Regulatory Guide 3.3: Difference between revisions

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{{Adams
{{Adams
| number = ML13350A258
| number = ML003740245
| issue date = 01/31/1973
| issue date = 03/31/1974
| title = Quality Assurance Program Requirements for Fuel Reprocessing Plants
| title = Quality Assurance Program Requirements for Fuel Reprocessing Plants & for Plutonium Processing & Fuel Fabrication Plants
| author name =  
| author name =  
| author affiliation = US Atomic Energy Commission (AEC)
| author affiliation = NRC/RES
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
Line 10: Line 10:
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = RG-3.003
| document report number = RG-3.3, Rev 1
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 1
| page count = 1
}}
}}
{{#Wiki_filter:1/8/73 U.S. ATOMIC ENERGY COMMISSION
{{#Wiki_filter:Revision 1 March 1974 U.S. ATOMIC ENERGY COMMISSION
                                          REGULATORY
                                REGULATORY
                                          DIRECTORATE OF REGULATORY                                                   STANDARDS
                                DIRECTORATE OF REGULATORY STANDARDS
                                                                                                                                                                              3UIDE
                                                                                                                            GUIDE
                                                                                        REGULATORY GUIDE 3.3 QUALITY ASSURANCE PROGRAM REQUIREMENTS
                                                                REGULATORY GUIDE 3.3 QUALITY ASSURANCE PROGRAM REQUIREMENTS
                                                                        FOR FUEL REPROCESSING PLANTS
                              FOR FUEL REPROCESSING PLANTS AND FOR PLUTONIUM
                                        PROCESSING AND FUEL FABRICATION PLANTS


==A. INTRODUCTION==
==A. INTRODUCTION==
This standard is adapltable to fuel reprocessing plailis as it .as prepared to satisfy the intent .tid atIiplif"y dIe Ap1 l.ndix It il 10 (iFR Part 50. "Qualiiv Assturance                                                    requLirCIletIts of AI[(' quality assurance i-CtIlatiOns and (riteria ti' Nuclear Po*evr Plants and F'tcl RIeprocessine                                                      prnvides gcneral requirements and guidance for It lants." eslablishes qualiiy assmuance tequireinntl11                                                  mr    establislhmient and execution of quality assuratnce theI designl. constiuctiOn.and operaitioolIfnuclear power                                                        prgtgra ins.
under the sponsorship of the American Society of Mechanical Engineers, has developed a standard wihich Appendix B, "Quality Assurance Criteria for                                includes general guidance for the establishment and Nuclear Power Plants and Fuel Reprocessing Plants," to                           execution of quality assurance programs during the
  10 CFR Part 50, "licensing of Production and                                    design, construction, and operation phases of nuclear Utilization Facilities," establishes quality assurance                           power plants. This standard was approved by the requirements for the design, construction, and operation                          American National Standards Committee N45 and its of nuclear power plant and fuel reprocessing plant                                Secretariat, and it was subsequently approved and structures, systems, and components. Paragraph 70.22(0                            designated N45.2-1971 by the American National of 10 CFR Part 70, "Special Nuclear Material," requires                          Standards Institute on October 20, 1971.


plant and Ibudl reprocessing plant structtures. systetms and conilionents. Thk regLulatory guide describes an acceptable iethod otf'coplyintg with the Comnmnission's                                                                                 
that each application for a license to possess and use special nuclear material in a plutonium processing and                                  This standard is adaptable to fuel reprocessing fuel fabrication plant contain a description of the                              plants and to plutonium processing and fuel fabrication quality assurance program to be applied to the design, fabrication, construction, testing, and operation of the plants, since it was prepared to satisfy the intent and am~lify the requirements of AEC quality assurance I
structures, systems, and components of the plant. It                              regulations and to provide general guidance for the further provides that the description include a discussion                        establishment and execution of quality assurance of how the criteria of 'Appendix B of Part 50 will be                            programs.


==C. REGULATORY POSITION==
met. Paragraph 70.23(b) of 10 CFR Part 70 provides that the Commission will approve construction of a                                                  C., REGULATORY POSITION
regulations with regard it )verall quality assurance program requirenents t'tr fuel reprocessing plants.
plutonium processing and fuel fabrication plant when it has determined that the design bases and the quality                                    The general guidelines for establishing and executing assurance program provide reasonable assurance of                                  quality assurance programs for nuclear power plants protection against natural phenomena and the                                      which are included in ANSI N45.2-1971, "Quality consequences of potential accidents noting that the                                Assurance Program Requirements for Nuclear Power criteria in Appendix B will be used in determining the                            Plants," ' may be adapted to fuel reprocessing plants adequacy of the quality assurance program. This                                    and to plutonium processing and fuel fabrication plants, regulatory guide describes a method acceptable to the                              and are generally acceptable and provide an adequate Regulatory staff of complying with the Commission's                                basis for complying with the program requirements of regulations with regard to overall quality assurance                               Appendix B to IOCFR Part 50 applicable to I uc:l program requirements for fuel reprocessing and for                                reprocessing plants and to plutonium processing and fuel plutonium processing and fuel fabrication plants.                                  fabrication plants. When adapting ANSI N45.2-1971 to fuel reprocessing plants and to plutonium processing and


Thle general requLiremen*s                                  and Muidelines for establishing and executing quality assurance programs
==B. DISCUSSION==
*                                         fuel fabrication plants, the term "fuel reprocessing and plutonium processing and fuel fabrication plants" should Subcommittee N45-3, Nuclear Quality Assurance                                be substituted as applicable wherever specific reference Standards (formerly ad hoc Committee N45-3.7), of the                              is made to the term "nuclear power plant(s)".
Cornmittee N45, Reactor Plants and Their Maintenance,                                   " Copies may be obtained from the American Society of Mechanical Engineers, United Engineering Center, 345 East 47th
*Uines indicate substantial changes from previous issue.                          Street, New York, New York 1001 7.


==B. DISCUSSION==
USAEC REGULATORY GUIDES                                   Copies of published guider may be obtained by request indicating the divons desired to the US. Atomic Energy Commission, Washington. D.C. 20545.
for nuclear power plants which are included in ANSI
                                                                                                                N45.2 -197 I. "Quality Assurance Program Requirements Stilahnimit lte N45-3. Nuclear Oiullily Assutrance for Ntclear Power Plants'                                   may be adapted to fuel Standards" ( Iornmerly ad liot Committee N45-3.7) of the reprocessing plants and a:'e generally acceptable and Anerican National Standards Inslisute. Standards provide ati adequate basis for complying with the Conitmitlce N45. React or Plants and Their Mtaintenance.


program requirements of Appendix B it) 10 CFR Part under the spoinsorship of the American Sociely of
Regfuletorv Guides We issued to describe end mike available to the public        Attention: Director of Reguletory Standards. Comments and suggestions for memhods asemPabte to the AEC Regulatory no"f of implementing specific parts of  imprtovments in t      guides ae encouraged and should be sent to the Secretary the Commlelioss's regulations, to delineate technirques used by the staff in    of the Commision. U.S. Atomic Energy Comemrission. Wahington, D.C. 20545.
                                                                                                                50. applicable to fuel reprocessing plants. When adapting Mechanical Itnoineers. has develoled a standard which ANSI N45.2-1971 to fuel reprocessing plants the term includes general requirenienis and guidance for the establishlnent and                             cxeculion of qualiiy assurance                                  fuel reprocessing plants should be substituted as applicable wherever specific reference is made to the programs during tlie design. construction; and ofpetation phases. of nuclear power plants. This standard was                                                              term nuclear power planils).
approoved by the American National Standards Committee N45 and its Secretariat. and it was subsequently approved and designated N45.2-19171 by Co'pies mal. ie otrai. cd front tihe, A et ic:                                    S ciet,0 ti the Aluerican National Standards Institute on October                                                            ,Medharlic'd E..ngirneers, Unitfled FI-nincerhig C,,.nler. 345 F~ast 471Ih Street. New Yo~rk. N.Y. 1~0017.


20, 1972.
eseluating specific problems or postulated accidents. or to provide guidanoc to  Attention: Chief, Public Proceedings Staff.


USAEC REGULATORY GUIDES                                                          Corsei of Puhhrhhedgultd'                may    .te ohtnaine  by 'eculpPt indicating the dii)iil esited ito the US. Atomic Energy Commission. Wathinigton. D.C. 20545, Regulitory Guidet            ate issued to dctribe              tnd mottle av.l-thle to tlh. pubhlc              Atltntion: Director of Rigutlaioiy Standards. Comm*nit and suggestion% for methotld acctislali to thih AEC Ail.glltlvry Sllf il milemrrontinq stoctfic P.1tt4 of                            imrpoverr, nts in the" guildes ae fnlcruif.ged And thould be sent to the Secretary the Conmmiiion's iitut.hnin                  tn  lnetie l          'theilititm tuMusedhoy the otlft ill              of the Commision, U.S. Atomic Enrtgy Commission. Wnhng*ion, D.C. 20545.
ep0plsmnt. Regulatory Gudes we not sulbstitutes for regulations and coomisanen with them is not required. Methods and solutions different from those    Out in
                                                                        1et    The guisds are issued in the following ton broed divisions:
the guider will be aemptable if they provike a bis for the findings requisite to Siw      to or Watinuance of a permit or licene by the Commission.               1. Power Reactors                         


ev.tluaitng iftctili iuinb ism (it PoM luIlt d ncit-it enint., a.t to proviefe qititdane' to                    Attelntion- Chief. Puhic P ,oce"            dings Stall, apltic.imts RegutIt.IOv Guitdf. life not slithtlluti trot      C          In wi ultOini ,tnir comtltinflcie The guldos ate is$lied in the following ten llrOat.d d              vio"ns  "
===7. Productt===
with them is not ! otluuilid. M Ihndi Fintl sotutions ififerent trOm those otel out in the tjlitýtu l wil he ,tccv*tatshlP I thy jtiorovile a a*~i. lot the flndri-os tenu#itp to the. issuance ior co timn      u.inrit of pei'muri ni I.censr liv thr Corrmmlrr              l.                  I. Poirp, Reactor,                                        6  P6iodu li
                                                                                  2. Reseacfh end Test Reactors             
                                                                                                                  2. Rpepimch andl Test Itelactor                           


===7. transooIItatmOn===
===7. Transportation===
                                                                                                                  .J            wl li la.*' -xlsi~l F.lroil.,-,'
                                                                                  3. Fuels end Materials Facilities          8. Occupetional Health Publstsefd guides will be rtad periodically.       aeppropriate to accomrnodte    4. Environmental and Siting                9. Antitrust Review coonmrts and to reflect now informntion or experience.                           5. Materials end Plent Protection         10. General}}
                                                                                                                            ..iiP                                          8   Occupationatlril Hiloallh Putili    lheit qulte,                  tiiFif ii' .
                          w -il Ii ' .I.         1 iiit iii .           **gipl qii .i
                                                                    - .i avvlIl        ' 1t i..    iintliiIit'i'                  rr 'i n ti            is SSint                    P  A    wrutii R eviepf tflutflri it.t .i-i t ta liI :t ll liiit         rtiii III    Il il'ri i                                                          n Pi.i.,t P ln ftctoion hL.antt.'rdi                              10. Ce ncrtit}}


{{RG-Nav}}
{{RG-Nav}}

Revision as of 10:15, 28 March 2020

Quality Assurance Program Requirements for Fuel Reprocessing Plants & for Plutonium Processing & Fuel Fabrication Plants
ML003740245
Person / Time
Issue date: 03/31/1974
From:
Office of Nuclear Regulatory Research
To:
References
RG-3.3, Rev 1
Download: ML003740245 (1)
v • d • e


Revision 1 March 1974 U.S. ATOMIC ENERGY COMMISSION

REGULATORY

DIRECTORATE OF REGULATORY STANDARDS

GUIDE

REGULATORY GUIDE 3.3 QUALITY ASSURANCE PROGRAM REQUIREMENTS

FOR FUEL REPROCESSING PLANTS AND FOR PLUTONIUM

PROCESSING AND FUEL FABRICATION PLANTS

A. INTRODUCTION

under the sponsorship of the American Society of Mechanical Engineers, has developed a standard wihich Appendix B, "Quality Assurance Criteria for includes general guidance for the establishment and Nuclear Power Plants and Fuel Reprocessing Plants," to execution of quality assurance programs during the

10 CFR Part 50, "licensing of Production and design, construction, and operation phases of nuclear Utilization Facilities," establishes quality assurance power plants. This standard was approved by the requirements for the design, construction, and operation American National Standards Committee N45 and its of nuclear power plant and fuel reprocessing plant Secretariat, and it was subsequently approved and structures, systems, and components. Paragraph 70.22(0 designated N45.2-1971 by the American National of 10 CFR Part 70, "Special Nuclear Material," requires Standards Institute on October 20, 1971.

that each application for a license to possess and use special nuclear material in a plutonium processing and This standard is adaptable to fuel reprocessing fuel fabrication plant contain a description of the plants and to plutonium processing and fuel fabrication quality assurance program to be applied to the design, fabrication, construction, testing, and operation of the plants, since it was prepared to satisfy the intent and am~lify the requirements of AEC quality assurance I

structures, systems, and components of the plant. It regulations and to provide general guidance for the further provides that the description include a discussion establishment and execution of quality assurance of how the criteria of 'Appendix B of Part 50 will be programs.

met. Paragraph 70.23(b) of 10 CFR Part 70 provides that the Commission will approve construction of a C., REGULATORY POSITION

plutonium processing and fuel fabrication plant when it has determined that the design bases and the quality The general guidelines for establishing and executing assurance program provide reasonable assurance of quality assurance programs for nuclear power plants protection against natural phenomena and the which are included in ANSI N45.2-1971, "Quality consequences of potential accidents noting that the Assurance Program Requirements for Nuclear Power criteria in Appendix B will be used in determining the Plants," ' may be adapted to fuel reprocessing plants adequacy of the quality assurance program. This and to plutonium processing and fuel fabrication plants, regulatory guide describes a method acceptable to the and are generally acceptable and provide an adequate Regulatory staff of complying with the Commission's basis for complying with the program requirements of regulations with regard to overall quality assurance Appendix B to IOCFR Part 50 applicable to I uc:l program requirements for fuel reprocessing and for reprocessing plants and to plutonium processing and fuel plutonium processing and fuel fabrication plants. fabrication plants. When adapting ANSI N45.2-1971 to fuel reprocessing plants and to plutonium processing and

B. DISCUSSION

  • fuel fabrication plants, the term "fuel reprocessing and plutonium processing and fuel fabrication plants" should Subcommittee N45-3, Nuclear Quality Assurance be substituted as applicable wherever specific reference Standards (formerly ad hoc Committee N45-3.7), of the is made to the term "nuclear power plant(s)".

Cornmittee N45, Reactor Plants and Their Maintenance, " Copies may be obtained from the American Society of Mechanical Engineers, United Engineering Center, 345 East 47th

  • Uines indicate substantial changes from previous issue. Street, New York, New York 1001 7.

USAEC REGULATORY GUIDES Copies of published guider may be obtained by request indicating the divons desired to the US. Atomic Energy Commission, Washington. D.C. 20545.

Regfuletorv Guides We issued to describe end mike available to the public Attention: Director of Reguletory Standards. Comments and suggestions for memhods asemPabte to the AEC Regulatory no"f of implementing specific parts of imprtovments in t guides ae encouraged and should be sent to the Secretary the Commlelioss's regulations, to delineate technirques used by the staff in of the Commision. U.S. Atomic Energy Comemrission. Wahington, D.C. 20545.

eseluating specific problems or postulated accidents. or to provide guidanoc to Attention: Chief, Public Proceedings Staff.

ep0plsmnt. Regulatory Gudes we not sulbstitutes for regulations and coomisanen with them is not required. Methods and solutions different from those Out in

1et The guisds are issued in the following ton broed divisions:

the guider will be aemptable if they provike a bis for the findings requisite to Siw to or Watinuance of a permit or licene by the Commission. 1. Power Reactors

7. Productt

2. Reseacfh end Test Reactors

7. Transportation

3. Fuels end Materials Facilities 8. Occupetional Health Publstsefd guides will be rtad periodically. aeppropriate to accomrnodte 4. Environmental and Siting 9. Antitrust Review coonmrts and to reflect now informntion or experience. 5. Materials end Plent Protection 10. General


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