ML20132E095
| ML20132E095 | |
| Person / Time | |
|---|---|
| Issue date: | 12/17/1996 |
| From: | Miraglia F NRC (Affiliation Not Assigned) |
| To: | Gardiner W AFFILIATION NOT ASSIGNED |
| References | |
| NUDOCS 9612230036 | |
| Download: ML20132E095 (6) | |
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UNITED STATES dd j
NUCLEAR REGULATORY COMMISSION t
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't WASHINGTON, D.C. 205554 m 1 December 17, 1996 Mr. William Gardiner 4726 Alvin Dark #2 Baton Rouge, LA 70820
Dear Mr. Gardiner:
Thank you for your letter of October 22, 1996, to Chairman Jackson of the U.S.
Nuclear Regulatory Comission (NRC), in which you discussed the advantages of standardization of nuclear power plants and better utilization of America's resources.
The Comission recognizes the benefits that could be obtained from standard-ization.
In its Policy Statement on Nuclear Power Plant Standardization published in the Federal Reaister on September 15, 1987, the Commission expressed its views as follows:
"The Nuclear Regulatory Comission believes that standardization of nuclear power plants is an important initistive that can significantly enhance the safety, reliability, and availability of nuclear plants." The full Commission Policy Statement is enclosed for your informa-tion.
The Policy Statement was intended to encourage standardization and to provide information concerning the Commission's efforts to develop a regulatory framework for certifying standardized designs. The NRC published 10 CFR Part 52 in 1989.
In the statement of consideration published with Part 52, the Commission indicated that it has long sought nuclear power standardization and the enhanced safety and licensing reform that standardization could make possible. However, the NRC can only encourage standardization, it cannot require it.
In addition, the NRC cannot restrict the number of standard designs. No company can be denied the opportunity to apply for approval of its design, provided the design meets NRC regulatory requirements.
The Commission recent'. approved the certification for two designs, the Advanced Boiling-Water Reactor and the ABB-Combustion Engineering System 80+,
which will be published in the Federal Reaister in a few months.
In addition, N,
the NRC is currently reviewing another design incorporating passive features for mitigation of accidents, the Westinghouse AP600.
Certification of this design is at least 2 years away.
Both NRC and the nuclear industry recognize that the current period is a very r
critical ore for nuclear power.
Licensees of nuclear power plants are under t
intense pressure to reduce their operating and maintenance costs. Although g
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. The Nuclear Reguletory Commission Important to the implementati:n af standardhation and to state the
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/ower Plant Standardiantion believes that standardization of nuclear Comm!alon's intent to develop Aosucr. Nuclear Regulatory -
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-. k safety, reliabWty and availability of. "*To mn b Comminion's intent AcTec polley statement.
. auc;earplants.The Commissionintends
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,.,to make resources available on a cu -v:ne Nuae.Regew,y.
'afla g,i'"e a
riority basis to facitiisie e af-nce Commission is issuing a revised policy -
to mduce complehd hin erstem design certi$ cation process for statement on the standardhation of the regulat dices M.N. mendab #2p e But **r pow" and O to T tE process. Apse Code ofplant des and for the licensing nur' ear power plant designs. The policy
- 10. Part to o etaternent encourages the use of Fedwal Regulations (10 CFR par nyiewe o ap standard plant designs and pmvfdes establish various opdons and
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thwe certiBe[descanons afmacing inforsytian concerning the certincedon
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procedures for the a[esigns. A provision.
Td" approach to mactw duism proval of af plan 1 designs that are essentially standardhed plant complete in scope and level of detall..
for Commlulon a val of a mference - oonstruction, and opersdon has led to -
The intent of these actions are to designin a rulem roceedingis
., an operating reactor population of great improve the !! censing procen and to included in Appendix.Ris has been.
variability and diversity, even among reduce the complexity and uncertainty -
termed Reference System Design reactors trom the same vendor.This in,the story process for Certi$ cation andis the focus of the variability is introduced when utilities stan ed plants. '
Commission's standardization and designers incorporate customs Sats: Effective on September 15.19s7
%!s policy statement revises [licy.
. featums into their designs; when varying
- Wukshop to be held October 20.1987 Standardiuton polfey Statement of conseuc6en pac 6ca an use& and i
ADOaES8 tar Submit comments to:%e 1978 (August 31.1978: 43 FR 3a854)..
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an D:cketing and Service Branch. A public mmiss o effo t e top a tranger of experience from one reactor j
w:rkshe will be held on October 20' certincation of plant des which:
to another. in technical speciscations. in l,
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.Bethesda. Maryland.
- Cent plant design, construe'6on.
The Commission believes that the use j
os. JRTHen mponuatioN oottfACT:
Lerry N. Wilson.OfEce of Nuclear and quality assurance programa:
of certi$ed standardized designs can 4
- Satisfy regulatory mquirements beneSt the public health and safety by l
Tegulatory Research. U.S. Nudear before construction begins: and concentrating resources on speciSc j
Regulatory Commission. Washington.
- Can be relemaced forindividual design approaches without s j
DC 20555. telephone (301) 492-4727.
plant applicationa..
. lagenuity; by stimulating stan d
- . suppi.saserrAmy mPonssatiote Use of certi5ed reference designsin programs of construction practice.
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futum license app!! cations abould quality assurance,and personnel enhance plant safety. inwease the training: and by fostning more effective The NRC staff wiD conduct a ef5ciency of the NRC review process, maintenance and improved operation.
workshop to inform the public of staff
' and nduce complexity and uncertainty Standardization should neultin
. efforts to develop an implementing in the regulatory process. A regulatory significant economies of scale in ruhmak2'ng on standardization and to framework which provides for learning and sharing operating provide a forum for public discussion of certi$ cation of afemace designs by experience. in maintaining qualiBed the revised polley statement and means of rulemaking will alleviate the vendor support, and in maintaining an wievantissues that need to be need to aconsider design issues in adequate inventory oflong lead. time, addressed in the rulemaking packase.-
individual!! censing proceedings on high cost spare parts that can be shared ne workshop will be held on October. ' futum 11conse applications which by a number of units.These concepts 20.1987 at the Hyatt Regency Dethuda.
nferisce the certified designs. Areas are embodied in fonisn experience with One Bethesda Metro Centn. Bethesda.
included within the scope of the the standardisation of nuclear power Maryland 20e14 in the Cabinet Room, nference system design certi8 cation plant design, contruction, and o ration.
De workshop will start at 9:00 a.m.no rulemaking would mquire no further Standardization is expected to NRC staff will present an overview of review by the staf the Advisory improve the safety puformance of the revised policy statement and the Committee on Reactor Safeguards
. future plants. Standardiastion will allow proposed rulemaking package at the (ACRS). or the hearing boards.
for a more expeditious and efBcient workshop.Those members of the public The Commission's primary objectives nyiew process and a more thorough who wish to make a presentation at the in issuing a policy statement on nuclear understanding of the designs by the workshop should notify the contact power plant standardization are industry and the NRC sta!!. In strongly Ned above so that they can be added thrufold:
endorsing the concept of t agenda. Anyone who wishes to
- To encours'ge the use of standard standardization. the Commission
'urther comroents to the record or plant designs in future license acknowledges that there can be cannot attend the workshop should applications in order to enhance slant drawbacks. %e most signif! cant is that
' cend written comments to the Secretary safety. improve the efficiency and speciSc problems may potentially afect i
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- ! arse number af react:ra. H: wever, on accomplished under its existing In the re'f;rence system design 6alance, the Comrnfssfon believes that statut ry authrity. In additirn, thers la certificati n process, the final decision te enhanced safe cf reactrr cperatin a need for regulations to implement the wiU be made by the Commissten itself 5-~!d far outwei any disadvantages.
Commission's standardization polic fo!!owing review by the ACRS. the l
unisalon p cy for plant safetyla more offsetively. For thase reasons,ythe -tasuance of a final design approval by Jated in its Policy Statement on -
Commission is divoloping proposed the staff, and the completion of a rule-
.ty Coa!s (August 4.19% 51 m regulations that will addresa licensing making proceeding. We reference s0H. Aupat 21.19% 31 m 300:8).no reform and standardization. With regard eystem concept means that an entirs 5:sodardization Policy also la cens! stent to etandardizadon, the proposed rules nuclear power plant de:fp or a major i
, arith the standardized plant provisions - will p'rovide a ngulatory framework for portion of the design is seceptable for j
. af the Commission's complementary Commission certScation of standard incorporation by reference in individual severs Accident Policy Statement ~
'das!gna by rulemaldng. as set forth in. '!! cense applications.ne design (August 8.19% 50 m 32158).Many of,
paras:sph 7 of Appendix 0 to to CFR certi$catfon concept focuses on the te desirable safety charsctedatica Part 60. ne proposed rules wiD addtna certi$ cation of a reference eystem 1
Ested in the Advanced Reactor Policy - the foUowing subjects: Relationship of design through rufemaking. as provided State lent Quly 8.19% 51 m 24643) are the new regulatory framework to the for by Appendix 0 to to CFR Part 50. ne squsUy desirable for evolutionary light existing provisions of Appendices M.N.
ru!es beina developed to implement this erater ras ctor standardized ;!esigna.
and O to Part 50 filing requiremantar polley wilf address the criteria and ne Commission believes that contents of applications; design procedures for issuance and renewal of Congresa should promote nuclear safety certification and renewal fees; dest'3n design certifications. as weU as the by pursu!ng legislative initiatives to certifica tion rulemaking procedures: -
. duration of the certification and krther encoursge the atandardization nferral of applicatfons to the Advisory renewals. We certiBed design must be soncept. De proposed Nuclear Power Committee on Reactor Safeguards used and reded upon by the staf the Flant Standardization and Ucensing Act (ACRS); duration and renewal of design ACRS. the hearing boards and the a
of1987.which the Commission certifications; changes to certi$ed Com:rlssion in their conalderstion of brwarded to Congress in January of this standard des!gns: and provialona for applications that reference the certified
, includes the following three plant speciSc variances.no design.Hs issus of relitigation of issues fative proposafs:
Commission's genara! spproach to considered and decided in the design
- lutance of a combined
- standard design certi$ cation under its certi$catice rulemaking wiU be mastruction permit and opersting existing rules la outlined In this policT addressed in the proposed rules.
Icense:
statement.ne lasues important to ne Comm!ssion believes that several
- !aenance of a site permit prior to execution of the Commisalon's b'**$
U' alized in thi' cbmission of an application for a standardization polley will be addressed,j gch wil!not oby enhance safety but ch,"n
' bcomb ed more fully in the proposed rules.
should also contribute added stability t
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Statement of Polley on Nuc! ass Power and predictabluty to the regulatory Jeance of a facility design P! ant Standardization procasa.He rulemaking will cartify the nal(Reference System Design De purpose of this standardisation-acceptability of the desip.He certined t
U rovide the regulatory desip willbe referenced in the urtiIlcation) prior to rubmission of an bcy la to for reference system design ework applicade for a ConstacHe Pumit or appilcation for a censtruction per=it or
. cmbined construction permit and certi$ cation of nuclear power plant Opustm, gUce,nse.ne rulemaking to sperating license, designs which are assentially complete obtain the des:gn certification will cover ne Commission believes that these in both scope and level of detail: cover the criteria necessary for design and yJevir.g the full benefits ofs!stive changes an important to p! ant design, construction. and quality construction of a plant; the quality ac assurance programa: satisfy regulatory assurance program: and whatever tests.
standArdisa tion. He One-s tep IjCensing requirements before Construction begins; analyses, and inspection criteria are pocets would give !!censees greater and can be referenced in individual necessary to assure that the plant is teurance thatif the facilityis
' plant applications.
built within the certified design enstructed in accordance with the ne reference system destps, at least specificadona.
hims of the application / permit.it wi!!
teitia!!y. an expected to be evolutioda ne Commission expects to be permitted to operate once of axisting proven LWR designs.
Implement the foUowing policies with cnstmedon la complete. De issuance Detailed information consisting of regard to design certification review. An af site permits and facility design design and procurement speciScations, applicant for a design certification must spprovals,in advance of specific performance requirements, and fint obtain a Final De:Ign Approval applies dons for their use, would aUow acceptance and inspection requirements (FDA) pursuant to Appendix 0 to Part subsequent facility applications to will be substituted for name plate data.
50.1f the applicant intends to seek a tference the permits and/or approvala For those systems, structures and -
design certi$ cation the FDA application without further regulatory actjon unless coc:ponent designs which represent must indicate that intent. As set forth in tere is a substantial resson not to do sipi$ cant deviations from previously.
Appendix 0, the FDA application must so. This process would also facilitate approved LWR designs, prototype include information on scope and design tarly identi$ cation and resolution of sits testing and/or empirical information detail which is essentially equivalent to and destp !ssues after affording an may also be required. Advanced design that required by 10 CFR 50.34(b), as weU 4
spportunity for pub!!c participation, concepts should be developed according as any other Information customarily ne Commission continues to believe to the guidelines of the Advanced required by the staff to perform a Final kat nuclear standardization and Reactor policy Statement. When an Safety Analysis Report review.in
- I, kensing legislatJon should be enacted.
advanced design concept is sufficiently addition. it must adhess the foUowing
,s Commissionrecognizes however.
meture, e g. through comprehensive, four licensing criter;. for new plant j
such of its legislative proposal with prototypical testing an application for desIps set forth in the Cornmission's
- t to standardization could be des!gn cartification could be made.
Severe Accident policy Statement:
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. gghamVETQTcimpitnoe cm the des er defin s a set of alte'?1 vadances in 1snited circumstances et.
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the rquirements cf the curnnt envel
- ' Cn,mmini:n regulati:ns, including the rainfa, a paraneters (selsmic events. - the reques? of the facilitylice see. - -
ood, etc. which are need in -
nree htile Island requirements for new the design cf the p)lant. ness All applica&ns f:rlicenus and plants as reft:cted in the constmeti:n pe mit rule.20 CR 50.34[ -
parameters tsuaUy are selected to approvals f r stendard designs are at envelop a large portion of the potential present subject to the fees and the fee I
n of allapplicable Unresolved certified by the Commission..
370. ne Commisafor. has autherfred a -
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I )l nonstration of te cal attes in the U.S. Once the destp la recovery rates Idercified in to CFR Part.
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.ssues and the medium. and high. conformance of actualsites with the revision of to CFR Part 17p to' include a'
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pi....sy Generic Safety issues, including established site envelope must be new provision for the reference system ~
o special focus on ensuring the demonstrated by the applicant and dulp ceruficaUon pmcess.nis nliability of decay heat removal.
venned-by the staff at the time an actual. revision would permit the phased. ' '
systems and the rehability of both AC plant application la reviewed.Other
- recovery of desip certincation costa i
cnd DC electrical supply systems-
[3) Compledon of a probabilisuc risk features of the design which ars.
through collection of fees from the supply, emergency pre (par,edness plana, dependent o assessment (PRA) and consideretion of I
des!p is referenced. lf the desip is'not the severe accident vulnerabilities that etc.) are also reviewed for acce referenced or if all the costs are not the FRA exposes. along with the insights and compatibility with the pre.ptability recovered within ten years. the holder of that it may add to the assurance that approved / certified desip at the time of the' des!gn certi$ cation will be there is no undue risk to public health an actual applicauon.
responsible for any amounts still due at and safety; and Currently. NRC. initiated changes to-
"the and of the ten yearperiod.'
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(4) Completion of st.!Ireview of the the desi certificauen rule will not be Although the Canminion stmns.ty design whh a conclusion of safety requin ut.less the Commission anc urages the un of certified designs acceptability using an approach that 6etermines that these modmcadona are r for es nun plantin su futun heenu -
aL-esses determinisue engineering m accord with the backSt rule specmed ; appheadas. de nyulsuma alw aUow 1
cnalysis and judgment complemented in to CFR 50.109. De subject of -
IIhI'"d*'di**II'"'EIf'"'
by PRA.
modifications to be required after the including the duplicate plant the ne design certitcation application abould also pro ose, for staff review design certification is granted, as ws!! as rep!!cate plant, and the manufacturing cnd approval, tke tests. analyses.. amendments at the request of the desip lican ceceptame ene opdons certification holderand variances at the may be used in the interim. they are inspections and acceptance criteria that' request of a utility,will be addresud in d!scouraged for the longer term.ne are considered necessary to provide the pro osed rules. In developing those. Comm!ssion also recognizes that review.
reasonable assurance that a plant which rules, t e Commission will consider the approvaland certification of maior references the certified desip ts built appropriateness of employing the ;. 4 Mua of comM M M k cnd operated within the specifications backfitting standard set forth in the unfulin the inteMownere --
ef the finaldesip. Additional proposed standardizadon and licanalng applicadas fw enudaUy complete if-mation beyond that required for an reformle slaUon.ne Commission designs an referred and wiU be given 1
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tay be necessary to support the expects at backfits to the desip. -
priunyin a locada of nwuren to certification rulemaking. Further cart fication rule would be applied. ;
support review and approval..
ed guidance in this area wiU be uniformly to all plants referencing the 5 result of experience with the first few certified design. Similarly, amendments i.' Dated it Washington. DCiths 7t nue!oped by the staff,if necessary, as a sep,tember. test.,
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to the design certification rule initiated " '.' If i the Nudear Regulatory Commluloa' ~
FDA/ design certification nviews.
o by the holder of the design certification features of the desip which can only - would also be applied uniformly to a!!
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' be determined when a specific site is lbants referencing the standard desip.'
- F'l g, g ***e, chosen generally are not included in the addition. procedures wiu be IFR D*87-8 8 N' @ l N ",'"I design approval or certdication. Rather, developed to aDow for plant-specific name soot '****H8 7 '*-
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