Regulatory Guide 1.84

Code Case Acceptability ASME Section Iii Design and Fabrication

ML13350A351
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Issue date:	06/30/1974
From:	US Atomic Energy Commission (AEC)
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RG-1.084
Download: ML13350A351 (5)

June 19740U.S. ATOMIC ENERGY COMMISSIONREGULATORYDIRECTORATE OF REGULATORY STANDARDSREGULATORY GUIDE 1.84CODE CASE ACCEPTABILITYASME SECTION III DESIGNAND FABRICATIONGUIDEA. INTRODUCTIONSection 50.55a, "Codes and Standards," of 10 CFRPart 50, "Ucensing of Production and UtilizationFacilities," 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 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) whichrequires that proposed alternatives to the describedrequirements or portions thereof provide an acceptablelevel of quality and safety. General De--ign Criterion 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 recognizedcodes 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.30, "Quality of Reactor Coolant PressureBoundary," 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," 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.B. DISCUSSIONThe Boiler and Pressure Vessel Committee of theASME publishes documents entitled "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.All published Code Cases in the area of design andfabrication which are applicable .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 divisionsdesired 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 formethods accptable to the AEC Regulatory stoff of Implementing specific pents of improvements In these guides are encouraged and should be sent to the Secretarythe 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 compliancewith 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 tothe issuance or continuance of a permit or license by the Commission, 1. Power Reachors 6. Products2. Research end Test Resictoct 7. Transportation3. Fuets and Materials Fecilities 8. Occupational HealthPublished 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 10, General applications not precluded by regulatory or otherrequirements or by the recommendations in this or otherregulatory guides. Contingent endorsement is indicatedin 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 limitationsresulting from Code Case usage.The acceptance or endorsement by the Regulatorystaff applies only to those Code Cases or Code Caserevisions with the date of "Council Approval" 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 continuingchange in the status of Code Cases, it is planned that thisguide will require periodic updating to accommodatenew Code Cases and any revisions of existing CodeCases.C. REGULATORY 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" and "Reply" sectionsof each individual code case, such Regulatory or otherrequirements as may exist, and the additional limitationsrecommended 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 Subjectedto Upset, Emergency, andFaulted Conditions1614 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 Subjectedto Upset, Emergency, andFaulted Operating Conditionsb. 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 QualificationTests, Section III1516-1 6-25-73 Welding of Seats in Valves forSection III Applications1554 3-3-73 Post-weld Heat Treatment ofP-number 1 and P-number 12A,Subgroup 1 Longitudinal Welds,Section III Classes 1, 2, and 3components1580.1 11-5-73 Figure NB4233-1(a), Section III1.84-2 (2) Other Code Cases Related to Fabrication1535-2 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 construction155I 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."D. IMPLEMENTATIONThe following guidance is provided for the implemen-tation of Section III ASME Code Cases involvingmaterials 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. Special authorization may begranted for individual cases upon special request to theCommission.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.zation may be granted for individual cases upon specialrequest 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."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 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