Regulatory Guide 3.3: Difference between revisions

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


==A. INTRODUCTION==
==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
Ap1 l.ndix It il 10 (iFR Part 50. "Qualiiv Assturance (riteria ti'
  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.
Nuclear Po*evr Plants and F'tcl RIeprocessine Itlants." eslablishes qualiiy assmuance tequireinntl11 mr theI designl.


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
constiuctiOn.and operaitioolI fnuclear power plant and Ibudl reprocessing plant structtures. systetms and conilionents.
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
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.
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==
==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)".
Stilahnimit lte N45-3. Nuclear Oiullily Assutrance Standards" ( Iornmerly ad liot Committee N45-3.7) of the Anerican National Standards Inslisute.
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.
Standards Conitmitlce N45. React or Plants and Their Mtaintenance.


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.
under the spoinsorship of the American Sociely of Mechanical Itnoineers. has develoled a standard which includes general requirenienis and guidance for the establishlnent and cxeculion of qualiiy assurance programs during tlie design. construction; and ofpetation phases. of nuclear power plants. This standard was approoved by the American National Standards Committee N45 and its Secretariat.


eseluating specific problems or postulated accidents. or to provide guidanoc to  Attention: Chief, Public Proceedings Staff.
and it was subsequently approved and designated N45.2-19171 by the Aluerican National Standards Institute on October
20, 1972.


ep0plsmnt. Regulatory Gudes we not sulbstitutes for regulations and coomisanen with them is not required. Methods and solutions different from those    Out in
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.
                                                                        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===
==C. REGULATORY POSITION==
                                                                                  2. Reseacfh end Test Reactors             
Thle general requLiremen*s 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. 1~0017.


===7. Transportation===
USAEC REGULATORY GUIDES
                                                                                  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}}
Corsei of Puhhrhhed gultd'
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 iitu
 
====t. hnin l ====
tn lnetie
'theilititm tuMused hoy the otlft ill of the Commision, U.S. Atomic Enrtgy Commission. Wnhng*ion, 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
,tccv*tatshlP I thy jtio rovile 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. Rpepimch andl Test Itelactor
 
===7. transooIItatmOn===
.J
.iiP
wl
.
la.*'
li
-xlsi~l F.lroil.,-,'
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 00:17, 11 January 2025

Quality Assurance Program Requirements for Fuel Reprocessing Plants
ML13350A258
Person / Time
Issue date: 01/31/1973
From:
US Atomic Energy Commission (AEC)
To:
References
RG-3.003
Download: ML13350A258 (1)
v • d • e


1/8/73 U.S. ATOMIC ENERGY COMMISSION

REGULATORY

DIRECTORATE OF REGULATORY STANDARDS

REGULATORY GUIDE 3.3 QUALITY ASSURANCE PROGRAM REQUIREMENTS

FOR FUEL REPROCESSING PLANTS

3UIDE

A. INTRODUCTION

Ap1 l.ndix It il 10 (iFR Part 50. "Qualiiv Assturance (riteria ti'

Nuclear Po*evr Plants and F'tcl RIeprocessine Itlants." eslablishes qualiiy assmuance tequireinntl11 mr theI designl.

constiuctiOn.and operaitioolI fnuclear power plant and Ibudl reprocessing plant structtures. systetms and conilionents.

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

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.

under the spoinsorship of the American Sociely of Mechanical Itnoineers. has develoled a standard which includes general requirenienis and guidance for the establishlnent and cxeculion of qualiiy assurance programs during tlie design. construction; and ofpetation phases. of nuclear power plants. This standard was approoved by the American National Standards Committee N45 and its Secretariat.

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 POSITION

Thle general requLiremen*s and Muidelines for establishing and executing quality assurance programs for nuclear power plants which are included in ANSI

N45.2 -197Property "ANSI code" (as page type) with input value "ANSI</br></br>N45.2 -197" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process. 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. 1~0017.

USAEC REGULATORY GUIDES

Corsei of Puhhrhhed gultd'

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 iitu

t. hnin l

tn lnetie

'theilititm tuMused hoy the otlft ill of the Commision, U.S. Atomic Enrtgy Commission. Wnhng*ion, 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

,tccv*tatshlP I thy jtio rovile 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. Rpepimch andl Test Itelactor

7. transooIItatmOn

.J

.iiP

wl

.

la.*'

li

-xlsi~l F.lroil.,-,'

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


Retrieved from "https://kanterella.com/w/index.php?title=Regulatory_Guide_3.3&oldid=5218152"