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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 GUIDE
                                          DIRECTORATE OF REGULATORY                                                   STANDARDS
DIRECTORATE OF REGULATORY STANDARDS  
                                                                                                                                                                              3UIDE
REGULATORY GUIDE 3.3 QUALITY ASSURANCE PROGRAM REQUIREMENTS  
                                                                                        REGULATORY GUIDE 3.3 QUALITY ASSURANCE PROGRAM REQUIREMENTS
FOR FUEL REPROCESSING PLANTS AND FOR PLUTONIUM
                                                                        FOR FUEL REPROCESSING PLANTS
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.
Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to  
10 CFR Part
50,
"licensing of Production and Utilization Facilities,"
establishes quality assurance requirements for the design, construction, and operation of nuclear power plant and fuel reprocessing plant structures, systems, and components. Paragraph 70.22(0
of 10 CFR Part 70, "Special Nuclear Material," requires that each application for a license to possess and use special nuclear material in a plutonium processing and fuel fabrication plant contain a description of the quality assurance program to be applied to the design, fabrication, construction, testing, and operation of the structures, systems, and components of the plant. It further provides that the description include a discussion of how the criteria of 'Appendix B of Part 50 will be met. Paragraph 70.23(b) of 10 CFR Part 70 provides that the Commission will approve construction of a plutonium processing and fuel fabrication plant when it has determined that the design bases and the quality assurance program provide reasonable assurance of protection against natural phenomena and the consequences of potential accidents noting that the criteria in Appendix B will be used in determining the adequacy of the quality assurance program. This regulatory guide describes a method acceptable to the Regulatory staff of complying with the Commission's regulations with regard to overall quality assurance program requirements for fuel reprocessing and for plutonium processing and fuel fabrication plants.


plant and Ibudl reprocessing plant structtures. systetms and conilionents. Thk regLulatory guide describes an acceptable iethod otf'coplyintg with the Comnmnission's                                                                                
==B. DISCUSSION==
*
Subcommittee N45-3, Nuclear Quality Assurance Standards (formerly ad hoc Committee N45-3.7), of the Cornmittee N45, Reactor Plants and Their Maintenance,
*Uines indicate substantial changes from previous issue.
 
under the sponsorship of the American Society of Mechanical Engineers, has developed a standard wihich includes general guidance for the establishment and execution of quality assurance programs during the design, construction, and operation phases of nuclear power plants. This standard was approved by the American National Standards Committee N45 and its Secretariat, and it was subsequently approved and designated N45.2-1971 by the American National Standards Institute on October 20, 1971.
 
This standard is adaptable to fuel reprocessing plants and to plutonium processing and fuel fabrication plants, since it was prepared to satisfy the intent and am~lify the requirements of AEC quality assurance regulations and to provide general guidance for the establishment and execution of quality assurance programs.
 
C., REGULATORY POSITION
The general guidelines for establishing and executing quality assurance programs for nuclear power plants which are included in ANSI N45.2-1971,
"Quality Assurance Program Requirements for Nuclear Power Plants," ' may be adapted to fuel reprocessing plants and to plutonium processing and fuel fabrication plants, and are generally acceptable and provide an adequate basis for complying with the program requirements of Appendix B to IOCFR Part 50 applicable to I uc:l reprocessing plants and to plutonium processing and fuel fabrication plants. When adapting ANSI N45.2-1971 to fuel reprocessing plants and to plutonium processing and fuel fabrication plants, the term "fuel reprocessing and plutonium processing and fuel fabrication plants" should be substituted as applicable wherever specific reference is made to the term "nuclear power plant(s)". 
" Copies may be obtained from the American Society of Mechanical Engineers, United Engineering Center, 345 East 47th Street, New York, New York 1001 7.


==C. REGULATORY POSITION==
USAEC REGULATORY GUIDES
regulations with regard it )verall quality assurance program requirenents t'tr fuel reprocessing plants.
Copies of published guider may be obtained by request indicating the divons desired to the US. Atomic Energy Commission, Washington. D.C. 20545.


Thle general requLiremen*s                                  and Muidelines for establishing and executing quality assurance programs
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.


==B. DISCUSSION==
eseluating specific problems or postulated accidents. or to provide guidanoc to Attention: Chief, Public Proceedings Staff.
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.
ep0plsmnt. Regulatory Gudes we not sulbstitutes for regulations and coomisanen with them is not required. Methods and solutions different from those
1et Out in 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.


program requirements of Appendix B it) 10 CFR Part under the spoinsorship of the American Sociely of
===1. Power Reactors ===
                                                                                                                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.
===7. Productt ===
2. Reseacfh end Test Reactors


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.
===7. Transportation ===
3. Fuels end Materials Facilities
8. Occupetional Health Publstsefd guides will be rtad periodically.


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  "
aeppropriate to accomrnodte
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
4. Environmental and Siting
                                                                                                                  2. Rpepimch andl Test Itelactor                           
9. Antitrust Review coonmrts and to reflect now informntion or experience.


===7. transooIItatmOn===
5. Materials end Plent Protection
                                                                                                                  .J            wl li la.*' -xlsi~l F.lroil.,-,'
10. General I}}
                                                                                                                            ..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}}
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Latest revision as of 02:06, 17 January 2025

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 GUIDE

DIRECTORATE OF REGULATORY STANDARDS

REGULATORY GUIDE 3.3 QUALITY ASSURANCE PROGRAM REQUIREMENTS

FOR FUEL REPROCESSING PLANTS AND FOR PLUTONIUM

PROCESSING AND FUEL FABRICATION PLANTS

A. INTRODUCTION

Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to

10 CFR Part

50,

"licensing of Production and Utilization Facilities,"

establishes quality assurance requirements for the design, construction, and operation of nuclear power plant and fuel reprocessing plant structures, systems, and components. Paragraph 70.22(0

of 10 CFR Part 70, "Special Nuclear Material," requires that each application for a license to possess and use special nuclear material in a plutonium processing and fuel fabrication plant contain a description of the quality assurance program to be applied to the design, fabrication, construction, testing, and operation of the structures, systems, and components of the plant. It further provides that the description include a discussion of how the criteria of 'Appendix B of Part 50 will be met. Paragraph 70.23(b) of 10 CFR Part 70 provides that the Commission will approve construction of a plutonium processing and fuel fabrication plant when it has determined that the design bases and the quality assurance program provide reasonable assurance of protection against natural phenomena and the consequences of potential accidents noting that the criteria in Appendix B will be used in determining the adequacy of the quality assurance program. This regulatory guide describes a method acceptable to the Regulatory staff of complying with the Commission's regulations with regard to overall quality assurance program requirements for fuel reprocessing and for plutonium processing and fuel fabrication plants.

B. DISCUSSION

Subcommittee N45-3, Nuclear Quality Assurance Standards (formerly ad hoc Committee N45-3.7), of the Cornmittee N45, Reactor Plants and Their Maintenance,

  • Uines indicate substantial changes from previous issue.

under the sponsorship of the American Society of Mechanical Engineers, has developed a standard wihich includes general guidance for the establishment and execution of quality assurance programs during the design, construction, and operation phases of nuclear power plants. This standard was approved by the American National Standards Committee N45 and its Secretariat, and it was subsequently approved and designated N45.2-1971 by the American National Standards Institute on October 20, 1971.

This standard is adaptable to fuel reprocessing plants and to plutonium processing and fuel fabrication plants, since it was prepared to satisfy the intent and am~lify the requirements of AEC quality assurance regulations and to provide general guidance for the establishment and execution of quality assurance programs.

C., REGULATORY POSITION

The general guidelines for establishing and executing quality assurance programs for nuclear power plants which are included in ANSI N45.2-1971,

"Quality Assurance Program Requirements for Nuclear Power Plants," ' may be adapted to fuel reprocessing plants and to plutonium processing and fuel fabrication plants, and are generally acceptable and provide an adequate basis for complying with the program requirements of Appendix B to IOCFR Part 50 applicable to I uc:l reprocessing plants and to plutonium processing and fuel fabrication plants. When adapting ANSI N45.2-1971 to fuel reprocessing plants and to plutonium processing and fuel fabrication plants, the term "fuel reprocessing and plutonium processing and fuel fabrication plants" should be substituted as applicable wherever specific reference is made to the term "nuclear power plant(s)".

" Copies may be obtained from the American Society of Mechanical Engineers, United Engineering Center, 345 East 47th 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

1et Out in 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 I


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