTION 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 gt 2-1/2 in.
(75 mm) - RTNDT (Cv - 100F)
- For t lt 2-1/2 in., Cv is Tested At Lowest Service
- Temperature and Acceptance Is Based On MLE
- Typical Charpy Curve
52SUBSECTION 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
53SUBSECTION NB - CLASS 1 (contd)
- NB - 3000 DESIGN (contd)
- Design Based on Maximum Shear Stress Theory of
Failure -
- Design Stress Intensities Used for Design
-
54SUBSECTION 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
55SUBSECTION 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
56SUBSECTION 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
57SUBSECTION 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
58SUBSECTION 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
59SUBSECTION 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
60SUBSECTION 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
61SUBSECTION 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
62SUBSECTION 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 (gt51mm), 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
63SUBSECTION 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.
64SUBSECTION 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.
65SUBSECTION 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
66SUBSECTION 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
67SUBSECTION 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
68SUBSECTION 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
69SUBSECTION 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
70SUBSECTION 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
71SUBSECTION 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
72SUBSECTION 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
73SUBSECTION 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.
74SUBSECTION 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
75SUBSECTION 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
76SUBSECTION 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
77SUBSECTION 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
78SUBSECTION 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)
79SUBSECTION 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
80SUBSECTION 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
81SUBSECTION 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
82SUBSECTION 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
83PART 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
84PART IVASME 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
85PART IVASME 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
86PART IVASME 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
87PART IVASME 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
88PART IVASME 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
89PART IVASME 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
90PART IVASME 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
91PART IVASME 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
92PART IVASME 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
93PART IVASME 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
94PART IIASME 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
95PART IIASME 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
96PART IIASME 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
97CONCLUSION
- 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