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  
GUIDE DIRECTORATE  
OF REGULATORY  
OF REGULATORY  
STANDARDS REGULATORY  
STANDARDS  
REGULATORY  
GUIDE 3.3 QUALITY ASSURANCE  
GUIDE 3.3 QUALITY ASSURANCE  
PROGRAM REQUIREMENTS
PROGRAM REQUIREMENTS  
FOR FUEL REPROCESSING  
FOR FUEL REPROCESSING  
PLANTS 3UIDE
PLANTS AND FOR PLUTONIUM
PROCESSING
AND FUEL FABRICATION
PLANTS


==A. INTRODUCTION==
==A. INTRODUCTION==
Ap 1 l.ndix It il 10 (iFR Part 50. "Qualiiv Assturance (riteria ti' Nuclear Plants and F'tcl RIeprocessine I t lants." eslablishes qualiiy assmuance tequireinntl11 mr theI designl. constiuctiO
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.


====n. and operaitioolI ====
Paragraph
fnuclear power plant and Ibudl reprocessing plant structtures.
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 me


systetms and conilionents.
====t. 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.


Thk regLulatory guide describes an acceptable iethod otf 'coplyintg with the Comnmnission's regulations with regard it )verall quality assurance program requirenents t'tr fuel reprocessing 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.


==B. DISCUSSION==
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.
Stilahnimit lte N45-3. Nuclear Oiullily Assutrance Standards" ( Iornmerly ad liot Committee N45-3.7) of the Anerican National Standards Inslisute.


Standards Conitmitlce N45. React or Plants and Their Mtaintenance.
U.S. Atomic Energy Comemrission.


under the spoinsorship of the American Sociely of Mechanical Itnoineers.
Wahington, D.C. 20545.  eseluating specific problems or postulated accidents.


has develoled a standard which includes general requirenienis and guidance for the establishlnent and cxeculion of qualiiy assurance programs during tlie design. construction;
or to provide guidanoc to Attention:
and ofpetation phases. of nuclear power plants. This standard was approoved by the American National Standards Committee N45 and its Secretariat.
Chief, Public Proceedings Staff. ep0plsmnt.


and it was subsequently approved and designated N45.2-19171 by the Aluerican National Standards Institute on October 20, 1972.This standard is adapltable to fuel reprocessing plailis as it .as prepared to satisfy the intent .tid atIiplif"y dIe requLirCIletIts of AI[(' quality assurance i-CtIlatiOns and prnvides gcneral requirements and guidance for establislhmient and execution of quality assuratnce prgtgra ins.C. REGULATORY
Regulatory Gudes we not sulbstitutes for regulations and coomisanen with them is not required.
POSITION Thle general and Muidelines for establishing and executing quality assurance programs for nuclear power plants which are included in ANSI N45.2 -197 I. "Quality Assurance Program Requirements for Ntclear Power Plants' may be adapted to fuel reprocessing plants and a:'e generally acceptable and provide ati adequate basis for complying with the program requirements of Appendix B it) 10 CFR Part 50. applicable to fuel reprocessing plants. When adapting ANSI N45.2-1971 to fuel reprocessing plants the term fuel reprocessing plants should be substituted as applicable wherever specific reference is made to the term nuclear power planils).Co'pies mal. ie otrai. cd front tihe, A et ic: S ciet,0 ti ,Medharlic'd E..ngirneers, Unitfled FI-nincerhig C,,.nler.


345 F~ast 471Ih Street. New Yo~rk. N.Y. 1~001
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.


===7. USAEC REGULATORY ===
1. Power Reactors 7. Productt 2. Reseacfh end Test Reactors
GUIDES Corsei of Puhhrhhed gultd' may .te ohtnaine by 'eculpPt indicating the dii)iil esited ito the US. Atomic Energy Commission.


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


D.C. 20545, Regulitory Guidet ate issued to dctribe tnd mottle av.l-thle to tlh. pubhlc Atltntion:
aeppropriate to accomrnodte
Director of Rigutlaioiy Standards. and suggestion%
4. Environmental and Siting 9. Antitrust Review coonmrts and to reflect now informntion or experience.
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 l tn lnetie 'theilititm tuMused hoy the otlft ill of the Commision, U.S. Atomic Enrtgy Commission. D.C. 20545.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 slithtllut i trot C In wi ultOini ,tnir comtltinflcie with them is not ! otluuilid.


M Ihndi Fintl sotutions ififerent trOm those otel out in The guldos ate is$lied in the following ten llrOat.d d vio"ns " the tjlitýtu l wil he I thy jtio rovile a 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. Rpepimch andl Test Itelactor
5. Materials end Plent Protection
7. transooIItatmOn.J .iiP wl .li -xlsi~l F.lroil.,-,'
10. General I}}
8 Occupationatlril Hiloallh Putili lheit qulte, w -il Ii ' ii' tii f 1 iiit iii ..i **gipl qii .i ' i.. .I. .Fi iintliiIit'i'
-avvlIl 1t rr 'i n ti Sint S is P A wr uti i R eviepf tflutflri it.t .i-i t t ta li : I t ll liiit rtiii III Il il'ri i hL. antt.'rdi n Pi.i.,t P l n ftctoion 10. Ce ncrtit}}


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

Revision as of 09:35, 14 July 2019

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 me

t. 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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