Regulatory Guide 1.84: Difference between revisions

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{{#Wiki_filter:June 19740U.S. ATOMIC ENERGY COMMISSION
{{#Wiki_filter:June 1974 0 U.S. ATOMIC ENERGY COMMISSION
REGULATORY
REGULATORY
DIRECTORATE  
DIRECTORATE  
OF REGULATORY  
OF REGULATORY  
STANDARDS
STANDARDS REGULATORY  
REGULATORY  
GUIDE 1.84 CODE CASE ACCEPTABILITY
GUIDE 1.84CODE CASE ACCEPTABILITY
ASME SECTION III DESIGN AND FABRICATION
ASME SECTION III DESIGNAND FABRICATION
GUIDE  
GUIDE


==A. INTRODUCTION==
==A. INTRODUCTION==
Section 50.55a, "Codes and Standards,"  
Section 50.55a, "Codes and Standards," of 10 CFR Part 50, "Ucensing of Production and Utilization Facilities," requires, in part, that components of the reactor coolant pressure boundary be designed, fabri-cated, erected, and tested in accordance with the requirements for Class I components of Section III,"Nuclear Power Plant Components,"i of the American Society of Mechanical Engineeri (ASME) Boiler and Pressure Vessel Code or equivalent quality standards.
of 10 CFRPart 50, "Ucensing of Production and Utilization Facilities,"  
requires, in part, that components of thereactor coolant pressure boundary be designed, fabri-cated, erected, and tested in accordance with therequirements for Class I components of Section III,"Nuclear Power Plant Components,"i of the AmericanSociety of Mechanical Engineeri (ASME) Boiler andPressure Vessel Code or equivalent quality standards.


Footnote  
Footnote 6 to Section 50.55a states that the use of specific Code Cases may be authorized by the Commis-sion upon request pursuant to §50.55a(a)(2Xii)  
6 to Section 50.55a states that the use ofspecific Code Cases may be authorized by the Commis-sion upon request pursuant to §50.55a(a)(2Xii)  
which requires that proposed alternatives to the described requirements or portions thereof provide an acceptable level of quality and safety. General De--ign Criterion  
whichrequires that proposed alternatives to the described requirements or portions thereof provide an acceptable level of quality and safety. General De--ign Criterion  
1,"Quality Standards and Records," of Appendix A,"General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50 requires, in part, that structures, systems, and components important to safety be de-signed, fabricated, erected, and tested to quality stand-ards commensurate with the importance of the safety.function to be performed.
1,"Quality Standards and Records,"  
of Appendix A,"General Design Criteria for Nuclear Power Plants,"  
to10 CFR Part 50 requires, in part, that structures, systems, and components important to safety be de-signed, fabricated, erected, and tested to quality stand-ards commensurate with the importance of the safety.function to be performed.


Where generally recognized codes and standards are .used, Criterion I requires that* they be identified and evaluated to determine theirapplicability, adequacy, and sufficiency and be supple-mented or modified as necessary to assure a qualityproduct in keeping with the required safety function.
Where generally recognized codes and standards are .used, Criterion I requires that* they be identified and evaluated to determine their applicability, adequacy, and sufficiency and be supple-mented or modified as necessary to assure a quality product in keeping with the required safety function.


30, "Quality of Reactor Coolant PressureBoundary,"  
30, "Quality of Reactor Coolant Pressure Boundary," of the same appendix requires, in part, that components which are part of the reactor coolant pressure boundary be designed, fabricated, erected, and ICopies may be obtained from the American Society of Mechanical Engineers, United Enginecering Center, 345 East 47th Street, New York, N.Y. 10017.tested to the highest quality standards practical.
of the same appendix requires, in part, thatcomponents which are part of the reactor coolantpressure boundary be designed, fabricated, erected, andICopies may be obtained from the American Society ofMechanical Engineers, United Enginecering Center, 345 East47th Street, New York, N.Y. 10017.tested to the highest quality standards practical.


Ap-pendix B, "Quality Assurance Criteria for Nuclear PowerPlants and Fuel Reprocessing Plants,"  
Ap-pendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part 50.requires, in part, that measures be established for the control of special processing of materials and that proper testing be performed.
to 10 CFR Part 50.requires, in part, that measures be established for thecontrol of special processing of materials and that propertesting be performed.


This regulatory guide lists thoseSection III ASME Code Cases oriented to design andfabrication which are generally acceptable to the AECRegulatory staff for implementation in the licensing oflight-water-cooled nuclear power plants.
This regulatory guide lists those Section III ASME Code Cases oriented to design and fabrication which are generally acceptable to the AEC Regulatory staff for implementation in the licensing of light-water-cooled nuclear power plants.


==B. DISCUSSION==
==B. DISCUSSION==
The Boiler and Pressure Vessel Committee of theASME publishes documents entitled  
The Boiler and Pressure Vessel Committee of the ASME publishes documents entitled "Interpretations of the ASME Boiler and Pressure Vessel Code." t These documents, referred to as "Code Cases," explain the intent of Code rules or provide Code permission to use alternative requirements under special circumstances or with suitable precautions.
"Interpretations ofthe ASME Boiler and Pressure Vessel Code."t Thesedocuments, referred to as "Code Cases," explain theintent of Code rules or provide Code permission to usealternative requirements under special circumstances orwith suitable precautions.


Most Code Cases are even-tually superseded by revision to the Code and then areannulled by action of the ASME Council.The Code Cases listed in this guide are limited strictlyto those applicable to Section III which are orientedtoward design and fabrication.
Most Code Cases are even-tually superseded by revision to the Code and then are annulled by action of the ASME Council.The Code Cases listed in this guide are limited strictly to those applicable to Section III which are oriented toward design and fabrication.


All published Code Cases in the area of design andfabrication which are applicable  
All published Code Cases in the area of design and fabrication which are applicable .to Section III of the Code and were in effect on November 5, 1973 were reviewed for inclusion in this guide. Code Cases which are not listed herein are either not endorsed or will require supplementary provisions on an individual basis to attain endorsement status.The endorsement of a Code Case by this guide constitutes acceptance of its technical position for USAEC REGULATORY  
.to Section III of theCode and were in effect on November  
5, 1973 werereviewed for inclusion in this guide. Code Cases whichare not listed herein are either not endorsed or willrequire supplementary provisions on an individual basisto attain endorsement status.The endorsement of a Code Case by this guideconstitutes acceptance of its technical position forUSAEC REGULATORY  
GUIDES Copies of published guides may be obtained by request indicating the divisions desired to the US. Atomic Energy Commission, Washington.
GUIDES Copies of published guides may be obtained by request indicating the divisions desired to the US. Atomic Energy Commission, Washington.


Line 61: Line 50:
Director of Regulatory Standards.
Director of Regulatory Standards.


Comments and suggestions formethods accptable to the AEC Regulatory stoff of Implementing specific pents of improvements In these guides are encouraged and should be sent to the Secretary the Commissioe's regulations, to delineate techniques v,,ed by the staff in of the Commission, US. Atomic Energy Commission, Wtshington, D.C. 20545,evaluating specific prob;ems or postulated accidents, or to provide guidsnce to Attention:  
Comments and suggestions for methods accptable to the AEC Regulatory stoff of Implementing specific pents of improvements In these guides are encouraged and should be sent to the Secretary the Commissioe's regulations, to delineate techniques v,,ed by the staff in of the Commission, US. Atomic Energy Commission, Wtshington, D.C. 20545, evaluating specific prob;ems or postulated accidents, or to provide guidsnce to Attention:  
Chief. Public Proceedings Staff.apolicants.
Chief. Public Proceedings Staff.apolicants.


Line 67: Line 56:


Methods end solutions different from those set out in The guides are issued in th" following ten broad divisions:
Methods end solutions different from those set out in The guides are issued in th" following ten broad divisions:
the guides will be acceptable If they provide a basis for the findings requisite tothe issuance or continuance of a permit or license by the Commission,  
the guides will be acceptable If they provide a basis for the findings requisite to the issuance or continuance of a permit or license by the Commission, 1. Power Reachors 6. Products 2. Research end Test Resictoct  
 
===1. Power Reachors ===
6. Products2. Research end Test Resictoct  


===7. Transportation===
===7. Transportation===
3. Fuets and Materials Fecilities  
3. Fuets and Materials Fecilities  
8. Occupational HealthPublished guides will be revised periodically, as appropriate, to accommodate  
8. Occupational Health Published guides will be revised periodically, as appropriate, to accommodate  
4. Environmental and Siting 9. Antitrust Reviewcomments and to reflect new Information or experience, S. Materials and Plant Protection  
4. Environmental and Siting 9. Antitrust Review comments and to reflect new Information or experience, S. Materials and Plant Protection  
10, General applications not precluded by regulatory or otherrequirements or by the recommendations in this or otherregulatory guides. Contingent endorsement is indicated in Regulatory Position C.l.c for specific cases; however* it is the responsibility of the user to make certain thatno regulatory requirements are violated and that thereare no conflicts with other recommended limitations resulting from Code Case usage.The acceptance or endorsement by the Regulatory staff applies only to those Code Cases or Code Caserevisions with the date of "Council Approval"  
10, General applications not precluded by regulatory or other requirements or by the recommendations in this or other regulatory guides. Contingent endorsement is indicated in Regulatory Position C.l.c for specific cases; however* it is the responsibility of the user to make certain that no regulatory requirements are violated and that there are no conflicts with other recommended limitations resulting from Code Case usage.The acceptance or endorsement by the Regulatory staff applies only to those Code Cases or Code Case revisions with the date of "Council Approval" as shown in the Regulatory Position of this guide. Earlier or later revisions of a Code Case are not endorsed by this guide.New Code Cases as they are issued or future revisions of existing Code Cases will require evaluation by the Regulatory staff to determine if they qualify for inclusion in the approved list. Because of the continuing change in the status of Code Cases, it is planned that this guide will require periodic updating to accommodate new Code Cases and any revisions of existing Code Cases.C. REGULATORY  
as shownin the Regulatory Position of this guide. Earlier or laterrevisions of a Code Case are not endorsed by this guide.New Code Cases as they are issued or future revisions ofexisting Code Cases will require evaluation by theRegulatory staff to determine if they qualify forinclusion in the approved list. Because of the continuing change in the status of Code Cases, it is planned that thisguide will require periodic updating to accommodate new Code Cases and any revisions of existing CodeCases.C. REGULATORY  
POSITION 1. The Section III ASME Code Cases 2 listed in the following by number, title, and date of Council approval are a:ceptable to the Regulatory staff for application in the construction of components for water-cooled nu-clear power plants. Their use is acceptable within the limitations stated in the "Inquiry" and "Reply" sections of each individual code case, such Regulatory or other requirements as may exist, and the additional limitations recommended by the Regulatory, staff given with the individual code cases in the list.a. Design-Oriented Code Cases With Title and Date of Council Approval (1) .Code Cases Applicable to Piping Design 1477-1 3-9-72 Use of 1970 Addenda of ANSI B31.7 "Nuclear Power Piping" 1506 12-13-71 Stress Intensification Factors, Section I11, Class 2 & 3 Piping 1601 11-5-73 Limits of Reinforcement for Two-thirds Area, Section III Class 1 1606 11-5-73 Stress Criteria for Section III Classes 2 and 3 Piping Subjected to Upset, Emergency, and Faulted Conditions
POSITION1. The Section III ASME Code Cases2 listed in thefollowing by number, title, and date of Council approvalare a:ceptable to the Regulatory staff for application inthe construction of components for water-cooled nu-clear power plants. Their use is acceptable within thelimitations stated in the "Inquiry"  
1614 11-5-73 Hydrostatic Testing of Piping Prior to or Following the Instal-lation of Spray Nozzles for Sec-tion I11, Classes 1, 2, and 3 Piping Systems 2 These Code Cases are listed numerically in the Appendix to this guide.(2) Code Cases Applicable to Valve Design 1533 6-14-72 Pressure Temperature Ratings of SA-35 1 Grades CF8A, CF3, and CF3M, Section III 1534 11.6-72 Overpressurization of Valves, Section III 1539 11-6-72 Metal Bellows and Metal Dia-phragm Stem Sealed Valves, Sec-tion II, Classes 1, 2, and 3.1540-1 3-3-73 Elastomer Diaphragm Valves Sec-tion i11, Classes 2 and 3 1552 12-18-72 Design by Analysis of Section III Class I Valves 1555 12-18-72 Certification of Safety Relief Valves on Liquids 1573 4-30-73 Vacuum Relief Valves, Section Ill 1574 4-30-73 Hydrostatic Test Pressure for Safety Relief Valves, Section III, Classes 1, 2, and 3 1581 6-25.73 Power-Operated Pressure Relief Valves Section 11I, Class I (3) Other Code Cases Related to Design 1470-2 12-18-72 External Pressure Charts for High-Strength Carbon Steels and for Low-Alloy Steels 1508 12-13-71 Allowable Stresses, Design Stress Intensity, and/or Yield Strength Values of Section 1, II, and VIII, Division I and 2 1536 8-14-72 Closing Seam for Electrical Pene-tration for Section III, Classes 2, 3, and MC 1575 4-30-73 Hub-to-Flange Fillet Radius for Bolted Flanges with Nut Stop 1607 11-5-73 Stress Criteria for Section III, C(lasses 2 and 3 Vessels Subjected to Upset, Emergency, and Faulted Operating Conditions b. Fabrication-Oriented.
and "Reply" sectionsof each individual code case, such Regulatory or otherrequirements as may exist, and the additional limitations recommended by the Regulatory, staff given with theindividual code cases in the list.a. Design-Oriented Code Cases With Title and Date ofCouncil Approval(1) .Code Cases Applicable to Piping Design1477-1 3-9-72 Use of 1970 Addenda of ANSIB31.7 "Nuclear Power Piping"1506 12-13-71 Stress Intensification Factors,Section I11, Class 2 & 3 Piping1601 11-5-73 Limits of Reinforcement forTwo-thirds Area, Section IIIClass 11606 11-5-73 Stress Criteria for Section IIIClasses 2 and 3 Piping Subjected to Upset, Emergency, andFaulted Conditions
1614 11-5-73 Hydrostatic Testing of PipingPrior to or Following the Instal-lation of Spray Nozzles for Sec-tion I11, Classes 1, 2, and 3Piping Systems2These Code Cases are listed numerically in the Appendix to thisguide.(2) Code Cases Applicable to Valve Design1533 6-14-72 Pressure Temperature Ratings ofSA-35 1 Grades CF8A, CF3, andCF3M, Section III1534 11.6-72 Overpressurization of Valves,Section III1539 11-6-72 Metal Bellows and Metal Dia-phragm Stem Sealed Valves, Sec-tion II, Classes 1, 2, and 3.1540-1 3-3-73 Elastomer Diaphragm Valves Sec-tion i11, Classes 2 and 31552 12-18-72 Design by Analysis of Section IIIClass I Valves1555 12-18-72 Certification of Safety ReliefValves on Liquids1573 4-30-73 Vacuum Relief Valves, SectionIll1574 4-30-73 Hydrostatic Test Pressure forSafety Relief Valves, Section III,Classes 1, 2, and 31581 6-25.73 Power-Operated Pressure ReliefValves Section 11I, Class I(3) Other Code Cases Related to Design1470-2 12-18-72 External Pressure Charts forHigh-Strength Carbon Steels andfor Low-Alloy Steels1508 12-13-71 Allowable Stresses, Design StressIntensity, and/or Yield StrengthValues of Section 1, II, and VIII,Division I and 21536 8-14-72 Closing Seam for Electrical Pene-tration for Section III, Classes 2,3, and MC1575 4-30-73 Hub-to-Flange Fillet Radius forBolted Flanges with Nut Stop1607 11-5-73 Stress Criteria for Section III,C(lasses  
2 and 3 Vessels Subjected to Upset, Emergency, andFaulted Operating Conditions b. Fabrication-Oriented.


Code Cases with Dates ofCouncil Approval(1) Code Cases Related to Welding1461 3-9-72 Electron Beam Welding, Sections1, 111, VIII1471-1 3.9-72 Vacuum Electron Beam Weldingof Tube Sheet Joints1494-1 3-3-73 Weld Procedure Qualification Tests, Section III1516-1 6-25-73 Welding of Seats in Valves forSection III Applications
Code Cases with Dates of Council Approval (1) Code Cases Related to Welding 1461 3-9-72 Electron Beam Welding, Sections 1, 111, VIII 1471-1 3.9-72 Vacuum Electron Beam Welding of Tube Sheet Joints 1494-1 3-3-73 Weld Procedure Qualification Tests, Section III 1516-1 6-25-73 Welding of Seats in Valves for Section III Applications
1554 3-3-73 Post-weld Heat Treatment ofP-number  
1554 3-3-73 Post-weld Heat Treatment of P-number 1 and P-number 12A, Subgroup 1 Longitudinal Welds, Section III Classes 1, 2, and 3 components
1 and P-number  
1580.1 11-5-73 Figure NB4233-1(a), Section III 1.84-2  
12A,Subgroup  
1 Longitudinal Welds,Section III Classes 1, 2, and 3components
1580.1 11-5-73 Figure NB4233-1(a),  
Section III1.84-2  
(2) Other Code Cases Related to Fabrication
(2) Other Code Cases Related to Fabrication
1535-2 4-30-73 Hydrostatic Testing of Section111 Class I valves1541-1 8-13.73 Hydrostatic Testing of Embed-ded Class 2 and Class 3 Piping forSection III construction
1535-2 4-30-73 Hydrostatic Testing of Section 111 Class I valves 1541-1 8-13.73 Hydrostatic Testing of Embed-ded Class 2 and Class 3 Piping for Section III construction
155I 12-18-72 Upset Heading and Roll Thread-ing ol SA-453 for High-Tempera- ture Bolting, Section III, Classes1, 2, 3, and MC1588 8-13-73 Electro-Etching of Section 111Code Symbols.c. Code Cases with Contingent Approval1355.3 3-9-72 Electroslag Welding, Section 1,I11, and VIII, Division I and 2This code case is approved subject to the condi-tions established in Regulatory Guide 1.34, "Con-trol of Electroslag Weld Properties."
155I 12-18-72 Upset Heading and Roll Thread-ing ol SA-453 for High-Tempera- ture Bolting, Section III, Classes 1, 2, 3, and MC 1588 8-13-73 Electro-Etching of Section 111 Code Symbols.c. Code Cases with Contingent Approval 1355.3 3-9-72 Electroslag Welding, Section 1, I11, and VIII, Division I and 2 This code case is approved subject to the condi-tions established in Regulatory Guide 1.34, "Con-trol of Electroslag Weld Properties."  


==D. IMPLEMENTATION==
==D. IMPLEMENTATION==
The following guidance is provided for the implemen- tation of Section III ASME Code Cases involving materials and testing.1. The effective date of this guide is July 1, 1974.2. This listing of Code Cases is applicable after theeffective date of this guide unless a particular Code Casehas been annulled by action of the ASME Council.3. Components ordered to a specific version of a CodeCase before the effective date of this guide need not bechanged because a subsequent revision to the Code Caseis listed as the approved version in this guide.4. Code Cases on the approved list may be applied tocomponents that were in process of construction priorto the effective date of this guide within the limitsspecified in the Code Case and applicable regulations orrecommended in other regulatory guides.5. Code Cases for Class 1 components which are not onthe approved list of this guide or other regulatory guides,or for which authorization by the Commission has notbeen granted, are not acceptable on a generic basis forClass I components.
The following guidance is provided for the implemen-tation of Section III ASME Code Cases involving materials and testing.1. The effective date of this guide is July 1, 1974.2. This listing of Code Cases is applicable after the effective date of this guide unless a particular Code Case has been annulled by action of the ASME Council.3. Components ordered to a specific version of a Code Case before the effective date of this guide need not be changed because a subsequent revision to the Code Case is listed as the approved version in this guide.4. Code Cases on the approved list may be applied to components that were in process of construction prior to the effective date of this guide within the limits specified in the Code Case and applicable regulations or recommended in other regulatory guides.5. Code Cases for Class 1 components which are not on the approved list of this guide or other regulatory guides, or for which authorization by the Commission has not been granted, are not acceptable on a generic basis for Class I components.


Special authorization may begranted for individual cases upon special request to theCommission.
Special authorization may be granted for individual cases upon special request to the Commission.


6. Code Cases for other Classes of components whichare not on the approved list of this guide or otherregulatory guides, or for which authorization by theCommission has not been granted, should not beconsidered acceptable on a generic basis. Specialiauthori.
6. Code Cases for other Classes of components which are not on the approved list of this guide or other regulatory guides, or for which authorization by the Commission has not been granted, should not be considered acceptable on a generic basis. Specialiauthori.


zation may be granted for individual cases upon specialrequest to the Commission.
zation may be granted for individual cases upon special request to the Commission.


13613-9-72 Socket Welds, Section IIIThis code case is approved when used in connec-tion with Section Ill, paragraph NB-3356, FilletWelds.1569 3-3-72 Design of Piping for PressureRelief Valve StationThis code case is approved subject to the condi-tions established in Regulatory Guide 1.67, "In-stallation of Overpressure Devices."
1361 3-9-72 Socket Welds, Section III This code case is approved when used in connec-tion with Section Ill, paragraph NB-3356, Fillet Welds.1569 3-3-72 Design of Piping for Pressure Relief Valve Station This code case is approved subject to the condi-tions established in Regulatory Guide 1.67, "In-stallation of Overpressure Devices." 2. Code Cases that are annulled by action of the ASME Council should be considered as deleted from the approved list as of the date of the ASME Council aclion.1.84-3 APPENDIX Numerical Listing of Code Cases 1355-3 1541-1 1361-2 1552 1461-1 1553 1470-2 1554 1.471-1 1555 1477-1 1569 1494-1 1573 1506 1574 1508 1575 1516-1 1580.1 1533 1581 1534 1588 1535.2 1601 1536 1606 1539 1607 1540-1 1614 1.84-4 APPENDIX NUMERICAL
2. Code Cases that are annulled by action of the ASMECouncil should be considered as deleted from theapproved list as of the date of the ASME Council aclion.1.84-3 APPENDIXNumerical Listing of Code Cases1355-3 1541-11361-2 15521461-1 15531470-2 15541.471-1 15551477-1 15691494-1 15731506 15741508 15751516-1 1580.11533 15811534 15881535.2 16011536 16061539 16071540-1 16141.84-4 APPENDIXNUMERICAL
LISTING OF CODE CASES 1361,2 1541-1 1623 14610i 1552 1625 147&.2 1553 1633 1471-I 1555 1635-1 1477,1 1569 1636-1 1494,1 1573 1651 1506 1574 1508 1580-1 1516,1 1581* 1533 1588 1535-2 .1606 1536 1607* 1539 1614 1540.I 1620 1.84-5}}
LISTING OF CODE CASES1361,2 1541-1 162314610i 1552 1625147&.2 1553 16331471-I 1555 1635-11477,1 1569 1636-11494,1 1573 16511506 15741508 1580-11516,1 1581* 1533 15881535-2 .16061536 1607* 1539 16141540.I 16201.84-5}}


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Revision as of 18:30, 13 July 2018

Code Case Acceptability ASME Section Iii Design and Fabrication
ML13350A351
Person / Time
Issue date: 06/30/1974
From:
US Atomic Energy Commission (AEC)
To:
References
RG-1.084
Download: ML13350A351 (5)


June 1974 0 U.S. ATOMIC ENERGY COMMISSION

REGULATORY

DIRECTORATE

OF REGULATORY

STANDARDS REGULATORY

GUIDE 1.84 CODE CASE ACCEPTABILITY

ASME SECTION III DESIGN AND FABRICATION

GUIDE

A. INTRODUCTION

Section 50.55a, "Codes and Standards," of 10 CFR Part 50, "Ucensing of Production and Utilization Facilities," requires, in part, that components of the reactor coolant pressure boundary be designed, fabri-cated, erected, and tested in accordance with the requirements for Class I components of Section III,"Nuclear Power Plant Components,"i of the American Society of Mechanical Engineeri (ASME) Boiler and Pressure Vessel Code or equivalent quality standards.

Footnote 6 to Section 50.55a states that the use of specific Code Cases may be authorized by the Commis-sion upon request pursuant to §50.55a(a)(2Xii)

which requires that proposed alternatives to the described requirements or portions thereof provide an acceptable level of quality and safety. General De--ign Criterion

1,"Quality Standards and Records," of Appendix A,"General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50 requires, in part, that structures, systems, and components important to safety be de-signed, fabricated, erected, and tested to quality stand-ards commensurate with the importance of the safety.function to be performed.

Where generally recognized codes and standards are .used, Criterion I requires that* they be identified and evaluated to determine their applicability, adequacy, and sufficiency and be supple-mented or modified as necessary to assure a quality product in keeping with the required safety function.

30, "Quality of Reactor Coolant Pressure Boundary," of the same appendix requires, in part, that components which are part of the reactor coolant pressure boundary be designed, fabricated, erected, and ICopies may be obtained from the American Society of Mechanical Engineers, United Enginecering Center, 345 East 47th Street, New York, N.Y. 10017.tested to the highest quality standards practical.

Ap-pendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part 50.requires, in part, that measures be established for the control of special processing of materials and that proper testing be performed.

This regulatory guide lists those Section III ASME Code Cases oriented to design and fabrication which are generally acceptable to the AEC Regulatory staff for implementation in the licensing of light-water-cooled nuclear power plants.

B. DISCUSSION

The Boiler and Pressure Vessel Committee of the ASME publishes documents entitled "Interpretations of the ASME Boiler and Pressure Vessel Code." t These documents, referred to as "Code Cases," explain the intent of Code rules or provide Code permission to use alternative requirements under special circumstances or with suitable precautions.

Most Code Cases are even-tually superseded by revision to the Code and then are annulled by action of the ASME Council.The Code Cases listed in this guide are limited strictly to those applicable to Section III which are oriented toward design and fabrication.

All published Code Cases in the area of design and fabrication which are applicable .to Section III of the Code and were in effect on November 5, 1973 were reviewed for inclusion in this guide. Code Cases which are not listed herein are either not endorsed or will require supplementary provisions on an individual basis to attain endorsement status.The endorsement of a Code Case by this guide constitutes acceptance of its technical position for USAEC REGULATORY

GUIDES Copies of published guides may be obtained by request indicating the divisions desired to the US. Atomic Energy Commission, Washington.

D.C, 20545.Regulatotyý

Guides are issued to desoibe and make avoilable to the public Attention:

Director of Regulatory Standards.

Comments and suggestions for methods accptable to the AEC Regulatory stoff of Implementing specific pents of improvements In these guides are encouraged and should be sent to the Secretary the Commissioe's regulations, to delineate techniques v,,ed by the staff in of the Commission, US. Atomic Energy Commission, Wtshington, D.C. 20545, evaluating specific prob;ems or postulated accidents, or to provide guidsnce to Attention:

Chief. Public Proceedings Staff.apolicants.

Regulatoty Guides are not substitutes for regulations and compliance with them is not required.

Methods end solutions different from those set out in The guides are issued in th" following ten broad divisions:

the guides will be acceptable If they provide a basis for the findings requisite to the issuance or continuance of a permit or license by the Commission, 1. Power Reachors 6. Products 2. Research end Test Resictoct

7. Transportation

3. Fuets and Materials Fecilities

8. Occupational Health Published guides will be revised periodically, as appropriate, to accommodate

4. Environmental and Siting 9. Antitrust Review comments and to reflect new Information or experience, S. Materials and Plant Protection

10, General applications not precluded by regulatory or other requirements or by the recommendations in this or other regulatory guides. Contingent endorsement is indicated in Regulatory Position C.l.c for specific cases; however* it is the responsibility of the user to make certain that no regulatory requirements are violated and that there are no conflicts with other recommended limitations resulting from Code Case usage.The acceptance or endorsement by the Regulatory staff applies only to those Code Cases or Code Case revisions with the date of "Council Approval" as shown in the Regulatory Position of this guide. Earlier or later revisions of a Code Case are not endorsed by this guide.New Code Cases as they are issued or future revisions of existing Code Cases will require evaluation by the Regulatory staff to determine if they qualify for inclusion in the approved list. Because of the continuing change in the status of Code Cases, it is planned that this guide will require periodic updating to accommodate new Code Cases and any revisions of existing Code Cases.C. REGULATORY

POSITION 1. The Section III ASME Code Cases 2 listed in the following by number, title, and date of Council approval are a:ceptable to the Regulatory staff for application in the construction of components for water-cooled nu-clear power plants. Their use is acceptable within the limitations stated in the "Inquiry" and "Reply" sections of each individual code case, such Regulatory or other requirements as may exist, and the additional limitations recommended by the Regulatory, staff given with the individual code cases in the list.a. Design-Oriented Code Cases With Title and Date of Council Approval (1) .Code Cases Applicable to Piping Design 1477-1 3-9-72 Use of 1970 Addenda of ANSI B31.7 "Nuclear Power Piping" 1506 12-13-71 Stress Intensification Factors, Section I11, Class 2 & 3 Piping 1601 11-5-73 Limits of Reinforcement for Two-thirds Area,Section III Class 1 1606 11-5-73 Stress Criteria for Section III Classes 2 and 3 Piping Subjected to Upset, Emergency, and Faulted Conditions

1614 11-5-73 Hydrostatic Testing of Piping Prior to or Following the Instal-lation of Spray Nozzles for Sec-tion I11, Classes 1, 2, and 3 Piping Systems 2 These Code Cases are listed numerically in the Appendix to this guide.(2) Code Cases Applicable to Valve Design 1533 6-14-72 Pressure Temperature Ratings of SA-35 1 Grades CF8A, CF3, and CF3M,Section III 1534 11.6-72 Overpressurization of Valves,Section III 1539 11-6-72 Metal Bellows and Metal Dia-phragm Stem Sealed Valves, Sec-tion II, Classes 1, 2, and 3.1540-1 3-3-73 Elastomer Diaphragm Valves Sec-tion i11, Classes 2 and 3 1552 12-18-72 Design by Analysis of Section III Class I Valves 1555 12-18-72 Certification of Safety Relief Valves on Liquids 1573 4-30-73 Vacuum Relief Valves, Section Ill 1574 4-30-73 Hydrostatic Test Pressure for Safety Relief Valves,Section III, Classes 1, 2, and 3 1581 6-25.73 Power-Operated Pressure Relief Valves Section 11I, Class I (3) Other Code Cases Related to Design 1470-2 12-18-72 External Pressure Charts for High-Strength Carbon Steels and for Low-Alloy Steels 1508 12-13-71 Allowable Stresses, Design Stress Intensity, and/or Yield Strength Values of Section 1, II, and VIII, Division I and 2 1536 8-14-72 Closing Seam for Electrical Pene-tration for Section III, Classes 2, 3, and MC 1575 4-30-73 Hub-to-Flange Fillet Radius for Bolted Flanges with Nut Stop 1607 11-5-73 Stress Criteria for Section III, C(lasses 2 and 3 Vessels Subjected to Upset, Emergency, and Faulted Operating Conditions b. Fabrication-Oriented.

Code Cases with Dates of Council Approval (1) Code Cases Related to Welding 1461 3-9-72 Electron Beam Welding, Sections 1, 111, VIII 1471-1 3.9-72 Vacuum Electron Beam Welding of Tube Sheet Joints 1494-1 3-3-73 Weld Procedure Qualification Tests,Section III 1516-1 6-25-73 Welding of Seats in Valves for Section III Applications

1554 3-3-73 Post-weld Heat Treatment of P-number 1 and P-number 12A, Subgroup 1 Longitudinal Welds,Section III Classes 1, 2, and 3 components

1580.1 11-5-73 Figure NB4233-1(a),Section III 1.84-2

(2) Other Code Cases Related to Fabrication

1535-2 4-30-73 Hydrostatic Testing of Section 111 Class I valves 1541-1 8-13.73 Hydrostatic Testing of Embed-ded Class 2 and Class 3 Piping for Section III construction

155I 12-18-72 Upset Heading and Roll Thread-ing ol SA-453 for High-Tempera- ture Bolting,Section III, Classes 1, 2, 3, and MC 1588 8-13-73 Electro-Etching of Section 111 Code Symbols.c. Code Cases with Contingent Approval 1355.3 3-9-72 Electroslag Welding, Section 1, I11, and VIII, Division I and 2 This code case is approved subject to the condi-tions established in Regulatory Guide 1.34, "Con-trol of Electroslag Weld Properties."

D. IMPLEMENTATION

The following guidance is provided for the implemen-tation of Section III ASME Code Cases involving materials and testing.1. The effective date of this guide is July 1, 1974.2. This listing of Code Cases is applicable after the effective date of this guide unless a particular Code Case has been annulled by action of the ASME Council.3. Components ordered to a specific version of a Code Case before the effective date of this guide need not be changed because a subsequent revision to the Code Case is listed as the approved version in this guide.4. Code Cases on the approved list may be applied to components that were in process of construction prior to the effective date of this guide within the limits specified in the Code Case and applicable regulations or recommended in other regulatory guides.5. Code Cases for Class 1 components which are not on the approved list of this guide or other regulatory guides, or for which authorization by the Commission has not been granted, are not acceptable on a generic basis for Class I components.

Special authorization may be granted for individual cases upon special request to the Commission.

6. Code Cases for other Classes of components which are not on the approved list of this guide or other regulatory guides, or for which authorization by the Commission has not been granted, should not be considered acceptable on a generic basis. Specialiauthori.

zation may be granted for individual cases upon special request to the Commission.

1361 3-9-72 Socket Welds,Section III This code case is approved when used in connec-tion with Section Ill, paragraph NB-3356, Fillet Welds.1569 3-3-72 Design of Piping for Pressure Relief Valve Station This code case is approved subject to the condi-tions established in Regulatory Guide 1.67, "In-stallation of Overpressure Devices." 2. Code Cases that are annulled by action of the ASME Council should be considered as deleted from the approved list as of the date of the ASME Council aclion.1.84-3 APPENDIX Numerical Listing of Code Cases 1355-3 1541-1 1361-2 1552 1461-1 1553 1470-2 1554 1.471-1 1555 1477-1 1569 1494-1 1573 1506 1574 1508 1575 1516-1 1580.1 1533 1581 1534 1588 1535.2 1601 1536 1606 1539 1607 1540-1 1614 1.84-4 APPENDIX NUMERICAL

LISTING OF CODE CASES 1361,2 1541-1 1623 14610i 1552 1625 147&.2 1553 1633 1471-I 1555 1635-1 1477,1 1569 1636-1 1494,1 1573 1651 1506 1574 1508 1580-1 1516,1 1581* 1533 1588 1535-2 .1606 1536 1607* 1539 1614 1540.I 1620 1.84-5