ML19221B106
| ML19221B106 | |
| Person / Time | |
|---|---|
| Issue date: | 03/31/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-75-087, NUREG-75-087-12.1, NUREG-75-87, NUREG-75-87 12.1, SRP-12.01, SRP-SRP-12.01, NUDOCS 7907120434 | |
| Download: ML19221B106 (4) | |
Text
NUREG 75/0b1 gR R e g<,
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.? i e' S U.S. NUCLEAR REGULATORY COMMISSION
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STANDARD REVIEW PLAN
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OFFICE OF NUCLEAR REACTOR REGULATION e
SECTIL. 12.1 ASS L I.1 TLAI C E IA!IC'.AL rADIA!!O. EXfCS
.S Mi AS LCW *S IS H AL1, m Y A Q ILt.Abtl M _/ I f.'.. R. S i N S I C I L I I I t 5 Pri-arf - - Miological ces
+nt br3+:h (RAC)
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i.S_ _t F_ '.Di H W a: plicant's ;ifet y analysis r"; oet (SA { } relatt J to a varin 1 tMt Iht followin ; areas of
'4 occwaticnal ra jiatic o,; cLres (CM) will v as leu as is reasen 'bly amhie. mle (A "A) an r.vi. e !:
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i'au ;m.n t v al i cy v. i ti n s ect to a signin g and cons trut t im; t'.
- lam (preliri-cary s a fe ty an alys i, r < ; ort, IT 1;) ard wi c rt' ; ec t to c crating the plant (final
.a fe ty ar.a l; si s rt,crt, TSA2) ' M the pl a 'r H ercanizatinual stractur. (PS"R).
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5 aptlic ile activittec -arried n-by the inJividaals in ra'u r en t '.av i rl i
ro, Sibility fo.
.atic TrM ectiro (PS/0),
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In+on atico Mcribir g tb i: T e: r:ntation of,olicy, organizatienal, traininj, l
9 sir;a revi< u u1Jance er r+, air n nts fro ided in Regalatory L ide "O
alatcry Cuide ".10, i nlatcry C.iJ 1.>, and in 10 CFR f art 20.
Info m aticn J urit ing alternatives, i f mu. a r<
- roposed (P5SH and u;Jate in FSSR).
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. SIG i LO'.SILE R AT I: S a.
Facility and m uip ent J'sian cn siderations (rSAo) (L not design feit;re, as u
ir Sfa Section 12.3).
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Ine Mcri; tion M 10 use of do w ass.>; ant (SAR Secticn 12.5) atd the resultant
'an-re se asscciated with varicas v.ork functions for evaluatinq tN facility e
dariign relativo to assuring that ORE will be ALARA (F5AR).
c.
The descri;-t;en of neu exrerience f r ot, past designs, fron varinas desiga guis -
lines, s,ch n ' :gulaLcry t;ide
.P., and fron c;mrating plants is med to develop igroved ruiation ; rotection desig ;> (ISAR).
d.
Infornation Mcribing the iralenentation of the design guidelines of Regalatory Guide o and t tber indus try developed design midance that include < tv ALAEA s
c ri teri a. Infcrm tier describing alternatives, if wch are trcrosed (I',A: and updato in F50 '
7907120 6 04 USNRC STANDARD REVIEW PLAN Svendsed revsee pene are per so ed for teme guideace af the Office of Nucieor Reactor Regu'etion etoff respaae bse 'or the rev'ew of apphe sticas to coristruct and openete nuclear power paonte These doeurnente oos made eve +tob4e to the public es part of the Commission a po'+c, to 6nform the nurseer enduciry and the generei pe.bhc of regutevery procedures and pahcees Stenderd review p'ene are not substreutee for regu4etary go see c,e the Comen,esion e requise+one end sempissace wteh them to not required The etende e reeew pinn sectarne are h eyed to Rev eion 2 of the Standsed Formet and C ontent of Se8ety Anseye e Reporte for Nuclear Power Ptente Not eH eeethone of the Stenderd f ormet have e corrsoporedmg rev eer plan Pubs.shed e:enderd rew*ew paene et# 6e revreed periodecepy as appetipnete to occa enmo4ete cornmente end,,,etiec, no, e,.to,me,,,,, and e=pereen e commente end suggestione foe tenpro.ement wiH be considered and should to sent t the U S Nucseer Requietory Comm eeson OW e of Nucleet Reactor Regu6etson Woohengton. D C 20bhb l 4 e)
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3.
OPEF ATIr al CON 51DERATIO;5 The techniques and nethods that will tm used for Nvelopinq detailed o;,eracional a.
plans and procedures (PSAR).
b.
The description of hcw procedures for creration ra/ in p3ct on an i interact with the plant design and on the design process (PSM).
c.
Tho use of operating plant ovperience in planning tho oporational considerations for r ew plart dr. signs (PSAR).
d.
'ho criteria and conditions under which vario;s en m uro reduction ProcedJres and techniaues are inplemented (f1AR).
Information describing the ir plenontaticn of radiatien protection progra"s, and e.
operational guidance of Regulatory Guide 8.8 and Regula tory Guide 8.10.
interma-tion describing alternatives, if such as preposed (f 5M and update in FSAP).
II AC C E PT Asr [ cpi;i p a The descriptise inforcation in th" SAR is corsidered to be cuf ficient i it reets the m i n i rN ' information
~ set ' orth in Eection 12.1 of the " Standard For^3t and Contents of e
Safety Analysis Peports for ;uclear Power PlantsJ Pevision 2.
Specific accep:ance criteria for these arer of review an as follcws:
1.
POLICY CONSIDE PATMNS Accertability wiil be based on evidence in the PSAR that a policy for assuring that ORE will be ALAPA has beer, f arr ulated, described, displajed, '
will be irplemented in accordance with Iegulatory Guide R.8, Regulatory Guide 8.10, C. I, and Pegulatory esignating and assigning a specifis individual responsibility Guide 1.8.
This includes d
and auth ty for impler enting At AP A polity. Alternative proposea policies will be evaluated on the basis c' a corpirison with the Pegulatory Guides and industry standat d5 2.
DESIGN CONSIDERATIC15 Acceptability will be based in evidence that the design rethods, approach, and interac-tions are in accordance witr Pegulatory Guide 8.S, including incorporation of: reasJres for reducing the need for raintenance; reasures to improve the accessibility to components requiring periodic raintenance or inservice inspection; reasures to reduce the production, distribution and retention of activated corrosion products throughout the primary syster, reviews of the cesign by coroetent radiation protection persono"l; instructions te designers and engineers regarding ALARA design; feedback of exrerience from operating plants and past desig',5; and continuing facility design reviews. Alternativc proposed design policies will be evaluated on the basis of a corparison with the Regulatory C41de.
<4b-3.
OPERATIONAL CONSIDERAfIONS Acceptability will be based on evicence that the applicant has a progran to develop plans and procedures in accordance with Regulatory Guide 8.8, which can incorporate the experiences obtained in facility operation into facility and equipment design and into operations planning and which will implerent specific exposure control techniques.
In the FSAR, acceptance of criteria and conditions under which various exposure
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reduction procedures and techniques are inplemented will also be based on Regulatory Guides 8.8 and 8.10, C.2.
Al ternative proposed plans and procedures,;ill be evalu3ted on th2 basis of a corparison with the Regulatory Guides.
III. REVIEW PROCEDURE 5 The infornation furnished in the SAR is reviewed fer cermlettness in acccrdance with the
" Standard Fo
.t and Content at Safety Analysis Reports for Nuclear pcwer Plants, Revision 2.
RAB reviews the management policy and the planned organizational structure to determine how the guidance given in Regulatory Cu. des 8.3, R 10 and 1 8 will te ir..nlenented or whether altarnatives have been proposed. The organization structure review includes determ inf r g if the individuals responsible for the radiation protection program are on a i
level in management that will assure implerentation of nanagsent's comitment for assuring that ORE will be ALARA. Any problems concerninq the review of organizatior.31 structure, as related to the radiation protection man 9ger will be connunicated to Ouality Assurance Branch, which has primary review responsibility for this item, in Chapter 13.
The reviewer uses ANSI N18.7-1972 for additional guidance on acceptable operating orqanizations.
The rav, ewer evaluatec information in this section to deternine if the orqaniTational strucLre p avides a rechanism for the radiation protection manager and his organizatior interacting with design groups to assure that rethods and techniques for reducing ORE will to incorporated in the design of the plant. Where the future plant radiation protection ra ager has not been selected, design review should te accomplished in accordance with the q;idance of Regulatory Guide 8.8, or a proposed alterna tive.
ihe reviewer deternines from inforration furnished by the applicant that he has incorporated previously accepted design features and has used operating experience to improve on the desiqn of the plant with reo rd to assuring that ORE will be ALARA. The reviewer rcrpares the raterial in this wction with the requireronts of 10 CFR Part 20 and the guidelines of Regulatory Guides e,B and 8.10.
Based on the review RAB may request additional inforration or rtquest the applicant to radify his submission in order to reet the accPptance criteria civen in hbsection II.
W.
EVALUATION FINDIZ5 The staff's review should verify thrit adequate and sufficient i n fo rma ti on is contained in the SAR and amendments to arrive at conclusions of the fcilowinq type, which are to be include:i in the staff's Safety Ealuation Report. The report will include a sumary of the applicant's coverage, the sr.af f's basis for review and acceptance criteria, and the findings of the review. The following 1s a Drief rep e Mtetion of the evaluation findings The a;mlicant provides a nanagement asur e that (plant name) will Le desiqned, construc ted, and opera ted r a, r wi th Req ;la tary Guides 8.8, 8.10, and 1.8.
The (title of person or group, e vn;
',n,sicist and staff) periodically reviews, t
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9 updates, and Fodifies all plant design teatures, as well as all operating and ry'ntenance features, using exposure 'ata and experience gained frca cperatinq nuclear pc'ier plants.
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This is done to a"sure that occupational exposures will be kept as low as is FrdsGnably achie/able in ccordance with Regulatory Guide 8.8 criteria.
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1 of the plant radia tion prot <?ction des iT, is to r:aintain individ;al dases and Itie cbje 6
total man-ren dnsos to fiant workers, including construction werk ers, and to rw bers of the general i ublic as low as is reasenably achievable, and to raintain individuil doses within tho limits o f 10 G R P $rt 20.
Within restricted areas all plant scartes of direct radiation and airborne radioactivo contam nation are considered in car review.
'n unre-stricted areas within the site baundary, this chapter considers radiation eritted frou sources contained in the plant facilitier and effluonts trai Tcsa facilitios.
(Utili ty) v.ill it torporate tho following facility and m;uipnent design consi & rations at (plant nare) in order to satisfy the aDove listed radiation protection design objectives (List several dosign consideraticos used.) Ttese design considerations confo.' with the p im lines of Roquiatory GJide S.h and are acceptable.
W erating and raintenance rersonnol follow 'potific plans and proced2res in or1er to a;sure that "as low as 1r reasonably achievable' <2als are ach'even in the operation of tM plant. High radiation exposure operations are carefully preplanned and carried nut by personnel well-trained in radiat'cn protection and using proper equipr ent.
During such
'3intenance activities, persernol are toni tor ed f or exposure to radia tion and con talination.
opon corpletion of major maintenanco jobs, personnel radiation exposures are evaluated in a t elj rinner and compared with predicted a n-rer exposures The resul ts are used to rai n change in future jcb procedures ard techniques The rana wrer1t taff annually reviews radiation verosure trend, to deterr,ine major changes in prohlen a ro.1s, a n d v.h i c h worker g ro u;" are accu:mlating tho highost exposures Tho staff uses those repcrts to retvrend design,.difications or changes in plant procedures These practices conforr I
with those in Regulatory Guides 8,8 and P 10 and are accentable.
P E F l _i _> W E 5_
l.
P yalatory G;ide 8.8, "Inf orma tico Relev3nt to Ensurir,g that Occupational Radiation Exposures at *,uclear Pcwor Stations Will En /s tcw As !s Peasonablj Achievable.'
J 10 LtR L rt 20, Stardards for Protection Nairs t Ra dia tion.'
3 3.
Pegulatory Guido E.10. " Operating Fhilos' phy for Paintaining Occupational Padiation Egcsures As low f.s ; racticable.
4 Pelalatory Guide 1.8, "Forsonnel Selection and iraining.
5.
Regulatory Guide 1.70, " Standard Forr.at and Centents of Safety Analysis Pecorts for
'iuclea r Cowor N an ts, Revision 2.
6.
ANSI NIH.7,
" Administrative Centrol for *;aclear Power Plents, American National Standards institute.
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) j (d Rev. I 12.1-4