ML20197H542

Advises That Plant OL Expires on 200709 & Util Has Not Applied for License Renewal

ML20197H542
Person / Time
Site:	Yankee Rowe
Issue date:	11/06/1990
From:	Taylor J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:	Conte S HOUSE OF REP.
Shared Package
ML20197H549	List: ML20197H542 ML20197H553 ML20197H557 ML20197H564 ML20197H569
References
NUDOCS 9011190073
Download: ML20197H542 (29)

Text

G Na ember 6, 1990

' M, J)

The Honorable Silvio 0. Conte 7'

United States House of Representatives Washington, D.C. 20515

Dear Congressman Conte:

The present license for 7NPS expires July 9, 2000. At present, Yankee Atomic Electric Company (YAEC) has not applied for a license renewal, thus a YAEC license renewal application extension is not under review by the Comission.

However, YAEC has informed the Comission that it plans to apply for a license renewal in 1991.

Several Regulatory Comission (NRC)public meetings have been held at which the Nuclear staff met with YAEC to discuss the scope of license renewal activities for the Yankee Rowe plant. YN?S is the industry's pilot pressurized water reactor plant for the license renewal process.

~

The NRC has promulgated draft regulations (10 CFR 54, 55 FR 29043, July 17, 1990, Requirements for Renewal of Operating Licenses for Nuclear Power Plants) for public coment (copy enclosed). These regulations will govern the issuance of renewed operating licenses for nuclear power plants licensed pursuant to sections 103 or 104b of the Atomic Energy Act of 1954, as amended. The public coment period ended in October 1990, and the NRC staff is currently reviewing

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comments received. Please be assured that the NRC staff will carefully consider all the public coments received, including those forwarded in your October 9, 1990, letter, in developing final regulations governing license renewals.

Also, be assured that members of the public have the opportunity to participate in a licensing decision relating to a future license renewal application for the YNPS.

Sincerely.

OrlEinal Signed By:

=

James LL Taybt James M. Taylor Executive Director for Operations

Enclosure:

Federal Register Notice l'

• See previous concurrence 0FC

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DATE :11/01/90

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OFFICIAL RECORD COPY,,.

3 GREENTICKETNO.5943!]."g Document Name:

9011190073 901106 PDR ADDCK 05000029 U

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DISTRIBUTION:

Docket File (W/ incoming)

NRC PDR w/cy of incoming Local PDR w/cy of incoming ED0 #5943 EDO Reading T. Murley/F.Mivaglia PDI-3 reading (w/cy of incoming)

S. Varga B. Boger OGC GPA/CA R. Wessnan h.

J. Taylor E. Tana, PMAS (ED0#-5943) w/cy of incoming Beverly Clayton P. Sears w/cy of incoming M. Rushbrook PDI-3 Green Ticket File i

J. Johnson, RI W. Russell F. Gillespie SECY #90-0614 J. Partlow T. Martin, Region I E. Beckjord, RES-NLS007 J. Sniezek H. Thompson J. Blaha m

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E. NCLOS.OP.E hederal Regleter / Vol. SS. N3.137 / Tuesday July 17.'1900 / Proposed Rules 3 043 vi) Milk chocolate and the allk spessaany:De Nuclear Regulatory YL Avstlebliity of Document ab(:colete component of other products; Comminion is proposing to leeue a rule V11 gnvironmentellepect.

(vil) Any other dairy product not that would establish the requiremente VEL PsPer**rk Rederben Act Statement.

Stherwise specified in this nction.

bl an applicant for renewal nf a DL Reguletary Analrom n 6ar power plant operating license X. Regulatory Nalbiltry Act Certificeuen.

i Prop eed b the Dairy Diviolon' must mut, the information that must be XL Non. App 16cebibly of pockfit Rule.

t Agrieulturaf Mukehag Service submitted to the NRC for review so that

1. latroduceem i

hoposa/No. E4 the agency can determine whether those requirements have in fact been met, and The f.iomic Energy Act of t:54 (AFA)

Make sech changes a may be the application procedures.This limite the duredon of most opnating necepary to make all marketing ProPond rule will inform nuclear power bcenses for nuclear power plante to e agreements and the orders conform with plant beensees of necepary maximum of 40 years, but perm!te their l

any amendments thereto that mey ruult requiremente for renewing opereting renewal.no Comminion's regulations from & heenng.

licenses.

et to CPR to.811mplement this authority Copies of this notice of bearing and the orders may be procured from the oatas:The comment period erpine by pumttting Mnewel. However. I 50.51 Market Administrators or from the October 15.1990. Commente received provides no standards or procedums for after thle dete will be considered if it is determining renewal oppbeations. The Hearing Clerk. Room 1083. South Building. United States Department of Practical to do so. but the Commisalon le nuclear utility industry has emprened able to anure considerstion ordy for considerable interest in opereting Agriculture. Weehington. DC 20:50. or commente received on or before thu exleting nuclear power plante beyond may be inspected thne.

their initial term of operation.%e

date, Copies of the transenpt of testimony taken at the hearing will not be Aoonassss: Commente may be sent to industry hee undertaken seveal available for distribut on through the the Secretary of the Comminion. U.S.

Initiatives in support of plant life extension. A Sturing Committee on Hearing clerk's Office. lf you wish to Nuclear Regulatory Commission, Nucleet Plant Life Extension (NUPLEX) purchase a copy, arrangements may be Washington. DC 20585. Attention:

bee been formed under the direction of cade with the reporter et the heanng.

Docketing and Service Branch, or may the Nucleat Management'and Resources Frote the time that a hearms notice is be hand deUvered to One White Fhat leeued and until the lousnce of s' final North.11555 Rockville Pike. Rockville.

Council (NUMARC).no Electric power decision in a proceeding. Department MD aos52, between h30 em and 4:15 pm Research lastitute (EPRI) in cooperation onployees involved in the deciolonel Federal workdays. Copies of comments with the U.S. Department of Energy (DOE), and two utilitin have eponsored proc:ee are prohibited from discussing received may be examined at the renarch on his extensica. lacludmg the terite of the heanns feeves on an ex Commiselon's Pubhc Document Room at parte beste with any person having an 2120 L St., NW. (14wer 14 vel).

Pilot studies on two nuclear plante, interest in tne proceeding. For this Washington.DC between the hours of surry 1 and Monticello.This has oulminated in DOE fundm' s of twolesd particular proceeding. the prohibition 045 am and 4:15 pm Federal workdays.

8pP catious for renewal of the opweting 11 cpplies to employees in the followmg poa puerfusa moonesanon ooerTAct:

boenees for the Yankee Rowe and Geo e Sege. Office of Nuclear organisational unite:

Omce of the Secretary of Agriculture Regu) story Research U.S. Nuclear MonunDo hcihbu.

De nuclear industry has urged the Omce of the Administrator.

Regulatory Commission. Washington.

NRC to develop standards and i

Agricultural Marhtmg Service DC 20555. Telephone: (301) 492-3r17.

procedures for license renewal so that Omce of the General Counal su,,t.ausertany moonmatiose the utilities would know what wiD be Dairy Diviolon AgriculturalMarketing L invoducuen.

required to obtain a tenewed operstmg Service (Washington omce only)

B. Background.

hoenas,he industry states that e Offices of au the Market RL Proposed Acoon.

11 cense renewal rule le needed now a

l W.Pnncip*alissues.

Administretore Philno y becaun of the need for a significant J

Procedural matters are not subject to

• R'e* !*]oenoms ge*and Approach.sumber of plants to make decisione in k Curw nt de above prohibition and may be discussed at any time.

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• • f,*',*L' the near future se to whether to seek y

boense renewal. For the oldest nuclear Signed at Weehington. DC. on: July it,

s. Latest Date for Tihas Renewal.

Applicaton, the Tunely Renewal P0.wer {lante the expiretion of their Doctnne. and Sumcaeney of the Renewal engina operating bcenses le see0.

Daniel Haley.

APPbeenon.

approaching.lf the los nuclear power M aunseuesor-

f. sarbeet Data for Flhas Appliceuene.

Plante licensed as of the end of 2000 IFR Doc. so-teaae FIN 7-16 ep,6 45 em) a RenewalTerm were licensed for 40 yeare from the date L Effeceve Date of Renewed Doense.

of their opereting license, the first eight ire a u me sees w w.eeei T,'g,,^** haia-T*a=>

,iania win have ibeir beenees egi dunne e years 3000 to m w s

wuCLEAM REOULATORY

[E" N "'*IISI8'menon.

anoen Meanen om hy N see Ceme6dennene.

Utilities contend that they wtU requDe COMMISSION

i. Heanage.

a Report of the Advisory Committee on 10 to13 yeare to plan and build 10 CPR Parts 1,80, and $d Rosetor safeguards.

replacement power plante if the

m. Emergency Planrung couldereno=-

opereting lleenees for existing nuclear Rm 31to-A004

c. Plant Ptiysical Secunty Considereuene.

power plante are not re,newed. Theyaiso wuoi.n power ri.ni Lio. nae R.new.i g, rey,gy,g,conge,uons requiremente for beense renewal must cCamev: Nuclear Regulatory r.Duommimonuss onsidereuono.

be established before utilities can c

e Anutrust Review.

reasonably determine whether renewal C0mmission.

L.t. Comphence with 10 CFR Part le0 of their existing operating hcenses is j

I cenoec Proposed rule.

Queouono.

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Federal Regir*er / Vcl. 88. No.137 / Tuesday. July 17.19e0 / Proposed Rules

'WD64

• economicaDy and technicaUy jutined.

impleve sted during b ext:nded sf the existing Ucensing basis with (Fzt more truormation on the empiretion oport tion ed for a number of the mysews in sarery sipincant areas or (c) of facility operating licenses, see mestares dutiAg the saisting license compliance with new plant standards at l

App:ndix A to the Regulatory Analysis term to well, the time the application is submitted.

i afor Ucense Renewel NUREG-1341) To Sin ultaneously, a mquest for Commenters wm asked to identify eneum a muoned process for cor:r ents on establishment of a policy whether any othe* mejor, regulatory souldering license renewal for those statement on hfe extension was options for beense tu.ewal should be who esy pursue it. the NRC has published in b Federal Register (;1 m considered. and whether vertnca tion of determined to proceed withlicense 403M: November 3.10e6). Comments the exleting licensing basis at each plant renewalrulemaking now in order to were requested on seven mejor policy, should be required for boenn renewal.

establish b requirements for renewal technical, and procedural leaves (21 Second, two ahermatives for handhns cf nuclear power plant operating separete questions).no first and sixth uncertainties in age related degradetion licenses in a timely feehton.

poljey amas focused on the timing of wm described and discumed:(a) 3.3.cky,v,,

regulatory action on life extension, emphaelse maintenance, inspection. and reliability assurance, or (b) emphasize including the need for a poli $ution of defense in depth.The relative merit of W NRC e twearch propam on the statement. and timine of two degrodation of nuclear power plant noucy, technical. and procedural issues.

the two alternatives was the second systems. structures and componente l'he earliest and latest dates for filing a subject for comment. Third, the tms. in 1stL gna be an in the earlylife extension application and b advisability of preparing a generic (SECS) due to a e NR staH potential term of such an extension were environmental impact statement (US) rec gnizing the potentialimp'act of plant the subject of the woond and a portion and whether part si should be amended aging phenomena on the continued safe of the fourth policy area.De question of to permit the NRC the option of tperston of nuclear power platus.

an a repriate licensing boele wee the pparing an environenental assessment eueda. Marriand. ne pu,,0. o th, i,,r,

,,,,luding,the need forM,,)laste,ad of a,n ES,,we,m di,scu,and, f2.vened e 'Workhop on Plant sol lie uce,inc

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e issues,sievanno we exiension. in te.

depedetion,its identiScation and Pifty.thru written comments won the Diviolon of Engineering of the Office mitagstion, and the need for research received from nucJear industry groupe of Nuclear Regulatory Research issued and changes to indus codes and and individual utilities, pubbe internt the first comprehenelve program plan standards.b final cy area was the poupe, and Federal and State agencies (NUREG-1144) for nuclear power plant need for procedural anges in the in response to the ANPRM and aging ruoarch. By tees age related Comminion's mgulations for handling sommenting on NUREG-1817. An degradation became a more important life extension requests. A total of to overview and summary analysis of the prt:rity with b recognition that utilities written comments were reenived from enamente am contained in NUREG/CR-were internted in extending the life of the electric utility industry public Saat " Summary and Analysis of Pubuc their existing power plante beyond the internt groups, private altisens.

Commente en NUREG-1317: Regulatory term of up to 40 years of their orismal independent consultants and Options for Nuclear Plant Uoense opereting licensee. In response, the NRC gownsent agencies.These comments Renewal"(March seep).

staff dneloped the " Plan to Accomphab were reviewed and a summary provided Also in sees the NRC.in cooperation Technicallatogration for Plant Aging /

in SECY-87-179. Status of Staf with the American Nuclear Society ufe Extension"(May 1997) and Activities to Develop a Ucense Renewal LANS), the American Society of Civil setsblished a Technical Review Group for

' and ufe Extension Policy. Regulations and Uoensing lIngineers (ASCE), the American Society A1.EX).The objectives of Guidance and to Report on Pubhc of MechanicalEngineers (ASME), and All.X were to clearly denne b Commente" Only 31,see7).

the inetstute of sectrical and meetronics techalcal safety and story pobey Based on these comments, the staff Engineers (IEEE) sponsored an issuis associated with laat aging and began to specinoaDy identify and laternational Nuclear Power Plant Aging hfe extension and to elopa resolve the wide variety of pokey and Sympoelua.N sympoelua. which was resolving the twues in a timely, plan for weU.

technicalleeues relevant to Efe held in Sethesda. Maryland, from integrated manner,la May les7 the extension. In August sets, the staff August 30 to September 1.1988, was TIRCA!E.X report was issued. it publiebed an Advance Notice of attended by more than 880 identined a br ad spectrum of technical Proposed Rulemaking(ANPRM)in the internationally prominent nuclear safety and regulatory policy leeves.

Federal Regleter (la FR 33rik August as, scientists and engmeere from 16 Dese included identi5 cation of teet)in which the Commisalon countries.De symposium focused on systems, structurn, and components announced its intention to bypese a the potential earety issues arising from that are susceptible to ap'ns and could policy statement and go directly to progroulve aging of nuclear newer adversely affect safety; segredetion preparing a pro rule on heense plants. Does Iseues included aging of Processee: lesting, surveillance, and renewal.De also announced structures in austenitic steel, fatigue ufe maintenance requiremente: and ettteria the availability of NUREG 1317 of structural materials, aging of for evaluating residual life. TIRGA1.EX "Reguletory Options for Nuclear Plant insulating materials, degradetion of concluded that many agins phenomena Ucense Renewal," and requested pumps and valves,rehability of safety are readily managed and do not pose commente on the leaves discussed. First, system components, radiation and major technicalleaves that would three alternative licensing bases for thermal embrittlement of metals, and preclude life extension. provided that suessing the adequacy of a hfe eroelon corrosion of Duld. mechanical tec2ssary compeneetory measures such extension application were presented systems. Discussion addmosed topics in as maintenance, surveillance, repair, and discussed:(a) h existing licensing the staff's report NUREG-1817. which end nplacement are effectively basis for a facility,(b) supplementation had been pubbsbedimmediately l

l

.. - - -. -. - ~. - ~.

Federal Register / Vcl. 55, No.137 / Tuesday, July 17, 1990 / Proposed Rules 29045

' preceding the sympostum. De industry he Nuclear Management end but ett fit mre than 30 years bey nd Resources Council (hTMARC). Yankee the ongmallicense expire, tan.

proceedmgs of the sympoemm wen pubbahed as hVp1C/Cp-0100 in March Atomic Electric Company, and Northem gy,p,g,,gp,3g,,,,,

States Power Company presented The NRC staff s views on specific prepared comments at sech session. In o Aegulatory Philosophy and Approoch 19es.

license renewalissues. as evcived in add tion, written comments were pg early 1989 were presented to the pubbe received from 12 organipuons.

in an NRC pane! &seussion and including substanual submissions by ne regulation that the Commission hTMARC, Yankee Atomic. Northern proposes for license renewalis founded quesuon and answ er session at the States Power. Westinghouse. the Ilhnois on two key pnneiples.ne fbst prmeiple NRC's Regulatory Informabon Conference, held on Apnl18.19 and 20 Department of Nuclear Safety. and an is that with the excepuon of age.related 1980 Among the issues escussed were independent consultant DOE was the depadston, the current Lcensms basis only Federal agency submittmg written for each reactor provides and mamtams the nature of a renewed beense comments. No comments were an acceptable level of safety for (renewed beense versus amendment of submitted by any pubbe interest group' operation during any renewal pened existing beense), the need for Tbe second and equally important 1

probabthey nok assessment (PRA).

UI. Proposed Action pnnetple is that each plant's cunent intepsuon with the In6ndual Plant The Atomic Enugy Act which bcensing basis must be maintained Examinston (IPE) process, and Permits renewal of beenees, and the dunng the renewal pened. in part compliance with the Nauonal license renewal rule alnady m effect (10 through a propam of age.related Er vironmental Pobey Act (NEpA).

CTR W1) do not contain specine depadetion management for systems.

On October 13.1969 (M TR 41960). the procedures. criteria. and standards that structures, and components that are Comnussion announced that a workshop would be held on November 13 and 14.

{",',$ish important in this connection.

o p

d 1980. to focus on specific technical estabheb the procedures. crttena. and (ii) First Pnnciple: ucensing Basis leeues. including identification of the standarde ge". erning nuclear power Retention significant techruc41 issues beanns on plant beense renewal.

ne curant boenslag basis. as used safety, the nefure and content of ne following we de principal above. means the Commlesion standards for issuance of a renewed elemente of the proposed rule:

requirements and beensee commitments beense. and the appropnete role and (1)The beensing basis for a nuclear imposed on a nudear power plant at the scope of determirusue and probabilistic power plant dunng the renewal ters time of the iniuol beanu as modihed or nok enessmenta in ad6 ton. the will consist of the current bcensing basis supplemented by the many additional schedule for rulemaking and for that plant together with any mquirements that have been imposed on alternativu for addressmg comphance additional consideratons related to the licenue by the Commission with NEpA wen identified as issues for possible degradauen through aging of subsequent to the inical beense and by discussion General queouons to focus systems. structures, and componenu the addjuonal commitmenta made by workshop &acussions were ptovided in (BSCs) troportant to beense renewal.

the bcensee during the period of plant the Federal Regiater nouce and later necouary to ensure that the facihty can OPersbon up to the filing of a renewal supplemented by a more detailed set of contmue to be operated without undue applicanon. his pnnciple is founded on questione. In addluon. the Federal risk to the health and safety of the the Comnuosion's inibal findmg of Register ne uce included a "PrehminarY pubbc. The " current beensms basie-adequate protection for the inlual design Regulatory Philosophy and Approach for includes all appbcable NRC and construccon of a nuclear power Ucense Renewal Regulacon" and an requirements and licensee commitments.

P ant. as weU as the Commiselon's l

"Outhne of a Conceptual Approach to a as defined in the rule.

continuing oversight and regulatory License Renewc! Rule." Wntten (2) Pronsions are included requinas actions with respect to nuclear power comments on the questons posed, the renewal applicants to perform and P ants. The Commission may issue at l

statement of regulatory philosophy, and submit an integrated plant euesoment.

the conceptual rule outime were in which systems, structures. and oPusting bcense to a utility only if it can make the findings required by to accepted by the agency up to December components important to boense CFR 50.5t More speci%cally, the 1.1989.Tranecnpts were made of the tsnewal are identified and screened. to

. Commission must conclude that the enttre workshop. Two hundred and one determine and describe the required facibty wiD operste in compliance with indjnduals (not including NRC staff) age related degradation management the appbeation as amended, and the representing to orgarussuons registered accons.

rules and regulanons of the Comnussion.

for the workshop. A parual heung by (3) An applicahon is required to Further, the Commission must conclude category includes 62 andmduals contain specified informanon for NRC npresenttag 28 electne utibtles.10 review, including a desenpuon of plans that the authorised scuvines can be conducted without endangenng the individuale representing 2 nuclear for aging management.

health and safety of the public and that industry groups.16 in&nduals (4) Opportunity for public hearings le the issuance of an operstmg beense will repreuntag 4 nuclear vendors. 5 provided.

not be inimical to the common defense individuals representmg 2 architect-(5) Appbcation may be made not more and security or the public besith and engmeer firms. 36 tndustry consultants than 20 years before beense expirabon.

representmg to ftrms. 6 tndmduals it must be made not less than 8 yeare safety. hus, when the Commuesion representmg 4 State agencies. 2 before beense expiration for the timely issues an taltlal operstmg beense, it has tournahets from 2 trade press renewal provision of to CFR 2_100 to determined that the design. construcuon.

and proposed operation of the facihty organizations. and 1 indmdual from a apply.

pubhc interest group Comments (6) A renewal beense is effecove upon uusfy the Commission's requintnents and provide adequate protecuen of the prended dunng the workshop were its tesuance.

from industr> representatives and (7) A renewal term may be granted or pubbe health and safety and common inmviduals affihated with the nuclear approved as justified by the hconsee.

defense and security l

e 39044 Fod:ral Roglet:r / Vcl. SS. No.137 / Tuesday. July 17. 1990 / Proproed Rules Howent, the licensin besie upon uttrwolved C$le 'enerall oddress only onelysee to define cornetin actions which h Commission fetermined that enhancements of esfety.Y$e conclusion that would improve plant safety with an acceptsble level of ufety existed was determined during the initial rupect to the diffmaces from current does not remain fixed for the term of the es sluotion of & pnenc concern which requirements bt were identified.

sperating beertoe. Rether, the Ucensing asuped whether any wpect of the De SEP effort highlighted a smauer basis continun to evolve dunna the senent concern might han a significant group of 27 regulatory topics for which l

term of operation,in part due to the hcpect on the protection of the public cornetive action was generally found to co2tinuing retulatory activitiu of the health and safety or that immediate be necanary for all of the init al SEP Commluiert Tbut indude renarch, mmedial action would be warranted.

plante and for which significant safety inspections. and the evaluation of he liceuing beste of individual plants improvements for other operating plante sporeting exponence. New requirements includes changes that have resulted of the same vintage could be expected.

and guidance are promulgated by the from ruolution of generic issues ne topics on this smaller het are Commission which may require plant detennined to be applicable and will nferred to es the SEP "lessono learned."

codifications on a plant specific basis:

include applicable generic leeve derived and the staff expects that these topico pneric and unruolnd safety issues are c.hanges in the future.

would be generaUy appucable to I

renlved and the ruolution may require A special fyoup of 22 pneric safety operating plants that received their that licensees evaluate and modify their luues deemed to be of sufficaent construction permits in the late 13eos or designs: and additional evaluations are significance to warrant both a high*

early 1370s.

routmely required as the Commission pnority tuolution effort and special As part of b curnnt staN eNon identifies arwe of plant operation that ettention in trneking wee designated as associated with documenting the require addjuonal understanding.

unruolnd selety issues (USIs). All U$1s regulatory procenes that contribute to han bun nelnd. Most of M US!

the contmued adequacy of the current (111) Review of Operating Events twolutions have been implemented; the licensing bwee et opereting plants. the he Commission has a program for remainder are being implemented on a staff has under way a shon term effort the review r f operetas enets et schedule founo satisfactory by the staff.

2 iduufy bw opnific **1mou tuelear power plants. As a mquirement De USl and GSI ruolution procou is learned" from the SEP effort beve been af the curnnt beeneing bula, and one limited to issues that an not of such fe***d I'" &' b**"*l'"8 he* *f dl whic.h would continue dunas the gravity that immediate action (remedy

1. Peths plants e ina ongoing or ebutdown)is nluired. Cost benefit ana yses were employed "I"I'*'Y P8'***'n and definluon of renewal term, each Ucenm to requind D 'l'E P"8#**

to totify the Comminion promptly of includes identihcatio any lent event that muts or excude as part of the basis of resolving GSls the lepons learned as generic safety b t reehold defined in to CTR 60.72 involving safety enhancement above the issues and determination of the and to fue a wrttien licenm ennt adequate safety level. In these tredeoffs

1. Ppropriate riority for the report for those events that meet or between net safety benefit and net moet.

moluuon o em inun.

e stan exceed b thrwhold defined in to CFR the remaining plant operstmg term offon wiU take pubbe communts on &ls 30.73.This information is reviewed daUy ordinarily enters the calculations.

iam into eocount and fouemup efforts are carried out for Howent, such calculetions do not have cvents that appear to be potentially risk a precision adficient to make a (vi) Consistency of Regulatory significant or are judpd to be a ponible significant distmetion between plant Philosophy precursor to a more severe event.

operating terms with and without a 3D-Th terulatory philosophy containing

)

Depending on the significance, further year renewal, given the fact that these the t vo fundamental petaciples is also action may be taken to notify all decisions han ban band on avwap comisunt with ee Comminion pobe]

lant spe in the first half of a 40 year licensees or to impose additonal stead in the Pobey Stakment enutle bconee term. Accordingly,it is not requirements. Information on opersting

" Severs Reactor Accidente Regarding cvents is dipeminated by the NRC in necepary to reenamine in the boons, Future Designs and Exteting Plants (60 the form of information notien, renewal context such cost beneSt FR 2188. August 3.1eR8)."la this Pohey bulletms, and other nports; by calculations underlying decisions not to Statement, the Commission concluded individual bconsen in the form of backfit. Should special circumstances in that existing plants pose no undue risk beensee ennt reports.no total process connection with a particular issue as cffers a high degree of enursace that applied to a particular plant warrant to public bealth and safety. Moreover, events that are potentally nok reaueesment. such messenment would the Commission stated that it has l

significant or precursors to potentially be undenaken on a plant.epecific basis.

ongoing nuclear safety programe..

described in NUREG-1970, that include significant ennte are being revkwed (v) Sysumatic Evaluation Program the ruolution of unrwolved safety and cad resolnd expedinously.

in1377 the NRCinitiated the generic safety issues, the Seven l

(iv) Generic Safety lasues Systematic Evaluation Program (SEP) to Accident Research program, opersting As described in SECY 46-186. the myiew the deelsne of older operating experience and data evaluation Commiulon aise maintains an active nuclear power plants and thereby concerning equipment fauures and program for evaluatmg and resolving confirm and document their safety,b buman error, and scrutiny by NRC peneric issues that may impact public mytews were organised into inspectors to monfter the quabty of nealth and safety. A generic safety twue approximately 90 review topics (reduced plant construction, operation. and (GSI)involvu a safety concern that may by consolidstions from 137 originally mamtenance. lf new safety information affect the design, construction. or identified).no review results were were to become evallable, from any cperation of all, eenral, or a cleos of documented in a pries of lategrated source. to question the conclusion of no reactors or facibties. Its ruolution may Plant Safety Awesoment Reports. As a undue risk, then the technjeal issue (s) so heve a potential for safety neult of these reviews with nopect to identified would be twolved by the NRC improvements and promulgation of new some of the issues, the licensees under its backfit policy and other or revised requirements or guidance. it proposed and implemented procedural existing procedures inclu the should be noted. bowever, that all or hardware modifications or additional poselbihty of generic rulema

l Fedarel Raglet:r / Vcl. SS. No.137 / Tuesday, July 17. 1990 / Proposed Rules 29047 i M.33(d), which states the licensing directed at addroning age.related

~

(vil)Probabbtic Risk Aeoeeement basis for the renewed license shall degredation during the ranewed license Although a plant.epecific probabilistic Mude h ple' curmat licene term. Sections H.13. H.21.' and H.23, elsk assessment (PRA) or plant safety basis se dehned in i M.3(a),inclu which specify the information that must revisione addrening age.nla d be submitted in a renewal application, spenment (PSA) will not be a those fation. and (b) continuing the nquire only information neerding nquirement for the renewal of plant dera ta oversight propam administrative matters, age.related opereting licenses, the Comminion RC's @he term of a plant's mnewed depadation, and environmentalimb recognizes that a plant.opecific throusbout t While the app!! cant must submit a et of probabilistic menment can be und as liceme. In this manner the curnnt an effective tool that can provide licensing beels will mmain enforceable documente doci;bing portions of the intepated insights into the plant design b & Commiselon throughout h term currentlicensing basis which are and procedures and provide an

,f the mnewed license to the same nlevant to h system. structure. and

' * ""I " """8

• • • P""'"I "'N'"I"8 P***"' N d' af The Co e ion d tande

"'e Comminion intende to continueinfor ti n m ot e dequacy of ed a bang. p,eth'p a[part Th I

t program a plant's current licensing basis. Secuon

"* "I" * *$'"""

t "" * '

""8

• • "**8-H.20 which defines the standard for dividual Plant Examinetion u$s This propam, which is dieeumd below luuance of a renewed license, does not am.

Probabilistic somsment tech uld also be d

pl tal ee is ont no tepa 1 a see t is to gp ie E

underbe the plant e age.related with applicable requiremente an7 e,

ne only shusuon in wWeb a plant,a deredation management program as licenm commitments, as weU as current beansing besle may be changed well as in monitorms the safety identifying important areas of in a bcena nuwal pmending is whu implicatier* of a plant's performance noncomphance.The Commission Se beenm asserte that it is imposelble s

dunns the renewal term. As part of the believes that this oversight,if continued or extremely impractical for it to comply monitoring function, time trende in the throughout the term of the renewed with its curnnt licensing boele due to o

frequency of events or in the rate of Ilcense and modified as necessary to age related depadation. Any changes in detenoreuen of equipment with reflect new information and exponence the current licensing basis proposed by significant safety impbcatione could be of extended operation, will also provide the licensee to accommodate age related identified.This monitoring process helps soeurance that licensees wiU comply degradation must be thoroughly enoun that acceptable levels of safety with their plants

• bcensing bases dwing analysed and justified by the bcensee.

are maintained dunns & lifetime o,f, h term of their renewed ucenses.

De justification must show that the any reactor. including any renewal.

(x)Ucensing Basis Changes beenue. proposed chanpo provide The pnnciple of comphance with the adequate protection to the public health terms.

I" N

A"*'"*"

licensing basie does not preclude and safety. Such licemee initiated nue. the Commiselon. required changes to the licensing bacia; se changes in the curnnt licensing basis changes to a plant's licensing basis discuued above, the licensing beels would be subject to challenge e a provide ongoing auurance that the changes throughout the wrm of the bearing.

onginalComnunion concluion of crismal operstmg license, and will also if the staff or the licensee seeks to adequate protection of the health and change throughout the term of h make changes in a plant's boeneing safety and common defense and renewed beenu.However, changes to basis for reasons other than age related security continues to remain valid the plant's cunent bconsing basis that degradation. they should be pursued throughout the remaining term of the are unrelated to age.related depadation either in the existing operating boense or lecibty's operating bconse.

will not be considered or proposed by the renewed beenee. osce issued. Staff.

the Commission in determining whether initiated change would be evaluated in

_=

(ix) Second Pnnciple: Maintaining the to Fant es nnewal appbceum Such accordance with b bacW mieE CFR Ucensing Basio During RenewalTerm changes to the beerseing boele are 30400.

De second principle for license inconsistent with the first key principle

6. CurrentLicensirig Seele renewalis that the Comrnieuon must of liconee.enewal vis that the current ensure that the plant.epecifie.bcensing licensing bute for a plant is sufBoient to (1) Current Ucensing Basie F.xplained basis le maintained during h renewal ensure adequate protection.De As discussed earlier and as defined in term.nis principle le a necessary propowd rule incorporates thle principle this propowd mle. the cuneet licensing complement to the first pnnciple. As by making a generic finding in i M.as basis (CIA) mean the Commission discuoted above, h first principle is that the plant epecific licensing bases requirements for the plant that are in founded upon a generic determination for all nuclear power plante are effect at the time of the renewal that each nuclear power plant's sufficient to ensure adequate protection appbcation. lacluded are the bconsing beste,if complied with, to the public health and safety.nis provida nuonable aneurance of flading will preclude reexamination of requiminente at the time that the initial adequate protection throubout the the adequacy of a plant's current beenes for the plant was panted renewal term. Therefore, it follows that licensing basie in individual license together with requirements subuqwntly each nuclear power plant that complies renewal proceedings.

Imposed. It includes the licensee a with its license throughout the renewal To preclude the renewal proceeding commitments for complying with those term will actually provide the edequate from developing into a general requiremente at the tiene the taltial protection thought to be provided by the reconsideration of a plant's current license was panted, including those licensing basis.The Commienton licensing basis, the proposed rule has documented in the operating ucense believes that adherence to the licensing been carefully structured to establish a appbcation or Final Safety Analysis basis can and will be ensured by:(e) regulatory process that is precisely Report (FSAR). Further. the Cl.B l

R-L

- - - - ~. -

i Federal Resist:r / Vel. 65. No.137 / Tuesday. July if.1930 / Proposed Rules 20040 t cludes eose requirements and bem et opmting plants at any time to plant licenas applications and licenses.

eommitments as modined or tuolve the new concern. nis process of ne document also illustrates how the supplemented by additional determinetione concerning backAtting of regulatory process will continue to mquiremente imposed by the evolving requirements to plants already ensure that an operating reactor's Comminion and by commitmente made Ucensed is curantly guided by the licensing beste will continue to provide by the Ucensee during the period of provisions of the backfit rule (1017R an acceptable level of safety dunns any plant operstfon up to the A11ag of a 30.100). Before promulastion of the senewal teria.

renewal applicacn that are part of the back. fit rule, similar considerations were In view of the differences in the docket for the plant's Ucense. More applied. though the backfit rule beansing ham among plants, uch spectAcelly this includes, but is not enhanced the discipline of the procesa.. beensee wlU be required to compile its in view of the regulatory programs plant's licensing basis for use in the halted to. plant specinc compUance and procenes just dueribed, itis screening process to identify SSCe with the Commiselon regulations as evident that the licensing basis differe

. requiring action to manage age.related presenbod in parts 2.19,20,21,30,40, among plante.Nu d1Norences arise gegredetion.Since portions of this so. 88. 72. 73 and 100 and the from attferences in license date as waU. oompilation constitute acceptance cppendices thereto of Title to of the as differences in such factors as site.

' witaria for determining the adequacy of Code of Federal Regulations: orders:

license condJtions: exempdone: and plant dulgn, and plant operating the screening methodology and will be technical specifications. In addition, the experience.The paragraphs above ha e carried forward in the unewed term, a described,in general torna, the ket of documents identifytag thue curmnt Ucensing besie includes written commitments made in docketed processes employed by the Commiselon portions of the current beeneing besie licensing correspondence, such as to provide continued apurance that the should be submitted as part of the licensing basis at an opereting plant application. All documents describing mopenses to NRC bulletins, generic providu an acceptable level of safety at the current Ocensing basis should be letters, and enforcement actione, that any point in time of its operating life and maintained in an auditable and i'

mnain in effect at the time of the that the current licensing bases of older retMevable fws.

cppucation.

[lants remain acceptable throughockfH of newly polving mquimments M Com%ance d % UceneW The licensing beels for the plant at the

(

time of abplication will form the basis and guidance when that is necessary for Samos fit each eensee's compilation of those adequate safe or warranted as he Commission has determined that items that would be tested against the wonhwhue sa en enhancemata.He" a finding of compliance by a plant with criteria used in the SSC ocreening regulatory processes also ensure that

. its current licensing basis is not mquired process se acceptance or rejection the licensing buse of older plants for leevance of a renewed licencs.When criterie and therefore, for determining excused from complying with specific,

a plant's wipnal opmung Ucean wu the need for additional meuures roleted new mquimmate menain acceptable.

issued. the Commission made a finding, to preventing. mitigating, or monitoring age.related degradation.

(U) Foundation for the Adequacy of the pursuant to to CFR 30J7(a)(1), that construction of the plant had been N Atomic Energy Act directs the IJcensing Bases embetandaDy coj, se construchonnpleted a Commission to ensure that nuclear in order to limit the Commiselon's eenfomaly wie power plant operation provides license renewal decision to Perall se opmdas Ucenu appucation, cdequate protection to the health and conalderation of whether age related 6a mquiremots of es Atomic Eurgy safety of the public. However, adequate degradation has been adequately Aat, and the NRC's rules and protection is not absolute protection or addressed the part M rulemaking must segulations. net fin was essentially sero risk and therefore safety make a generic flading for all neolear selvalent to a finding t the plant improvements beyond the minimum power plants that the reasonable was la sosophanos wie He hcensing teeded for adequate protection are assurance fladings for issuanos of as basis as H uisted at se um of possible. As new information is opereung license conurm to be true at

. leeuance of the operenne hoenu.

developed on technical subjects, the the time of the mnewal applicaties and Once the operating lineau is issued.

NRC identifies potential hasards and accordingly need not be made anew at then may require that designs be able to the time oflicense renewal he r + *', 'the Bosnoce must osatinue to comply withitslicensing basis, unlue se cope with such hasards with sufficient technical and poucy besos for this h-ming basis is properly chansed or safety margins and reliable systems, generic finding am set forthin a the lleensa is excused by the NRC from When this new information may mveel document enutled " Foundation for the

, semphanos. Assuranos of continued an unforneen significant hasard or a Adequacy of the !.icenetag Bases" boensee comphanos during the licenn substantially greater potential for a (NUREG-1412),which is a separete term mots en two factors. to) Licenm I

known hasard, or insufficient margins supplement to this statement of programs voquired by the NRC's rules and backu capability,the Commission considerations.This document desertbes tions to ensure sentinued safe may. In h t of the information.

how the licensing process has evolved la aas conclude t usurance of an major safety tuve areas,under '.,

opere of the plant, and (b) the NRC's cceeptable level of safety mquires procepts that have ensured contiated foglatory overeight program.

changes in the existing regulations, adequacy of oldet plants.He document _

ne hoenses programs include self-Therefore, se the Commission identifies thus details the Commission's reasons laspection, maintenance, and new issues or concerns, reasoned for considering it unnecessary to re-eurveillanos programs that monitor and engineering decisions occur within the review an opereting plant's hoenstag test the phyotoalocodition of plant l

Commission concerning whether any basis, except for age related equipment as the plant operates, as well I

edditional measures must be taken at degradation concerns, at the time of as review of systems, structures, and plants to resolve the issues. When license renewel.The document does thle components to ensum that plant hfe can specific actions are identified, the in generic terms. Plant 4pecific details be extended beyond the ongmally Commission. through its regulatory can be found in the docket files planned 40 years, nrough these programs, can modify the licensing contairting the records ofindividual programs, hcepees identify the i

l

.- --~

i Federal Regleter / Vol. S8. No.137 / Tuesday July 17, 1990 / Proposed Rules 29049 1

degradetion of componente due to a Reactor Impection Propam, and DdC-embrittlement. creep, oxidation, wear, Cumber of different environmental 1815,1.ight Water Reactor laspection fatigue, and vibration.

i l

stressore and are,in seneral, able to Propam-Operations Phase. is designed g.zisting regulatory requirements.

l mplace of refurbish their equipinent so lo provide for renonable neurance that ongoing licenne propams, and national that the frequency and severity of the licemee is in compliance with the consensus codes and standards addrese challenges to plant systems etructures.

NRC regulatory requirements, to ensure the aforementioned aging mechanisme and components remain within that the plant to operated and and b means of mitigating age mleted acce table limite and the necessary maintained in a safe condition and that degradation. However, the Commission j

este features would work when conditions advme to quallry and ufe believes that not all age re'ated actua y called upon under transient or operetion are identined and corrected.

degrodation that may be important in cccident conditions.

In sum. b Ucenm's propane and the renewal term will be adequately ne Commiselon's regulatory actions to ensure continued compliance addressed by existing regulatory or eversight propame an established to with its evolving beeneing basis.

Ucensee programs and, for some SSCs.

cnsure ht the plant's Ucensing basis is together with the Commiselon's age related degradation.if unmitigated, ordined as appropriate to aflect nev' activities to ensure continuing licensee could affect the operability and informstion on technical topics affecting compliance with its licensing baele, reliabibty of SSCe important to license the design. construction, or operation of provide reasonable soeurance that a renewal and could lead to loss of safety the licensed plant so that the Uce noing licensee continues to be in compliance functions or to unacceptable reduction bases at operating plants continue to with its curmnt licensing boele at the in safety margim during the mnewel provide an ecceptable level of safety.

time ofissuance of the renewed lleense.

g,,,

nose continuing acuviues in place herefore, the proposed rule's standard The approach reflected in the during the infusilicene term would for inuance of a renewed operating proposed rWe is to nguire each renewal continue during the renewal term se liceme does not require a Anding that a applicant to address age related l

weU. Examples of these types of nuclear power plant is in comphance

'p8 e programs include its inspection.

with its current licensing basis.

Q ' hl m,,

j

c. AgingManagement age related depadeuon of the facility's se ri sues pro e a d are systems, structures, and componente discussed in greater detailin the N proposed rule requires that the have been identined, evaluated. and parapsphe below.in the cases where opphcents for license renewal take the commiselon finds that additional necesury actions to ensure that h accounted,for se needed to ensure that b faculty a beneing basis wiD be protection is necessary to ensure the plant will continue to meet an maintained throughout the term of the public health and safety or where acceptable level of safety during the l

aignificant additional protection at a mnewal term. Required actions y ould snewed license. The required asensment consists of a semening masonable cost substantiaUy enhances include those neceuary for the effective plant safety, the Commission may management of age related depadation procm to select $$Ce important ta licene renewal. based oc their intended requin b backSt of a uceand plant.

of systems, structures, and components 1.e., the nadition. ohmination, or (SSCs) important to license renewal.

safety functions or contribution to chauenging safety eyewsw an codincanon of the systems, structurn.

Aging can affect au SSCs to some evaluation and demonstration of the or components of the plant.

depee. Generally, the changes due to effectivenen of the alrudy ongoing HistoricaUy. the Commiselon's the aging enechanisms involved are bcensee actions usder existing inspectier, propam has bun pedual. Where neensary, ruelear regulatory mquiremente and plant.

constructed a. sund a serin of power plsnt hcensees are and have specinc programs to address agms inspection procedume ht provide for been required to establish prograsse for concerns: and the implementanon, as the routine examinadon of activities at managing age related depadation mensary, of supplemental programe to an operating nuclear facility on a Juring the original Ucense term. As,.

periodic basis. Once bcomed. a nuclear related degrecation becomes a subket prevent or adtieste age related facility mmains under NRC surveillance of regulatory concern in the context of degradation during the mnewed beense and undergoes periodic safety bcones renewalif the SSCs involved term. Where such supplemental inspection during its operating term.The have a role in one plant safety and - Programs are not needed at the inspection program to designed to obtain the depedation of '

can progrees to aception of the renewal term. the plan sufficient informauon on hcean a post of impatring safety performance may provide for a deformd start.

performance, through direct observation durms the renewal term. but the SSC4 Scruning of SSCs wiU identify those and verification of heensee activities to involved are not yet subket to an that, by virtue of safety roles, are determine whehr the f actitty is being established effective program of aging important to license mnewal and, operated safely and whether the management, accordingly, could require additional beensee management control program le Continued safe operation of a attention. la the screening. it is effective and to ascertain whebt there commercial nuclear power plant recognised that bre am many SSCs is reasonable soeurance that the requires ht SSCs ht perform or that are either coved by the existing hoenm is in compliance with the NRC support safety functions continue to ongotag NRC requirements and licensee-regulatory mquirements. The program perform in accordance with h established programe or are not subject includes inspection of the licensee's applicable mquirements in the curmnt to age related degredation.De performance in technical disciplines licensing beels of the plant and ht screening process and mebde for the such as operations, radiological controle other plant SSCs do not substantiaUy selection of SSCs important to license cad protection, maintenance, increase the frequency of challenges to renewal an expected to take such surveillance, emergency preparedness.

plant safety systems. As a plant ages a factore into account and wl!1 allow physical secur.ty, and engmeering.1n variety of af'ng mechani:me are propame for understanding and summary, the policy contained in NRC operative. Tney include erosion, managing age related degradation to be lupection Manual Chapters (IMC) 2500, corrosion thermal and radiation properly scoped and focused.

Federal Regleter / Val. 58. N3.137 / Tuesday. July 17. 1980 /. Proposed Rules i

30080 he renewal app!! cant is required to Maintenance, mfurblehment.

terms in excess cf 40 years, together with b statutory provision for renewal.

identify and propose acceptable replacement of parte and componente, the Commission concludes that the tem methods to be employed for the $$C residuallife assessment, and changes in selection process.The methods are opereting environment are other of a section 103 opereting license may not be extended beyond 40 yeare by cxpected to b4 primarily deterministic.

elemente useful for mitigating age.

Consistent with requirements for related degredstion effects. Timely amending the expiration date in the sorphance with the current licensing mitigation of depedation through existing operatinglicense.While b buis, the uleetion process is expected utvicing. repair, refurbishment. or record does not show any safety basie to employ a deterministic basis for replacement of componente is the prime for the Congress's decision to set the 40-l Identifysng SSCe with known important-function of an effective maintenance year hmitation, the Commission le not to.sefety functions.

program. Mitigation of age.related tree to ignore the statutory mandate.

I The screening methods-4s well as degradation can be construed as the Section1Mb does not contain any i

aging management approaches-collection of activities tLet to a large limit on the term of operating beensee selected by the license renewal extent relate directly to phyelcal for nuclear power plante bcensed as applicants Inay also include use of maintenance of components, muerch and development facilities.8 probabilletic risk assessment (PRA)

Opwating practices ht mduce although the Commlufon bee as a j

techniques as a supplement to the stresses on the equipment by adjustment matter of practice limited section 1Mb primardy deterministic methods. De of the operating environment are also opwating licenses to 40 years.

public commente at the November 1989 important considwetions to mitigating Nonetheless, the Comnuselon believes Licenn RenewalWorkshop and those depedetion effects.For example. if that ufe extension for nuclear power submitted in writing following the warranted, opwetions could be requird plante licensed under section 1Mb j

reflected the view that the use in an environment with lower should also be accomp!!shed through wsrkshogould be permitted, but not temperetums. reduced flux, or controlled luuance of renewed ucenses.

af PRA e required in the semening process for humidity. However,in taking such From b point how oWatwy systems, structume, and componente, actions, the potential consequences complexity, stability, and consistency. It Appropriate og ng data and models have nud to be evaluated and considered in is simpler to have one p,rocess and one est been developed for many SSCe for order to guard against inadvertent ut of mgulebone govening Uc nu inclusion in the PRAs. and uniform advene side effects on some other mnewalfor allnuclear power plante.

criteria do not exist for evaluating the upect of ufety.

For all practical purposes, there is no PRA results. However, as aging muarch sf. Nature o/ License technical distinction between the cleos progresses. It may become appropriate of nuclear power plante beensed under to use PRA to a greater extent in license

. An leeue that the Commission section los and the class licenud under renewal appucations.

Identified early in the rulemaking 6. the ocction 1Mb. Only the 1970 change in The planning for the management of legal neture of the license authonsing the AEA mandsted by Congress age.related degredation mflects the operation beyond that approved in the separates these two clanes of plants.

knowledge that materiale. etmoeore, the original opereting license. Industry Accordingly, the proposed rule makes operating environment, and toelt commentere suggested that exteded no distinction between section los and interactions contribute to age.related operetion could be accomplished section 1Mb power reactor ucenses.

depedation in SSCs. When these through amendment of the expiration Non pown macton. including muerch interactione cause depedation of date in the existing opereting license.

and test reactors. on the other hand, reliability and may impact safety, then After reviewing the Atomic Energy Act differ as a class from nuclear power age.related depedstion effects must be (AEA), as amended, and the relevant plants: they are not covered by this mitigated to ensure that the aged SSCe legislative history, the Commission will edequately perform their design concludes that extended operation of rulemaking safey functions.

nuclear power plante licensed under la sum the Comminaion has To gain the necessary understandin8 section los of the AEA should be concluded that life extension for Cf aging mechanisms, the renewal accomplished by issuance of renewed facilitiu with both section los and applicants will need to review the operating licensee.De Commiselon secdon 1Mb opersting licenses shall be achieved through leeuance of renewed system structure.or component design, proposes that extended operation of

' operating licenses, rather then through f:brice tion, ins tells tion, testing, nuclear power plants licensed under laservice inspection. operation, and section 1Mb of the AEA also be amendment of the existing operating telnunance cyclu.

eccomplished through issuance of license.The Commission does not The recognised elemente for timely

,,,g,,,,.ing ucasu.* Seedon g h W twm of a hm

- mitigation of age related degradation 103c of the AEA halts the term of authorizing extended operation as e5ects are inspection. survetllence'.

bensu fu commweial nuclear power having y substantialeffect on the condition monitonas, maintenance planu inwd unde ucum 10s to 40 technica aspects of hfe extension.

yeare, but provides that they may be ladeed. as discussed in the following Ighg",C'

8 d p a

mnewed u n upiration. Band on the section, the licensee.epplicant for a adjutments in operating envimament of AEA e exp cit prohibition oflicens*

renewed license la entitled to favorsble the equipment in which the degradation treatment under the Timely Renewal

occun, i vanwn swiew poww planu wm hemand Doctrine of the Administrative Adequate recordkeeping is needed on ne nee sh ad scelopeudemue.i ene" Procedure Act and 10 CFR $ 1100. This such items as transients, component failures. and root causes, and repair and O,h*MM ""m"6* * ","'o*ce w-e Reeesseh and toes sessiers..hich are heemoed replacement of componente. Records nadara fee ear power plant d eien. = bah woe e unde messe me er me AEA. m ste eet haswd

• • • 'y pmmwow tw smeno u epmnas W euww w ear parannar mem**w"n

• being generated now will be usefulin bann unen man m in w's b AEA wee Censueem hasL as a mener of proctice. answed providmg the technical bases ior asmendes so ubet etl eesumere el sucJoer power esmune he tw eust recibum tw shone' continued safe operation of nucleat

,is, on

,,,,m,,u

,,,,,w== na.e etwv power plants.

wrc sat be yvu e com im eemmas beensa name. es to rem

. - - - - ~ -.

- - - ~

Rderal Regist:r / Vel. 55. No.137 / Tuesday, luly 17. 1990 / Proposed Rules 20051 treatment le not available to en tum (s premised on renewal applications understanding of age related opplicant for a license amendment.

that are reuonably complete and degradauon effects.

sufficient when filed. In addition, the ne propond rule does not include a Aenewal

o. Lorest Date for filinh Aenewol Commission does not wish to encourage minimum term for a mnewed license Applicorion, the Time b filing of pro form 8 f**6I that may be requested by an applicant.

Doctrme endsufficiency of Aenewal ApFiccEon applicauone which am filed simply for De primary reason for such a limitation l

the sake of meeting the 10 CFR 2.100 would be to discourage mpetitive Section 9(b)of the Administrouve deadline. For these reasons, the renwd appucadone for mieuvdy short procedure Act (ApA) referred to as the proposed revision to i 2.100 requires a pende which

'boourm

• timely nnewel doctrine." provides that *eufficient" renewal appucation. By p

d am o

if a licensee of an activity of a making thle change the Commiteion to review, as well se h potential for continuing netun makes a " timely and does not contemplate lit!gation over the abuse. Upon consideration. the sufficient" application for renewal in

• eufficioney" of the application in order Commission believes that the renewal accordance with agency rules, the for a license to continue in force under existing license does not expirt until the time y renewal. Sufficiency is applicant's need for longet term appbestion has been fmally determined eenntially a matter for the staff to planning of its electric power generating by the ager>cy.ne timely renewal determine beoed on the required capacity will ordinarily motivate him to doctnne is embodied in the contents of an applicauon under seek a longer renewal term and that Commission's regulations at to CTR ll H.19 and H.20. It is enough that the setting of a minimum terta would be an 1109:

licensee submits the requimd reports, unnecessary constraint on flexibility.

If, et least thirty pol days pner to de analyses, and other documente required A. Effective Dose of Aenewedlicense empireben of an emoting beense authormns in such application. Det such any actmry of a conunuias nature, e beenue documente may require further Two alternatives were identified early he an apphcotion for a renewal or for a new supplementation or review is of no by the Commission with respect to the beense for the actmty oc authonsed, the consequence to continued operation effective date of a renewed license:(a) a aby under timely nnewal.

" tack on" license whichiakes efiect at pUc on be n

t e

,e,A*y gu'M"e'!o'""li of

• =>

• uca d 6 = aio" a uas a r=~d license, and (b) a 'superseulon-license The so day deadline for timely nuclear power plant licean renewal which takes effect immediately upon renewal contained in i 2.10e would not applications that willpresent one MC approval of the renewal provide the NRC a reasonable time to acceptable way of pre [ meet baring a renewal appucadon.De tack on approach is twiew an application for a renewed applicauon that woul LaitiaUy attractive, since. in ge..rel, operating licenu for a nuclear power enterion of a " sufficient" apphcation.

renewale oflicenses take effect upon plant. Staff review of a technically f.Korlie8f DateforTilitti APP o81/888 expiration of the pre existing bcense.

li complete and sufficient renewal application to projected to require Neither the AEA not the Moreover. it may be argued that " tack.

approximately 2 years. Any necessary Commission's current regulations on" licensing was contemplated by heantg would likely add an additional contain a hmit on how long before &

Congress, since section tosc of the AEA year. Therefore, the Commiselon expiration of the operating bcense a states that beensee "may be renewed proposes that i 2.100 be modified to nnewal application may be illed.

upon the expiration of [the specified require that nuclear power plant However, the Commiselon has decided license ters)." However. nuclear power operating license renewal applications to impose such a halt to ensure that plant licensing renewal is unipe in that be submitted at least 3 yeare prior to substantial operating experiosos for the a potentially long period may occur their expiration in order to take nuclear power plant to accumulated between b ncy decision to approve advantage of the timely renewal

'before consideration of the renewal a renewal app cation and the expiration doctrine.

application for that plant. no 30 year deu M h Mginal opmung um (in Renewal applications should be hmit established allows the licensee some caen se avch as 30 yean). m euentially complete and sufficient when ample time to plan for license renewal stilities need ample time to develop Blei Section 9(b) of the ApA confers or alternative actions.

alternative sources of power if the the benefit of"timel renewa!"to those who make a timely ikling of a " sufficientg. AenewalTerm license le not renewed.1f issuance of the application." although the current Although the AEA permits the renewed licean were kept in abeyance wordmg of b Commleston's parallel Commleston to Laous operating licenaea, for such an extended period, there rule in $1100 only refers to the timely including renewed licenses, with terms would be a great deal of snoortainty in Ahng of an " application for a renewal or of up to 40 years, the Commission has terms of the administrative finality of for a new license * * * " and does not decided tolimit the maximum term of a the renewal deciolon. As for the "upon include the proviso for a " sufficient" renewed license to 30 years beyond the expiration" language of section 10sc. the application.no Commiselon proposes expiration of the existag (provtone)

Coinmission does not believe that to modify i 1.100 to parallel the ApA's operating license.%e Commission Congress intended by that language to provision for a

• sufficient" apphcation.

believes that there is now sufficient preclude supersession licenses. Since Other consideratione lead the technical understanding of age related section 10sc provideo for licenses to be Commission to incorporate the degradation to justify permittas luued for a "specified period." it would requirement for a sufficient application extended oper9 tion for an addiuonal 30 be natural to speak of renewal following into i 1.100. First, the proposed 3 year years beyond er.piration of existing h "expirsuon d auch period." On deadlme for timely submission of licenue. However, a 30 year hmit on balance, the Commission has renewal applicatione is based upon a extended operation will. in the determined that a renewed license projected 3. year period for completing Commission a judgment. provide a should be in the form of a evpersession staff review of a nnewelapplication useful opportunity to vabdate and dh sung opmung beenu.

and any necessary heanng. which in nosene. if necesury, the current

ed:ral Register / Val. as. No.137 / Tuesday. July 17.19e0 / Propoud Rules 900g

f. con eat of ApplicadorwTecAnical renewal rule that explicitly imposes cpportunity shculd be provided.

1 backnt requirements during the ucense Renwal of an operat nglicense is plication review in order to:

enentially the[ fall under sectionanting of a Infirmorien senewal afh NRC's recoulderation of thmfore woul i

ne proposed rouwal rule identines (a) contro specine requiremente for the content of the adequacy of the curant licensing 200a(1)'s requinment for a beanns a renewal application.

basis (CLB); (b) require the NRC to use opportunity for "lasuance of a license."

Unless updated the information the " substantial increase in safety" and A contrary reading of section teta(1) submitted in the previous operating value/ impact tute to utred b to Cm would produce the anomalous result un b est u opmunity for huring is Dcese docket continues to apply and is moem & e inc:rporated into both the renewal acceptability of the renewaf provided for less significant license Ucense application and the renewed application's proposals for addressing amendments, but a headas opportunity afear that the backAt rule app (uese related depadation: and c)make is not provided for license renewal.

license docket under the provisions of Accordingly, the proposed rule will ll H.19 and M.33.

g in addluon. the proposed rule requires throughout the term of h renewed provide an opportunity for an interested roon to request a bearing. iia request the submittelof specineinformation license.The Commiselon does not spee for hearing in connection with a renewal related to the intepeted plant that a new backAt provision or a change casessment for age related depadation.

to the backnt rule is required.

application is panted, the Commission in general, the topond rule requires The Commission believn thatit proposes that they be hearin s that noewel app 'cante submit. for staff would be useful to explain how,in its conducted in accordance wit subpart G nView tad approval, a methodology for view, the current backAt rule would of to Cm part 2 as is customary for cuneing plant systems, structures, and apply to the review of individual licen*e nuclear power plant licensing componente for age related degrodation renewal applicauons, should the license proceedings.

and to provide the results at specine renewal rule be adopted. All age related At the license renewal workshop and steps within the spesoment. lt also requirements that the staff believes are in written comments. Yankee Atomic mquires that the applicant ducribe necepary to enoun adequate protection Electric Co. and several other utility 8

8 fw'i[out

[o

t. This is hsbf aIti o be t r e ch system. structure, and component for h same u the "7e equate protection pm d e

a renewal. Three procedurel proposals which pruent propans were not judged exemption" in 10 CR 80.10e(s)(4)(U).

were made:(a) a hmit on the number of stor be fued by an to be effective in preventing or Second. any age related requirements inte)non (ies that maf the provision in mitigating deletenous deredation.

necepary to enun that the plant will inte b)inlieu o operate in conformance with the current to CFR 2.749 for summary disposition, a

/.I.nrito mentallnformation part separate emaking, the re3 oe t.

ecategory a ti to ou e by Wnir""Co&l5*oi"'""" hE,"Y'ieh'5'%?e nt M 2'u CPA""

fever, would ruult in b af plication

't I ining t e beets cnvironmental effects that need to be

$,pa[fW d lon. ' ftead, the basis for being denied or substantially c nsidered in individual relicensing t oon 1

cetions. To the extent this study is such a conclusion will be explicitly N

successful. reductions in the scope and documented by the staffin a safety O'e a schedule hymud u an wi focus wiu be codified through changes evaluation report that pruents the ePpendu to a license rouwal rule, ti to CFR part St. The programmatic neults of the staffs !!oense renewal The Commission le disinclined to findings in the environmental assessment (E.A) suppo the present a$lowever,if a proposed requirement to develop special proceduru for bearings

!icadon revkw.

l' h***" ""***1 P*" dings. The Proposed rulemaking.10 part H.

address a related depadation goes timely renewal doctrine of the

- indicate ht the generic environmental beyond w t le necenary to ensure Administrative Procedun Act allows study will achieve some depee of adequate protection or compliance with es licensu to conunu opmting its succen.T; study will assess b fuD the curmat licensing buis, the staff facility until final determination of its range of NEPA issun that will need to must prepare a backAt analysis that renewal application even though its be reviewed in individual milcensing addtme6 the factors in 150.10e(c) and onginallicem has expind. Thmfm. a cetions.The propcoed action would be shows that the direct and indinct oosts licenses puhns a renewedlicene l;

relicone!ng under part H. NEPA issues ofimplementing the proposed whose application is yet to be acted l-it.clude need for the proposed action.

requinment an justified in view of the spon because of an incomplete bearing alternatives to the proposed action increue in the overall protection of the is not as substantially and directly environmental effects of the proposed public beelth and safety or the common affected as an applicart for an initial l

action, and alternative actions.The defense and security to be derived from operating license (OL). though the study will attempt to bound the full the propoud requirement.

renewal applicant's need for timely range of plants and sites in order that

1. Nectings contingency planning in view of possible cny issues eliminated or bounded by to Section teDa(1) of the AEA provides denial of renewal could be impacted.

CR part 81 will be applicable to se

'!%e staff also points out that the Large a number of plants as possible.

an interested person the opportunity to Commission has recently adopted The study will attempt to build from the request a hearing for the " granting.

changes to part 2(H FR 331% August f:undation provided by the EA for the suspending. revoking or amending of 11.1900). which reise the thrnhold Ior to CR part H rule.

any license * * *." Although " renewal" adminion of contentions. reduce of a license is not explicitly mentioned A. AccAfit Considerofions as an action where an opportunity for discovery assinet the stsff and The nuclear industry propoon that a hearing must be provided, the explicitly authonse 6 presiding officer new section be added to the proposed Commission concludes that a hearing to requin the filing of cross examination e

.------3-,

-*-----w-

l Fed:ral Reglet:r / Vgl. $$. No.137 / Tuesday, July 17, 1990 / Prop sed Rules 20053 p'lans (the Uni:n cf Csneerned Scientists

n. Emergency plonning Considerotions fit b proper functitning cf the licensee's emergency pnpanda se his filed a suit in the DC Circuit Section 50.47 and appendix E to part program (as denned in to CFR part 80, challenging the validity of the changes to establish requirements and oppendix F. section IV11tems 1 b part 2). These procedural changes are performance objectives to protect the through g) remain in a state of likely to be more effective in focusing public health and safety by ensuring the operational toedinese, without and expediting any necessary hearing existence, implementa tion, nvision. and significant Performance impairment due j

than & industry. proposed chang e.

maintenance of emerpncy to age.nlated degredation. Accordingly, With regard to the industry's preparednese programa for licensed the additional aging management scheduling reposal the Commiselon nuclear power plana.These provisions of the proposed to CFR part points out t at it has plenary authority requiremente apply to all nuclear power H rule am not needed for those facilities P ant licensees and require the specified l

to impose a hearing schedule. The Commission has exerceed that power levels of protection from each licensee and equipment.

eeveral times in beeneing proceedings in neardlus of plant design or

o. plant physico/ Security the past. Moreover, the Atomic Safety constructierL Section So.54(q) requires Considerations and ucensing Board or presiding officer that the emergency plane be maintained Ucensees must esteWeh and maintain until the Commission terminates the also possesses the authonty,in the license. The requirements of I S0 47 and a system for the physical protection of an mste a e rdanc absence of any e ecific Commission sppendix E an independent of the ayn directive on scheduling. to adopt a duration or renewal of b operating P

y, P

{

's d

ochedule for conducting the beanns.

e.

th con u o apply t Np ciaIbb sets o m Finally, the Commission believes that pmy. th material.

the scope of litfgeble fesues in a license To ensure that a licensee's plan The NRC reviews the status of renewal proceeding are much narrower rotect b health remains adequate to fic. NRC requires a physical security measures at each than in costruction permit and initial and safety of the pub cperating license proceedings. Technical detailed annual review of the facility's individual plant during the Systematic Assessment of Ucenses performance findings forissuance of a renewed emeryney pmpandness plan by license will focus primarily on age

• persons who have no direct (SA1.p). The NRC has also used Regulatory Effectivenne Reviews related degradation concerne (ne ruponsibility for its implementation.

(RERs) to determine site compliance 6 H.23 of the proposed rule) and included within b review is an l

therefom are much narrower than the to evaluation of the continued adequacy of with to CFR 73.58 and ensure that the level of rotection required by part 73 is CFR 50.87 findings for issuance of an applicable and appropriate maintained. The RER teams use NRC P

j taitial OL The scope oflitigable communication and working securfty personnel and members of the environmentalissues in a license nlationships with State and local noewel proceeding le also expected to governments.Ucensees must also U.S. Army Special Forces to test plant be limited by virtue of proposed to CFR perform an annual exercise or drill of security systems and personnel.

part 81 rulemaking and the generic theit emergency preparedness plan and The requimments of to CFR part 73.

cnvironmental document. In view of have h drill evaluated by the NRC notably the testing and maintenance l

l_

Cese factore, the proposed rule don not assinet definitive performance criteria.

requinments of to CFR 73.8&(s), include 1

i include any special hearms procedures These drilla, performance criteria, and provisions for kuping up the for license renewal.

Independent evaluations serve to ensure performance of security equipment continued adequacy of emergency against impairment due to age related i

l m Aeport of the Advisory Committee on propandness in light of changes in site degradation or other cases.

Ae:cierSofeguards characteristica, such as transportation Once a licensee establishes an Section142b of the AEA statu:

systems and demographics. Changes acceptable physical protection system.

occumns during the term of any changes that would decrease &

'fbe ACRs shaU revww each oppucation renewed license will be addrened just effectiveness of the system cannot be as changes an addressed during the made without filing an application for under seenen los or secnon toeb. for a Ucense amenhnt in occhce d sonstruenon permit or en operstmg Ucense der a facihty, any application under seenon "ifinal heense term.

The NRC has determined that the to CFR 80.64(p)(1),

losc. for a construenon permit or an current requirements, including Application for a renewed license will operenne beense for a twung factury, any continuing update requirements for mot affect b etandards for physical cppucenon under sectori tosa. or c.

emergency planning, provide reasonable protection required by the NRC.The spectftcaUy referred to it by the Comunauton.

assurance that an acceptable level of level of protection will be maintained and any apphcotion for an amendment to e sonnenon permit or na amendment to an emergency preparedness exists at any during the renewal term in the same operetua boense under seccon toe or 106a operating reactor at any time in its mannar se during the originallicense

b. or c. sporscaDy reformd te it by the operating lifetime. For this reason, the term. he requirements of10 CFR part Conunlesion has determined that no 73 will continue to be reviewed and Comalaion * * *.

new finding relative to the adequacy of changed to incorporate new information.

. The NRC will continue to Section 182b does not explicitly refer the emergency plans for license renewal as necessary!!ance of a!!!icensees.

t3 applications for renewal of an need be made. The Commission is ensure comp Cperating license as requiring ACRS proposing changes to 10 CFR 8047 to whether operating under an original review. However. a tonewed operating clarify that no new finding on license or a renewed ona through license is an operating license, an emergency preparedness willbe made ongoing inspections and reviews, application for which is explicitly as part of license renewal.

The Np.C has reviewed curnnt required by section st b to be myiewed The licensee programs the annual requirements for physical protection and by the ACRS. Accordingly, i 54.25 of the exercises, and the NRC inspection determined that they provide reasonable proposed rule mquires ACRS review of activities provide continued assurance assurance that an adequate level of a license renewal application.

that the facilities and equipment needed physical protection w!H exist at any

^ - - - -.,,

.,. ~

39054 Tederal Res: ster / Vcl. 88. Ns.1s? / Teesday. July 17. 1990 / Propos:d Rules t

reactor et any time in its operating review sf their financial qualificatitne power plant's operating license. Five lifetime. Based on the above the by the NRC during an operating Ucense years before an operating licenu is to C:mmission has determined that the proceeding. In publishing the final rule, expire, the licensee is required by to ediquacy of a renewal applicant's the Comnuosion stated:

CFR S0.&4(bb) to submJt wntten physical protection program will not be The Comminion bglievu that t!.c record of notification to the Commlulon for readdressed danns review of individual this rulemebas demonstrates genencally that review and approval of a program for license renewal applications.

the rete procue suuree that funds needed funding of the costs of management of e

nt d

tim b n

\\

p. Operotor Licensing Considentions

&l,*,Q*,*m*,"ja R*,*,*;g, *g*

P Individ::als who manipulate the such escurence wu the sole objeceve of the the spent fuelle transformd to the U.S.

controle of nuclear power facilities finsecial quahncauon rule. the Comminion Department of Energy for disposal in a concJudu that other than ta excepoonal bcensed under 10 CTR part 60. and spHa fuel mposHMoo nu years I

individuals who direct activities of those uns, no caubcan Ub3,eup of the perstion. t e 1 e nees a required.

NR Spect t ti ro si ti a This finding was band on a netional pursuant to 10 CR &c.75(f). to provide a l

Ifeense are set forth in to CTR part $5.

survey subautted by the nuclear preliminary decommissioning plan a l

which establishes & procedume and industry and the National Association of cost estimate for implementing the plan.

cnterie for inuing operator licenses and Regulatory Utility Comminioners and any c.hanpo in funding necuury to defines the terme and conditione under regarding the provision of opereting ensure that there will be sufficient funde which the NRC grante, modifies, and funds for nuclear power plants through for decommissioning. One year before renews these licenses. The licensing the rate makins process of State the license is to expire, b Ucensee proceu for individual plant operators is commissions.The study conduded. /nfer must file an application to terminate its independent of the facility licensing ollo, that rete-making authorities had operating license, topther with a I

procus, and no chenge to10 Cm part various mechanlems to ensure the detaued plan for decommissioning. In

$6isnecessary, evallability of utuity revenues sufficient accordance with to CFR 80.4L 1.lcense renewal of the facility could affect operators. however. in that to meet the costs of NRC safety 1f an operating licenst is renewed.

additional maintenance, surveillance, or requirements.More specificau,most decommissioning is poetponed until equipment replacement may be rete making bodies indicated at while on of &

edU m 'I'h e

necuenc/ at some plants. Plant no specific provieton was made for NRC CoWe dm m Meve ht personnel would be informed of and safety re utremente. rates are genersUy bcensees who fue their license renewal trained to handle these activities estimate to produce sufficient oversu applications should also be required to through training programe. Operetore revenues to ensure sound functioning of Proceed as if their facility wiu be are curmntly required to participate in electrical power systems, including decommissioned at the expiration of the pericdic training programe, which cover nuclear planta. Some public utihty curmnt operating beenes. Submiselon of important chanpa to the faculty or commissione indicated that their orders the funding sporte mquired by ll 8035 supporting prograrse and procedures, specifically allocete funds to meet NRC and to.4L as well as application for cnd to requahty for their Ucenses.

safety requiremente (se FR 38780).

termination of the operating beense and demonstrating this knowledy on a The Commission believu that this periodic basis.The requiremente for flading is also true for renewed decomminioning plan in accordance operator knowledy ut forth in to Cm opereting licenses for nudear power with I no.at will require substantial part S5, subpart L "Wntten plants.nerefore, the exclusions in licensee resources that will be wasted if Examinations and Opereting Tests." as il 50.57(a)(4) and L104(c)(4) with the renewal application were well as normal NRC review of plant respect to the need for financial reviews approved.8 The proposed rule addroun (perations, are adequate to ensure that of applications for operating licenses thou concerne by amending cperatore are aware of any license will be extended to applicante for ll 30.&4(bb] and 80.82 in such a way renewel developmente that may affect renewal of operating bcenses. The that licensees who fued sufficient their duties. In addition, the use of Commiselon concluded that the rete-sonewal applications, but have not yet approved plant simulators for test ng making process generaUy provides received a final determination on their individual plant operatore is required of assurance that funde needed for safe application, would not need to fue either all licensees by May 26.1991, and will operation willbe made avausble to the interim apent fuel funding plan or the not be affected by license renewal.

regulated electric utilities, it further application for termination and ongoing NRC inspection and licensing conduded that case by case Utigation of accompanyme detailed Cfforts wdl verify that important license the financial quellfication of applicants decomminioning report. The renewal developniente are adequately for operating licensee le not warranted.

Commiselon does not beheve that any addrened in the trairung of plant except in exceptional cases (se FR chany to 6 80fS(f)le necessary, since operators.

35750).The Commiselon also stated that the current wording may be interpreted gJinancio1 Qualification eeg{]ta to exclude licensees who have fuod g

mnewal ePpucations imm se the Atomic Energy Act concerning the in 1984, the NRC adopted changes to need for financial qualification reviews

' 8' 8 N **'

• d'inued seammesame Il 50.57 and L104 concerning the need (49 FR 38782)'

• "*'**d I'""** '8 Pl** *****d 8' ** 8"g**w'd 13 perform financial qualification

r. Decommissioning Considerations li, age ag y eene reviews of applicante for commercial nucleer power plant licenses (49 FR The Commission's current iermiessen ereseremen, A. c6 as as teen id 38747; September 111964).

requirements with respect to un peased kn me pinei paperenen and

• • • "** **d " 8 8""* 6 ** '**h*'** 3 Under the revised rule, electric decommiseloning assume that utilities that apply for or possess en decomminioning is the only option D"M",38T,"'",,"* "

34 g

(peratin6 icense are excluded from following the expiration of the nuclear de m e ween es iew l

~-*-~w--

,n---n-

f Federal Regleter / Vcl. S5. No.137 / Tuesday. July it.1990 / Proprsed Rules 28088 requiremente for submiselon of the the requirements of par

• 140 when the (1) NUREG-1412. " Foundation for the intene funding reporte.

original operating beense was inued.

Adequacy of the Ucensing Swee." Draft it le expected that,in consideration of Subsequently, the NRC reviews the for Comment. U.S. Nuclear Reguletory their planning needs, licensees will indemnity provisions and maku Comminion (USNRC). July 1990, crdinarily elect to apply for license required adjustmente se a result of (2) NUREG-1411. " Response to Pubbe nnewal well before the 6 year lead time further licensing action. In addition. the Commente Ruulting from %e Public of the decommiseloning plar ning nuclear power plant insurance poole Workshop on Nuclear Power Mont requirements of Il to.64(bb) and 80.82.

that form the boele for compliance with Ucense Renewal." USNRC. july 1990.

Thus, timing problems with roepe" ti the financial protection requiremente for (3) NUREG-tatt," Environmental contingency prepareuona for 10 Cm part 140 inform the NRC each Asunment for Propond Rule on decommissioning. in case renewalis year regarding any changes in insurance Nuclear Power Plant Ucense Renewel."

denied, would ordinarily not be or potential cancellations.

D. aft for Comment. USNRC July 1990, expected to arise.The req 2ement for Because au licensen are required to (4) NUREG-u62. " Regulatory submittelof a proposed comply with to Cm part too, and Analyste fu Proposed Rule on Nuclear decommiseloning plan le retained with because the NRC continues to ensure Power Plant Ucense Renewal," Draft for a proposed new previolon.

compliance with those requiremente. the Comment, USNRC. luly 1990, t 80 42(a)(1)(ll), to allow delay to within Commission concludes that the finding A free eingle copy of Documente (1).

1 year after dieepproval of an of compliance with part 140 need not be (3), and (4) above, to the extent of cpplication for a renewed license.

made in any individual nuclear power supply, may be requested by those plant opereting license renewal under 10 considering providing comment by

s. Anthrvet Aeview CFR part 84.

writing to the U.S. Nuclear Reguletory The proposed rule does not require Commiselon, ATI'N: Distr.ibu.ti.on V. Questises Souen. washin, ion. DC enutrust re,v,iew by the Attomey ma io=aa rhe Comm esion aviies,ubuc Co ie of au documente ened in ud, cea =i, i',

"U "' cts of this proposed Suppfem,entary Information are

) of t e N.

ch fe the

• • • • • "' "". in ad[ tion. the Commiselon avausble for inspection and/or for 5.(

rulemaking see o statutory basis for antitrust review of specificaUy solicite views concerning copying for e fee.in the NRC Pubbe commercialnuclear power plante Se foDwing quedone:

Document Room. 212e L Stmet. NW.

licensed under uction 103 of the AEA.

(1) Are there any specific equipment (Lower level), Washington DC.

makes clear that such review is required items, equipment categories, or topics in addition. copies of NUREGe cited in l

only for the initial app!! cation for that should by rule be excluded from this document may be purchased from construc pn permit (CP). or the irdtial review under the age-related the Superintendent of Documente. U.S.

u cpplicatan for operating license (if an degradation management program Government Prin Office. P.O. Sox antitrust nview was not done for the requirements of the propond rulet if oo.

37082. Washington.

200 4 7082.

CP), unless there are changes in licensee what equipment or toptos should be Copies eve also eveDeble for purchase cctivities or modificatione that would excluded. and what would be the from the National Technical lnformation constitute a new or substantisuy justification for euch emalusion?

Service,8245 Port Royal Road, l

different fecJlity. (Joint Committee On.

(2) Should any equipmentitems:

Springfleld, VA 32181.

l Atomic Energy. Amending the Atomic equipment ostegories, or topico ygtg, %,,,gg,,,,

Energy Act. H. Rep. No.1470, flot Cong..

ad Sese. Se (1970); S. Rep. No.1247. 31st (incle topics related to the alte, such se nearb hasards or demography) that A draft environmental assessment of Cong.,2d Sen as (1970).) Ucense may invo n changes over time be this rule has been propand pursuant to renewal wiu not mquire modifications

(

to commercialnuclear power plante added to the review requiremente under the National Environmental Policy Act auch that they will constitute e "new or the proposed rulet if so, what equipment (NEPA), the Council on Environmental differerit facility; therefore, an antitrust items, equipment ostegories, or toples Quality Regulations,40 CFR 1800-1808.

review by the Attorney Generalwould should be added, and what would be the and NRC"o regulations in to CFR part 21.

not be necenary. Nuclear power plante justification for such addition?

Under NEPA and to CFR Part si,the licensed under seedon 104b of the AEA (8) For sertain limited tochaloal lesees NRC must consider, as an integral part are exempi from anutrust review under with respect to which requirements how ofits decisionmaking process on 6e been established, some work on proposed action, the expected section 106c(3).

l environmentalimpacts of promulgeting imhementation and compliance remaine g,

completed. Unimplemented USla, the rule and masonable alternatives to J. Comphonce with 10 Cm hrt W Section170of the AEA(commonly such as Station Blackout and the action.The NRC concludes that refwred to as the Price Anderson Act)

Anticipated Transiente Without Saram, promulgetion of the rule would not establishes financial protection and C$le, and the " lessons learned" lesses sign 18cantly affect the environment, indemnification requiremente for NRC of the Systematic Evaluation Program and, therefore, a fuU environmental l

licensees.10 CFR part 140 codifies the are examples. le there a beels for impact statement le not required, and a mquiremente of ae Pnce Anderson Act.

removal of such issues at this time from Anding of No Sign 18cantImpact sen be The part 140 requirements with respeet the provision of 6 542 of the proposed made.The environmental assessment to nuclear power plante apply to all rule that the findings under to CPR and Anding of No Significant impact are licensees regardless of the plent's design 80.87(a) need not be made in order to issued as a draft, and public commente er construction date. Furthermore, tesue e renewed liceneet if so, what are being solicited.

licensees are required to comply with would that basis bet laplementing the proposed action would produce sesentially the same cny tevisions in part 140 thet are V1. Availability of Documents effects as would result from required as e result of changes in the Pnce Anderson Act.

The principal supporting documents of implementation of the existing license in accordance with to CPR 50.57(e)(5), this supplementary information are se renewal rule, since the proposed rule is cach licensee wee found to comply with foDows:

distinguished from the exist ac rule in

Federal Reglet:r / Vol. 85. No.137 / Tuesday. July 17. 1990 / Proposed Rules t

39086 that it would utablish the specific Under the propond license renewal 012. 0011. and 0021). Office cf criteria and standards for renewal.

rule, each licensee will be required at Management and Budget. Washington, wheren the existing rule is silent about the time of application to identify safety. DC 30603.

criteria and standards. However, the significant componente and structures of IX. Regulatory Analyana proposed rule would add discipline to the plant that an subject to aging and, the license renew al procen. tending in during the renewal term, to aness and De NRC has prepared a regulatory the dinctions of effective centrol of rak manage the apng degradation of those analysis of the benefits and costs of the and environmental consequences and components. Thne activities will ensure proposed rule and of a set of significant that a reactor would not continue to attematives. The analysis is reported in fevereb'e benefit cost reistionships.

Operate if the probability of radiological NUREG-122. Some highlights are Renewal under either the existing rule or release evente inenases significanuy preunted below.

the proposed rule would result in repair, during the renewal term because of The specific objectivu of the nvised nplacement, or nfurbishment of degradation of plant systems.Though license renewal rule are to establish the selected nuclear plant componente and elmilar obiectives would be required to standards that must be met by license structures that are subject to apng The be met under the eurnnt rule the renewal applicants, to define the scope scope of such activities would be current rule don not specigat would be the applications and to speelfy the the ofinformauon required for nyiewtna specific to each plant. based on an procedune and standards anessment of plant safety and involnd.

procedune for submittmg the e retien. Depending on the specific in eithu can, annual radioacti" applications. In order to determine the c nges required in each can, the

• • • te production is not expected to wtm fic content of the rule consiste sp,ci ese obiecoves.ibe,taff has 7,lante would,make thest cheg,es at aanse si,ntficancy f,om,etes du,ing ab td wns.b rne a t me r quire addftfon to a yea t r o ration lt m ti e at cov r the e

additional abutdown for as much as 1 to for a plant would. under either the alternatiwe that would meet thne 2 years prior to expiration of the initial existing or the proposed license renewal objectives se summarized below. (Also hc4 nee to accomplieb the chanps. A rule, ruult in about a to percent conaldered and covered in the cited full wtrk force of from 300 to 950 could be increase in the requirement for high*

report, but not included in the summary cn ette during this period, regardlen of level waste repository storage, some below, are alternative regulatory whether renewalle under the aktsting increase in the spent fuel storage positions on inves related to the j

rule or the propond rule.

capability at each individual plant. and environmental review and procedural The environmental impacts associated about a 80 percent incrosse in low level requirements.)The altemative sets of l

with repair. replacement, or waste storage capacity.

asfety criteria and standarde. reflecting refurbishment would be of the same in sum. the environmentalimpact of differing approaches and strsnpacies.

j magnitude as those experienced during no new rulemaking (i.e not establishing that were evaluated and compand in ather maintenance of nplacement ePecific criteria and standards for the regulatory analysis are as foUows:

ectivides conducted during the previous renewal) would be elmilar to those for Niernetin A Current licensing beels cperation of the plant. Occupational license renewal with the proposed rule:

(originallicensing basis, se amended to however, there would be an undesirable the date of the renewal application): no exposures resulting from these activities level of uncertainty and lack of additional requirements.

are expected to range from 270 to 1930 predictability in the plant relicensing This attemative is based on the person rome band on exposure data frzm previous maior maintenance Procese.

propostbon that risk significant changes activities. These impacts would not vary VIII.Paperweek Reduction Act in the plant's materiale and equipment significantly whether renewall*

Statement pnerally occur as a gradual, progresolve Process. Knowledge of plant condition.

accomphe d under the current or the The propond rule amende maintenance actions to keep up an propose e.

information collection requirements that adequately safe condition, and agmg The modifications,mpaire and are subject to the Paperwork Reduction management are all required dunng the replacemente undertaken in each plant Act of teso (44 U.S.C. 3801 et seq.). This original Ucensing term so weU as after would not entall chanpo to the overaU proposed rule has been submitted to the renewal.The current Ucensing basis.

design of the plant. Thus, basic plant Office of Manapment and Budyt for sperating parameters such as thermal review and approval under the topther with such future changes in requimmente as may become applic ble performance. Power output. and fuel paperwork requirements. Public to particular plants could thus be etilization would not,in pneral, be

,,norting burden for this collecton of viewed as adequately accommodating expected to change during any renewal informationis estimated to averap the evolvina technicalissues of plant term under either the current rule or the approximately 130.000 person bours per aging past the renewal date.

proposed action. Further. occupational response,inclu time for reviewing exposure and both radiological and non-instructions. osa esisting data

'Iba altemative would require the radiological minne from the plant sources, gathering an maintaining the lowest renewal expenditures but would would be essentiaUy the same whether data needed, and completing and be least intenalve in ar' dressing the renewalls done under the current or the reviewing the ooDection ofinformation.

advancing age degredation issues.

Niernative Ac F.xtension of proposed rule and are not expected to Send commente regarding this burden Alternative A to require assessment and differ in magnitude from those utimate or any other aspect of this experienced dunns operation prior to collection ofinformation including management of aging.

License renewal. The current everage suggestions for reducing this burden, to This altamative would place the occupational radiation dose per plant of the information and Records foUowing requirements on the Ucensee:

)

4:5 person reme per year (based on 1967 Management Branch (MNBB-m4). U.S.

(1) Systematic identification of systems.

1 l

clata)is expected to continue at about Nuclear Regulatory Comminion.

structume, and componente important to l

that level through a 20 year license Washington. DC 20555; and to the license renewal:(2) screening to renewal term.

Paperwork Reduction Project (3150-determme componente requinns action nw-r-

ls canage age related degradethn:(3)

The abjective cf this alternative respect 13 the proposed licene renewal sweeanent cf aging to provide the basis wruld be is seek the cl:ust possible rule. The rule. if adopted, wruld have a fit estimating the remaining service his safety equivalence cf renewal lic:ase prospective effJct gnly.Then are no af the components,foridentifying plants with new plants. in recognition of beenues curnntly holding renewed changes necepary to the operational the historic gradual tightening of safety nuclear power plant operating licenses; cad maintenance plau, and for requirements over the years and copequently, thm are no valid determining the parameter that should increasing evolution of more expectations that may be changed be monitored dunns the rer.ewal term:

comervative, more risk svene public regarding b tsrms and conditions for and (4)identincanon of agtng attitudes toward safety objectives of obtaining a renewed operating license, canagement activities to eneum that technological enterprises, notably As b Comminion has previously adequate margins of safety are nuclear power plants.

expreued in the Statement of proerved throughout the renewal term.

Altemative D would be the most Considerations for to Cm Part 52.

Altemative B would provide a formal ambitious in its safety objectives and which prospectively changed the and consistent structure to the licepee's highest in renewal expenditures.

nquirements for receiving design efforts to anus and manage arm' s Altemative B was chosen as the certincations, the backSt rule:

dunng the renewal term. The ruults of preferred attemative. Its intensive agm.g licensee sesessments also would management requirement, absent from was not tatended to apply to every regulatory provide informauen for an NRC Tmding Altemative A. is warranted by the

• ch'n which than8" "ttled expectsbons.

cf whether or not the renewal term importance of equipment aginf as the Gearly, the backat rule would not apply to a requested by the licensee is justined.

key safety inue in nuclear plant life rule which impond more etnngent extension and licene renewal and is mquimments on au futum appucants for As compared with Altemative A*

Altemative B offers the benefit of a weU justified on a cost benent basis.

construenon permJts, ma though such a rule The enhancement over Alternative 8 might arguably hm an adveme impact on a core intensive and :ysternetie program l

I offered by the selective or fuU P**'n "h' *** ***8id'"^8

• PP Y1^8 '

y b Mu

{U r go e Al emotives an D s' new-trod c n of a w an d

e e we an n & r nece a o

Alterne ve B wo invoIve greater renewalexpenditures than Altemative 4

'Y p p,ct ve e p e t v

ep ent cost benent bacia.

appbcant.

A. but ten than Altemeuves C and D.

See 84 m 18346-se: A'pril18.1989.

X. Regulatory Flexibility Act Ahernative C Extension of Altemative B to requin euessment of Certincation At the Novernber 19MG workshop and in written comments, the industry design diferences against selected new.

De proposed rule will not have a asserted that a backSt analysis for the pl:nt standards.

significant impact on a substantial license renewal rule is desirable to The ulecton of applicable new plant number,1 smau entities. The proposed ensure that the NRC engages in standards would be based on potential rule nts sorth applicadon procedurw risk importance and the practicality of and technical requirements for nnewed

" disciplined decisionmaking" when determining what addiuonal actions evercoming obstacles to the operating licenses for nuclear power modifications involved. Applicants plants. Nuclear power plant licensees do should be requi.ed by the rule to wsuld be requind to demonstrate.

not fall within the defitution of small address age related degradation.The through PRA sided analyses. that their businesses as defined in section 3 of the Commission believes that the industry specine plants' differences from the Smau Business Act.15 U.S.C. 631 the concerns in this regard will be schieved selected new. plant standards are not Small Business Sise Standards of the by properimplementation of the risk significant or that the plant and Small Business Administrator (13 CFR regulatory analysis process, the internal procedural changes are adequate. The Part 121) or the Commission's Slas nyiews by the Committee to Review cblective of Altemauve C would be to Standards (80 FR 80241: December 8.

Generic Requirements (CRGR) review of the license renewal rule by the ACRS, upgrade the safety of renewed. license 1965).

plants above the degree of safety that the analyses that are required by the had been domed acceptable for the XI. Non Applicabillry of BackAt Rule Paperwork Reduction Act the high cristnallicense term by weking to attain ne proposed rule addresses the degree of public interaction and the improvements envisaged for new procedural and technical requirements conunent which the NRC staH has plants in the more promisms and less for obtaining a renewed operating sought to date with respect to license difficult areas.

license for nuclear power plants. The renewal (e.g public workshops.

Alternative C weks safety Commluton hu not previously advance notices of rulemakmge), and enhancements over Altemstive B. but its addressed the policy. tehnical. and the public intmetion which the staff renewal expenditures would be higher.

procedural leaves unique to renewal of will continue to seek on the proposed Ahernative D: Extension of nuclear power plant operating licenses license renewal rule, as part of its Altemeuve B to require compliance with in a rulemaking. Accordingly, the obligation to comply with the all new plant standards.

proposed rule. If adopted, would not rulemaking provisions of the ApA.

Some limited compromises would constitute a "backfit" as defined in to la sum. because the proposed rule recenarily be involved, both in new-CFR 50.100(s)(1) and a backfit analysis does not constitute a backfit under to pl:nt requirements that it may not be need not be prepared. The primary CFR so,100(a)(1) because the reasons possible or practical to comply with and impetus for the backfit rule was underi the Commission's adoption in the fact that much retained equipment " regulatory stability." ris that once the of the t rule an inapplicable to the would not be free of all aging effects.

Commission decides to issue a license, kind of rulemaking being undertaken Without some tolerance for near-the terms and conditions for operating hm, and because the proposed rule equivalents or specific exemptions, this under that license would not be would not adversely affect licensees attemative may assimilate to the no-arbitrarily changed post hoc. Regulatory with respect to backfit considerations, renewal option.

stability is not a relevant issue with the Commission has determined that a l

l l

l

e g

39058 Federal R gleter / Vcl. 85. No.137 / Tuesday. July 17. 1990 / Ptsposed Rules backfit analysie need not be prepared

$ 3.100 stfest of enefy renewal application for a renewed operating fit the proposed rule.

apphasten.

license under part H of this chapter.

(a) Except for b renewel of an Final Comminion review wiu be N N I"N'

operating license for a nuclear power undertaken as part of any proceeding for 30 CM hrt 2 plant under 10 CFR 80.21(b) or 90.22,if, continued licensing under part 80 or part at leset 30 days prior to the expiration of 72.The Ucensee must demonstrate to Adminletrative practice and u estir huunuewi&g my NRC ht se elected sedum MU be procede. Anttrust. Byproduct acevity ofa conunulag nature, the consistent with NRC requirements for caterial. Cinehd informabon.

Heenen Ales a sufficient application for licemed ponession ofirrediated Environmental protection.

a renewal or for a newlicense for the nuclut fuel and that ee actions wi!! be intagovernmental mlation. Nuclear activity so authorised, the existing implemented on a timely beefs. Wbm materiale. Nuclear power ph.nts and bcense will not be deemed to have implementation of such actions requires reactore, penalties. Sex disenmination, expired until the application has been NRC authorisations. the bespee shall Source material. Special nuclear AnaDy determined.

verify in the notificadon that submittele matenal. Waste treatment and dispont.

(b)If the licemee of a nuclear power for such actions have been or will be JO CM Port A0 plant licensed under to CFR 80.21(b) o' made to NRC and shaU identify them. A 1

30.22 files a suf5cient a lication for oop of the notification must be retained Administrative practice and muwelof an opmung cease atleast by e licenen as a scord until procedure. Antitrust. Backfitting, 3 yeare prior to b expiration of the expiration of the reactor operating Claulfied informetion. Criminal penalty. esting license. the existing license will license or renewal license. ne bcensee Fire protection. incorporation by not be deemed to have expired until the shall notify the NRC of any sigrtificant reference. Nuclear power plants and application has been SnaUy determined.

changes in the proposed waste mectors. Redirition protection. Reactor olting criteria. Meporting and PART S0-0000ESTIC UCENSING OF

$"'",*[,*g*f"[gg,7"""'

T noordkaping mquirements.

PRODUCTION AND NEATION l

P C M ES

7. In i 80.82, paragraph (a)is tevind Administrative practice end 4.The authority citation for part to to read as foUows:

i cedure. Age.related degradation.

continues to reas in part as foDows:

l ckfitting. Claselfied information.

Authertty: Section ist. Es Stal 944, at Envirmeental protection. Incorporation amended (a2 U.Sc saan sec. act. es Stat.

(a) Any licenan may apply to the by mierence. Nuclear power plante and tas2. es amended (42 U.Sc settl * * '.

Commission for authority to surrender a reactore Reporting and recordkeeping

8. In 80.47 ph (a)(1)is revised bcsan voluntardy and to decommission requirements.

r*

8 8:

the facihty. Each application must be For the reason set out in the preamble accompanied.or preceded,b a and under the authority of the Atomic l 80.47 Emergency plena, Proposed decommissioning p an.

Energy Act of 19H. as amended. b (a)(1) Except as provided in paragraph (1) Ahw]sculty est permanenUy y27.1888.

Energy Reorganization Act of1974, se (d) of this action. no inf tial operating

0) For a amended, and 6 U.S.C. S&3. b beense for a nuclear power reactor will on8# operation. this appbcation must Commission is proposing to add a new be inued unless a Andingis made by be made within 2 yeare foUowing part H to 10 CFR chapterI and the NRC ht there is reasonable Pwinament cepanon of opmbons but proposing to adopt the followmg aneurance that adequate protection can noim &an1 ym prior to expiradon of amendments to 10 Cm parts 2 and 30.

and wiu be taken in the event of a es opmung boense.

radiological emergency.No Anding (U)For a facihty that has not PART g-RULES OF PRACTICE POR under this section is aseenaary for permanendy esand operstion and for DOMESTIC UCENSING PROCEEDINGS issuance of a renewed operating license a

ap a

1.The subrity citation for part 2

""d,10 CPR part N of this shapter.

n as bun docketed &is continues to road in part se follows:

8. In i 80.M. paragraph (bb)le revised c a('ca6on must be postponed fw est 8Pp Authertry: Section tel, as Stat tea, as to "*d se foUows:

period of time until a Anal determination amended (42 U.SC 3301). sec 301 as Stat.

1342. as amended (42 U.Sc SN1) * * *.

100.84 CondBueneof teensa.

of the renewal application has been made by the Commission. If the

2. Section 1.4 is amended by revising the definitions of "hcense" an]

(bb)For operating amolear power application for a renewed license is "Ilconsee" to med as follows:

mactors. b heenase shall, ao later than disapproved an application for termination of Ucense must be evbmitted 5 years before expiretiae af the reactor within 1 year of the disapproval of the I a.4 Dennemana, operating license, esbelt written SPplication for the renewed license.

actification to the Casuelaaion for its Ucense means a license, including a review and pre approvalof the (2)For a facihty that ha pwmanendy renewed license, or construction permit program by which the intends osaaed operetion prior to July 27.1988, leeued by b Commission, to manage and provide funding for b requirements for contents of b decomminioning plan u specified in Ucensee means a person who le management of aU irrediated fuel at the cuthorized to conduct activities under a reactor upon expiration of the reactor Parafrophe (b) through (d) of this section may be modined with approval of the license. including a renewed license, or operating license astu utie to b Conunimion to reflect the fact that the construction permit issued by the irradiated fuel and poneesion of the fuel decommluioning process has been Commission.

is transfermd to & Sentasy of Energy for Ltd ultimate disposal in a repoeltory, initiated previously.

However, no mport need be submitted if

3. Section 2.100 is revised to read as follows:

the licensee has timely Bled a sufficient

8. Part k is added to read se follows:

' Fed:ral Register / Vcl. 55. No.137 / Tuesday. July 17, 1990 / Prop sed Rules 3g059 PART $d-REQUIREMENTS POR polyvnerisation, viscosity, and dielectric (ill) Establish acceptance critaria CENEWAL OF OPERATING LICENSES

strength, against which the need for corrective PCR NUCLEAR POWER PLANTS Currentlicenshtg hos/s (Cla) meane action is to be evaluated and require the NRC's regulaments imposed on a that timely correcuve action be taken 8'**l *,*

particular tiuclear power plant at the when these criteria are not met.

ase.

time that the initiallicense for that Nucleorpowerplant means a Na purpou and scope.

Power plant was granted and the commercial nuclear power facility of a i

M.3 Defmiuona.

Ucenne's commitments for complying type decribed in 10 CFR to.21(b) or d M eWo"!"'u,uc.

o..

-i* Saa aa*=ni"i S' n=*

• so n I

iniballicense was granted, including Aenews/ term means the period of M.0 Infonnscon coUecuen mquimments:

OMB spproval.

those required to be documented in time which is the sum of b mmeining M.11 pubhc mopection of apphcations.

either the licemee's initial opersting number of yeam on the opereting license M.13 Completeness and accuracy of license application or Final $afetY currently in effect, plus the additional informeuen.

Analysis Report (75AR). Addabonally,it amount of time beyond the expiration of M.16 specific eumptions.

includes allmodifications and new the operating license (not to exceed to pp1Ir[uon-peneral mquirements impond by the NRC and years) which is requested in the mnewel tents o modifications and new commitments application. The tatal number of years informatan.

made by the licensee dunna the period for any mnewal a.1n shaU not exceed 40 ed.2 contents of appheauoo-sechrucal information.

of plan *. Operation up to flhng of the yem.

M.23 Contents of appbcauort-license renewal application and Systems, structures. and components envvenmentalinformauon.

remaining in effect at the time of (SSCs)/m

1. 1. 1. //"### #####/ **

M.18 Report of the Admory Committee on application that are part of the docket R**ctor safeguards.

for b facility's license. bee plant.

(i) Safety.related SSCs. which am M.tr Hunnte specif e requimments and commitments thou relied upon to remain functional M.as Standards for issuance of a renewed (and modifications and additions during and following design beste events

benu, thereto) include, but are not halted to to mm b inkgrity of b mac2r tb actor and Pa ill to e ut o e a d con r

ed cones.

at nea pre el 1O maintain it in a safe shutdown M.35 Requimments dunne term of renewed Parts 1.10, 30, 21, 30. 40, 30. 88. 72. 73.

condition, and the capability to prevent beenu.

and 100 and appendices thmto; orders:

MJr Addjuonal records and recordkeeping license conditions; exemptions: and or mitigate the conpquencu of squuements.

tocanical specifications. In addition, the accidents that could result in potendal Authertry: Secs SQL 103.1o4.181.181.14L current Ilconsing basis includes written offsite conuquences compareble to the ta3 ses. see, as siet. eas, est ess. eea. osa, commitments made in docketed to CT1 Part 100 guidehe. Design basis events are defined the same as in.10 l

eM. ess. se amended. not. 3M. 83 Stat 12a4.

licensing correspondence such as ce amended (42 U.S.C. asst 21:3. asM. rssa, bcomu mpomu 2 NRC bulleuns.

CFR 80.4s(b)(1).

$m**,*, $8N8"ui,[M$

generic letters, and enforcement actions (U) All systems, structures, and L

g that remain in e5ect at the time of components used in a safety analysis or U.s.t ust. 3e42).

Ea.nt evaluation for the licensing boele.

l application.-

Kasablishede me would include, but is not hmited to.

O'*"*IPN'I83*88 a documenia,f,fect/m program meansog,aasi s...es *ai g g,. g g g,3n a g,

...,,w,.e an...

s's e

or t

This part governs the issuance of Report. the technical specifications, and renewed operating licenses for nuclear h po funcdon the evaluations submitted to show continue 2 pwform 1h saJfe C'0,'s s'ol*2'f."""0'a d g eagf,*g'Z,fng iau =

gn=,0a* = ol

.ucce.sfZooom,hame a.afe,y swa -i.Pr-a w m raai m a.

l tal37u^;;&'!,'o'g;j"'dd * $at-Fim Protection, and Environmental L

Reorganissuon Act o 10 4 Stat.

function by another eyeten, structwo. or component and wiu continue to Qualt8 cation.

1842)'

function with sufhclent rehability to (10) Any. including notaafety.related.

l l

9 64.8 Dennmena, maintain the hoensing basis. This SSCs whose fauuro could pavent (a) As used in this part.

Program shallinclude as appropriate, entisfactory accomphahment of req" ired

' Aging mechanisms are the phyelcal or but is not halted to,inspectiorL eafety functions.

chemical processes that result in aging surveillance, maintenanos, trending.

(iv) Post. accident monit degradation. hw mechanisme include recordkeeping, replacement.

equipment as defined in to i

but m not hmited to fatigue. crack refurbishment, and the assessment of 80.es(b)(3).

growth. corrosion. erosion wear, thermal operetional ufe for the purpose of timely (b All other terms in this part have enbrittlement, radiation embrittlement, mitigation of the effects of aging

. the s)ame meaning wt out in to CFR 50.2 biological effects creep, and shrinkage, degradation.This program must er menonit of the Atomic Energy Act.

Age.m/oteddegrodotion means a (1) Se documented in the FEAR.

as apphoeble.

change in a system's, structure's, or approved by onsite review committees.

component's physical or chemical and implemented by the facility

$ 64.3 henrymessons, properties resulting in whole or part operating procedures.

Encept as specificaUy authorised by from one or more aging mechanisme.

(11) Ensure that aU system, structure, the Commission in writing. no l

Examples of change due to age.related or component safety functions and age.

laterpretation of the meaning of the degradation include changes in related degradation am properly mgulations in this part by any officer or i

dimension, ductihty, fatigue capacity, evaluated by the program procedures, employee of the Commission other than fracture toughness mechanical strength, and a written interpretation by the General i

l, i

j 30000 Federal Registor / Vgl. 88. No.137 / Tuesday July IF.1990 / Proposed Rules Counsel will be recognised to be binding i M.is speeme esempeona.

I ed.t1 centenes of appseemen-teennessi Womecem Upon the Commission.

Exemptions from the requirements of thle part may be granted by the Each application must include a I 64.7 1rrmen osmnwesomens.

Commission in accordance with I 80.12 supplement to the Final Safety Analysis All applications. correspondence, of thh chapter.

PePort (75AR) which pruents the sports. and other written information required by thfe part. ne communications shaU be Aled in I e4.17 pane e appaesse*

FSAR supplement must include an cocordance with applicable portions of (a)he filbs of an application for a evaluation of the aging mechanisme that to CFR 80.4.

renewed license must be in accordance are present and that result in with Subpart A of10 Cm part 2 and degredation of the plant's systems.

I e4.0 wwmemen esteesen ll 80.4 and 80JD of 10 CFR part 30.

structures, and components, and a i.

roeutromeetse Dess approveL (b) Any peon who is a citisen, demoestration that b effects of such (a)ne Nuclear Regulatory degradation will be effectively managed Commission has submitted h national. or agent of a foreign country, h throughout the renewal term. Each or any corporation. or obr enuty whic information couection mbuirementse Office of h Comminion knows or has mann to FSAR mut contain b foUming contained in this part to behm is owned, controUed, or infwmauon:

Management and Sudget (OMB) for dominated by an aben, a fordgn (a)Intayrotecfp/antassessment. An

. approval as mquired by the Peperwork corporation, or a fomign gove nment. is integrated plant assessment which Reduction Act of1980 (44 U.S.C. 3801, et ineugible to apply for and obts in a demonstrates that age mleted seq 4 OMB bu approved the beenes.

degradation of the facility e systems, information collection mquirements (c) An application for a renend structures, and components has bun contained in the part under control license may not be submitted to 'he identined evaluated. and accounted for zumber Commission mller San 30 ywe befom as nuded to asom est the facuiys (b)De approved information the expiretion of the operating Dc ense licensing beste wiu be maintained

.i oouection requimmente contained in this currently in effect.

throughout the term of the renewed part appar in (d) An applicant may combine in hoenee. Each license ropewel applicant 9 84.1t Pumas heposeen et apphaseena.

application for a rene9ved boense with abau identify.and justify any changes in Applications and documents' appucations for, other kinds of licenses.

the current licensing beste associated submitted to the Commission in (e) An appbcation may reference with age.related degredation. Each connection with renewal applications information contained in preview licean renewal applicant aball compus a list of documents identifying portions may be made avausble for public applications for licenses or boense of the current licensin6 asis relevant to N

inspection in accordance with the amendments statements, provisions of the regulations contamed correspondence or reporte iWed with the the lategrated plant assessment. to be

' in 10 CFR part 2 of this chapter.

Commission: provided that such submitted as of the application, and references are r.' ear and specinc.

maintainau ente describing'the surrent licensing basis in an auditable I ed.13 compemeness and seaweer et (f)If the appucation contains and retrievable form. Each applicant Restricted Data or other defense (a)Information provided to the information. it must be prepared in such. abaD review the current licensing beefs Commission by an appbcant for a a manner that all Restricted Data and compustion for the purpose of dekraining es systems, structures, and heense or by a beenen orinformation other defense information am separated components to be evaluated and the required by etstute or by th*

from unclassined information. in Commission's regulations, orders, or accordance wie i 80.330) M put 80.

acceptance criteria to be used in the -

heense conditions to be maintained by (3) As part ofits application and in integrated plant ascesament.This asmoment met:

the appucant of the licensee must be any event prior to the receipt of (1) Describe the appheant's

. complete and accurate in su material Restricted Date or the issuance of a mthodology, for the identincation of aH MPects.

renewed license, the applicant aball SSCs importsat tolicean waewal, as (b) Each applicant or licensee shall agree in writing that it will not permit defined in i 54J (a), and het the notify the Conuniosion of information anyindividual to have soonw to identined SSca.

identt8ed by the applicant or licensee se Restricted Data until an investigation is (3) Describe the appheant's having for the regulated activity a made and mported to the Comunission methodology,incluam' s selection eignificant implication for pubbe beslth on the character, association, and criteria, for the identincation of those cad safety or common defense and loyalty of the individual and the structwee and ocaponents that am security. An appbcant or heenew Commission shall have determined that enastituent elements of the SSCs on the violates this,

graph onlyif the marmitting such pmon to have acons to het from paragraph (a)(1) d this petion appucant or new falls to notify the

[tastricted Data will not endanser the that contribute to the pwformance of a Ceauniesion ofinformation that the common defense and security.%e applicant or beensee has identined as agreement of the applicant in this regard hokd SSC's safety function or whose fauure could prevent a usted SSC from having a significant implication for is part of the renewed license, whether performing its intended safety function.

l~=

defonn and security. Notification must public bealth and safety or common so stated or not.

and het sunkidentined structums and be provided to the Adminletrator of the I se.to centenes of appasseen. general componente,

1. d*'*8888-(8) Ducribe the applicant's cppropriate Regional Office within 2 working days ofidentifying the Each application shan provide the -

methodology for the 6dentification of informatiorL This mquirement is n.1 information specined in ll 30.33 (a) -

those structures and components applicable to information which is through (e). (h). (i) of part 80.

Identined in paragraph (s)(2) of this already requimd to be provided to the Alternatively, the application may section that are subject to an l

Commi:'sion by other reporting or reimace other documents that provide established effective program as defined i

updating requirements.

the information required by this section.

In i 64.3(a), which will continue to

FCdcrat Regleter / Vel. S5. Ns.137 / Tuesday, lu)y 1P.1990 / Proposed Rules 2g061 ensure the capability of the structures extent that security clasetacation (1)Each renewed licenu will contain and components to perform hir safety prevents disclosure, and obrwise be subject to the functione dunns the renewal term, and conditione set forth in il 80.H and het such identified structures and iHAF Meerstes.

80.56a(g) of this chapter.

componente and the apociated A t4!!ca of an opportunity for a (b) Each renewed beame will be established effective programa, hearing will be published in tb Fedeal tuued in such form and contain such (4)(1)For those et uctures or Register,in accordance with 12.105 of conditions and limitations. includmg components included on the list from part 2.1n the absence of a request kchnical opdncehm' u h parapoph (a)(2) of this section but not therefor Eled wl thin 30 days by a person Comalselon deems appropriate and included on & list from parapaph whose interest may be aff6ed, the necepary to addren age.related (a)(3)of this petica.dueribe and Commiselon may issue a renewed degradation, including such previolone operating license wihut a hearmg.

with respect to any u.tconapleted items brovide the bases for actions taken or to upon 30 day notice and publication once taken to manage the age.related of P c.at modincauon and such l

depadation or demonstrate, by in the Federal Register of its latent to do hmibbne a co, ddone se h n

evaluation. that the ege related so.

ComnJulon bebeves are required to degradation is not sirnincant with

$ HJS 9tanderes for leauense of a ensure that operetion during the period respect to the current licensing beefs.

N"***8 #88a**-

of completion of such items will not (U) Actions to manese age related A renewed beene may be leeued by endanger public health and safety.

degredation could include but am not the Commission. up to the full term Other conditions and limitations.

hmited to maintenance, component replacement, or refurbishment.

authorised by i H.31, based upon a including technical specifications. in the finding that actions have been identined curant booming basis that do not modification of operating practices; or and have been or will be taken with addrese age related depadation estabbehment of a propam to evaluate respect to age.related degradation of oontinue in effect for the renewed and tmnd effects of the depadation during the renewal term.The beels of those SSCs important to boense geen,

renewal. such ti.at there is reasonable (c)Each renewed beense willinclude any action could include informauon assurance that b acuvities authonsed b u m & W u 2 p m k et b concerning the component design mquiremente. functions. environmental by the renewed license can be conducted in accordance with b environment that were imQed pun i 90.36b ud re W d conditions, the depedation mechanlems, and any other relevant curant beesing basis. Such a Bading b current beeneing buis for the informetion se necessa to demonstrate will constitute a finding that the facihty g

gg g g, g

P sun e co tinu d sai o tion of M'

"0 beeup men e a

d a

(b Kre'mptions. A het of allplant.

oommon defense and security and the necessary to protect the environment specific exemptione panted pursuant to findinge under to CFR 80.87(a) need not during the term of the renewed licene anted be made in order to issue a renewed and willbe derived from informatien to CFR 80.12. and rehefs for thou

beenos, contained in the supplement to the pursuant to I 50.55(a)(3) environmental report submitted d reli f Y

688 1 88888ase W e renewed 80en88.

pursuant to 6 81.53(b) of this chapter. as y n ed on the basis of an e umed (a) A renewed beene must be of the analysed and evaluated in the NRC oorvice life or penod of operation bound clan fw which ee opwoung hoense moord of decielon3e condiens will by the originalliceue term of the currently in effect was leeued.

Identify the obligations of the licensee in facility, or otherwise n!ste to $$Ce

@) A mnewed beense willbe Leeued the environmental area, including. as subject to age.related degradation, a for a Exod pened of time to be specified appropriate. Mquimments for reporting justification for continuing these in the bcense but in no case to exceed 40 and recordkeeping of environmental oxemptions and rebefe must be yeare from the date ofissuance3e data and any conditions and moniterms provided.

(c) Mont modifications. A description term of a mnewalbeenu will be Qual requirements for the protection of the to the period of time rematamg on e monaquatic environment.

of any proposed modifications to the operanns license currently in effect at (d)The beans bastefor h facility or its administrative control the uma d &e approval of the renewed bunn a dl bdude h procedures resulting from the evaluation app acation lue the additiona period of current licensing basis, se defined in l

or analysis required by parapaph (a) or "u8 th hoenaw ut no acha H.8% b bdulon in b (b) of this section.

th Beansing beste M manen such as

$ 6423 centents et esosention-(c)The renewed Scense will become hoensee commitments does not change enwonmentowormemen.

effective immediately upon its issuance, h Iqal ctatus of mon manen unleu Each application must include an thereby Mndering the operating license environmental report that complies with previously in effect entirely ineffective spec 15caDy so ordered pursuant to the requiremente of subpart A of part 81 and superseded.

parapophe (b) or (c)of this secha; of this chapter.

(d) A renewed license may be 9 esas shouenoment emns term of esbeequently renewed upon expiration renewes amenee.

g

!a;,'g:s;',',*,""W"n:='*-""$*

ouras se== a a mnewed ucose.

-- a.--

licensees shall continue to comply with Each renewal appheation must be tofermd to the Advisory Committee on i 54.38 contenuemen of surrent seensens all Commission regulatione contained in Reactor Safeguards for a review and bases and eenemone of reneweg beenen.

10 CFR parte 3.1g,30. 21. 30,40,50. 51, report. Any report must be made part of (a) Whether stated therein or not, the

86. 72. 73. and 100 and appendices the record of the application and made following are conditions of every theretc which are applicable to holdere available to the public, except to the renewed beense toeved under this part:

of operating licewes.

39085

• Fed:ral Regletor / Vel. 55, No.137 / Tunday. July 17. seco / Proposed Rules i 64.07 Ao*Wenal mesees and Sled in the essigned mgulatory docket 14 CPR Part C3 rese'ekeeping movimunek and are evallable for examination in the h licenae shcll retain in an Rules Docket (AGG-10), room finG.

(Decket No, eD 4A6416-AD) e cuditable and retrievable form for the FAA Headquartere Building (FOB 10A).

AirwoWnen DkwheaMnnett term of the renewed operating license tooindependence Avenue,SW.,

Dougies Model DC-M W1h DC.

aU information and doeumentstio" Washlegte DC 2891: telopbane (302) 942 (MD42k DW43 (MD43), and mquired by, or otherwise necessary to 27-3112 er comgliance with, the his notice le publiebed pursuant to M

d paragraphs (b) and (f) of i 11.t7 of part p

l Deled at Rockville Maryland, this 10th day 11 of the Federal Aviation Reguladons Asasecy: Federal Aviation oflul i1880-(14 CFR part it).

Administretion (FAA) DOT.

F For the Nucleat Resuletory Commission.

leaved la Washington, DC se )ely to, geso.

Actioec Supplemental Notice of SamuelI Ch.

proposed Rulemaking (NpRM):

Deelm heehn M 8*civaary of she Commission.

mopening of comment period.

[FR Doc. so-t4600 Filed 7-1Ho sees am]

Manager ProgramManayementSaaff. Office ofshe ChiefCounsel.

epteenaarv:This notice revises an earber saAme ones tum.e peddons for mata-aMag Proposal to supersede an existing sirworthiness directive (AD). applicable CEPARTME.NT OF TRANSPORTATl0N Docket No.t 3274.

to McDonnellDouglas Model DCM41 Muoner: Air 1.ine pilots Association. (MD41), DC442 (MD42) DC+41 Federal Avietion Administraton Asyulodons Affected:14 CFR (MD43) and DC-047 (MD47) eenes airplanes, and Model MD48 airplanu.

ll 121.471 and 135.388.

which would have mquimd that certain 14 CFR N Descripuon of Mdon:N shanges Power transfer unit shutoff (PTU S/0)

ISummary Hetes No. PR.0017) would: Require increased minimum rest valves be removed from urvice and an for Right omwmembe who am improved valve be installed.Det Petitlen for Rulemaking; Summary of echeduled to Oy less than a bours in a two une of pmpoulwu pmmpud)fure during Poguone Roselved; Dispoeltions of 34 bour period to 10 bouro: limit duty dual bydreuhe system fal p,yg,n, gegy,g time to14 houn in a 3&bour period:

Bight.His action chanpo the part cosmev: Federal Aviation mandate 1 omiendar day tree of duty number of the specified splacement Administration (FAA) DOT.

every 7 days,even when they are volve and extends the public comment Actioec Notice of petitions for assigned reserve and/or training datin:

period, rulemaking received and of dispositions and restrict air carriere from interrupting Dafts: Commente must be received no e fuS t crewmember's rest by later than August 10,10eo, af prior ptitions.

h communicadag we Ma or her during a maaaaaaaa Send comunents on the sunessaem pursuant to FAA's rulemaking provisione governing the mquimd mt period proposalin duplicate to the Federal epplication, process. and dis ition Masoner's Aeosonfor AWiiom Aviation A.tministration. Northwest cf petitions for rulom (14 part De petidoner believes this rulemaldag Mountain Region. Transport Airplane 11), this notice contains a summary of is neessaary to ensure adequate root for Duectorate. ANM-103, Attention:

certain petitions requesting the lattistion tight anwmembers who transport th*

Airworthinese Rules Docket No. es-NM-af rulemaking procedurve for the Amortaan traveling public -

315-AD,17000 pacific Highway South.

amendment of specined provisions of Asoket No. 3 380.

C40ses. Seattle, Washington estet The the Federal Aviation Regulations and of pggyanoff Aem p g,dut,(a applicable service information may be obtained from McDonnell Douglas denials or wl&hdrawals of certain Anociaden (A1A) and Apockdon Corporetion st&B Lakewood Boulevard, petitione previously received. De da hre de Lang teach. California 80e01, ATTN:

purpose of this notice is to improve the Maurk! Aeroepdal(ABCMA)'

Business Unit Mana_ger, Technical public's awareness of and participation Asyulodens Affeessd14 CPR publications, C1-HCW ($440): or from in. this aspect of FAA's regulatory activities. Neither publication of this il 3.14s(c). as.14s(f),35.148, and 3L301 Whittaker Controls, lassa saticoy Estice not the inclusion or omission of Desenpden ofMilanthe Strut. North Hollywood Cahfornia information in the summary is intended petitionare propose abanges in both the 91806.%1e informetion may be to effect the legal statue of any petition Federal Aviation Regulanons (FAR) and examined at the FAA. Northwut or its final disposition.

the European joint Avieden Mountain Region. Transport Airplane Datsa:Conunents on petitions roosived Requirements OAR) with the purpose of Directorete.17s00 PeetSc Highway must identify the petition docket number reducing the differences between the South, Seattle, Washington, or at the 14e lavolved and must be aceived as or two.

Angeln Aircraft Certiacation Office, before: September 17.1980.

Maloner's Asesonfor she Mder asas East Spring Street. Lang Beach.

Accessses: Send comments on any he petitioners believe these reviatons Cahfornia, petition in tnplicate to: Federal Aviation to be beneScial to the public laterest as pea pusmesa aeronesattom ooerract:

Administration. Office of the Chief they will standardise the requirements, Mr.RobertT.Rasseto, Aeroepece Counsel. Attn: Rules Docket (AGC-10),

soccepts, and procedures is e Engineer.1me Angeles Aircraft

' petition Docket No.

800 oortification Sight testing and will Certification OfBce. Systems and Independence Avenue,SW enhance roeiprocity between he Equipment Branch. ANM-1311. FAA.

Washington. DC 30591.

regulatory agencies.

Transport Airplane Directorste. 3229 East Spring Street. Lang Beach.

poa pusmesa sosponesatsoes coerract:

I" D* 'bl#8'U~I** **8 '"I Cahfornia 80006-2428; telephone (213) he petition. any commente received.

'*'88 me en **

se64355 cnd a copy of any final disposition are

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The Honorable Silvio 0. Conte United States House of Representatives Washington, D.C. 20515

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Dear Congressman Conte:

i 1 am responding to your letter of October 9,1990, concerning the Yankee Nuclear L

Power Station (YNPS) and its plant life extension program.

The present license for YMPS expires July 9, 2000. At present, Yankee Atomic Electric Company (YAEC), has not applied for a license renewal thus a YAEC license renewal application extension is not under review by the Comission.

However, YAEC has informed the Comission that it plans to apply for a license Regulatory Comission (NRC)public meetings have been held at which the Nuclear renewal in 1991.

Several staff met with YAEC to discuss the scope of license

['

renewal activities for the Yankee Rowe plant. YNPS is the industry's pilot pressurized water reactor plant for the license renewal process.

The NRC has promulgated draft regi1ations (10 CFR 54, Federal Register 29043, July 17, 1990, Requirements for Renewal of Operating 1.icenses for Nuclear Power Plants) for public coment (copy enclosed). These regulations will govern the issuance of renewed operating licenses for nuclear power plents licensed pursuant to sections 103 or 104b of the Atomic Energy Act of 1954, as amended. The public coment period ended in October 1990, and the NRC staff is currently reviewing coments received.\\ Please be assured that the NRC staff will carefully consider all the public comments received, including those forwarded in your October 9,1990 letter, in developing final regulations governing license renewals. Also, be assured that members of the public have the opportunity to participate in a licensing decision relating to a future L

license renewal application for the YNPS.

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Sincerely,

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James M. Taylor Executive Director for Operation's\\

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Enclosure:

As stated

• See previous concurrence

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7 Document Name: GREEN TICKET NO.5943 Z

The Honorable Silvio 0. Conte United States House of Representatives Washington, D.C. 20515 DearCongressm\\

e Conte:

I am responding your letter of October 9,1990, concerning the Yankee Nuclear Power Station (Y

) and its plant life extension program.

The present license for YKrS expires July 9, 2000. At present, Yankee Atomic Electric Company (YAE'C), has not applied for a license renewal thus a YAEC license renewal app 11 tion extension is not under review by the Comission.

However, YAEC has info ed the Comission that it plans to apply for a license renewal in 1991.

Seve

)public meetings have been held at which the Nuclear Regulatory Comission (N staff met with YAEC to discuss the scope of license renewal activities for th Yankee Rowe plant. YNPS is the industry's pilot pressurized water reactor ant for the license renewal process.

The NRC has promulgated draf regulations (10 CFR 54, Federal Register 29059, July 17, 1990) Requirements fo Renewal of Operating Licenses for Nuclear Power Plants for public comen These regulations will govern the issuance of renewed operating licenses f nuclear power plants licensed pursuant to sections 103 or 104b of the Atom 4 Energy Act of 1954, as amended. The public coment period ended in October 199, and the NRC staff is currently reviewing coments received. Please be assur that the NRC staff will carefully consider all the public conments received in uding those forwarded in your October 9,1990 letter developing final regulations g'overning license renewals. Also be assured that members of the public have the ophortunity to participate in any staff review of a future license renewal application for the YNPS.

Please let me know if I can be of further assistance to you.

Sin erely, 1

James

. Taylor Executi e Director for l

Operations

• See previous concurrence 0Mb DR

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Document Name:

GREEN TICKET NO.5943

_____._..;,;.aww....__:....

,p The Honorable Silvio 0. Conte United States House of Representatives Washington, D.C. 20515

Dear.Congre ; nan Conte:

I am responding to your letter of tober 9,1990, concerning the Yankee Nuclear Power Station (YMPS) and its plant life extension program.

-The present-license for YNPS expires July 9, 2000. At present, Yankee Atomic Electric Company (YAEC), has not appl ed for a license renewal thus a YEAC

. license renewil. application extension s not under review oy the Cont..sion.

' However, YAEC has -informed the Conniss n that it plans to apply for a lic e

-renewal in 1991.-

Several cicar Regulatory Comission (NRC)public meeti gs have been held at which the staff met wi h YAEC to discuss the scopy 6f license renewal activities for the Yankee Rowe p nt.

YNPS is the indu fy's pilot pressurized water reactor plant for the 1 cense renewal proc The NRC has promulgated draft reguir.tions 10 CTR 54, F eral Register 29059, July 17, 1990) Requirementsifor Renewal of Operatin icenses for Nuclear 1

Power Plants for public coment. These reg lati will govern the issuance of renewed operating licenses for nuclear p we ants licensed pursuant to sections 103 or 104b of the Atomic Energy A -

f 1954, as amended. The public c ment period ended in_0ctober 1990, and HRC staff is currently reviewing coments received. Please be assured t t e NRC staff will carefully consider e

all the public~ comments received inc1 ing th se forwarded in your.0ctober 9,1990 letter developing final regulations overning license renewals. Also be assured that members of_the pub 1'.c have.t opportunit to participate in any staff review of a future license rene 1 application for the YNPS.

Please let me know if I can e of further assis ance to you.

Sincerel,

~/-

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(ames M.

aylor /

Executive ir cMr for Operatio

• See previo concurre D C ~ifbr 3 i, -~

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Please let me know i gl'can be of further assistance to you.

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Sincerely, 0

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-James M. Taylor t

Executive Director for im Operations li;

.L

Enclosures:

l J

11.. Greenfield Recorder article

^

[

concerning Yank ~ee-Rowe Reacto Vessel 2.

NRC letter to Yankee Atomic Elec ric l

- Cor:pany; dated. August 31, 1990

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• Se previous concurrence-1 ll. _.

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Sincerely, 3

t James M. Taylor

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Executive Director for /

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Operations

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Enclosures:

/-

1. - Greenfield Recorder article

/

. concerning Yankee-Rowe Reactor Vessel

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2, NRC letter to Yankee = Atomic Electric Company, dated. August 31, 1990

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OFF1t!ACHtDTC UPY LDocument Name: bREEif TICKET N0,5943 a

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NUCLEAR REGULATORY COMMISSitN =

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'+,..... p FROM:

DUE: 11/07/90 EDO CONTROL: 0005943 DOC DT: 10/09/90-FINAL REPLY:

R p.: Sillio O. Conte

TO

O Chairman Carr J: 'FOR SIGNATURE'OF:

• • GRN CRC NO: 90-0614

i Ex0cutive Director

>DESC:

ROUTING:

h":'

AND' SUSAN KRAMER ET;.AL.-CONCERNING YANKEE ATOMIC ENCLOSES--LETTERS FROM SANDRA REDEMSKE, BETSY EVANS TMartin, RI Beckjord, RES

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< DATE: 10/26/90

. ASSIGNED TO:

CONTACT:

NRR Murley

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SPECIAL' INSTRUCTIONS OR REMARKS:

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. RECEIVED NRRi-OCTOBER 26, 1990 a

" ACTION:

DRPR:

VARGA I

'NRR ROUTING:

MURLEY f

MIRAGLIA d

PARTLOW

. RUSSELL

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GILLESPIE ACTION TANA DUE TO NRR DIRECTOR'S OFFICE i

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OFFICE OF'THE SECRETARY CORRESPONDENCE CONTROL-TICKET a

i CRC 90-0614 LOGGING DATE: Oct.

9.90-T-

-PAPER-NUMBER:

1

. A'CTION ' OFFICE

-. 'EDO i.;

" AUTHOR':

Silvio' Conte--Const Refs

! AFFILIATION:

U.S. HOUSE.0F REPRESENTATIVES LETTER DATE:

Oct 9 90 FILE CODE:.ID&R-5 Yankee Atomic

SUBJECT:

Plant life extension program as it relates to-Yankee Atomic-nuclear power plant aACTION:

DirectiReply-DISTRIBUTION:

'OCA to Ack, Chairman

-SPECIAL' HANDLING: None

~

' NOTES:

DATE DUE:

'Nov 9 90 o

SIGFATURE:-

'DATE SIGNED:

' AFFILIATION:

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