ML20058B557

Forwards Biweekly Notice of Applications & Amends to OLs Re NSHC

ML20058B557
Person / Time
Issue date:	10/19/1990
From:	Murley T Office of Nuclear Reactor Regulation
To:	Graham B, Sharp P, Udall M HOUSE OF REP., ENERGY & COMMERCE, HOUSE OF REP., INTERIOR & INSULAR AFFAIRS, SENATE
References
NUDOCS 9010300295
Download: ML20058B557 (37)

Text

. _..

' October 19, 1990 t

IDENTICAL LETTERS SEtti TO:

(Seeattachedlistofaddressees)

The Honorable Bob Graham, Chairn.an Subconvittee on Nuclear Regulation Occmittee on Envitorx.ent and Public Works

'Jnited Statt s Senate Washington, D. C.

20510

Dear fir. Chairman:

Public Law 97-415, enacted on January 4,1983, arrended Section 189 of the Atomic Energy Act of 1954 to authorize the Nuclear Regulatory Consnission to issue and make irrediately effective at:y amendment to an operating license upon a determination by the Consission that such antendn.ent involves no significant hazards consideration, notwithstanding the pendency before the Conrission of a request for a hearing.

In addition, the legislation requires the Consission to periodically (but not less frequently than once every 30 days) publish notice of any an,endments issued, or proposed to be issued, under the new authority ebcve.

Enclosed for your infornation is a copy of the Conmission's Biweekly Notice of Applications and Amendments to Operating Licenses involving no significant hazards considerations, which was published in the Federal Register on October 3, 1990 (55 FR 40455).

Sincerely, Thorras E. Murley, Director Office of Nuc1 car Reactor. Regulation

Enclosure:

Federal Register Notilie cc: Senator Alan K. Sirnpson DISTRIBUTION w/o enclosure:

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The !!onorable Morris K. Udall, Chairnan Subccomittee on Energy and the Environment-Committee on Interior end Insular Affairs United States House of Representatives Washington, D. C.

20515 cc:

Representative James V. Hansen The Honorable Philip R. Sharp, Chairman Subcoramittee on Energy and Power Connittee on Er.ergy and Connerce United States }!ouse of Representetives Washington, D. C.

20515 cc: Representative Carlos Moorhead h

Federal Regleter / Vol. SS. No,13 / Wednesday. Osteber 8, tego / Nottoes 40455 ender onew provision of section

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of the Act.Tids provision pants the autnority toleeve and lamediately effective any t to en operatingliconee upon deterudaation by the Comunission inet g

amendment involves no sign &Aonat eensideretion, notwithstanding

/the pendency before the rhmmission of a request for a hearing from an wroom.

This biweekly notice includes all 4

motions of amendments issued, or proposed to be leeued from September 10, teep through September 21,1880. The last biweekly notice was published on September te,1950 (58 FR asses).

NOTICE OF CONSIDERATRON Of ISSUANCE OF AMENDMENT 10 i

FACIIJTY OPERA 11NG IJCENSE AND PROPOSED NO SIGNIFICANT HAEARDS CONSIDERATION DETERMINATION AND OPPORTUNITY FOR HEARINC -

N Commleelon has made a proposed deterannation that the following amendment sequestsinvolve no signlAcant hasards consideration. Under the Coaunission's regulations in to CFR 80.93, this means that operetion of the facility in accordance with the proposed amendments would not(1) involve a signlAcant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from.

any accident previously evaluated; or (3) involve a signincant reduction in a margin of safety. The basis for this proposed determination for each amendment request is shown below.

The Commissionis seeking 1

comments on this proposed

• public determination Any comments received within 30 days after the date of publication of this notice will be

- considered in makins any Anal determination. The Commission will not :

normally make a final determination -

urdess it receives a request for a hearing.

Written commente may be submitted i

by mall to the Regulatory Publicetions.

Branch. Division of Freedom of Stweekty Notlee AppRostione and Information and Publications Services, s

Amendments to Operating Laconese Office of Administration, U.S. Nuclear.

Involving No Signifloont Hasaries Cr-2:r'x Regulatory Commission, Washington.

DC 20665, and should cite the -

L Background publication date and page number of

,i Pursuant to public Law (P1)ON1&c this Federal Register notice. Written commente may also be delivered to the Nuclear Regulatory Commission the Room P.sts, Phillipe Building. 7330 ~

Comunisolos)is publisalag thle regula(r Norfolk Avenue.Bethesda, Maryland ~

btweekly notice. PL gr-418 revised -.

from 7:30 a.m. to 4:15 p.m. Copies of 4

section 1st of the Atomic Energy Act of written comroents received may be '

e 1964, as amended (the Act to require

the Commission to publish),nottom of any examined at the NRC Public D Room, the Gelman Buildi. 2130 L.

• amendments leeued, or proposed to be'-

Street, NW. Washington.

h filing O

1 i

40456 Federal Register / Vd 55, N2,192 / Wednesday, Ocitber 3,1990 / N:tices of requests for heeri and petitions for intervene which must laclade a list of provide [that its final determination is leave to intervene is iscussed below, the contentions which are so@t to be that the amendment involves no By November 2,1990, the licensee litigated in the matter, End contention signifieant hazards considerstion. %e inay file a request for a hearing with must consist of a specific statement of final determination will consider all respect to issuance of the amendment to the issue oflaw or fact to be raised or public and State comments received the subject facility operating license and controverted. in addition, the petitioner before action is taken. Should the any person whose interest may be shall provide a brief explanation of the

- Commission take this action,it will affected by this proceeding and who bases of the contention and a concise publish a notice of issuance e.ad provide wishes to participate as a party in the statement of the alleged facts or expert for opportunity for a hearing after

.f proceeding must file a written petition opinion which support the contention lasuance. The Commission expects that for leave to intervene. Requests for a and on which the petitioner intends to the need to take this action will occur hearing and petitions for leave to rely in proving the contention at the very infrequently, intervene shall be filed in accordance hearing. The petitioner must also A request for a hearing or a peution with the Commission's " Rules of provide references to those specific for leave to intervene must be filed with Practice for Domestic Ucensing sources and documents of which the

• the Secretary of the Commission, U.S.

Proceedings"in to CIP Part 2, petitioner is awere and on which the Nuclear Regulatory Commission, Interested persons should consult a petitioner intends to rely to establish Washington, DC 20555, Attention:

current copy of10 CTR 2.714 which is those facts or expert opinion. Petitioner Docketing and Services Branch, or may available at the Commission's Public must provide sufficient information to be delivered to the Commission's Public I'ocument Room, the Gelman Building, show that a genuine dispute exists with Document Room, the Gelman Building, I

2120 L Street, N.W., Washington, DC the applicant on a materialissue oflaw 2120 L Street, N.W., Washington, D.C.,

N555 and at the Local Public Document or fact. Contentions shall be limited to by the above date. Where petitions are Loom for the particular facility involved, matters within the scope of the filed during the last ten (10) days of the if a request for a hearing or petition for amendments under consideration. The notice period,it is requested that the leave to intervene is filed by the above contention must be one which,if proven, petitioner promptly so inform the date, the Commission or en Atomic would entitle the petitioner to reliet A Commission by a toll. free telephone call Lafety and ucensing Board, designated petitioner who fails to file such a to Western Union at 14800) 3254000 (in by the Commission or by the Chairman sapplement which satisfies these hfissouri t-(000) 342 6700). The Western ci the Atomic Safety and ucensing requirements with respect to at least one Union operator should be given Itoard Panel, will rule on the request contention will not be permitted to Datspam Identification Number 3737 e ad/or petition and the Secretary or the participate se a party, and the following message addressed to designated Atomic Safety and Ucensing Those permitted to intervene become (Project Director): petitioner's name and I',oard willissue a notice of hearing or parties to the proceeding, subject to any telephone number, date petition was e a appropriate order.

bmitations in the order granting leave to inalled; plant name: and publication As required by 10 CFR 2.714, a intervene, and have the opportunity to date and page number of this Federal ptition for leave to intervene shall set participate fully in the conduct of the Register notice. A copy of the petition f arth with particularity the interest of hearing, including the opportunity to should also be sent to the Office of the he petitioner in the proceeding, and present evidence and cross. examine General Counsel, U.S. Nuclear haw that interest may be affected by the witnesses.

Regulatory Commission. Washington, r.sults of the proceeding.The petition if a hearing is requested, the DC 20555, and to the attorney for the should specifically explain the reasons Commission will make a final heensee.

w hy Inters ention should be permitted determination on the issue of no Nantimely fdings of petitions for leas e with particular reference to the significant hazards consideration.The to intervene, amended petitions, f allowing factors:(1) the nature of the final determination will serve to decide supplemental petitions and/or requests retitioner's right under the Act to be when the hearing is held.

for hearing will not be entertained rnade a party to the proceeding:(2) the if the final determination is that the absent a determination by the j

r.iture and extent of the petitioner's amendment request involves no Commission, the presiding officer or Ae l

property, financial, or other interest in s gnificant bazards consideration, the p*esiding Atomic Safety and Ucensing th e proceedir.g: and (3) the possible Commission may issue the amendment Board, that the petition and/or request effect of any order which may be and make it immediately effective, should be granted based upon a entered in the proceeding on the notwithstanding the request for a balancing of factors specified in 10 CFR retitioner's interest. The petition should hearing. Any hearing held would take 2.714(a)(1)(i)-(v) and 2.714(d).

also identify the specific aspect (s) of the place afterissuance of the amendment.

For further details with respect to this subject matter of the proceeding as to if the final determina. ion is that the action, see the application for which petitioner wishes to intervene.

amendment involves a significant amendment which is available for public Any person who has filed a petition for hazards consideration, any hearing held inspection at the Commission's Publiu l ave to intervene or who has been would take place before the issuance of Document Room, the Gelman Building, admitted as a party may amend the any amendment.

2120 L Street, N.W., Washington, D.C.,

petition without requestbg leave of the Normally, the Commission will not end at the local public document room roard up to fifteen (15) days prior to the issue the amendment until the for the particular facility involved.

first prehearing conference scheduled in expiration of the 30-day notice period.

the procreding. but such an amended flowever, should circumstances change Ala ama Power Cornpany, W h petition must satisfy the specificity

d. iring the notice period such that failure 54364, loseph M. Farley Nuclear P! ant, l

requirements described above.

to act in a timely way would result, for UnH 2. Houston Couny, Mahma 1

Not later than fifteen (15) days prior to example. in derating or shutdown of the Date of amendment request: Augu.

I

'the first prehearing conference facility, the Commission may issue the 27,1990 s:.heduled in the proceeding, a petitioner license amendment before the Description of amendment request:

shall file a supplement to the petition to expiration of the 30-day notice period.

The proposed changes replace the

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-i Feder:1 R: sister / Vcl. 55. No.192 / Wedn:sday, October 3,1990 / N:tices 40457 cxisting heetup/cooldown curves found calculations were performed utilizing the Description 4f othendment requesf

}

in Technical Specification 3/4.4.10 with guidance contained in Regulatory Culde 1.00.

The proposed amendment wobld make new curves applicable through 14 Revision 2.W updated cmes)the mact"

. minor nomenclature changes consistent tovide offective full power years (FSPY) of 8y',p,%bge trecjm with Standard Technical Specifications; operation.%ese changes will allow g,,,

operation of the Joseph M. Farley consequences of a previously evalueted removes the requirements that the Nuclear Plant (Farley). Unit 2. beyond accident are not elsnificenny increased u a Technical Section Manager must hold a mult of this change.

Senior Reactor Operators License:

the 8 EPPY limit of the existing heatup

2. The proposed change will not create the removes the requirement that the and cooldown curves. Operation of possibility of a new or diffmnt kind of Operation Review Committee (ORC)

Farley, Unit 2 could reach the 8 FTPY accident from any accident previously Chairman be the Technical Section.

limit of the existing cteves as early as evaluated.

March 23,1991 The updated pressure. temperature Managen substitutes a requirement of i

enIaP ' b ny "within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />" for "immediately" for The proposed curves are based on the g$nglg,w, int k$d f reporting disagreements between ORC analysis of surveillance Capsule X that o

was removed from the Unit 2 vessel mviously evaluated. The revised operating members and the Chairman to the after approximately 6 41 EFPY The limits m merely an update of the old limite Senior Vice President Nuclear: corrects by taking into account the effects of the reference to 10 CFR 50.36(c)(1)(1) to analysis of Capsule X le documented by irradiation embrittlement, utilizing criteria 10 CFR 50.36(c)(1)(il(A) concerning 4

WCAP 12471, " Analysis of Capsule X defined in Regulatory Guide 1.90. Revision 2.

actions to be taken if a safety limit is I

from the Alabama Power Company, ne updated pressure. temperature curves are violated; extends the allowable ORC i

Joseph M. Farley Unit 2 Reactor Vessel conservatively ediusted to account for the Radiation Surveillance Program."

'ff'Ct8 OU"*d2duon on the hminns macto' review time from 7 days to 14 days for submitted to the NRC via Alabama vesul meterial. No physical chenges to the temporary changes to Power Company letter dated April 12.

plant are belns made, therefore. no new renumbers the pages. procedures: and modes of operation are provided.

Basisforproposedno significont Bases section 3/4.4.10 is also being 3.The proposed chenge does not involve a hazards consideration determination:

revised to reflect that the proposed sigmncant reduction in a margin of safety.

The Commission has provided he method for performing analym to hestuplecoldown curves are applicable guard against tmttle fracture in reactor standards for determining whether a for 14 EPPY of operation as well as to pfvoeure vessels as presented in " Protection significant hazards consideration exists delete Figure B 3l4.4-1 which is no

^4einst Non ducule Failure." Appendix G to -

(10 CFR 50.92(c))k operating license for a A proposed longer used Section 111 of the ASME Boller and pressure amendment to ar f illt I vol fi i

d ha r scons m io, de o one t

's h' It m*C p and

,consi erations if oper o of ti facility The Commission has povided 34 based on the reforence nil-ductility

.a accordance with a proposed standards for determininc whether a no temperature (RT ).These methods have significant hazards consittaration exista been und to set the operating limits for amendment would not:(1) involve a Farley Linit 2 and take into account the effect signiTscant increase in the probability or as stated in 10 CFR 50.92(c). A proposed of treadiauon on the reactor vueel materiale consequences of an accident previously amendment to an operating leense involves no significant hazards while maintaining a required margin of evaluated:(2) create the possibility of a ufety. Therefore, the proposed change does new or different kind of accident from consideration if operation of the facility not invoin a signihcant reduction in a an accident previously evaluated; or (3) in accordance with the proposed in of ufety,has concluded that the involve a significant reduction in a ma amendment would not:(1) involve a e licensee margin g sgety, significant increase in the probability or proposed amendment meets the three The licensee addressed the above consequences of an accident previously standards in 10 CFR 50.92 and, three standards in the amendment evaluated; or (2) create the possibility of therefore, involves no significant application. In regard to the three a new or different kind of accident from hazards consideration.

standards, the licensee provided the any accident previously evaluated; or (3)

The NRC staff has made a preliminary following analysis; involve a significant reduction in a review of the licensee's no significant

1. Operation of Pilgrim Station in ma in of safety ~

hazards consideration determination accordance with the proposed amendment abama Power Company (the and agrees with the licensee's analysis.

will not involve a synificant incruse la the licensee has reviewed the proposed changes)and has determined that the Accordingly, the Commission proposes probability or consequences of an accident to determine that the requested previssly evaluated.

requested amendment does not involve amendment does not involve a his proposed amendment does not alter a significant hazards consideration for sign c a, a e co a a on.

the following reasons, Re o ng t SRO r men en y 1.The proposed change will not foc, tion: gouston-ve yemoriay imposed on the Technical Sectic o Manager is significantly increase the probability or I.lbrary,212 W. Burdeshaw Street. P. O.

administrative. le consistent with STS, and consequences of an accident previously Box 1380. Dothan. Alabama 36302 allows a wider range of candidates for the evaluated.

Attorney position.The removel of the SRO Esq., Shaw.forlicensee: Ernest 1. Blake, Neither the probability nor the Pittman. Potts and requiremente does not effect the safe

• consequence of a previously evaluated eccident la increased due to the updoted Trowbridge 2300 N Street. NW~

. operetton of the plant because the holder of Washingtosi. DC 20037 th' " ' i' " "" " *h' 9 " **" t sh)e5' P' '

The mpere W

NRCProject Director: Elinor G.

NaNeYt.

ct$o andTra fng f talt!ine matettal was und to correct the Aden882 -

taluine pressure. temperature curves to Personnel for N'aclear Power plants." in tecount for irred.ation effects. Thus, she Boston Ediana Counpany, Docket No.O acc rdance with Pilgnm Technicat operating limits are adjusted to incorporate 298. Filgdes Nuclear Power Station. _

Specification 6.3 Unit Staff Quahfications."

ths initial fracture toughness conservatism PlyusoutCaenty,Massachadte _

Removing the requirement that the ORC Chairman be the Technical Section Manager pneent when the reactor vessel was new.

Dole O[4metidmerit request: August 9 does not Impact plant safety for the same The adjusted refrence temperature 1990

rusons, t

40458

' Federal Register / Vd. 55, ND.191/ Widnesday, October 3,1930 / Notic:s Substituting *wethin 24 hourf for Besed upon the above discussion the ensum that tV treceient evaluetmn of new tr: mediately for rqporting disegnements t etween ORC menibers and the ORC staff proposes to delet1nine that the teloads em bounded by previously accepted Chairman le to provide e concreta, proposd change does act levolve 8 e nelyses.nis examinauon, which will be rnsesurable time penod in pace of the vague significant barards consideration.

performed per the requimments of to Cm

• imtr*ediately." he 24 hout period is gg,7gypy3jgpggy,,ggg,g,

u wW ensum futum mioads ut Wu a consistent with Standard Technical lxotion: Plymouth Public ubrary,11

, significant incresee in the probabibty or i

6pecihcations.

North Stree., Plymouth, Massachusetts consequences of an accident previously Adding an (Al to correct the referente to 10 02300 evaluated. ne plant will continue to operate mithin the limits specified in the Core CFR S0.36(cllt)D)(Al does not impact the safe Afforne'/ for licensee! W. S. Stowe.

Opereting 1.lmits Report (COLR] and to take eneration of Pilgnm. and is strictly Dq., Bos'en Edison Company,000 the some actione when, or if, the limits are t

6 tm!nistrative. Changmg " Facility" to " Unit" Boylston Street. 36th Floor. Boston, exceeded as required by the current is a nomenclature change consistent w tth inandard Technical Specifications and is Idassachusetts 02199 Technical Specifications a.iministrative and does not impact selety, NRC 4ctingProjectDirector Victor B. ne proposed chanpes do not creete the humbering tl.e pages sequentially is also ger,,,

possibility of a new or di'ferent kind of occident from any accident previously s:ncuy admmistrouve with no impact on safe Boston Edison Company, Docket No. 50-esaluated because no physical altereuone of opnation-Extendmg time allowed for the ORC to 293, Pilgrim Nuclear Power Station, plant conf.guretion, changes to setpoints, or ti view temporary changes to p ocedures Plymouth County, Massachusetts e.fety hmits are proposed. As stated above, l sm 7 to ts days is consistent with Standard Date of 1mendment request % gust the removalof the cycle specificlimits does

'lechnical Specificat ons. It is an 21,1990 not inDuence, impact nor contribute in any administrative change that 6a made to reduce tr e number of special smgle-purpose ORC Description, of amendment request!

m ey to the improbabihty or consequences of eny eccident. The cycle-specific limits will be rneetmge comened solely to satisfy the 7 day The proposed scendment would chan8e calculated using the NRC-approved methods, the Technical Specifi.e.ation to remove The Technical Specifications will continue to

'W"I' ference that 6.9.B w e deleted e cle specific parameter !!mits, add require operation within the required core Addi e re 6 ternstive reqdrements for fi;cl opereting hmits and appropriate actions will p c on et t reflects en earl er assembling, upgrade the minimum be taken when, or if. lunits are exceeded.

e mendment enf,is made to explain the critkal power ration (MCPRI safety C. The proposed changes do not invols e a rambering seqt.ence in consideration of the hmits and changes to make the affected sismf. cant reducti n in a safety margin tank pages beira removed from Technical

'I echnical Specifications consistent with fety.' rela ed E;>ccifications. Deleung *d" from Table 6.9.1 the " Improved BWR Technical ces !

or u

ent.

r lects Amendment of March 1.

e Specifications for DWR/45."

The margin of safety presently provided by Uc8/8 forProPosed no significant the current Technical Specincetions remains echnIa Sp fl e t ncati e into 14g tm's Technical Specifications.

14tords consideration determinotion!

unchanged, ne proposed amendment stdl raquins operetion within the core limite as

/ tendment makes 6.9.1.d The Ccmm16sion has provided obtelned from the NRC-spproved reload v.recesssry and its renovel is standards for determining whether a design methndolostes and appropriate Un.inistralis e with no impact on safety.

significant hazards consideration exista actions to be taken t' limits are violated. The The proposed changes are admmistr.tive (10 CFR 50.92(c)). A proposed development of the hmits for future reloads e sd are cor.sistent wnh Starderd Te::hnical t recsfications.The preposed changes do not amendment to an opcrating license for a wiH conuinae to e nform to Gou mee da amer the cenngurabon of pilgnm. or th*

facility involves no significant hazards fj[ntauon eId$t dI heopersu n tocsiderations if operation of the facihty each future -

nc It;Ge p,9p9, in accordance with a proposed reload willinvolve e safety review to assure t. in in that operation of the plant within the cycle-changes does not involve a significant e,rnendment would not:(1) involve a specific limits wiu not involve a significant heresse in the probabihty or consequences significant increase in the probability or reduction in a margin of safety, of an accident previously evaluated, tonsequences of an accident previously

2. Alternofive Requirements for Fuel 2.The opershons of Pilgnm Station in evaluated:(2) create the possibility of a Assemblies s ~cordance with the proposed amendment new of different kind of accident from A. The proposed changes do not involve a w dl not create the possibihty of a new or en accident previously evaluated; or (3) significant increase in the probabihty or tafferent kirid of accident from any accident tr.volve a significant reduction in a consequences of an occident previously reviousty evoketed.

The proposed change does not alter Inargin of safety evaluated berause any future modification of equipmer t configuration or equiprnent. It is The licensee addressed the above fuel assemblies must be just!$ed by a cycle-a Pdnivrvtive and is consistent with three standards in the amendment sped $c nl ed analysis using an NRC-roved methodology.The reload analysis 1:andard Technn el Rpecincation: therefore.

spplication. In regard to the three so[1 postulate the same events previously cperatav P.c'm Station in acccrdance with standards, the licensee provided the trie proposea amendrient will not create the following analysis, analyted using hRC-approved re!oad design methodologies to ensure the transient possibility el e new or dif'erent kind of L Remove Cycle-specific Parameter e.:cident p?eviously evaluated.

Limits evaluation of the new reload core ic bounded by previously accepted analyses. This 3.The opervion of Pdgrun Stauon in A. The proposed changes do not involve e esamination, which will be performed per the atcordance with the pr.> posed amendment s.<nificant incresse in the probability or r*quirements of to CFR 5J.50. will ensure the w.ll not involve a syn.ficant reduction in the t..argia cf safety.

consequences of en accident previously modaned reload core will not involve a eveh.ated because the cycle. specific hmits e.gnif! cant increase in the probabihty or The proposed edn.in'strative changes do will still be determined by enelysing the consequences of an accident previously rat affect equipinent er processas impacting a eme postulated events previously ana!yzed.

es aluated. This proposed change will t' e margin of safety: hence, opersting pilgnm The remosel of the cycle specine limits from lisprove the response of the fuel performance le e"ordance with the proposed changes the Technit.al Specifications has no influence program and result la potential reductions in daes not involve a significant nduction in the or impact on a Design Basie Accident future occupetional radiation exposure and c a* gin of safety.

occurrence. Each Design Basis Transient and plant radiological nicases.

his change has been reviewed and e acident analyses previously addressed will B.ne proposed changes do not create the approved by the Operations Review be examined with respect to changes in the pouibihty of a new or different kind of C ommittee and reviewed by the Nuclear cycle dependent parameters using the NRC-6 ;cident from any accident previously S..fety and Audit Commities, ei> proved reload design methodologies to evaluated because any future modification of

i Fendeval Resister / V:1. 55. N2,192 / W:dnesday. Oct:ber 3,1W0 / N:tices

& 51 fuel enembhes will be justified using NRC.

transient is met Thefore, the proposed B ne prop:is'e'd ch$nen do notlevola tpproud methodology which wtil ensure charge does not insolve a sigruheent any changes to plant design or conheatetion confumience to esisting design hmits and reductton in the motstn bf utely.

ney only serse to conform the Technkel tafety ensi)sh bues This eum6netien.

t trnproved TechtiicolSpecifscrifions

$pecifiutions to "Improg ed BWR Technical which mill be performed per the requirements A. Proposed changes are made to make of to CIR R!ie. mill ensure the modified ulected uctions of Tethalcol $pecifiution*

$pecificatione for BWR/4s

• For this reeson.

reload core will not trute the possib ht) of a consistent with the " improved BWR the proposed changes do not creeto the new or d.fterent kind of accident from any Tuhniul Specificaticne for BWR/4s "

possibthty of a riew or edelt nt kind of cocident prev 6ously enlueted.

contained in NilsC.31tist, dated Apn119as.

u~c6 dent previoudy enheted C.ne proposed c.heryres do not involve e ab revised. To accomphsh this. Technical C. The change in the range og a ppj;,ep.it).

sign 6 hunt reduction in a oefety mergm 5peuhcotions were relocated and redundant of the MCPR and thermal power safety limits becevu any future snodifinuon of fuel cuernbhes will be justthed usar g NRC-requirements dele'ed to clanfy the fc*nat of 0.3 pel does not involve a sign 60 cent and improve reedobihty. In addition. tt, reduction 6n a utsty mergin. The, change in apprmed methmlology per the requirements

'ollowirig minor modihcations we*: inc.luded.

the tvector vessel water level sately limit to c.f to CPR 6049 This euminenon will ensure

1. The conditions for opphcot.ity at the the top of active fue! does t.ot involve e the modihcotion of fuel essen bhes does not MCPR and thermal pow er safety hmits are significant reduction in a esfety mergm involvt a sigmftcent reducuon in a safety tevtsed to be consistent with Technical baceuse it enanntains en adequate meram for tr.org:n 1 Upgraded Afin/ mum CriticalTower 1.pecihcotion bases and restated in pois to be c.acthe action before the wster lesel eutly compared to plant thurvmentation.

holio (A/CTR)Sofefy Limi; W rnuit of tha change is to inctesse the r,eches two thirds core height. No fuel A 1he proposed change daes not invohe a range of opphubility of the MCPR safety demap is predictedif the waterleulis cignifir ont inctesse in the probabahty or limit (and cortopondmgly decrease the tange maintained above two. thirds core height. A t

consequenen of an occident prn sously of apphcabihty for the thermal power safety reactor sepel waterlevel ufety hmit of the esslated The NRC approud trethodology hmit) t.y reactor steem dome pressure of 0.3 top of actio fuelis cons; stent with the NRC-used to dente the upgraded MCPR safety psid Specthcally. the reactor stum dome e proved " Standard Technital herit of104 apphed the ome enterie es that pressure of too pois conserts to 785.3 peig.

Specifications.,, NUREG.0113. Revision 3.

und to dense the current MCPR ufety hmit w hich is rounded off to 783 peig and roults in luued Fell 19e0 and the ' improved techmcal cf 107. The upgraded MCPR ufety limit e difference of 0 3 paid. This change does not Spn4fications. Accordmgly, the propond selve of )h4 ensures fuel claddmg protection trisolu a significant increase in the changes do not involve a sigmficant squhelent to that provided wlth the 1.07 probability or consequences of an accident reduction in a safety mergin.

enfety hmal maintemed in the sefety previously evaluated.

evaluauon for Amendment 14 to NI'Ds'.41 set.

2. Current Technical Specification 1.1 C to

3. Admin /sitclire Changes 1

P-A lGtST AR.ll). dated December 27.1987, deleted because it to redundant to the A The proposed ch6 iges include editerial the NRC approved the use of the 104 MCPR requirements of to Cllt 60 36(cIltlllil( Al and changes to update the Table of Contents.

safety limit for D lattice llWRs subject to the to Cllt 5013(b)(31 In the case that reector cornet grammatical and spelling errors.

f allowing constremte 1) the fuel hos a screm is accomphshed by andtrect means.10 cortect a reference to the I' mal Safety besmnma of hfe R fector of greater than or CFR to requires en snel) sis be performed to Analysts Report (PSARI. make the Techmcel squel10104 and cenelsts ni fuel tspes Pg a determine whether ufety hmits were Spmheshon fonnel conmnt and add lot BR. llpe s 6R. Cta a bE. or Cta a 3131. Il the esteeded when the direct serem signal failed inednrtently deleted in a p*evious fuelis at least I 80 weight percent N35 to perform es espected hus current amendment. Then changes add to the clarily bundle eutage enrkhment, and al the lower Technical Specafication 1.1 C makes no new and readabihiy of Technical Specifications entschment bundles residma in the core have requirements and mey be deleted.

and are considered to be entirely opetsted tot et Inst 3 tyclu 14ecoup the 3 he reactor Huel mater level utely administrative in nature Accordingly, the Pi!gr6m Nuclear power Station currently hmat is tevind from not less than 12 int.hes propopd changes do not involve a significant rnnts then constramte and will mnt them in obow the top of active fuel to greater then increase in the probabihty or connquences future reloods, the 104 MCPR utely hmtt the top of actne fuel No selety anal > ses or of an scendent previously evaluated presides the same degree of assurance for design bes4 transients rely on a teactor B. The proposed changes do not create the fuel cladding integrit3 as the 107 MCPR s essel water level safety hmit of it inches possibthty of a r.ew or different khd of safety hmit did for previously reload co ts abme the top of actiu fuelin addiuon the Wus, the consequences of accidents c.henge does not alter the automouc n' accident from any acddent prev'Ously previously en sluated are not significantly manuel response of the opetetors or plant en aluated beceuw no plant design of inctened The MCPR safety hmit does not equipment to any design basis transient.

configuration chango are involved, effect any physical e) stem or equipment that Therefore, this change does not involo e C. The proposed thenges do not invohe a could change the probabibty of en occident.

sigmficent increase in the probabihty or significant redi.ction in a safety margin heefore, the reposed change does not consequences of an occident previously becoup they do not affect any operating Invohe e signi icant increase in the euh.eted.

practices, hmits. or *efety.related equipment.

prol4bthty of any accident previously 4l An ettematin action statement is added noe changn han bon nyiewed and sutusted.

to lechnical Specification 31J11 in the event apptsved by the Operations Review it Adoption of the prvposed MCPR ufety that the trastmum fraction of hmiting powet Committu and reviewed by the Nuclear hmli vela don not effect the function of any density (h0VD) esteeds the fraction of Safety Review and Audit Committn.

component et s>eem Therefore the rated power (PRP). Specifically. the APRM Dased on the above discuselon, the proposed change does not create the gotn may be ad6usted suc.h that the APRM staff proposes to deterrnine that the ponibthty of a new or different kh.d of cec 6 dent from any accident previously readmas are 3 eater then or equel to MIVD.

proposed change does not involve a in heu of edlusting the APRM ectem and rod cs aluated.

block trip setpoints. Both alternettve actiona significant hazarde consideration.

C ne su of the 104 MCPR ufety hmnt ruult in concerntive edluetments in the Locol/'ublic Document Room J

teflects the utthannon of cureent General APRM netpoints and provide adequate locatione Plymouth Public Library.11 Electnc fut design and does proude the protecuon from escoeding ufety hinits.

North Street. Plymouth. Massachusetts name margin of ufety as 107 does with older nerefore, this change does not involve e 0 300 General Electrtc fuel t) pes as discuped in significant Pureen in the probabihty or es atuauon. Because equtvelent fuel cladding consequences of an accident previounty Aflorneyforlicenseet W. S. Stowe.

the previously referenced NRC safety evalueled.

Esq., Boston Edison Company,800 protection is rovided with the 1.04 MCPR As di-naad above, the proposed che.riges Boy 1aton StrMt. Mth Floor, Boston, safety hmit, t e design critenon that so a do not levolve a significant incrosse in the hiassachusetts 02199 percent of all fuel rode do not experience probabatty er sensequences of an accider.*

NRC Acting Project Directon Victor teihng trenettion following any dwisn beste previously evaluated Nerses i

u_.

40660 Federal Reg 6stee / Vol. 65 No.192 / Wednesday, October 1,19eo / Notices Corolins Powe'e & ught Cesapany, et al, cuabfwetiset prese== has beam twelaer 4 for to estad so years. For the past severel Desset Nos. 9s 338 and staat, DbtJ> to ensive thei aestwarmaal Bnsnamic8. Staass Doctr6c Plant, Unita 1 quabhtst6am to annessassed tleeughest she tafe years it hos been the NRC's practire to estend these licenace vpon request from med 1, DnensmM Ceesnty, seerth si se le@ey e abasqsue to agusemanal the licensee with adequate justification

'",',M to regain the difference between tLe OL Carolina Dole of amendments te pur:st A.: gust nqunt?llie popeeM orasmshment artil an CP duratione.

17,19ft7. ae supplemented May 30,1WO, mnety anm a hat e yem spassene of the 80sss forpronosedno significant 8

June til,1990, and Jul 30,1 hn as,p unne-

/mmds consicferosion deferrninotion:

3 Dwirtson of omendaients request

2. m proposed amendment dose not The Commission has provided Corohna Power & bght Company has

$*['fNdd yS pr standatds f r determining wl ether a no o

requested etiensions of the emptration y

dates for the Brunswid Ste4m Dectric ennested tiocuee the proposed chargpe significant hata*ds consideration estats introduces no new a, ode of plant operation as stated in to CFR LO.92(c). A proposed Plant (IISEP), Unit Nos.1 and 2.

rior does it require phre6 col moddnetton to amendment to an operating license operstmg beenses (OL) from the present uw rient.

involves no significant hasards da'es of February 7,2012 to September

s. m proposed seendment does not consideretion if operation of the facibt) ft. 2(Titt, for Unit 1 and February IA atrio, inveto e e snthennt redachon in tie merinn in accordance with the proposed to December 27,2014, for Unit 2. The of nfety.The seem of safety ootabbahed in strendment would not:(1) involve a current espirelion dates are based upon e onamn 16DiMR to tened on e significant increase in the probabillt) or the constrechon permit (CP)inuance

[(,*,N,$,'

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consequences of an eccident previously date oflebruary 7,1970. At the time the as ynt penod eutusted, or (2) create the possibility of full power OL were issued. It was NRC ne beensee has concluded that the a new or different Lind of accident from practic e to specify an expiration date of proposed amendments meet the three any accident previously evaluated, or (3) 40 years from the date of CPissuance, standards in 10 CTR 50.92 and, involve a signihcant reduction in a

' Itis resulted in an eflective OL of 31 therclore, involve no sigafficant hazarde

• • '8 " 'I** M '

l F

years and 6 months fot Unit 1 and 25 conalderation.

Carolina Power & Ught Company (the years and 2 months for Unit 2. NRC The NRC staff has made a preliminary lice nsee) has reviewed the proposed Merulations (10 CFR 50 $1) specify that review of the licensee's no s!gn!ficant changes and has detarmined that the such heenses be issued for a period not Lazards consideration determination requested amendment does not involve to esceed 40 years. f or the past several and agrees with the licensee's analysis, a significant batards conaldercuon for years it has been the NRC's practice to Accordingly, the Commission proposes the following reasons:

estend these licenses upon request with to detennine that the requested 1N adequate justification from the licensee I"*I" *r"l*ew! e'erndment dan not amendments do not involve e significant

8"d '"' S " " '" 8*

to ternin the differente Uween the OL hasards considershon.

probabihty or careequenr.as of an seddent an CP durations.

3*I"*! '"I"*

• d b" * "" O' P * "' " "

LocalPubhc Docuncar Room Y

I Bosis forproposedno sigmficant d

haeords consioerofJori drierminotaan:

location: University of North Catchna at

",'gi,

$*,','dM,'tN,Yn, Wilmington. William Madison Randall p

The Comrolnion has provided Ubrary,1i01 S. College Road, f:nvamnmerital Report and i%AR (Fir el atandards for determining whether a no Wilmington, North Carolma 28403 3297, 4;,f,,y Anahais Reportl anatyved for e s'gnificant hasards consideration exists Attorney for heensee: R. E. lones, and parems m in place to detect ebnormel minimurn of to years of opereihm. Procedures aa stated in 10 CFR 50r(c). A proposed GeneralCounsel, Carolina Power A dewrioreuen end asms of criticel plant amendment to an operating hoense Ught Company, P. O. Dos 1551 Raleigh, coinconents. A con.prehenske envinmmentel involves no significant hasards North Carohna 17en2 quahlication program has been deieloped for coMiderat on if operation of the facihty NRC Project Directorr Elinor C.

trie Robinson plant to ensure it at in accordance with the proposed Adensam

""onmental quahncebon is ma6ntemed amendment would not:(4 involve a thronshout the hfe of the facihty No chenges significant increase in tht probability or Camhna hwer & UgM Company.

to wnetmnel restrictions or physic al consequences of an accident presteusly Docket No. !E381 H. B. Robinoon alteratinns to the facil.ry will be erede es e evalvsteJ; or (2) create the possibility of Ste am Electdc Plant, Unit No.1, enut' of this recunt. W propnnd a new or different Mnd of accident from Darlington County, South Carolina em ndm t wi m y one a ful! 40 wars any accident previously evaluated, or (3)

Dofe ofomer:dment request: August

1. m proposed amendment don s.ot involve a significant reouction in a 17.1987, as supplemented luly 9.1@0.

create the possibihty of a new of thfierent innrgm of safety.

Description of att'endment request Mnd of accident trum any accident previnusiv Carchna Power & Ught Company (the Catchna Power & Ught Corapeny has evaluted because the proposed chaare beensee) ho review ed the proposed requested an estension of the espiration introduces no new mode of plent operetton thangn anJ has determined that the date for the H. R Robinson 5 team nor don it require phpic.) modAcatione to requt9ted amendments do riot involve a Electric Plant, Unit No. 2. (l!BR2l the plant.

signliscant hazards enneideration for the operating license (OL) from the present a N propond emendment doce cot fallowias reasons:

date of April 13,2007, to July 31,2010.

Inwin a Osnhant reduchon M de ma$a 1 W preposed emendrnent don not The current expiration date is based

,'f,'

,'k]h *,

[,*h*,

I" levohe a significant increen in the upon the construction permit (CP) probabthey or consequences of en accident minimum ereist;onalperiod of 40 maht cetions have bon made la tkurs No prestously evaluated because the plant was issuance date of April 13,19C?. At the e

designed and constructed on the basis of 40 time the full power (OL) was issued.1 Robinson p!ar.t which odarsely effect the was NRC practice to specify an conclusions of the Robinson p arnt ISAR. Tt.e u'n f t cili f a expiretion date of 40 years from the date propond amendrnent mmly p ovido this A anat e r s.t.nimum of 40yests procedares and of CPissuance.TNs resulted in an 4% ear period.

programs are in place to detect abnormal effective OL of less that 37 years. NRC The 1.censee has concluded that the deteneration and eFes of critical plant Regulations (10 Cf R Sahl) specify that proposed amendment meets the three entaranents e corvrehensive enttrcueental such licenses be issued for a period not standards in to CFR SOM and.

l l,

]

1 Fedetal Register / Vd. $5. N N 192 / Wedn:sday. Octeber 3.1990 / N:tices 40461 4

tierefore, involves no algnificant consequencs

• of an accident previously Although thEplent vent radiation monitor hazards consideration, evaluated, or (2) create the poe61bility of don not perform any ulety relaled functions The NRC staff has made a pteliminary a new or different Lind of accident from to prennt or to mitigste the conuquenen of review of the licensee's no significant any accident previously evaluated; or (3) eny analysed and unenetyred accidents. its hazards consideration determination involve a significant reduction in n

[d to r q red o m n tor 7n e e i

and agrees with the licensee e analysis, margin of safety, te Accordingly, the Committion proposes Carolina Power & Ught Cornpany (the detnton epociated with the replacement plant opmtion is within limits. no fin e i

to determine that the requested licensee) has reviewed the proposed plant vent radiation monitoring system hos e I

amendment does not involve a changes and has determined that the equal or greater equipment performance significant hatards consideration.

a Loco /Pubhc Document Room requested amendment does not involve specificahoris compmd to the en,istmg locolion: Hartsville Memorial Library, a significant hasards consideration for detectors.

Home and Fifth Avenues.Hartsville, the following reasons:

The detection of particulete radiation also i

South Carohna 29535

1. Operation of the facihey,in accordance improves because the new isokinetic sample with the proposed amendment. would not noulee have e greater particle collection Attorneyforlicensee R.E.lones.

Lavolve a significant incrop in the efficiency. The replacement plant vent General Counsel. Carolina Power &

probability or corwequences of an accident radiation monitors are installed in the same IJght Company. P. O. Ilox 1551. Raleigh, previously analynd.

location *e the esist na offlme detectors, so North Carolina 2?002 Regardirig the probability of previously there is no significant change in the semple NRC Project Director: Elinor C.

analysed accidente the instrumentation transport tubing Therefore. there is no Adensam changes w hich require the proposed sigraficant decrene in a margin of urety.

amendment merely provide effluent This effort requires changes to the plant Catuline Powet & Light Company, accountability. Neither the esisting moniton Technical Specifications to correctly identify Docket No. 80 261. H. B. Robinson not the new monitors participate in any instrumentation which tr onitor plant gaseous Steam Electric Plant, Unit No. 2.

accident sequence, therefore. N new effluente, ne Technical Specifications will Dettleston County, South Carolina monitors cannot increen the probability of also be revised to ehminate the requirements Date of amendment equest August any accident previousi evaluated.This of the condenser eistustion system todietion propowd amendment on not increen the monitortr g equipment. This equipment is no 21,1990, se supplemented September 19.

probability of a previously evaluated longer a Technical Specification requirement 1990-accident because it upptedes instrumentation since effluents from this system are Description of amendment requeste doigned to follow the coune of an occident escharged to the plant vent and are The requested changes to the Technical and thereby reduces the probability of monitored by the plant vent redietton Specifications:(a) upgrade the plant equipment malfunction.This equipment doce detection equipment. At present, there are vent radiation monitor (particulate, not perform any control function mociated two low rer se noble see detectors monitonng lodine and noble pas detection),(b) with any analynd accident.

the plant vent. One detector provides upgrade the stack flow monitor and Regardmg the consequences of att accident isolation of b weste su pystem on high incorporate lookinetic sampling of the previoust ' analyted. the equipinent which activity level plus indication and alano plant vent effluente. (c) provide new mquires e propond amendment is not functione.The second detector provides contre.1 room indication and recordi^8 required to function to mitigste the indication end alarm functions only. nen equipment for the upgraded conuquences of an accident. l'urther, two low range noble ses detectore m instrumentation, and ehminating W nnd to divert condenar replaced with a single low range ses detector, divert the condenser a(d) permanentlydier.herse from h etmosphenc vent to the This single detector providu control.

lt ejector p'ent vent on high ecovity levels elin'inates in&cetion and alarm functions of the discharge from the atmosnheric vent to the consequences of equipment malfunction existing two detecton. De new detector the plant vent and remove the automatic since the condenser air radiation monitor no incorporatu pinent day technology with divert interlock from the condenser air longer performe e control funcuon Replacing highly tehable components for impimed ejector radiation monitor.%ese changes the two plant vent gas monitors with a single performance and operability Manuel cre required se a result of Plant monitor does not incrnse the conuquenen umphng of h spectfic release paths and of Modification M.1005 which removes, of en equipment malfunction o!nce the two the plant vent are required by the operating modifies, and installe radiation m nitore do not perform ndundant weste gas procedures should the plant vent monitor fail; detection equipment related to the plant eystem to ett n function and the cepabdity thmfore, h propowd amendment does not i

vent system. Additionally, a change le to obtain greb eemples of the plant g ent le desired to the required actions of the provtd,d and mquired in the event of a involve a significant reduction in a margin of failure of the plant vent monitor.

oefety' i

radiation monitors (RMS 11 and 12) to

2. Operstma of the facility in accordence e licensee has concluded that the assure adequale effluent accountability with the propoud amendment would not proposed amendment meets the three for containment vessel (CV) releases emte h poutbility of a new or &fferent standarde in 10 CPR 50.92 and, whsn containment integrity le not Idad of accident from eny accident previcuely therefore, involves no significant required and the associated effluent evaluated.

hazards consideration, nonitoring instrumentation le out of ne equipment chanan which require the ne NRC staff has made a preliminary serv h pr posed amendment upgrade plant vont review of the licensee's no algnificant Basisforproposedno significonf N"

ft ejector d cha hazards consideration deterininstion e

oh hasards consideration determination he Commiselon has provided plant vent. no new equipment performe the and agrees with the licensee e analysia.

umo function as the nieung equipment. No Accordingly, the Commission proposee standards for determining whether a no

&ffent operating conditions or functione to determine that the requested elsnificant hasards conalderation existe moctated with thle project are created, amendment does not involve a i

as stated in 10 CFR 80.92(c). A proposed th*fm. the propowd amendment don not algnificant hatards conalderation.

amendment to en operating license oneta the poulbilny of a tww or &ffent Loco / Public Document Room involves no significant hatards Any accident pnvious4 conalderation if operation of the facility location: Harteville Meteorial 1.lbrary, in accordance with the proposed

3. p,,,eues of b factl4 in accordance Home and Fifth Avenues, Harteville, with the proposed asundswet, muld not South Carolina 29535 amendment would not:(1) involve a invoke a alp 4 Scant reduction in a margin of Attorneyforlicensee R. F. jone:,

significant increase in the probability or anfety.

General Counsel, Carolina Power &

l 1

i 1

l 4N82 Federal Registse / Vol. 66, No.182 / Wednesday. October 3,1eso / Notic:a Ught Company. P. O. Bos 1661. Raleigh, mentrdiew to abe prehehBay of any C. mand the operoboa of the lecibty 1

l North Caroltna 17002 98'va*eal eesleased assadenL he sahannbty ineolve e meruficant enducteun to the mergin F

NRCfrryoct Armeder. Ehner C.

and sinnabibty of the new h

of malet;f Ademeam erlanc.ed ever tt.st of the 3seen (pre.

De margin of safety is erlanced by thus refuelma outage 13) due to the : ' - ' y of modificapon and Technical Specification Carolina Power & Ught Casapney, the safety retowd octm r ---es change Redundancy of equipment is 1

Docket No. 96.ast it 3. Rondamun provided. properly coordmetod posee prooded where et &d not previously eslat.

blaam Electr6c Plaat, Unit No.1, euppbes am provided far the new assipment.

Rodeolopcal condiuono for control room Dariaegten Co anty South Carchma Wre to no increase in the conay-= of operetore are lepreeed due to the higher an scendent previously realeeted. laswed, efhciency abarwal bad and the reduced i

Date c/omendment request August t)w conneonaces of to occident are redused unfiltered paleakage theret'y 6enprows the i

29.1m:0 becaun of the reduction in the rodsological abihty edliv operetoe to rnpond to the Drscription of ometidment requesk don to the control room operelors resultmg moudens seviously tulusted Modification is required as a result of from en trnproud fiher system and the ne Lioansee has concluded that the tyr.luations that were conducted reduction of urifatered in leakage into the proposed amendment meets the three pursuant to the requiren:ents of NtJREG-controlroon Aleo.redundaney of active otaridards in 10 CFR 60.92 ard.

0737. Item III.D.3 4, Control Room sefety.related componente ereances system therefore, involves no algnificant Habitability, ne control room fdter evellability and rehability.

hasards conalderation.

Th e

U '

system previously identdied in the ne NRC staff has made a prellminary gg Rc ty Technical Spectheations (W)is being demonstrate that the dose to the control room review of the licensee's rio signihcant replaced with a new system.

operators don not enceed the limite hazards consideration determination The W Section 3.15 specification of estabbahed by to Cf7 60. Appendt A.

and agrees with the licensee's analysis.

operability will be revised to identify General Design Criterion 19

• Control Room " Accordingly, the Commission proposes act!ve and passive components and it Would the operatien of the facihty to determine that the reque sted redundancy of active safety.related crote the possibihty of a new or different amendment does not invoh e a componente. The be slo is revised to 6 tnd of accident trora any accJdent previously significant has.ards consideration.

consider radiation exposure limits evaluated?

kco/Pdlic Document Room specified in 10 CFR 60, Appendix A, m poselbihty of a new kind of accident General Design Criterion 19 Control from any accident prestously evaluated will locofione HaMlle Memoda1 Ubrary.

not be created by thle mod.faceuen and llome and Tifth Avenues, Hartsulle, Room' nical Specification Section 4.16 Tech TecWeal Specmcehon change.m contml Sod h ha m definee the revised surveillance Room itabliebibty System interfaces with h Attomeyfor licensect R. E. Jones, requirernents gor the control room att safety rehted electrical distributlos eystem General Counsel, Carolina Power &

and the safety.related service water system.

Ught Company. P. O. Box 1551. Ralelah.

tonditioning system. Requirements will Proper coordination of power supphes le North ".arolina 27002 be added for temperature and pressure provided, the service meter system edition

- e NI. # p,[i"O' "

testing and staggered testing of design considere the additional demand on A d'"* ""

redundant equipment.

b eervice water erstem and to dnigned to Basis forproposedno s/gmficer.t Seismic One 1 requirements, ne Carolina Power & Ught Company, et al.,

hotords consideration deterininctione redundancy of safety.rehted scuve pocket No. 89 489. Sheaton Harde The Commissica has provided componente provided by this modificauon Nucker Power Plant. Unit 1. Wake and standards for determining whether a no increcen the rel.abihty of b Control Room Chatham Counties, North Caroline i

signi!ncant hazards consideration exista liabitablhty System to perform its functio 6 ae stated in 10 CTR 60.9 (c). A proposed Adequw wpenuon tatwne safey tralne h Date of amendment regmc amendment to an operating licetse pmvided 2 usum mat a single leDum of an September 10,1990.

involves no significant hasarde n$y$,"

["'**

O'8Cfi tion of amendment request P

consideration if operation of the facility cause adverse conitions ruultma in new The proposed amendment would revise in accordance with the proposed accident scenarios but bounded by preunt the Reactor Coolant System (RCS) stnendment would not:(1) involve a occident analyses.

Pressure / Temperature umita of algnificant increase in the probability or ne poulbihty of a ddierent kind of Technical Specifications (TS) 3.4.9.1 and consequences of an accident previously accident from any accident previouly 3 4.9.2 to protect the reactor pressure evaluated; or (2) create the poulbility of evaluated wiD not be created by this vessel (RPV) from the potential of brittle a new or different kind of accident from modificauan and Technical Specif.cetion fracture as the RPV neutron exposure any accident previously evaluated; or (3) change.m Contml Room Habitabihty increa6es from three (3) effective full involve a significant reduction in a Syews inted cas wie e uhty.nlawd power years (MY) to Dve (6) EFPY.

electrical detribution system and the ulety.

margin of safety, related service water system. Proper in addition, the low pressure Carolina Power & Ught Company (the coorthnauon of power sapphu to provided.

overpressure protection (1. TOP) met licenere) has reviewed the proposed h service water system edition du;sa pointe are adjusted accordingly and an changes and has determined that the considers b edSuonal demand on the effective lower temperature hmit for requested amendment does not involve eersics water eyelem and le duigned to usage af the I. TOP set pointe has been a significant harards consideration for Seismic Cue 1 tequirements.The added to ensure that the setpointe are the following reasons:

redundancy of ufety.nlated acuve used only in the region w bere the A. Would the operation of b facility componente provided by this modification eyetem can provide the necessary involve a significant increese in the increases the rehabihty of the Cantrol Room protection, probability or consequenu of an occident Habitabihty Sysum to perform its fundion.

Basisforp otedno significuni previously enluated?

Adequete separetion between safety trains le hMords cens e' n detchnoM' at l

ne probabihty of cccurrence of any provided to enure that a single failure of an Chapter 15 accident previously evoluted is ocuve component will not roult te pyotem The Commiselon has provided I

not inceveeed by this inodificetion and inoperabihty. No einsle active failure oma standards in 10 CFR 60.92(c) for Techrdcal Specification change tmuse ceuee eduree con &uone ruulting in new determining whether a no significant netbr the Control Room Habitabihty System accident scenance not bounded by pruent hazards consideration exista. A propossJ nw the optein tving replaced accident analysee.

proposed amendment to an operating

l renderal R:gistor / Vcl. f.5, No.192 / Wednesday. Octaer 3.1100 / Notices 43463 license involves no significant hatards Therefore, the pregooed amendment to the LJbrary,1930batk As enue. Raleigh, cunsidefation if operation of the facility imace terrg.ersture limitations, the hestup North Carolina 27N6.

in accordance with the proposed and cooldown rentes and the recalculated A ttorney for licenseer R. F. Jones, amendment wotdd not:(1) ins che a luniurg matenal(RTein! 6 not inn.M e General Counsel, Carolina Power &

sgnificant increase in the probebihty of

{,*,"$#$g*" "ec sIy' IJ ght Company. P. O. Dos 1531. Ralcish, I '

en p e consequences of an accident predously n elusM collecunty they maintain th, North Caroline 2202 etalueted; or (2) create the possibihty of r, quired buffer necesaary to protect the MICho/ect Dintior: Flinor G.

e new or differcnt kind of accident from es utor nuel from brittle fracture given e Adentam any strident p'eviously evaluated, or (3) lunattr. mese or terrperature input to the RCS involve a significant reduct on in a for up to hve ITPY of operat on.

The Cleselstad T.lectric !!!uminating margin of safety.

1 Th proposed amendment don not Cornpany. Duquesne Ught Company.

Carvitna Powet & Li ht Company (the crute the ponibihty of e new or dinerent Ohin Iklir.on Connpany. Penny Ivania licensee) has reviewe the propowd Led of ec.ciderit from any accident previt. sty Power Company. Toledo I;dWon etalasted.

Company, Docket No.56-440. Perty channs and hat determined that the requested amendment does not irnol e This amendment does riot introdace enF Nuclaar Powet I'lant, l'oit No.1.1.ske new equ!pmerit, operstmg procedures o' County

• Ohio a signifmant hatards consideratiori for engiettstrite it simply edlusts the entsting the fclltwi.ng teesone:

ctersting krnits to compenu'e for the shift in Dofe of ornendment reyuest;lu'y 17

1. The popond amendment does to tie nil ductdey reference temterature c.f the IWO in vohe e quifkent inerene m the teettor vessel due to neutron eaposure.

Des @fion cf cmendment nvuesti probabihty or consequences of an occident Therefore no new occident or malfunction The ItoEused amendment would add periously eveheted as descr beJ below.

m.thenism is introduced by th.s ernen.irnent.

Techenal Spenhcetions 3 4 91 and 3 4 0 2 3 The propose amendment does not the Centerior Service Compat as a

'tLAC'f 0R COOLANT SYSTEM involve a sigruficant reduction in the energin licensee to iscility Of* erat.ng.kensee PRESS L; RE/ TIJUT*lA it'Itt: llMITS' of u ety.

NPf.58 for the Perry Nucleet Power r

proude RCS pressure temperature hmits to The hestup and cooldown rates of Plant (PNPP). The proposed addition proted the reactor pressure venel from

$pecificat6ons 3 4 91 and 3 4 91. end LTOP would authorire both the Clevelar'd bnttle freetere by clntly separating the

p. points in Speci6 cations 3 4 0 4 er, Cectric illuminating (CC) Compney and recol of normel opershoos frora the region designed to ensure that the to CPR to Centerior Service CornMny (wholly.

Ehe he t p erd coo $o re$e

^ PPN" C

""""d'* P"'"" hm I"'

owned subsidiaries of Centerior Ibrgy P

de m not nece ed dunng an specincetkms 3 4 91 and 3 4 91. end LTOP

",["$*[Tg*M" l,]Z Corporallon) to act as agents on hehalf j

of the other licensees for the PNPP, and setpomis in specificanon 3 4 0 4 are doigned to ensure that the 10 CIR So Appendte G pressure len.perstm hmits for the RCS are s> siem hydroetatic tests have excit;alve responsibilty and control New Nd Dur.tdity Refer-nce Terrtereturce c)er the physical constructwn.

o ret nni g en ic pe e bo end hrr.iting p' essure temperstm curves npe'HIiOn and maintenance OI the ci currences and system hydrostenc tests.

"" P" pared f ar the protacted reactor

facility, General Design Cntenon 31 of Appendte A sopi npoem et fin Meetite Full Power Under the preposed reorginitation of to 10 CFR SC requ!ree that the reutor ccolent I'*"' d opnsuonMs rnulted in a bour.dary shall be dn'Fned with sufficient I wenng M the Appenda G cursn To Cen'erlor Tnergy Corporation, the CFI Nuclear organlaation would report to truirrn to assute that w hen stressed undee compensate, the effective rupes to the operetag. maintenance, testing and hotup and cooldown cetes mere shif ted, Center.ior Service Compty. As a result, ostulated auident condihana (11 the where necessary, in order to maintem the gp pgg 3 'ggP boundary beheses in a nonbrittle ment.cr and "ector meel protection p-mded by L1Dps.

would be revised tr, reficct a change in

(:l the paobabihty of rapidly protegatmg The remed hutup and cooldown tenses, the title of the CD Vice President.

fractm is muumized.

in ennluntnon with the cu~ent rates and NucJear Croup to Centerior Service Title to of the Code of Federal Regulaboos LTUP se'pomts ensure that the Appendit G Company Vice Prea; dent, Nuclear. Perry, Part 50 Apptoda G, 'Tractare Toughness pres 3m terepereture curves are nnt Basis forproposed no signifscant Requiremente." reqmtes the effects of chabenged gis en a hmitmg eness or heet input hcrords consideratien determJnotion?

chaners in the faectare toughness of tvector to the RCS dunns normal cremtions, vessel matenets caused by neutron redaation enucipated occurrences and sys'em The Commission has provided throughout the service hfe of outleet reactors hjdrostette testnig.

standards for determming whether a to be considered in the pressure-temperature Stace restrictu,ns remain in place to ensur, significant hatertia consideretion e Aists hmits. The 'cberse' is used in cimiunct:en the Appendit G rperstmg limits of the as stated in 10 CFR 50.92. A preposed m;th the imtial metenal referente reactot vessel are not cha!!enged. the margin amenrirr.ent to an operstmg hcense for a temperature (RTinni to estabbsh the hmitma of safety deimed to the Techrucet facility involves no signihcant hazards pressure.temperstm rurvet Regulatory

$pecifkettan tisses is not signinca Rv consideration if operation of the facility Gmde 190 conteurs prxedures fue reduced b) this c.her ge.

in accordance with a proposed calculahng the effects of net. tron red;4 hon The licensee has concluded that the amendment would not (1) involve a pr p sed amendment meets e three significant increase in the probability or art ntly e rg ma rc 1 reactor

,,, g,.

standards in to CFR 50.92 anh.

consequences of an accident previously Users the RG t w Revisian 2 and Appendia therefore, involves th) sigmfic.a nt evaluat9d,(2) create the possibility of a G to to CFR 50. new Nil Ductihty Refmnce hazards consideration.

new or different kind of accident frem Teteperatures (RT.e,1 anJ heitme prusur,.

The NRC staff has made a preliminary any accident previously evaluated, or (3) tempereture curves mere prepared far the review of the licenree's no significant invohe a significant reduction in a protected reutor meet npeem et fae hatards consideration determication margin of safety.

F.ffect:ee Full Power Years (ITPYi of end agreca with the licensee's analysis.

The licensees have provided the bp ACCW

" u PF PM" following analysis of no significant e e's c late h es in t m

and cwidown renses and the esisting low to determine that the requeated hatttds considerationa using the Tempeceture Overprneure protection System amendment does not involve a Comminion's standards, setpcmas gwovide the rec,utred enurerv e that s'rgndseant hasards consideration.

This proposed amendnarnt does not invorve the reactae prneure vessel Le groteesed froan lade %MicDoicursenf Room e orgru0 cant increne in the probability w brttile fractm up to Ove DTY of opershoit kceiser Ommerom Village Regional consequencwe of en occi*nt previonLelF

i 40464 Federal Register / Vol. 55, No.192 / Wedne6 day. October 3,1990 / N:tices es elusts.! sinc 4 th's la 6. edmitustro uve u6e of generically a ved fuel type CE algnificant tr[ crease in the probability or change which only involve *he addition of asBNB and the tes 1 change in the consequences of an accident previously en additional beenece Lato the hereting 1

LJcense (OL) and a title tha fo. *he Woe-Minimuto Crttical Power Ratio (MPCR) es aluated. does not create the safety limit from 14r? to 1.05.

possibilit of a new or different kind of na a on As oted e, e ital N #'#[## M E### ## #M Scent rom any accMent PNk to operate pNPP hagords conside/otion determm.otioni evaluated, and does not involve a queht utions necesse7 by the prenously The Commluton has provided reduction in the required margin of continue to be provide opproved CEl nuclear organisation and well.

standards for determining whether a

6afety, defmed hnes of authonty, responsibihty and significant hazards consideration esists The staff has reviewed the licensee's communication continue to esist for au as stated in 10 CFR 50 91. A proposed no significant hazards consideration activtties effectmg the safety of the plant. %e amendment to an operating hcense for a determination and agrees with the addihonal hcensee bems added to the 01. to a facility involves no significant hatards licensee's analysis. The staff, therefore, cr ei h th curr t ow er/

consideration if operation of the facility proposes to determine that the hcensee's operstor (CEICO) belongs nese changes do in accordance with a proposed request does not involve a significant not treke any changes to plant systeine or amendtnent would not (1) involve a batards consideration.

have any affectisicj on accident condiuone or significant increase in the probability or Loco /Pubhc Document Room assumthons. They also do not effect ponible consequences of an accident previously locotion! Diton Public Library,121 intttetmg eunts for accidents previously n eluated. or any system functmr.el evaluated. or (2) create the possibihty of Hennepin As enue, Dison, !!hnois 61021.

a new or different kind of accident from Attorneyfor heensece Michael L requirements.

any secJdent previously evaluated; or (3) Miller, Esquire: Sidley and Austin, One the pofsIt I t of a new o d cren k invoh e a significant reduction in a First NationalPlaza Chicago,Illmois accident smce it la en admmistrotne change mardn nf safe M

mhich only involves designation of heennes The licenst t' as provided the NRC hoject Director: Richard J.

and the title of a management representative.

following analysis of rio significant llarrett The proposed changes do not enete the hatarda consideration using the possibihty of a new or different accident Commission's standards.

Consumers Power Company, Docket No, since they do not effect the reactor coolant

1. ne proposed c.henge does not involve a 60155. Big Rod Point Plant, Charlevola pressure boundary or other plant systems or significant increase in the probabihty or County, Michigan structures in such a menner that could consequences of an occident previously initiate any new or different accidents, and evaluated.

Date of amendment request. August tinte they do not adversely effect eriy system The pnmary fission product barner will 1 4, 15510 functional requirements nor plant contmue to be protected dunns normal and Dc8ct>Ption ofomendment request:

snemtenance or operabihty requirements.

transient operation Opetetton of au The amendment would revise Technical ne proposed amendment does not involve secondary fission product barners are Specifications Section 6.2.2 g(4) 6 $ 1.1, e sigmficant reduchen in the mergtn of eefety unaffected by this change.

and 6.3.4 to reflect changes in the since at is adtrimettetne in nature. and does The 1.06 MCpR safety hmit vetue will organizational structure of the not effect any t!SAR degn or accideni preserve the required margin of safety fo' assumption, not any '!echnical Specification clad integrity. This htCpk safety hmit ensures Operations and Engineering bun that on of the fuel rods would be espected Departments. The preposed changes The staff has reviewed the licensecs' to sved boilmg transit on dunna steady. state would:

no significant horards consideration or transient conditions with a 95 4 confidence a) remove the reference to htln from the determinetion and agrees with the level The new fuel type (GEas6ND) and portion of the Technical Specifications

[itensees. analysis. *therefore, the staff, analytical methods for estabhshing the safety deshng with working hout hmitations, proposes to determine that the licensees limit hose received NRC approval. Thus, this b) modify the composition of the plant change does not incnese the probabih Resiew Committee, and request does not involve a significant consequences of a previously eseluate[t or c) change the title of the individual harafds consideration.

accident.

1.ocalPublic Document Room required to hold a Senior Reactor Operetors 2 The proposed change don not create the t.icense end responsible for directing the location: Perry Public Library,3753 htaln possibihty of s new or different kind of schvines of heensed operators Street, Perry. Ohio 64081.

eccident from any accident previously Basisforpreposedno significant 1

l Attorney for hcenser:lay Silberg, evaluated.

botords considerotion determination:

i Dq., Shaw, Pittman, Potts &

The pnmary noion product barrier will The Commission has provided Trowbndge, D00 N Street, NW,

• nt nue to be protected dunns n rmal and standards for determining whether a ton tnutent oreauon O nehon of en Weshinfrvje. DC 20037' )ohn N.Sec'edIy$Us c'hangeIoYe"w

• as sta1ed in 10 CTR 50.9:(c). A proposed algnificant hazards consideration exists NNC ct Director-un Hannon-opera tional modes are introduced by this amendment to an operating license for a Commonwealth Edison Company.

• nge ib of n fac ue h' Pfe"no,,, f w o, coasi erstio operat of the fact i y Docket No. 50463, Quad Cities Nuclear g,,,

c,nts Pow er Stetion, Unit 2. Rock Island 3 The proposed change does not involve e in accordance with the proposed County, Illinois significant nduction in the margin of safety.

amendment would not:(1) Involve a ne r, quired mersin wlH be mainteir ed for Date of opphcotionfor amendment, all fuel typo and increwed for some fuel significant increase in the probabihty or August 31,1WO types The proposed Technical Specification consequences of an accident previously "8

evaluated; or (2) Create the possibility of

'h[8 b"B f et, whilYesta

$pR a new or different kind of accident from Description of amendments request:

C ishi e Commonwealth Edison Company, the licensee, submitted an application to ufet) hmit that is more conservatne than any accident previously evaluated, or (3) cmend the Technical Specifications of required for su other fuel types The margin involve a significant reduction in a of utety is therefore not significantly margin of safety. The licensee provided l

Operating tJernse No, DPR49 for Quad reduced.

an analysis that addresses the above l

Cities Nuclear Power Station, Unit 2.

Based on the previous discussions, the three standards in the amendment This apphcation would change the licensee concluded that the proposed application.The licensee stated that the Technical Specifications to reflect the amendment request does not involse a changes do not involte a significant l

Fenderst Register / V:1. 65. Ns.192 / W:dnesd:y, Oct;ber 3.1990 / N:tices ee4A5 hazart's consideratiIn for the following surveilknce int:ry:1 will still be does t on inv:In a significant hasards reasons:

constrained by the 25 percent inten al considers on.,

lti pace not invoin a eteniheent increase estension criterion of T/S 1.1.4.

Locc/ blic Document Room in the probabihty at c neequencee of an Scsisfor wsed no sigruficant locottone North Central hlchigen occident previously entuated.

horcrds consi ration determination:10 College.1515 Howard Street. Petookey. -

ne organint onal chansee do not offut CFR 50.92 statea that a proposed hilchigan 49170 n eEnNtr eye $e reta ed amendment will not involve a significatit Attorneyforlicensee ludd 1. Escon.

throv h the addition of generel requirements harards consideration tf the proposed Esquire. Consumers Pow et Company, modi ed after the guidenue and philoeophy amendment does not ( Involve a 212 West Michigan Avenue. lackson.

provided to Genenc 1stter taw significant increase in e probability or Michigan 49201.

(21 Deen not create the possibdity of e e ew consequences of an accident previouly NRC Profect Director: Robert C.

or different kmd of acendent two anF evaluated; or (2) Create the pouibihty of Pierson previously et aluated.

1he proposed thenges are administreute a new or different kind el accident from in uture. No modifications to slant ey udM prniopl evaluated; or (3) Duke Power Capany, Docket Nn 96 equipment, thennes to setroints or opereting Involve a significant te uction in a see and 86 370. McGuire Nuclear limitettone are being proposed.Derefore, the margin o safe Station. Units 1 and 2. Mecklenburg chenpco do not create the pmsibthey of a new The licennee ee evaluated the County, North Caroline or different kind of eacident froen any proposed amendment against the Date of omendment trvurti geeviously evetuated-standards of to CFR 50W., and has September 4.1990 (3 I) not invo e a significant redaction detertnined the following:

Description of amendment request th. '. 'delmes for a " Unit Review Group *'T s proposed chanses tormnue to endorse gh 325 estensioce hmitadon The proposed amendments wordd which it*, o chel enen ered a minimum of will not significantly of'eet equipment reduce the required snatured reactor four mei m he beensee willconuous to reliabibty and does not affect the probability coolant system flowrote by one peicent maintain its Quality Anurem program or conoQvences of accideras prevtoup from Irt220 CPM / loop to 96250 CPM /

troplesnentetaan to amoure eqeelent

,g;g, ne surninence intmet wl etill loop. Also, an administrative criange 16 be constrained by the 25 percent intmal being made to delete references to the iba evd estenean crttma of T/81.14. The nah to RTV bypass manifold system. This

.R st u

tn

• licennee's no significant hatards system was removed from both McGuire consideration determination analysis enesEfety

1. ' " I

"'N *EF" N

u i6 incurred and og ees with its conclusion.

when a stiveillance inten at le estended at a NRC in Feellity Operating 1.lcense Therefore. the staff proposes to time that condiuana er, not euttable fo, Amendment Nos. 64 (Unit 1) and 65 determine that the requested performmg h suneillanos, eut.h u. during (Unit 2).

amendment involves no significant transient operating conditions or conditior.e Basis forpropsedno sipuficant hazarda condderation.

In which utety eystem are out of eerske hczcido consideration determination:

Loco / Public Document Room l*euw of ongoing maintam or other The Commission has provided location North Central Michigan

'"'vullance *ct vtM*-

standards for determining whether a College.1515 lloward Street. Petoekey, nefm, h proposed cham doce nw significant hazards consideration esists Michigan 4mo.

$"[,"d,*[

(**,'r [e ceidant as stated in 10 CTR 50.92. A proposed Attorneyfor //censeer judd 1. Bacon, previonly evaluated.

amendment to an operating license for a Esquire, Consumere Power Company, Criterion 2 facil! involves no significant hazards 212 Weet Michigan Avenue. Jackson, w p, po I revision to h T/S will oot conei eration if operation of the facility hiichlean 49201.

MID Project Directorr Robert C.

result in any phpical alteration to any plant in accordance with a proposed entem. nor would there be a change to the amendment would not:(1)invol e a P:erson niethod by which any safety.related erstem significant increase in the probability or performa ne function-Consurnero Power Company, Dor.ket No, nefore. the pr, posed change does not consequences of an accident previously

$4155. Big Rock Point Plant. Charlevolz e,eete h possibihty of a new or different evaluated; or (2) create the possibility of County, hiic.higan kir.d of occadent from er y acendent previously a new oe dif!crent klad of accident from any accident previously evaluated, or (3) lbte of amendment request August "h"*

g involve a significant reduction in a

15. N Description of amendment request-Deletion of the requirement that any three margin el safety.

conucut!n surnalence Intmal ehall not With regard to the pectosed The amendment would modify esceed 3 :5 times the tatmal will not arnendments, the licensee statea that the Technical Specification 1.1.4 in sign:ficantly affect equipment reliebitlty.

changes do not involve a si nificant accordance with the guidance in rather Lt will reduce h potential to interrupt hasards consideration and as provided Genenc letter 89-14. "Line item normal plant operations due to earveillance improvement in Technical Specification scheduhng. This proposed revienon witl allow the following in support of that Retnovel of the 3.25 Limit on Extending ett sunn!!ance intmals to te constrained by determbatkn.-

Surveillance Intervals." Technical the masimum allowable estension of 25 im seem wW nd inmfic.antly g,g g p,,g,y,,

,,, og Specification 1.1.4 currently pertatto Q

[n[b,'"", * ",["

any accident predomly evaluated.

dn aarveillance intervals to be extended up I t No component modification, system to 25 percent of the specified interval.

EYhe

"'U "*"' " 'h* "8 ' I" *P""**

• 8 o

e proposed changes do not However, this Techrdcal Specification invoin a ognineent redaction in a marvtn of occur which'e uld effect the probabihty of limits extending sur% tillance intervals, safety.

any arc ent M Mnsunt h nduchn in so that the combined time intervals foe ne eteff has reviewed the licensee's h'*," *$g',*1[v[ ice.The consegancu h* 8,m*,,N,h any thnic consecuuve surveillances do no significant hazards analysis and t y,,,

(Esq or other not exceed 3.25 times the specified concurs with the licensee's conclusiana.

pg,viously analysed accidens have been intervals.The proposed change would herefore, the staff proposes to found to 14 insistuficantly diflevent if a is j

i delete the 3.25 extension limitation. he deteralaa that the requested chango lower flow rate is eneumed in the analysee, j

l

__ __ A

i 4 Hee Fedoes) Replatee / W1. 65, N2.1~] / Wednesday, October 3,1990 / N:tices h eyotes trenoient weponw le not effected Description of amendment togesset.-

officent and effective une of the ISEC's ty the initial RCS flow usumpuost unless The proposed license amendament would P'oducts. However. changing the the initial assumption le so low as to impatt the ettedy.etete core coohng capabihty or the tey se the Independent Safety

'd*lal** b" **"t*l '"d P'*8 et:am genetetor heet transfer capabibty. nie F.ngineering Group (ISEC) repoeting and

• 9"i" atle ty, "*" *iU ""' ' "' ""Y ** '8'" "I b clearly not the cope a tih 41% reduction in administrative requirementaSm RCS flow, changes are needed as a result of Dowd on the abon, we have determined 3 This emendment will not create the organizational changes withift the that the proposed amendment does not til e

ent previovely evolusted.

Nucleat Energy Department.

involve significant increase in the probabihty pnelbihty of any new or d fferent accident No component modsticauon. eystem Basisforproposedno significont or consequences of an accident previously enluated. f21 create the probabihty of a new real.gnment, or r.hange in operstmg hasards considention determination:

or different hmd of accident frote any procedure will occut which could create the he Commission has provided accident previously evaluated, or (3) involve prebebihty of e' new event not previously standards for determining whether a e significant reducuon in a margin of ufety; conaldered The reduction in flow will not significant hazards consideration exists and therefore does not involve e significant Initiene any new events. All credible accident (10 CFR 50.92(c)). A proposed hacerde conaldereuon.

oc:nnrios have been conendered, amendment to an operating licente for a ne staff has reviewed the !!censee's 3 nis emendment will not involve a significant decrene in e enargin of safety.

facilit 'invohes no significant hazards no slgnificant hazards consideration 4

As described in Attachment U [heenne o conal eretion if opetation of the facility Mumyshn and age d b fieptember 4.1puu application the decreene in accordance with the proposed licensee e analysis. Accordingly, the in RCS flow has been analyse end found to amendment would not:(1) involve a Commisalon proposes to determine that have an insignthcant effect on the apphcable significant increase in the ErobabilltI or the proposed changes to the T$ involve transient anal ne in the ITiAR. N reduced consequences of an accident previously no significant hatards considerations.

flow rete reeufted in shghtly reduced DNg hmits. l'igun 1.1 1 provndu revised core evaluated, or (2) create the possibility of LocalPublic Document Room safety bmite for T-evs u e function of power a new or different kind of accident from location: Indian River junior College at the reduced flow rate These hnute will any accident previously evalua ted; or (3) Library,3200 Virginia Avenue, Fort provide equivalent assurance that opersting involve a siFnificant reduction in a Pierce, Florida 34954-9003 margin of safety.

Attorneyfor licensee: Harold F. Reis.

Eh

=$leren$

te given in Thelicensee provided the following Esquire Newman and Holtzinger, tell L el T.S S/411 em unchanged. and all of the discussion regarding the above three Street, N.W., Washington, DC 20036 turrent thermal bydrauhc design critens ar, criteria.

eatisfied at the reduced flow contbtione. The Criteriott J

/OfCProject Director: Herbert N, Berkow c:rrent overtemperature delta T and Operation of the facihty in accordance tvsrpower delta T wtpomte ers conservatige with the pmpond amendment wedd not Gulf Steles Utilitise Company. Docket and provide the necessary protection.

involve a signif cent increase ln the II; wever. the deed band of the fldelte 1) probability or consequences of an accident No. 80 488, River Bond Station, Unit 1 functwn (eee Note 1 of Table 2.211 wp Previonly evaluated.

West Feliciana Parish,lauleiana revised from 294 prester then q.. g greeter ne propoecd changes are adminletrouv, Dateofamendmentrequest August than + 9% to 29% gneter then q..g greater in nature and do not effect Technical 28.1990 then + r%, The effect of this change to to esaure protection in the event of a power Specifications that preserve 6afety analysie Description of antendment requeste enumptions. Additionally, these changes do (mtalance between the top and bottom of the not moddy the physical design and/or The proposed amendment would modify core. No margins of safety are reduced by operation of the plant. Herefore, the the Technical Specification th:ee changes.

The Commission has made a pro ioned changes do not effect the requirements of the Facility Review pro bihty or consequences of eccidents Committee (FRC) and the Nuclear prehminary review of the licensee's no pmrtously analysed.

Review Board (NRB) by deleting the significant hashrds consideration Criterion 2 specific composition list for each and including the licenste's assessment of Use of the modified specification would not replacing it with general statements the impact of the requested amendments create the possibility of a new or differe'it defm' ing levels of expertise for j

cn the Final Safety Analysis Report N"jo",$'*g*'d'"'I**'"#"*'d'"'P"Wouly membership. Additionalproposed j

sccident analyses and agrees with the n, chenau being pmpond are

• I" ", and an editoria[ chang'e that licensee's determination. Accordingly, administrotne in nature and will not lead to l

e6 ternates the Commission proposes to determine that the proposed amendmente do not materiet procedural chango or to phyelcat deletes a reference to the initial year of invcive a significant hazards modifications to N feelhty. nerefore, h operation, which has been completed, proposed changes do not create the Requirements regarding meeting consideration.

poselbihty of a new or different kind of frequency, audit / review areas, and Locolfublic Document Room accident.

location: Atkins Library, Univeretty of Criterion 3 records will remain unchanged.

North Carolina, Charlotte (UNCC Un of h erodhd e fication would not Basisforpwposedno significant

• ' '8"' ** *' " "*"" I" * * * '8'" 'I hasott!s consideration determination:

eeI,,'y"'chenen belns proposed are Station) North Carolina 282:3 The Commlulon hae provided Attorneyforlicensce: hit. Albert Carr.

The standards for determining whether a Duke Power Company,42 South Church Street, Charlotte, North Carolina administratin in nature and do not relate tosignificant harards consideration exists

)

26241-0001 or modify the urety mersine defmed in or as stated in to CFR 50.9:(c). A proposed NRCPm required and maintained by b Technical hiatthews /ect Director: David B.

Specificatione.

amendment to an operating license for a The changes proposed amend the facility involves no significant hazards Florida Power and Light Company, et al.,

Independent Sefety Engineenns Group consideration if operation of the facility l

Dock t No.56-309, St. Lucie Plant Unit (ISEGl administrative control and reporting in accordance with the proposed requiremente and will focus the control.

amendment would not;(1) involve a No. 2., St. Lucie County, Florida reports and reporting requiremente of the.

significant increase in the probability or Dateofamendmentrequest August ISEG to the Chelrmen. Company Nuclear consequences of an accident previously Review Bootd. lloride power & IJght evaluated; or (2) create the possibility of 10.1990 Company (f'Pl.) will thus ensure the moet a new or different kind of accident from l

I

4 l'edeial R gister / Wl, 55, N,192 / Wedn:sday, Oct:ber 3,1990 / Notic's 4N67 any accident pres tously es ah.ated. or (3)

NRCPro/cet Dimetor Christophet 1.

significant irteresse in the probability or j

insolve a sigmficant reduction in a Gnmes consequences of an acciden,t previously i

evaluated; or (2) create the possibility of margin of safety.The licensen provided liouston Ughting & Power Company, a new or different kind of accident from an analysis that addressed the above three standards in the amendment City Public Service Board of San Antonio, Central Power and Ught any accident presiously evalua ted, or (3) spplication' Criterion f: Operation of the facilit). in Company, City of Austin, Tesas, Docket invoh e a significant reduction in a Nos. 50 498 and 50 499 South Tenas margin o(safety. The licensee provided accordance with the proposed amendment would not invoh e a Project Units 1 and 2, Matagorda en analysts that addressed the abose three standards in the amendment s gruficant increase in the probabdity of Coq Tnas appl; cation. Based on the staff review, consequences of an accident previously Date of amendment request the proposed changes will change evalaaled.

December 18,1983 and supplemented neither the technical disciplines required The proposed charges are admirnstrouve jul) 30,15n0. The December 18,1989, not the level of espertise represented on in naute and do not effect sesumptions e,nbmittal was previously noticed April the committees. The function of the enntemed in the safety ana1> ses not do they 4,1MO (5$ IV 1I594).

PORC will remain unchanged. With a$a N :a nIA

1. 1. W#

o u

t to I respect to the NSRil, the enembers will fe these chnges do not mod >fy the pbuir of The proposed ange woutd revise e continue to be qual fled in accordance de:Wn and/or operation of the plant.

description of the flant Operations with ANSI 311981 and Regulateey 1 herefare. the proposed c.her ses do not effee Committee (PORCI and Nuclear Safety Guide 1.8. Conse uently, the changes the probatahty or consequences of eccidents Review Doard (NSRB) compositions are considered a ministratise.The staff pieuously anel)ted.

Included in the plant a technical h " ' "* * 'd th' !I"'" "'

Criterma:Use of the resised specifications 6 5.1.1 and 6 S.2.2.

specifich'icna would r$ot create the rnper.tively Currently, the cornposition hnf[an er s c '

, the t ns s d

possibilit of a new or different kind of c! both groups is defined by accident frorn any accident previously organizational titles. In the proposed M*

• M MM N" Nd evaluated, change for the PORC, the members shall amendments involve no significant batards consideration, The changes bema proposed ere be senior experienced onsite eJrr.inistrative in nature end will not lead to irdividuals, at the man 4ger level or Loco / Public Decument Rooms er eterial pnxedural chanees or to ph)sical e utvalent, represer ting each of the location: Wharton County Junior enodMcations to the facihty.Therefore, the g } lowing disciplines: engineering.

College, l. M. Ilodges Learning Center, o b$ y o a new or ffe nd of operations. chemistry, heelth physics.

{ 4681 Boling flighw ey, Wharten Teses

e. clJent.

q'1616ty assurance / quality control, and o

Criterion i Use of the modified rr aintenance. One of the members shall Attorney for licensee: Jack R, specification would not intoh e a rnett the requirements for a Radiation Newman, Esq., Newman a lloltzinger, o ynificant ieduction in a margin of Protection Manager Originally P C.,1815 L Street, NW, Washington, DC

salety, (December 18,1989), the NSRil would be 20036 itie charves being proposed are cortpnsed of a full titre chairman and at NRC Prvject Director: Christopher I.

edrnaastratae m nature and do not relate to least four individuals who have Crimes or rno&fy the safety maron denned in or obtained the position of area manager.

r' aubed and maintained t,y technic al The luly 30,1990, submittal contained e Ill'nols Power Company and Soyland specinceSons.The deletion of the speufic revised mark.up of Section 6.5.2 2. The Power Cooperath s, Inc., Docket No. 50-n r her 11 no de te e the e ctneness prop sed NSRil w ould be comprised of 461, Clinton Power Station, Unit No.1, of these organisatiers. Adtnmistratae senior managers reporting to at least the dew itt County,Illinols controts are in place to control membership, vice presidentiallevel within the 42ahfwations and teilew regerements for licensee organization. Additional Do!c of omeedment regtzest:

December 21,1988 bath the onsite reuew actmty and the members shall be appointed so that the trdepe%1ent reuew program.

NSRD will ha >e the capability to review Description of omendment request:

The staff has reviewed the licensee's technical matters identified in Technical The proposed amendment would add a no sigmficant hartsrds consideration Specifl:ation 6.5.2.1, namely; nuclear note to Technical Specification 3/4 4.1.3 determination. Based on the review and power plant operations, nuclear to specify that the recirculation loop the above discussions, the staff agrees engineering, chemistry and fl w is the summation of the flows from that due to the administrative nature of radiochemistry, metallurgy, all of the let pumps associated with a the proposed changes, a significant instrumentation and control, single recirculation loop.

increase is not involved in the ra diological safety, mechanical and Basis forpropcsed no significant probability or consequences of a electrical engtncering, civil engineering, hazards consideration determination previously evaluated accident The training, nuclear anurance, nuclear The Commisalon has provided proposed changes would not create the lisensing, plant secunty, and standards for determining whether a possibility of a new or different kind of environmentalimpact.

s;gnificant hazards consideration exists a:cident from any previously evaluated, Basis forproposed no significant as stated in to CI'R 50 92(c). A proposed and they would not involve a significant hosords consideration determination:

amendment to an operating license for a reJuction in the margin of safety.

The Commission has provided facility involves no significant hazards Therefore, the staff proposes to standards for determining whether a considerationif operation of the facility determine that the proposed changes do significant hazards consideration exists in accordance with a proposed not invohe a sigmficant hazards as stated in to CFR 50.92[c). A proposed amendment would not (1) Involve a consideration, amendment to an operating license for a s!gnificant increase in the probability or Loco / Public Document Room facility involves no significant hazards consequences of an accident previously locofion: Covernment Documents consideration if operation of the facility evaluated. (2) Create the possibility of a Department touisiana State University, in accordance with the proposed new or different Lind of accident from Daton Rouge, Louisiana 70803 amendment would not:(1) involve a any accident previously evaluated, or (3)

eus,s redecal Reglater / Vol. C. Nr.18: / Wednesday. October 3,19eo / N:tices lin olve a e' nificant reduction in o es slanted. (2) Cre:te the possibihty of a Remos al and Coolant Circulatiors, Rgh i

act.rgsn of s fety,,

new or different kind of accident from Weter Level). and 3 9.11J (Refueltrig The bcensee has reviewed the any accident previously evaluated. or (3) Opera tions. Residual liest Rernovel and pre;med request and t aa provided the involve a tigrtificant redec46en in e Coolant Ctreulation, low Water Level).

following no sipificant hazards margin of safety.

considera tion determinatiote The beenser has eerdewed the Basis forpreposedno significant lu ne propowd chanse doo not tr,voh e a hczords considero%on determmotion:

synficant increase in the probabthy or proposed request and has prmtled the

'Ite Commission has provided following no alpificant hetards connquences of any oct, dent previanoft culusted because the proposed clanfic ation consideration detertninetton:

standards for deterrtuning whether a i

to techrucal bpecafkabon 3/4 41J wttl (1) The proposed change dare tot involve e significant hazards consideration taists ensure that the correct patameter is opificant inutane le the probabihty o' as stated in to CFR f,0SNc). A proposed norotored such that the mtent of the consequeness of a prevknusly acelped amendment to an operating license for a g,ggjgg Speuficat on to ashofied occident.ne VG and VC systern heatere consij. Involves no si nificant betards E

(2) ne proposed thenge does not ueste operste to reduce the relative humid.ty in the tration if operation of the gactgit).

the possibdity of a ntw or different 6 md of VC and VC chatteel bede following initte nc n in accordance with a proposed accident from any accident pres tously of then opterns. $ince these eystems are ernendment would not (1) Involve a es elueted because it will not result in any initiated following the onwt of an accident significant increase in the probabihty of ct enees to plant design parameters or chann the hesters can riot impact the p*obabihty of consequences of an accident previously eey mode of plant operation, and will not occurrence of en acadent. De minimurn create any nrw failure mode for the plant.

required heat dissipation cele for thene evaluated l2) Create the possibihty of a (3) ne protmed change does not tavulu a heaters is not cAangad and the heaters will new or different kind of accident from s'p ficant reductwn in any sistgtn of safef).

conunue to be required to function in any accident previously evaluated, or (3) 1rie proposed clanfication to technical

,een,denu with their design requirements into)ve a signtyscant teguction gn a

!specihcs. tion 3't 41.3 wiu clarif the intent Threfm. thee is no change in the margin of esfety.

t of the sub ect $pecificatic;tt Therefore, th' consequences of an ecAldent.

The licensee has reviewed the t

plant mill contmue to be operated in 1:)1his proposed change does not create screrdance with the metons enumed in the possibility of a new or different kind of proposed request and has provided the pe tinent desyn calculations-erident. The pmposed change le applicabl' following no si nlficant hatards hcensee,RC steff has reviewed the only to the heat dimpation capabihty of the considetahon etermination:

The N e anal)sla and agrees with the VG and VC eptem heaters and doce not (1) %e proposed change does not inn oh e a litenRe e conclusions. Therefore. the invohe any change to the plant's phys 6 cal ognifunt increue in the probabibty or staff proposes to determine that the configurat.on or the operstion of any plant cornequenue of an accioent previously optems-es aluated.n, proposed changes to requested changes do not invoh e a (3) The proposed change does not invoke e Spectfu.aborn 3 911.t and 3 911.2 do not significant hntards considef auon.

opn$ cent reduchon in a marpn of ufety invohe a significant degredation in decay LocalPvMic Document Room ne proposed change does not im oh e a '

kat nmoval and/or coolant circulation locotion: Vespasian Warnrr Pubhc reduction in the mintmum required heet requirements smce decay heet remosal and/

IJbrary,1:0 West Johnson Street.

Chnton. Illinois 61707

'",'h"d' he m e

or coolani circulauon is provided for in the n,.

h re te ACTION requirements of the effected Aflornerfortscenste Sheldon Zabel.

hunudity, when required. to the levels 6PI' cations The propoa*d change to l'sq., SchiII. Nrdin and Walte,7:

usumed in the safety analpis. De ov,,,

$pecthcahon 3.8.2 does not coneutute a 00 Scare Tower. 233 Wacier Dra e.

tempereture cutout prevente ery m erheating s'gnificant reduction in ECCS m eter andeup tonurn.

Chicago. Ilhnois 60000 capabiht) emu m!y OpfAAT10NA1, The NRC staff has reviewed the CONDITIONS 4 AND T" m affec'ed, and N/lC Pm/ect Detector: lohn N. llannon licensee's anal sie and agrees with the dunna thene conditions one ICcs Illinole Power Company and Soyland hcenne's cm usions. Thudon, h subsptem/ system to sufficient for m eter P2w er Cooperath a. Inc Dacial No. no.

staff proposes to determine that the mdeup requiremente for the abort time (four 461. Clinton Pow er Station. Unit No.1 requested changes do not invoh e e hw shed by AC'f10N *aof DeWitt County. lllinole significant hasards conalderation.

spectf cat 6on 16.2 Turthermore. the proposed trico/PuMr Document Room changes do not involve e ognificani increase Date of cmendment request: june 30 locofion Vespasian Warner Public in the probabinty or consequences of the IIM Description of cmendment request /

IJbrary.100 West Johnson Street, primary postulated accidents associated with The proposed amendment would delete Citnton. Ilhnois 01727 shutdewn conditions (inadsertent criticality the upper hmit on the values for the heal A ttorney for licensee: Sheldon Zabel, and fi.et handhng accidenti emce those Esq., Schiff, liardin and Waite. 7:00 accident m prevented or mitigated by other Snergy required to be dinipated from Sean Tower. :.33 Wacker Drive, controle. desyn features. and reqmrements.

the heaters for the Standby Gas (2) ne proposed change does not create Treatment S) stem and the Control Chicago. llbnois 60000 the possibihty of a new or different kind of Room Ventdation 5) stem, NiiC Project Darectorr John N. llannon accident from any accident previously Fasa forrmposedno signi/ ant Illinole Power Company and Soyland evaluated becaun the proposed chane does 1.atords consideration determination Power Cooperative. Inc. Dociet No. 50-not mvoh e any changes to plant design nor The Conunlulon has provided 461. Chnton Power Station. Unit No. l.

does it invoh e e signacant change in plant standards for determining w hether a DeWitt County. Ilunols operation from what le currently allowed by the Technical Specifications. De impact of eigmficant hazards consideration esists Dcte of omendment req.restc june 30, pQdchaf C t

dt o e as stated in 10 CPR f>0.9:(c). A proposed 10ft9 p,

,e, e el a,

atteidment to an operstmg license for a Description of amendment requeste decay heat removal / coolant circulehon f:cility involves no signihcar.1 batards The proposed amendment would add a relative to the volume of weter conhiaed in considerstica if operation of the facihty 3.0A exemption to ACTION the reactor cavity / upper containment puoh in accor, lance with a proposed requirements associated with Technical during Mode s tesclud+g fuel bit,thng tmendment would not (1) Involve a Specification 312 (Cmergency Core operations). lP bchem that the proposed significant increase in the probabihty et Cooling Systems Shutdown). 3.9.11.1 changes do not intche e ognificant change consequerces of an accidcol pvviously (Refuehng Operatica.s. Residual Heat to the requirements for meeting these concerns during then conditions.

i

1 l

1 Federal Register / W1. 65. NL 192 / Wednesday. Octeer 3,1990 / N:tices 4M69 (3) ne proposed chnee does not invohe a (21 The recpowd charge does not create can perform their required safety fune:tions.

t e possibdity of a new or different kind of Specifically.'the revised Action *a" would h

sigrancent reduction in a mergm of safety enumed or required in any orcident or occ6 dent from triy acc6 dent previously still ensure that the minimurirnumber of proposed chanses do not involve e significent involve any c.henga to the configuration or perform the openmg functions of these j

transient anal) sin. As noted above, the en aluated.no proposed change does not valves / penetrations remain sveilable to reduction in core decay heat remosal operetion of any plant components, saltes/penetratione; revised Actions *b" and c.cpabdl'y or I~CC5 rnakeup capabi!4ty for the structures or systems es described in the cps

• c" and the proposed footnote """ would i

applicable plant conditions.

L'pdated Safety Analysis Report.

still ensure that each drywell s acucm relief The NRC staff has reviewed the (3) The propowd change does not involve e penetration is sufficiently closed to insintain licertsee's analysis and agrees with the s'rnificant reduction in any margin of safety, the drywell bypass leakege within the limits bcensee's conclusions. Therefore, the sina epusuon of the RW notem in the of the plant des;en and the current Action

'*** **"d'""

mnde fr m either the main

$1stements for DRYW11L WIT.CRITY. As a staff proposes to determine that the contml mm a ja Rs system is not enumed seeult. plant operation would continue to be requested cho!'ges do not involve a or required in any sectdent entlysis as maintained within the bounds of the current s gnificant hatards consideration.

emolained per IPs criminal commitment to not oefety enelyses. nerefore, these proposed Localfublic Document Room otise the steem condensing mode of changes do not result in a significant increene location: Vespas!an Warner Public operation.

In the prob =M!; vs the consequences of any IJbrary,1 0 West Johnson Street.

The NRC staff has reviewed the seeW.a previously evolueted.

Clinton !llinois 61727 licensee's analys!s and agrees with the (2) ne proposed channe does not ins olve Attorrey forlicensee: Sheldon Zabel.

licensee's conclusions.Therefore, the any change to the plant desiss Therefore. no leg, Schiff. Hardin and Waite,7:00 staff proposes to determine that the new failure modes are involved. and r! ant i

Sears Tower,233 Wacker Drive, eaquested changes do not invohe a cperet6an continun to be limited to the Chicago,I!!!nois 00000 significant hasards considerstion.

bounds of the current safety entlyses. As a j

Loco /Public Docum result, these propowd changes cannot create l RC Pm/ect Director: John N. Ilannote location: Vespasian %,ent Room arner Public the possibility of a new or dJ!erent kind of ocetdent from any accident previously Illinole Power Company and 80) land Power Cooperative, loc Docket No. 80-1.ibrary,120 %,est lohnson Street, evaluated.

Clintan,!!!ittois 61727 (3) The incorporation of the proposed 481, Clinton Power Station, Unit No.1, A trorney for licensee: Sheldon Zabel.

chango into the Ter.hnical Specifications mill DeWitt County, Illinois l'eq., Schiff,liardin and Waite,7:00 riot adversely impact the capability of the Date of oreedment request lune 30.

Sears Tower,233 Wacker Drive, drvwell post.LOCA vacuum relief s elves to 3

1389 Chicago, Illinois 60606 perform their raquired ufety functions.

Description of arr cadment requesi:

NRC Proiret Dimcror: John N.Ilannon Additionally, plant operstian will cont:nue to 1

The proposed amendment would delete be It'nited to the bounds of the current sa'ety the operability requirement for certain

!!!1aolo Powor Company and So) land ennlynes.neref m. these proposed chanses velves dedicated to the Residualllcal Power Cooperative, Inc., Docket No. 50-do not insolve a significent reduction in a eat, Clinton Power Station Unit No.1 margin of ule'y.

Ramoval system steam condensing mo.le which the licensee has committed DeWitt County,Illinola The NRC staff has reviewed the not to use.

Date of amendment request August 1:censee e analysis and agrees with the j

licensee e conclusions.Therefore, the lazords consi?rm' sed no significant Sosis forpro 31,1 @ 0 tion determinction:

Descriptio:t of amend: rent request:

staff proposes to determine that the ne Cotnmission has prodded

%e proposed amendment would resisa nquested changes da not involve a j

s'andards for determining whether a the operability and surveillance significant haratds consideration, Loco / Public Document Roorn s'Jnificant haraids consideration esists provisions of Ter.hnical Specification 3/

aa stated in to CI'R f09:(c). A proposed 4 0.5 to reflect that two drywell post.

locatiot'!Ve9Paslan Warner Public a:nendment to an operating license for a I.OCA vacuum relief 5 alves are 1.ibrary,120 West lohnson Street, facthty involves no significant herede gtosid,id in series in eech penetration.

Clinton, Illinois 61707 consideration tf operation of the facility Basis forp'oposed no significant Attorneyforlicensee:Sheldon Zabel, in accordance with a proposed 1:osoids cons /demtion determination, Esq., Schiff,liardin and Waite,7200 amendment would not (1) Involve a The Commission has provided Sears Tower,233 Wacker Drive.

l significant increase in the probabihty or standards for determining whether a Chicago, Illinois 00606 -

consequences of an accident previously significant hazards consideration existe

/VRC Project Dinctor-John N. llannon evuluated. (:) Create the possibility of a ee stated in 10 CI'R 50.9:(c). A proposed Illinois Power Company and 50) land new or different kind of accident from amendment to en operating license for a Power Cooperative, Inc., Doc.ket No. 50-eny accident previously evaluated, or (3) facility involves no significant hazards 441, Clinton Power Station, Unit No.1, involve a s'.gnificant reduttion in a consideration if operation of the facility DeWitt County, Illinois margin of safety, in accordance with a proposed The brensee has reviewed the amendment would not (1) Involve a Date of amendment equest August 31,1990 proposed request and has provided the s'gmficant increase in the p obability or following no significant hazards consequences of an accident previously Description of amendment request-consideration determination:

evaluated. (2) Create the possibility of a

%e proposed amendment would make (11 The proposed c.henge does not involse e r.ew or d.lferent kind of accident from several changes to the neutron o gamcent increase in the probabitty or any accident previously evaluated, or (3) monitoring functiors of Technical consequences of an accident previously involve a significant et duction in a Specifications 3/4.3.1," Reactor evalated. The proposed change will remose

[ ag Protection Instrumenta tion"; 3/4.3.6, RS t

nntro for va vee 1 -

Th licensee as reviewed the

" Control Rod Block Instrumentation";

louA/B anJ ti'12-fVasA.nese valves ar, proposed toquest and has provided the and 3/4.3.7.6 Source Range Monitors.,

only used dunne operation of the R)(R Iollowing no slpnificant hazards ne changes would incorporate optem la the steam condensing mode whke canalderation ceterminatioru statements of exception to Technical le not allowed by the Ci$ prowdures and (11 With the proposed chansa, the Specification 4.0.4, clarify startup precluded through sppropriate controle in Tec.haical Specincetione =ill stal ensure that surveilla** requirements, delete APRM e.conlance with established comunttments, the drywen post-tDCA vacuum relief volves Neutron Flux 4:'3h RpS setpoint l

i

k i

4N'70 Federal Register / Vol n N3,192 / Wednesday. October 3, teso / N:tices y

venfication, revise liRM control rod kw requiremente easier le ingdement Atsomer for 1/etraseve Sheldon Zabel, block applicabihty, revise IRM and SRM without enducias the afiscacemens af thsee Esq., Echtft. Hardin and Waite, ratio c:ntrol rod. block cAannel calibre Lion sunelDances. 71e Techn6 cal' "

Sears Tower 233 Wacker Drive, frequency, and incorporate an editorial "g

Chicago. Illinois 80000 m

se

• b""8

j perfonned within seven doye prier to erteeneg NRCPmjectDirector John N.Hannon ha o s cons e t a det no on' are i

Northeast Nuclear Energy Cosapany, art i

The Commission has provided ne denehan of N wtpoint eenficouan of al. Docket No. SD 338, Milletone Nuclear standards for determining whether a the APRM Neutroc flus 4hgh RPG funchas et Power Statloa Unit No.2, New landon significant hazards considerauon exists lust once pw eenn days suu provideo County Connecticut I

as :la ted in 10 CFR 50.92(c). A proposed adequete suurar ce that ttus inp function le amendment to an operating licente for a P'opwly cobbrated. Ttus RPS netpoint to Date of amendmentrequest A iguet 9-I:Cilit maintained et a constant value and le corel)' involves no significant hasards eretion ig operstjon of the facility therelom ennUer to the APkM Neutron ilua.

Descriptw, n of amendment request:

in accordance with a proposed

}tiph. Setdown RPS function which done not currently require setpoint venfkcation at least he proposed amendment would change i

em:ndment would not )1nvolve a once per seven days This propoud chenp is Section *, Umiting Conditions for s!gnificant increase in e probability or also onnoisient with the Standard TecArutal Operation, and Section 4. Swycillance consequences of an accident previously bpecif c.euuns and the Technical Re9utrements, of the Technical evaluated. [2) Create the possib!Lty of a Spec.ncet:one of the other BWR/6 plante.

Specifications for blillstone Nuclear ncw or different kind of accident from Resording the propeesd change to modify Power Sta tion, Unit No. 2. He proposed any accident prwlously evaluated, or (3) 6e AppbceWht) of the SRM control rod changes would be consistent with the

!nvoIte a siantfscant reduction in a block functions with respect to Opetettonal guidance and proposed changes m rgin of safeT Condstion L the T nhrdcol Specince hone, as recommended by Generic Letter BM9 The licensee nas teviewed the revned, wiU ettu eneum that adequate which was issued as part of the monitanng or n,,,,,, gig, l'"l* "

roposed request and has provided the evedeble to N operator dunns control rod initietive to improve Technical

{ollowing no slynificant barards consideration determination:

movemente. The IRMe on tens 4 or h6 sher Specificauons' provide adequate neutron monitonna 80818forProPosedno signi/s. cont (Il nne pronomed c.herien do not result in capability without the SRMs The SKMe hazartis considerotion determination any chartse to L.be plant desyrn or its provide no other input to the RCalS other The licentre has reviewed the proposed opersting modes Derefore, these proposed than ensuring neutron monitoring to a.alleble changes in accordance with 10 CFR changes cannot increase the probaldlity of during control rod movements.

cny accident previously evolunted he proposed chanp to the Channel 50.92 and hu concluded and the staff De proposed addition of SunelUance Cahbration frequency for the IRM and SRM agrees that they do not involve a Rrquirements 4 3.14 and 4 3 81 topther with control rud block functione should not result significant hasards consideration in del the incorporsuon of the pmposed add:tional int for Santillance Requirements 4.316 3.

in any signihcent change in the avellebihty of the changes would not:

4.316 e and 4.31.4.b. provide h Desth!hty these functions with respect to ensuring that 1.1nvoln a sign & cant intman in th i

required to perform h unociated IRM and neutron monitonns cepebihty is etelleble to Probabihty or connquences of en accident hRM surveulanr.co during plant shutdowns the operators dunna control rod movemente P"'. I'"'I ""*I 3'd F

Y following extended operetwn in Opstational et low power condiuona, s Sectson $4 De current Technical Condiuon 1. Thew surveiUenen cannot be ne emetning changes are editorial only Specification 3 0 4 prohibite changing mode of perfonned with the unit in Opereuonal end do not effect any technical requiremente operation unlese ou IJmiting Cnnditions for Condition 1. De proposed change mmi of the current Technin! Spec 6hcotions.

Opershon (ICOs) are met. Certeta Technical f

provide the funnel mean to avoid violen" Boed upon the abose, these pro eed Specihostione. however, contain en c.f Tschnical Specthcauon to 4 and provide change cannot increpe h probe hty or enempuon to Technical Specincetion 3.0 e cdrquete tune to perfono thne sunelllances the consequences of any occident previously that allows etert up with equipment ce mithout ceuelns unnecewary strets on plant euled parametm that am not in complienne with (3)Rene p ny dey to]eed chenpo da not rnalt in en opplicable 100 nis eumphon typicaUy pmonnel to coniplete these surveillances undxt the provisions of Act.on Statemente (or plant design or operation.

is provided for that equipment covered by Txhnical Specification 30.3) Adeque te As a neu!t. no new fellm n. odes am Technical Specincetions that is not necesury introduced Dersfore, thne proposed to edequately mittgete des!gn besie ked'unns changes cannot create the possibihty of a occidente. In these cases, because equ ment I

r prov ed he A sun sillances. period needed to perform thne new or different kind of accident from any operabiht3 don not impact the design sesis, h short time accident precionly evalueled thm is no need for a restriction on plant Th) proposed change to allow entry toto (3) As dieevowd in (1) above. thne ster 1.up. In all of these cases except one Opershonal Condition 1 before the APRM propowd chango still proside adequate (Technical Specification 3.4 sj. the ACTION stina have been adjusted to conform to h

'#urance that each of the opphemble nefety stewmente eBow conunod opmhon for an rower selues c.elculated b e best belance functions are capable of teing effected when indefinite period (Technical Specincetion 3

providee adequate time for plant conditione mquired including mector scram protection.

3 4 8 provides en stemption so that a poettrip to is achieved that wiu result in an accurate control rod block. and neutron monitoring.

lodane spike will not preclude rutart.)

best belence calculation. The APKM 11ow.

Thmfort thm proposed chanan do not The proposed revision to Technical themed Simulated Thenu!Ibwer4hgh ruult in a algnificant reduction to h margin Specification 3 0.4 would specificaUy allow functon still provides edequaw eerem of eefety, entry into en operational mode whl:e sub}ect protection dunng the short tune penod The NRC staff has reviewed the to ACDON tequirements, provided those nuded to schlese 26 of RATED 11tERMAt.'. licensee's analysis and agrees with th, requirements allow indeflatte contmuod POWER and perforin tbcee ApKAf gain adjuottnents after entenns 0;wrational licensee's conclusions.Therefore, the opmum. The revlud Tednical Condibon 1.

staff proposes to determine that the Specinceum 344 is eue cueistut with uw.

The proposed deletion of the requirenente requested changes do not involve a peopt and latut of me curnnt Tedrucal to p:t!onn Channel Functional Teets within significant haterde conalderation*

Specifications; the numerous esemptions i

04 houre pnor to startup or within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Locolfublic Doctunent Room from Technical Specthceuon sat would no prior to moving the resetor mode switch frore locationt Vespas!an % arner Public lonpr be necemry or appropriek. As ud.

the proposed changee wiU not incruee the the Sheldown poettion. 6nlen perforned Library.120 West Johnson Street.

probability or consequences of any acc6 dent within h ptsvious seven days, makn Clinton. Illinois 61727 previously analysed a

m.

m-,

s Federal Regist:r / Vol. 55, N:.192 / Wedn:tday. October 3,1990 / Notle:s 404M Several che current TedrJent clanficauon of esisting Technical Basis forpnyDsedw significant f pecif cations in Secuen 3 0 (3 4.3. 3 4 8.

$pectfacations. As each, this c.hange wGl al**

ha ords contiderofion determitiction 3 6.1.3 sad 3.y.11) conta'n limited have no eflut on the pec4 ebsiity w he Commission has provided e ar rptior,s fram the cwrent Tnhnleal consegaenres of accidents presiovs'y standards for determining whcther a Itpecifir.ation 344 theI e.annnt tw simply entlysed.

SWc.6 cant h.& tarda contidetation eM ddeted as a ruutt of h proposed revisian b

1. Create the Sabihty ol e new or ee stated in to CFR 50.92.

Techruost $pec.ficatson 3 04 N?aCO bee dJlerent kird o au.ident bom any vanalysei ne licensee has evaluated the therefore prosesed tev6e'ona to these that are prenous'l the proposed c.havn to either proposed amendment against the consistent with the intent of Generte 14tte 34oce o show and thet ensure change.nerefore.

section am or section 4 0 of the Tnhnen standards provided abose and has thne proposed changes as well ee the

!,ec6ficatxes ce the proposed editorten supplied the foDowing infortueSon:

venous eetorial chartges will also not trapact changre wiu have any trpact on plant (1) Does the toposed license amendenent the probotnhty or consequent ce of ecadente sw;nnee, ne amendmente reques'ed 6!ao involve a sigm cant Lncrease in the previo6s!y anained involve no a.hanan to plant equ;pment or t*

probabulty or consequences of su accident I taally, the proposed charan to Tnhaical either normal or emergency opet6ttes preytoy,1 e ntgee,df 7

• • N" 'u Em edures.Thes.no new fatture acdes wiH Operation ofInd!an point 3 in erecatleve l$p na M

n'4*"'""MfS""n'EP wNeua"-'-

E***Cfs@ E"*U"L'"

8 3 4

• [ntr pr bebihty or consequences of an acc4 tnt which petmits indef6ru e ontinued crer' tion I

f t

n of e

with en anoperable contatnment foolshon de s.gn basis accident or the o pplocable Implementation of the propo ed thenge ha valse provided the penetration is loofeted l'y Te&nical Spechcahon ACTION stammert espected to result in en tneresse to the e denctn sted s alve) in thew cases, the proposed te vtsions to Tnhnical Specatatum P"3" ** @*I"' '* "I *I ".

F probeMhry of enre damree, froin 134 a 10 '/

3 0 4 would al;ow start.up twcause the plant response 3611 be aca!! acted

)nt 2136 n 1(F'/yee Ute toernse le opphcebie ACTION requireinents a!!ow In wnmary.

O cwsMu est b cons dered to be insinficant relalive to the indefinite continued operet on tiowrur, this proposed c.henges will not create the undertying sncertaintee involved Thle m* ror change is conoment with the ottetive pcasit'ah of euy new or diffe ent k6nd of preposed e.hange wondd return tie EDG AOf of Gonsric Letter s".co erd theintent of the

• • • *de t u prevM anahwi technical spectatum tio 7 date. Seven days martpn el talety, "I' cant redactaen en the is the orig siel tedngal specificat.nn and

&I"YSI" *'4P other proposed revistona. te to sUow eude chansen when subreci to ACT10N licensu;g basis valee of the EDG AOT.

rsquiremento that do not impact continued As discuped show, none of h propowd (2) Does the proposed bcense trund:nent operettorL In then cases, the ACTION chanees to either Seeston to or $ett'on 4 0 of create the poss;bairy of a new or 6fferent rTquirements provide en equitalent level of the Technical Spectfketione et the ed terial kind of accident from arty accident prcuously s fety without requiring a shutdown.

changes willimpact piemt equspeient. P ant l

gg AUom6ng start up in these situations wi!!

M850M or any parameter related to the thirsfore have no adverse impact on the tutwn of h nettor coolant presum Operation of Indian Point 3 fn accordance probabihty or cocsequences of any accident boundary Fcither, the changee will with h prom lese ernerdrnerit does previously analynd not effect either norma er emerpney not create the possibdtty of a new or diferent b Section 4 0 The proposed cherige wou!J operating procedwee. Therefore, the k6nd of accident from any occident previously

, gg ros*J chanpo wdl not in pect any asfety rettse Technical tpecification 4 0 4 to a !ow a deley of up to it bours to implement pimit or reduce any energin of eefety.

N'o % WW M h h me a gg

,, p, g

ACTION requirements in the event a required Based on the above, the staff proposes new modes of plant operation are tavolied surveillance mee not performed and the to determine that the proposed changes fatending the EDG AOT don not nectuttate allowable octage time hmits of the ACnON do no, t involte a Mgnificant hasards I pical efteration ofit.e plant or chenIes in h

etstement are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This delay e

m ould epply only in the event of a missed plant opnewnal hmus We pmrosed Na a

n.

ourseillance,it would not apply to e failed PtMc Dorvment fl.iom chenp would retum the EDG AOT technical survettlance.

location? learning Resourece Centee, specif cehen to ? dare Sewn dar* 18 the The proposed dela y in implementrra the Thames Valley State Techt Jcal College, ortatnal tedmical sawcification and beeneirs ACTION requirements to intended to e!!ow

$74 New tendon Turnpike, Norwit.h.

buis vahse of the EDG AUT.

aufhelent time to complete the required Connecticut 063tIO.

D1 EMS ikie ProPased amendment inndw eSrveillance, ne prepneel r=cogmree that e AttJfney[Jr/rcenSec' Cerald Carfleld' O'peretien of Lad:so Point 3 in accordarire mined nrseillance is much len sigmficant Esquire, Day, Berry a fl'oward, Cit),

with the pmpoemd ucanas amendment dois thsn a failed surveillance. Farther,3:ren that Place, Hartford, Connecticut 06103 3499-not involve a signtficant reducuan ln a ths vest ene}onty of nrveillances performed meet relevant acceptance criter a. m most NRC Project Director: John F. Sto!

rnergin of sefety.

caeee h missed eunedlance-well As detailed in h study contained in I

a tyof a State of New i.oweeork, Doc.kat No. 50 288, ladies Palatoutage time involves an incrementa!

Appendia A. extenang the EDC a!! owed demonstrate the equ pment to be ofwelde.

The propeerd charge recesMece that et le everly eeneenstive to eseume the, Nuclear Censreting Unit No A reduction in the mersin of safety.The equarment 6e inoperable sireply because a Westdicatur Cosmity, Now York ma;;n tude of this redisction is insignificant compared to b itncartainties involval earsedience mu mined.

Dcte ofomendment reques& July 10*

m up@ to pmr ntal and anhary Tka reemoed champ to Techencel Specaf. cation 4 0 4 does not irrpact the 1990, as supplemented At gust 24,1990 splem componente remalna nadable via the De8cti fiom of amesid nent request:

oht two EDGa.nia propaced change would integnty of any component or of the reacter f

rool.et grenure boendary. W proposed he proposed change to the Indian Polal return b EDC ACT techracal spec.ibcataan chenee does not impact, in a eihtentin 3 (IP3) Technical Specifications would to 7 days. Seven doye is the origme! inhneral way, the operetshty or earveiDenre increase the a!! owed outage time (AOT) epecification end lococeans basie value af the requirements for any component nor t'ose 18 for the Emergency Diesel Generetors EDG AOT.

change the e st servallanee/testens t EDCok Teeknical Specific'*tten Sect!on he staff lies reviewed and errece

"*', "hg (a.7h (page 174) would be thenged to b

$N 3

with the licenece's analysis of the p

llow an EC eatsge tinue ed erven signfficant hazarda consideration or essesqnences of any ucident ynnously I

cnalyzed.

days, insteed sf the suevently alloiseed y2 determination. Based on the review and 1

l The protamed cheese to Twknical hours. A no een day ACFT was in eMed the above discussion, the staff proposes Specificatam ut as eneentW1y a when IPS was originally lionneed.

to determine that the prgposed change i

l

l

1. r/2 Federal Register / Vol. $$. N2.192 / Wedneadry. Octaer 3,19e0 / N:tices does not involus a significant hasards Removal of b pretemperature limite Descriptien of amendmcalrequest consideration. I for artticality dan not taareene the

%e proposed amendment would revise Loco / Pubhc Document Room conwquences or probebehty of any socident locotion White Plaine Public 1.ibrat),

becauw thne hane am minseneenly Table 3.61 and Table 4.41 (Page 6 of 7) of the Technical Specifications to reflect 100 Martine Avenue, White Platna, New 7,'O,d '",d,f M

.gY the removal of Containment toolation Yotk 10601 A ttorney for licensee: Mr. Charles M.

It) Don the proposed boense sessadment Valves UH 37 and LTF138. Containment Pratt.10 Columbus Circle New York.

er,ete the possibihty of a new or ddlerent isolation Valves LTH 37 and Ull 38 are New York 10019.

Lind of scendent from any accident previonly on the Auxiliary Steem Supply and svaluated?

Condensate Return (ASC) System steam NRCPrvicctDirectort Robert A.

ne updated P T hmits will not crate th*

supply and condensate return lines.

Capra poulbihty of a new or different kind of acendent. The revised opeteting hatite menly respectively. Dese lines originally were Power Authority of De State of New update the esistmg hmits by taking into designed to supp1y steam io the York, Docket No. 90 384, Indian Point account the effecu of redietion Containment Unit }lesters. Since the Nuclear Generating Unit No 3, embrittlement, utthatng critena defined in RG temperature in contalnment is Wootcheeler County, Nov York 1.se Revision L ne updated P T curyn am maintained without the use of the Unit coriservettvely edjusted to account for the Heaters, auxiliary steam is no longer Date of amendmenf reglast: August effect of t rediation on the hm! ting reactor required to be supplied to containment.

31.1990 vnsel metenet.

Valves UH 37 and Ull 38 are therefore Description of amendment request:

No change is being me le to the wey th*

being removed.

314 amendment to the Irdian Point 3 pMuum-temperature 1.tatto Irovide plant Technical Specificatinne nould amend p otect on. No new modes o operation ero Basis forp sedno significant Section 3.1.D (lleatt.p and Cooldown) involved, incorporating this amendment doce hosords consi erotion determinations Section 4.3 (Reactor Coolant SIstem '

nc4 neensnete physical ahereuon of the h Comm%n has FM Integrity Testing), and Section 3.1.C plant.

standards for determining whether a (Minimum Conditions for Criticality).

is! Don the propowd amendment invoin significant hazards consideration exists Sections 3.1.B and 4.3 att being e olpnificant reduction in a margin of safety?

as stated in 10 CFR 50.91 ne proposed amendment does not involve amended to incorporate revloed a signif cent reduction in the met sin of The licensee has evaluated the pressure temperaturelimits %ese oefety.no pressure temperatun operating proposed amendment against the revisions are being made in accordance limits are designed to provide a narpin of standarde provided above and has with Generic Letter 8811 which enfoy, The wquired margin is al ocif ed in supplied the following information:

requested that lic?nsees ute the ASME Boller and preputo Vue,1 Code, (1) Does the proposed license amendment methodoloII of R,,Radiationegulatory Guide (RC)

Section IIL Appendix G and 10 ( TR [pertj go, involve e signmcant increue in the 1.99, Revision 2, Appendix G. The revised curvn are bened on Probebihty or consequences of en occident F.mbrittlement of Reactor Vessel the latest NRC guidehnu along i rtth actual previously evolustedt Materials," to predict the effect of neutron flux / fluence date for the ' vector The proposed changes reflect a plant vessel. The new limits reteln a ma rain of modification that will enhance the integnty of neutron radiation on reactor vessel eefety equivalent to the crismal m tryin when the containment penetrations associated with materials. Section 3.1.C is being the vnsel was new and the fractura the Asc steam supply and condensate retum amended to delete Section 3.1.C.2 which toughnees wu shshuy gruter.The 'ew hnn. De mod & cation will cap the two establishes pressure temperature eperating hmits account for irrediation lensthe of piping penetrating containment.

requirements on the reactor coolunt embrtttlement effects, thereby maintelning a ne capped piping will be leek tight, s), stem wgen t e reactor it critical.

conservetive margin to safety.

therefore the technical specification changes Bosis forpippesedno spificant The removalof the pressure-temperature associated with this modMeetion do not hatords consideration determination for enticahty does not reduce the plant ufety involve a significant increen in the nargin beceuw thne hmns are probabihty or conuquences of en accident The Commission has provided conurvettuly encompawed and bounded by previously evalueted.

standards for determining whether a the regatrement of specification of 3.1.C.3.

(2) Does the proposed beense amendment significant hazards consideration exists he staff has reviewed and agrees create the pouibihty of a new or d2fferent as stated in 10 CFR 50.91 with the licensee's analysis of the kind of accident from any accident presiously The licensee has evaluated the significant hazards consideration neluotedt proposed amendment against the determination. Based on the review and The proposed changes renect a plant standards provided above and has the above discussion, the staff proposes g"oj, onj" d aca Pmen \\

supphed the following information:

to determine that the proposed change cc e ns (1)Does the proposed bcense amendment does not involve a significant hazards epocleted with the ASC steem supply and involve a significant increase in the consideration-condensate retum knes. Since this is the pobability or consequences of an accident locolfublic Document Room ume function certently provided by he cr th

[a containment is.stion velyn Ull.37 and Ull.

hty nor the locotion White Plains Public Library, so. the removal of these valves and consequences of a previously analynd 100 Martine Avenue, White Plains,New unociated technical specification chanan to occident is increased due to the propond York 10001, not create the poulbthty of a new or different changes ne ediusted reference temperatum Attorney /orlicensce: Mr. Charles M.

kind of accident from any accident previous!y of the hmittng belthne material wee used to Pratt.10 Columbus Circle, New York,

"

• I" * d-correct the pressure. temperature curvn to New York 10019.

(3) Don the proposed amendment involve account for triadiation effects hus, the NRCProject Director: Robert A.

• *I8"#C*"' "d **" " I" ' **'8 " "I "I"f" I

operating hmits are ediusted to incorporate Ca ra the initial fracture toughness conservatism a signihicent reduction in a mergin of safety

' "E"**'""'"'"""'I"*

present when the reactor vesul was new.

Power Authority of %e State of New since n nnects a plant modification that will The adjusted reference ternperature York, Docket No. 30 3e8, Indian Point enhance cotitainment integrity by providma calculetions were performed utihong the Nuclear Generating Unit No. 3 I'

• k 8h' '"I' th' P'"i*"' * "**id

~*

guidance contained in RG 1.99, Revision 2.

The updated curves provide enurence that Westcheolor County, New York e W ASC cum n#y and conmuu return lines.

brittle fracture of the reactor vneelle Dole of omendment requeste he staff has reviewed and agrees prevented.

September 19,1990 with the licensee's analysis of the oweA=

e.

.-m.e-

Feder:1 Reglat:r / Vol. 55. Nr.192 / Wednesd:y. October 3.1990 / Notices 4N 73 significant hasards consideration The licenses has provided an analyane Attorney fw heenaea: Troy R. Corner, determination. Based on the review and of no signifkant huards tona6derations lr. Enquire. Conner and Wetterhabn.

the above discussion the statiproposes Iwith the request for the licer.se 1747 Pennsylvania Avenue.N.W.

to determina that the proposed change amendrnent.The Iker We analysis of Washington. DC 20000 does not invohe a sigmficant hasaros the proposed amendment against the NRC ripfect Directorr Welter R.

consideration.

three standards 1o 10 CFR 60.92 is Butler localMlic Document Room reproduced belew:

location Wlute Plains P'.:bbc 1.ibrary,

1. Invol"

• NFdcaut inenone la b Pdlic Service Electric & Gas Comr/eny DockM Nos. 2 272 eud $4 311. Salem 100 Martine Avenoe. White Plains, New F,o',Quences of an om Generating Statten. Unit Nos.1 arid 2 Y"h N Attorneyfor b.censee: htr. Charles M.

The occidents of concern with respect to Salem County, Now lasey Prott.10 Colutnbus Circle. New YotL.

h ArkM/tRM e >rripeMon ecmm, caused by an APRM downseate conewsnt wtth eithe, Date of o'rendment requeet July 10.

New York IX119.

at IRM "h'gh high" or inoperable trip, we the 1980 and Supplement defed August *8.

NRCPirjeetDirector Robert A.

rod drop occident (FDA) and the low power 19tIO Capre rod wttherewei error (RwT1. The TSAR end DescFption cfemeadtnent request-reined sefey enelyen do not credtt tNe Public Service rfectric & Gas Company, anns fancties in e e terrowntion of eithe of The Operating 1.leenses for Salem 1 and Salem 2, DFR 10 and DPR 75.

Docket No. 60 354, llope Creek these acckhts. Sinca ha scram function is Generating Station. Salera County, Now not credited in the terminetion of these respeettvely, wot.ld be cmended to add JoeneI accidente, the elingnetion of this screm a new Section 2.l to Di,R 70 and Section funetton has no adverse ef'ect on peeriously 2.N to DPR 75, to read-Dole ofomemfment revueste eeeber,d sectdenre.

"The sense of the Mey e. taa3 Order heve Septembee 4,1990

2. crn's she poes,bility of e cew ee been settsted t y the incorpention of the Descr:ption of amendment requese d.f'erent needent from oss seceleus long term carrocene octase regehements lato The ame idment would eliminate h pr' vical 'vab***d-the Salem tJpdated una Repoq Appendas W,1 Selety Asa!ysia F

as etage Power Range Monitoe (APRM)

Tte nmuns ac4adents in h opentana downacale Reactor Protection System

8E "

• • • ""I'eiwwa the ananup and

& rata fomepad ao significant (RPS) acram Tec.hnkal S cific.ation run moJn an well understwd and are hoenids cenaldenttion deterannolion:

(TS) requirements (Itam 2 in TS Tablee Ena yIe d * "3 On May 861983, the Nuclear Reguletory h ne it te 2.2.1 L 3111. 3112 and 4A1.11k The downecaletiRM %:h hish* arinoperable Commieeion Iseved an Order modifyteg APRM downscale scram was designed caused uram does on ineruduee any erw the operating licecees for the Salem to reactivate the Intermediate Range accidanit scenerte ena it le out sewheed im Generating Station, Unit Noc.1 and 2.

Monitor (IRMI upscale scra a functions the termination ei these events lia RDA and he Order teferenced a series of letters when the associated APRM channel La RW E). tame tuniung evente La h respan sud in which Public Service Electric and Ces downscale and the Reactor Mede switch na control 'od in! hated last paned evente Co. (PSEAC) had evenaitted its is in b Ran paaltion. Normally proper M dW to openW nme m CRD wrecieve actwin program in response le Reactor Mode awitch positioning in N Nnt a n) er eI*

"S"d the reectee breaker failures. nie administratively ensured by compliance the design bees RDA. In e&fitwn, General correctin action program included short with the integrated opersting procedures Electne has indicated ht kie reoctivity term. interim and long term actions.

for plant startup and shutdown.ne insertion evenne occa r.se enth as Subsequantly, the Ordee was auxiified surveillance testa for the APRM ineppnspnate sente ewitcA pastion, the by letier dated January 31.1964, to downscale trip function, required by the ellect af the denetaan af M APRM d change the implernentation schedule foe TR require the plant to be placed in a

" **'kl be that b tmtal power leul severallong term actions, and again cm be a few persect krwarme gaunic

' hall scram" condition, thus increasing c

March 18,1988, to remove the l

the probability of a spurious trip or ESF fe$ N e',f, [

['p"[g'yg, g, requirement to submit Nuclear actuation. Since the downacale trip is weald teund any po sibir event et Hepe Oversight Committee Reports on a not judged to be perfora Ing a function creek with m propo.ed chan,,,

quarterly baala,ne March n t9es I

with a value commeneurate with its t invoin a sigmficant redussian in e letter also stated that the terms of the astociated risk ue butden. b licensee marsa of safety.

Ordee have been satisfactordy preposea elimination of its TS The ApRM downscele/tRM *hrgh high" or completed.

requirements.

InoperoMe caused octem La not ceedsted in PSE&G has performed a detailed Basisfarp.rysed so a4tnifical

$'j",'",

h'"*j * 'h * *M review of the correspondence hacids considention deterrmaationi The Commission has provided eliminatian of tlus scram function has ao addressing the corrective action atendarda for determ' dng whether a effect on any Technkal Specification def.ned program and identified a total of farty-u ufey lfaut.

three (43)long term program rignificant hazards determination e Alsta The staf! hae reviewed the licensee *a committnests which will be e,s stated in 10 CFR 50.92(ck A proposed submittal and significant hatarde consolidated into a new updated Final amendment to en operaung license analysis and concurs with the licensee's Safety Analysis Report (UFSAR) involves no ignificant hazarda determination as to whetber the appendix.ne cor tents of this appendiz consideration af operation of the facility proposed amendment invohoo a wi!! be controlled in accordance with in accordance whh the proposed significant hasards consideration.

the provisions of10 CR 50.59.

amendment would not.1)involw a Therefore, the staff proposes to The consolidation of the long term sige2 cant increue in the probalAlity ne determine that the preposed amendment program comer.itnwnts Leto the UFSAR sonarquenors of an accident pteviously involves no signifbant hazards assures that changes to these programa evalueted:1)cnate h possibuity of a conalderation.

win te properly controDed. Any changes new or different kind of accident from LocalNcIbcument Room involving an unreviewed safety questias any accident previously evalented; as 3) locaban. PeasavWe Pubhc library.190 or a change in the technical involve a significant reduction in a S.Emeeduey. Pennavina, New larsey specifications would be submitted to the margin of safety, on04 Commisnaos Ier prior approval.

-=.

40474 Federal Resister / Vd. 55. No.192 / Wednesday Oct1ber 3,1990 / Nttices I

ne forty.three (43) program element determine that the proposed ansendment detenninstion shalysis. Based upon thl descriptions will be grouped in the involves no significant hasards review, the staff agrees with the UFSAR under the following headmgs:

consideration.

Licensee's analysis.

Loco /Public Document Room Based upon the above discussion, the

. Training

. Procurement & Management location: Salem Free Public library,112 etaff proposes to detertnine that the

. Operating Procedures West Broadway Salem, New Jersey proposed change does not involve a

. Malntenance & Surveillance 08079 significant hazards consideration.

. Control of Vendor Information Attorneyforlicensee: Mark 1 lacolPublic Document Room The Commission has provided Wetterhahn. Esquire, Bishop. Cook location Rochester Public 1.ibrary.115 standards for determining whether a Purcell and Reynolds,1400 L Street.

South Avenue Rochester,New York significant hazards consideration ettete N.W., Wa shington. DC 20005-3502 14c10

\\10 CW bo.92(c)). A proposed NRC Project Director: Walter R.

Attorney forlicenser: Nicholas S.

arnendment to an operatir4 license for a Butler Reynolds, bishop. Cook, Purcell 4 facilit involves no signthcant hazards consi eretionif operation of the facility Rochuter Gas and Electric Corporation, gRe nolds,1400 L Street N.W" i

d th th d

Docket No. 30 244, R. E Glana Nuclear a6.ington, DC 20005@2 amendrnen o d no : )

olve a Power Piant, Wayne County, New York N C[roject Director: Victor Nerses signihcant increase in the probability or Date of amendment request )nne 1, consequences of an accident previously 1990 South Caroline Electric & Gas Company, evaluated; or (2) create the possibility of Description of amendment request!

South Carolina Public Service Authority, a new or different kind of accident from ne proposed amendment would c.hange Dociet No,30 3e5, Virgil C. Summer any accident previously evaluated; or (3) the Ginna Terhnical Specihcations, Nuclear Station. Unit No.1, Fairfield involve a significant reduction in a similar to the Stendard Technical County, South Carolina margin of safety.

Specifications for Westinghouse Date of amendment request: May 16.

The license has analyzed the Pressurtzed Water Reactors (NUREG-1990 and August 13,1990 proposed amendment to determine if a 045? Revision 4). in specifying time Description of amendment request signihcant hatards consideration eAlsts:

limits when required to shutdown the The amendment proposes to modify 1.no proposed change does not incres**

plant due to the quadrant to average Technical Specification (TS) 3/4.4.2,

((ctd ri p oIst 1uaYbe.ause a 1 power till ratio exceeding 1.12.

P Safety Valves, for both the shutdown breaker.related technical specification 80838 forProPosedno significant and operating conditions. Specifically.

requirements remain in effect and additional hozords considerotmn determination!

TS 3/4.4.2.1 covering shutdown would controle. beyond 10 CR IA59 and 5011(el.

De Commission has provided be modif ed to change the setpoint apply es follows:

standards for determining whether a tolerance from plus or minus 1% to plus a Training to CR 55; Regulatory Guides signihcant hazards consideration exists or minus 3%. In addition, the 1.8.1.La and 1.14& Generic tatters 81@ and (10 CFR 50.92(c)). A proposed surveillance requirement for this TS was

$1i l ase, ao@a am em as-amendment to an operating license for a proposed to be modified to indicate that

,,d un

b. procurement & Management.10 Cm fach involyn no signTicant hazards either the surveillance requirements of So.54[e)(3). ReFult. tory Guides 1.33 and t.44.

considerations if operation of the facility Specification 4.0.5 shall be met or the

c. Operstms Procedures Regulatory Guide in accordance with a proposed nressurizer safety valve shall have its 1.33. Generic letters 83-32 and 85M LNPO amendment would not:(1) involve a

[ift set pressure verified under cold 84 @ 4.

significant increase in the probability or conditions. The tolerance was also d Maintenance a Surveillance: Regulatory consequences of an accident previously changed to plus or minus 3% for13 3/

de 3 c m ne re z as aand evaluated;(2) create the possibility of a 4.4 2.2. A footnote was added to indicate

e. Control of Vendor Informatiore ^

new or different kind of accident from that Mode 3 applicability did not apply Rigulatory Culde 1.33. Generic tatters 82 04, an accident pre lously evaluated; or (3) when there had been at least five de s Ene and 90 04. INPO 84@0. 67 009 and as-involve a significant reduction in a of operation in Modes 5 or 6 since the 015 margin of safety, reactor was last critical and all rod 2.ne proposed change does not create the The licensee addressed the above cluster control assemblies (RCCA) are possibthey of a new or different kind of three standards in the amendment fully inserted with all control rod drive occident from any previously evaluated application. In regard to the three mechanisms (CRDM) deenergized. De cou e th c nge df a ta1lg at ndards, the licensee provided the bases for this TS,3/4.4.2, were also equipmer.t or the operating procedures.

"ggf

,*3,, og t[e facility in accordance pr p sed i be modified toindicate that

3. The proposed change does not involve a with the proposed amendment to provide E'"

Y**

designed to relieve a given amount of sigmhcant reduction in a margm of safety generically accepted guidance would not because the change neither impacts hvolve a significant increase in the saturated steam at the valve setpoint comphence with 10 Cm 50 a2 nor affects the probability or consequences of an occident plus 3% accumulation. In addition, the selety hmits hmiting safety system set s.

.buQ evaluated.

proposed change to this bases section surs elllance requirements, hmiting contro (21The guidance merely specifies the time deleted the indication that the safety h Weh th te utred power reductions must valves will demonstrate their lift es gn fee ored n tre e con 1 as d:senbed in the Salem Technical t* eccomphshe. Use of the modified settings only during shutdown and that specificauon would not create the possibility such a demonstration would be Specifications of a new or denenWnd of eccidat from The staff has reviewed the licensee's performed in accordance with the 1974 submittals and significant hazards "g*3j s f el"[w,",'Me*f"o'n's fsos and Edition of Sect,lon XI of the ASME Boller enalysis and coacurs with the licensee's hot shutdown) are still required, use of the and Pressure \\ essel Code. In the determination that the proposed modified specification would not involve a proposed change, no edition of the code amendment does not involve a significant reduction in a margin of safety, was specified.

significant hazards consideration.

The staff has reviewed the licensee's Basis forproposedno significant Therefore, the staff proposes to no significant hazards consideration hosords consideration determination:

Federal Register / Vgl. 55, ND.192 / W:dn;sday, October 3,1990 / N:tices 40475

==

The Commission has provided env trannent in Mode 3. In addition. ell ether NRC Prrject Director: Elin:t C.

standards for determining whether a no ufety systems und to mitigste any occidents Adensam l

s!gnificant harerde consideration esists

[,"h*,,d la $dN*,','g*,"'D thr South Carolina Electric & Cao Company, e

as stated in to CFR 50 92(c). A proposed lenits as dehned in the ISAR remain South Carolina Public Servica Authority, amendment to an operating license opphcaNe for non.LOCA postulated events Dociet No. 53 395, Virgil C. Summer involves no significant hatards For the SGTR analysis. the core decay heat Nuclear Station. Unit No.1, Fairfield considerationif operation of the facility m ould be signincantly less in Mode 3 and, County, South Caroline In accordance with the proposed ti,erefore, the consequences are bounded by a nendment would not:(1) involve a the results provided in the f3AR.Therefore, Date of omendment requeste luly 18.

significant increase in the probability or the probebility or consequences of an 1990 consequences of an accident previously accident previously evaluated in the PSAR Description of amendment neueste

'I evaluated; or (2) create the possibility of

• iU,n\\t, ouQue th The proposed Technical Specification 9

d (TS) changes concern the deletion of a new or different kind of accident from

2. The pmposed change does nog Figure 3.13, Required Shutdown any accident previously evaluated; or (3) cnote o new or different Aind of involve a significant reduction in a occident from any pnviously evoluoted.

htargin (Modes 3,4 and 5)," from the TS trargin of safety.

and add a reference to it in 3.1.1.2, South Carolina Electric 4 Gas As premusty stated, se PSVs pmvide Shutdown Margin Modes 3,4, and 5. In Company (the licensee) has reviewed overprenurtration protection for the primary T3 3.1.1.2, reference is now made to the the proposed changes and has ofstem The analpes results as presented in Administration Controls Section 6 9.1.11, determined that the requested the FSAR remain vehd and no new fail, ire Core Operatins Limits Report (COLR) amendment does not involve a r.echanisms were determined Thus.the and Figure 3.13 is now located to the significant hatards consideration for the pmibility of an accident which is different COLR. Additionally, the proposed following reasons:

than any already evaluated in the F3AR change revises Bases Sections 3/4.1.2, J. The pr.' posed change does not would not be creeted due to changing the Botation Systems, to delete the repnseni o significant menose in the PSV[fy",1"l,8 3] *j,',",Pli,[ th' teferenee to Figure 3.13 and replaces it C'

with a reference to the COLR. A change probabihty or consequences o on All safety systems required in Mode 3 occidentprevious/y croluote.

function, and no new failure modes are is also proposed to the Bases Section 3/

The 15Ve (pressunser safety valves]

6denuhed for any system of component, nor 4 2.1, Axial flus Difference, so l' refers provide protection from overpressurination of has any new limiting einste fe'ture been to the COLR rather than the Pe sking I'f entified. Therefore, testing the PSVe in Factor Limits Report (PFLR).

occade t 6 i t ed. ) owe er t e acci e to bt de 3 does not create the possibility of en Amendment No. 88 to the Su' amer deprenurtsation of the RCS (reactor cocient accident which is different than any already Facility Operating License replaced the et stem) can be trutisted by the cpenmg of a e'.elusted in the PSAR.

FFLR viith the COLR Finally, PsV. !ncreastna the tolerance on these velves does not create e new failure mode et result 3 The FmPosed chor'se does not Administrative Control Sec tion 6.0.1.11 in a hft setpomt that would increase the NPnsent a significant reduction in the is proposed to be modified to add the probabihty of an inadvertent openirs of these margin ef sofety shutdown margin limits of IS, CAP 92*2-3.1.1.2 to e lves Also, as discussed in the evolustion As indicated in the evaluation. the the scope of the COLR and %

l safety). DNER (departure from nucleate conclusions provided in the ISAR remain t othns totio and PCT (pnmary coolant vahd. All acceptance entene continue to be P.A is identified as the document temperature values affected by the non.

met.Therefore there to no reduction in the describing the methodology used in L.OCA Inon-on.of. coolant accidentj and mergm of safety dehned in the bases to the developing the shutdown margin limits LOCA acc6 dent l SIC) events remain within Technical Specif cations.

for modes 3,4 and 5.

the hmits specified in the licensms basis The verification of the PSV setpoint values Basis forproposed no significent documentation. The es aluation also in Mode 3 does not restrict the values from ha:ords consideration determination!

demonstrates that the man / energy releases performina their intended function. All The Commission has provided inside and outside the containment acceptance enteria contmue to be met.Thus, previously documented in the ISAR remain there is no reduction in the margin of safety standards for determining whether a no vshd. In addition. the SGTR (steam generator es defined in the bases to the Technical significant hazards consideration exists tobe rupture] analyseo show that the change Specifications.

as stated in 10 CFR 50 92(c). A proposed in the pressunser safety valve setpoint The licensee has concluded that the amendment to an operating license tolerance has no impact on the analysis.

proposed amendment meets the three involves no significant hazards Therefore, the probabihty or consequences of standards in 10 CFR 50.92 and, considerationif operation of the facility en accident previously evaluated in the F3AR therefore,invohes no significant in accordance with the proposed would not be increased due to changmg the harards consideration.

amendment would not:(1) involve a

0' The NRC staff has made a preliminary significant increase in the probability or c rte e ical pec f t o v lue review of the licensee a no significant consequences of an accident previously (With respect to the allowance of PSV hatards consideration determination evaluated; or (2) create the possibility of testing in htade 31. the installed [ Crosby Cape and Valve) SPVD setpomt venfication device and agrees with the beensee's analysis.

a new or different kind of accident from does not restnet the vertical movement of the Accordingly, the Commission proposes any accident previously evaluated; or (3) spindle before, during or after testing The to determine that the requested involve a significant reduction in a internal mechanism of the SPVD tnagers e a'nendment does not involve a margin of safety, solenoid and releues the spindle allowing significant hazards consideration.

South Carolha Electric & Cas the s alve to rescat. It is highly unhkely that Loco / Public Document Room Company I'he licensee) has reviewed

• h',}*N'p,,Nn'gf,$[,','gncd I###'I#"# I'l'IIeld County Library, the prossed changes and hae aue

,n transient Carden and %.ashington Streets.

detr. mined that the requested Since the plant is in hiode 3, the plant is in e Winneboro, South Carolina 29180

• aendment does not involve a no load condition. Assuming that all rods are j

inserted and deenergtred while the valvee Attorneyforlicensee: Randolph R.

significant hazards consideration for the are betna tested, no reactivity may be added Mahan, South Carolina Electric & Ces following reasons:

to the pnmary through rod motion. Because of Company, P.O. Box 764, Columbia,

1. The proposed chanae does not invoh e a this, the PSVs are not required to mitagste South Carolina 2B218 sign 6ficant increue in the. probability or

~

1. 08 Fedewal Restater / Vol 15. No. In: / Wednesday. OctcAnet 3.1900 / Notices 2

ci esequences of in sectdent prmocaly The denlopment of the tequtred 3Dht involn a syntlicatn tocreese in tlw tulue:ed.

curves for fetuse estceae wEl asennee to probebibty or eeneequemen of en occHent ne esanol of b Ra,pawd SDkt osrn s.ontorie to those siethods deacreed in ifRC-pwmush eareluatosf?

[htdown hiargin Carve ISDkf). Tigure 113) approved documentenson le ad tiene, each Mesponse: No from h Wy2 C kremer Nucleat Staboo Techints) Speerht eticms has ne infleenee or future reloed w1U involee a 1cCPRao.te malety The operation d San Onofre Unit 1. in rettew to aneurs that operet6on d he aardi tmpoet on the probabihty or consequenose of any accident previcesty eeslaeted ne Isaits wit 1dn the curve wi!) nat letpha a engedtk. ant accordance with thas prvgmeed cAance, wiU in the curve. although not to Techtmel tedxUun in a margin of anfety.

nel teeoh e e algraficotriintrsese an the Speethrations will be followed tn the The proposedievision to charge *PfM* to probabdpy a opeeequanee of as occ. dent opereun of the Vesil C. Summer Nuclear

• Cotr in Tec.hnical Specification Aeons S/

preymfy eulpted nu proppeed change bianen. The f*opoecd emerwMer.1 adu 4 21is admutistrative an nature The chave intohee only a t.!artf.caten of a refererce to stropiy deletes a refereree to en obsolete en tricorrect edittun of NrpA Standard No requtare etactly the 6 erne chan6 to be taken w hen or Af lunne are escoeded as as required report (I'!U) and referenctl the report WUch to his tinne wul tuuh in the Tettakki by current Techfuc.al $peci! c stens i.e:.h replaced it (COUL). he eter.pt dare not ftpecification referenetr$ the editicm of the affect the tnargin of Seiety currently prvvi6vd NYTA stendard en Weh the fire tegede acc.ident ana!ysts addressed in the Vargd C.

t,y the Tetimkat i+pecifications-treirurig is tened. entbar then the yearly escue Summet Nucitat tasuon t'mai $sfety Anah sie Report (11 AR) W11 le e narrened herefm, die proprised t bange skee not deu of the NITA Code.11m-eInte. this with respect to chenpas tn t)e reautrod SDat.

impact the operation of the Wryil C. Summe' change willi:r.v*ote the quehty of Tet knical aih4 are obtained frors apphcetion of tie Nuclear fuscen in a maaner that ar>volves e Epecthcotion Secteas No. 841 Tie etense is NkC eppromt rebd deogn me% dol r,doetans en the martnn of enfety*

adrnatustreon in ambture and eviu noi allect to ensure that the transient en alvatwn The hcensee has conchded that the arctdent probehbues or consequencess oes.

proposed amendment enects the three

g. W U opeest;on of the tat,ihty 6n new en 1 es a i t.

It standards W M M2 and, accordance with this propopd change create N pmibiltty of a new 07 differett kind of performed per the requirments of therefore, involves no significant enetdern from any occident previously 10CFMo 69 enserve that futm reloede will harards consideration, cwlueud?

noi involve e eignincent increan la e.e The NRC staff has made a prehminary Resoonse: No prohnbdity tn conseqeences of en encadent review of the licenace's no algnificant The ' proposed eevleton le adstnistrouve 6e preneush culueted he propond remiue to cJ.arge "Plu* to hetards consideration determination meta and om set effect prem61y

• Colf'io Techrucal Specification benas 3/

and agrees with the lice.naWe eastysis.

enslysed scesdents or cente any sew 4 21 is administrata e in nature and does nat.

Ancordmply, the Commienion preposes accidents. Thmfore, it es tumeluded thet therefore. Invoh e an Increase in h to determine that the eequested wereuon of the feedit so accordanu mth probabihty or ennsequentes of en errident amendment does not irtvoke a the poped chans oss not ersate the previoush euluoted.

significant hatards consideration.

puusitdhty of a near at chflarust Lied of 1 The proposed change dies not neste the sondcut possibihty of a mew or different kind of Locc/PuMic DocumentRoom

8. Wdi opm tion of t)w facihtyle locofion: Fairfield County Library, armrdeinco with the poposed c.baan eccalent trum so) ocuderd premualf Carden and Washington Streets, ineoln a equuhcoal reductos la e sarpn of As stated eerher, h remoul of the Winnsboro South Caroltna 21r180 sefet)?

requeed SIM curve has no incuence or Attorneyforlicensect Randolph R.

The wormed embos no an administratin impart, nor does it contritmte to any way to blahan. Sod Carollaa Ekctric & Cas champ only. it duse act 6mpact a cy marym of the probabihty or coneemienet=e of og Cotapa oy, P.O. Box 784. Colutabla, safety. hmfore,it is condaded that tecident. No esfety<eleted eqepnwnt. safety South Catoima 20:18 pp,,,,um of the facth:3 in accostlance wth functam, or plant opereuone wdl be altmd NRCfruMt Diretton Ehace C.

this propoord chany does not tenln a es a result of this proposed chany na Adensam s sniAmnt sodochon in a ssertita of safe ty.

cuts e e data wal canunue to be cakstated The NRC staff has teviewed the wns the NRC-approveJ nicthods Th, Southern Califoenia Ediaori Contpany, el analysis end.besed on that teriew,it Technical $pecmcahone wd conunue to al., Dodel No. 30 308. Sea Onofre appears that the three criteria are required operation mthin h required hmus.

Nuclear Generatics Statioen Unit No.1, satisfied. Therefore, the NRC staff and oppropriet, eetions will t.c toen when oriflimits are exceeded San Diego County, Califemh, proposes to determine that the The pmpoord intslan the thany *Plut.

Date of amendment request.\\ugust amendment request invohes no 1o *COiJr en lechnical Spectficetmn innow 22 1500 significant hazards consideration.

sis 21 is adminsetreun to nature. na chann simply delees a telerence to an Description of amendme '. request:

LocalPuNic Document Room obsolete repet (plul e nd references the Proposed Change No. r < *hich was hcohmMain Way, WmW of report w hich replaced it (COtR).

submitted by Amendment Applicalion Califernia, P.O. Box 19557.1rvine, f or these reuona, the proposed No.187, proposes to rev!se Technical Cohforrua 92713.

amendt.ent doce tet in any wy create the Speelfication Section 0.4, ' Training.* to A!Mmeyforlicensor jamea Deoletto.

reference the correct edition of the Enquite, Southern California Edison f

a any a o ee y

National Fire Protection Association Company, P.O. Box paa Rosemead, sielus ted.

(NTPA) standard concerning the fire CaMomiaF1 M 3 The proposed amendroent daes sat result brigade training program. The existing NRCPre/ccf Directon lames E. Dyer, in e :::nificant redacuan to the snars:n of Technical Spec 1Leations make reference Acting safety The margin of safety is not affected by i 'e to the 1976 edition of the NFPA removal of the requtred SIN curu from th-standard, but that standard has no 1970 Southm California Edjoon Company, et Technical Spacif4euens The mars a of ditj0"-

al., Dcdot No. 50 308. San Doofre safety presently prwided 1 current y;08/#/0fEf9M8#d88#I8UI[IC#l Neckar Generating Station, Unit No.1, 7

1e h tB h

cks b##0?$# ####'0*ICNO" E'IF"AU?500 San Diego County, Californla ne pro $osed amen $c'nIcst to As required by 10 CTR 50 D1(a) the Date of amendment request: August from the NRC-epproved reload design licenace has provided the following no 31.1990-req are operaten wittun the hmlie obtained significant hazards consideration Or*Cri fion of amendinentrequest methodalogaes and appropriote actions to be determination; f

taken when or if hmits are dotated remota Proposed Chat?Fe No.151. submitted by um. hanged-

1. Will operation of the facitty in Amendment Application No.188, accordance with thle proposed chenp proposes to reviae Technical l

Federal Register / V:1. 55, No.192 / Wcdn:sd:y, Oc: ber 3, stoGo / N:tices 404'71 i

__c_

hceble. with the SONCS 1 etectricil fpecification (TS) Section 3 3. " Safety with the cor.toinment sprey syste a es opbution optom.

lejtclion and Containtnent Spray equirements of esisting Spectft:.6 tion d.stri fjstems," Section 3 6 5. "Contomment 3 it.A.2 to form Speciftunon 3 3 3.

ne operebihty nquirements er,e being "Containtnent Spny Sptem

• Cateinment nylpd p follows:

Isola.. tion ins tru. mentation." onri Section sprey flow hmiting velvn OV.8tf and CV.613 he SONGS 1 design has redunder.t pump Spray System,cetion and Containment 4..,. Safety inj

,,, requimJ to te meintemed in the open trains connected to c.ummon flow toths. ouch The licensee ha' pos:t on for the injection phese and stuot be es two purnps connected to three common pro' posed this thenge to irrptove the operet,le so Ser can te cloud during the Cow peths The proposed change provides e sistiryg Tec.hnical $pecilketions by rectxuleuon f, hen; the provisions of es.istind seperate operebihty requirements fut the

c. eking the optcifications recte Specificeuon 311.D which would require pumpe and flow pathe.The use of separate ternplete, using the Westinghouse p.edna CV lif and CV.610 in the c.losed oprobihty requiremente will reduce the Siandard Tet.hnical Specificatione (STS) pos;uon to removed. RWST supply isive potentiel ror misellynment of componente for the fortnet and beels to the degree MOV.aa3 is included in the epecthcotton to sed therefore not increpe the potenuel of eque H is operable for contelnment sproT.

tousing en accident, or increest the lectical. Wre opt:t.ifleelly, the and the specificet.on requires both refuehPS consequentse of en accident.

llowing changre are beirg posed.

i for mpe te operable in Modn 1 ECCS components required to be operable t trouaf4.

In MODES 1 L and 3 above 800 pois are l

1. Entetmg Specifketton 31' efety trrection and Containment Spray Sptems'.

' E'I'U"E 8"

" U'" IM'

• " 'I

• • perated from those required for MODE 3 la replaced t new Specincetion 3 3.

C*lont S)eem hnsun leolet on \\, elves.

below eau pois and MODE 4.This wdl

'T.mertene) fore Cochng Systems (FCCS).

1 ya hout action statemente are provided

• es knumt* red Spectht.atton 3 3 6. Minot effectinly incrun the time afety inlettion rey;olons are made to move the MODt!

la required to te enilable over the f ar emergency tore coohng system (FCCS) nquirement into the APplJCAll!LfTY section requirements of the ettsty specificatione.

components se ellowed by STS requirements.

3 The eniettna requirernent of TS 3 31 C to ead to refer to the specthution in tre act6on and does not increpe the con.squerices of s'atement. e 11,ete section is added; and accidents requinna ICCS opereuon.

perfarm survettlance testing of redundant tunpatients et trains prior to entry into the Table 3 3 8514 revloed to use the new tes STS 72 hout action statements for s esociated act.on statement le deleted to n,mtem fw <he eusting ched isiv"-

redundant pump tratne er.d flow paths.

c inform m tth current STS requiremente.

10. Nm ipecification 3 3 7. " Component including the pnmary injection and

4. Spesthtetion 3 31 to revised to spectfy Coolms Neter System.* to edded to provtJe rectreulation flow pethe. are progided. The f CCS operabthty taquiremente end operabstty requirements for the component propnnd change eleo moves the e scociated action statemente for tvector cebig m eter eyetem.

requirements for the Contatnrnent Spiey and coolant system (RCSi pressu*e greater then 8L N"v Specificetton 3.3 8. "Statu of Component Cooling Water Splems from c equel to enn pelg The Itaoie Section le iCCS Cotaponents,"le added to provide g,,ction 3 31 to separate sections, and tesiore te vloed eccorrhngly, operabilley requiremen's for ECCS tehet.

T able 3.3.51 with naw volve numbers.

3. Specif"etion 312 and acrwnpanying 11 Brecificatior 3.3 8. " Containment The amendment provides for inctened I tese to added to spetafy ECCS operebthey 1.olatim Instrurientation."le ther' gad to pedabihty of cold leg eefety injeuton by t-piremente and eseoristed actiott e*1fy a 72 hout actwr1 sh tement inetcod of requinns one pump train, consistleg of one i

sniternente for RCS prenure ine then 810 e fLhout act6on staternent for the ocquencer che'ving putnp and enori.sted flow pathe, in pg.

autr.hanneta to enn'orm with the 7: bout t:rne MODE 3 (telow eno pais) and MODE 4. It

e. Ftisting Spec fiutmn 3.31" Shutdown b.th turren9y allowed foe the sequencer.

also requires the hot leg and cold leg I:stue." to r*tified Specification 3 3.3,

13. 3pecif.cetion 411. "Sately injection rect culation pathe to be opereb:e through l

• aoletion of hedweter/Sefety iniec9an and Conteinment Spre) Byeem Per6 odin MODE 4 no hot leg rectreulatian f *om Re>4ctor Cn,lant System " Operet,thty Testing."is changed to inchde add;tional requiremente inemorate the alternate hot les t qcarements e e clanfied to allow toolation reqetrements coceistent with STS T ath into the spe -

Hans Operabihty of of the esfevy inlection/feedweter pumps from rmlutrements and to correct ta.inot t' e RCS et om peig. e new acuon statement

t. IngrapLcel errore.

.these paths is not ma..enUy required by the T WlW Sp h u bMdc i

t to mcladed m hk.h will require e once per shifi Basis forpmposed no s!gnifg, anf req stwments have been added for the t enficetton of the rerneming positive bemer f crords considerofion deferrninatiom residual temoval heat eschenger teh es to s'iould one of the two barners not be As required by 10 CR So ln(e), the ensure they wiu tw operable. omce they are d et r purep ra tt rocked out i'. centre hoe provided the following no c urren0y not enuronmenteUy quehned for significant heterds conalderation sub.aergence.no propoecd spcification postuon is changed to proiide for opereuon delarmination:

eleo includes requiremente for the of the breaker in the trol position, and certain crou-teferences are corrected. A note le

1. Wiu opereHon of the facihty in rectreuleuon pump discheage n eh ee, w hich edJed to cler fy boron concent etson 8"cordence with this proposed change tre being modified diaring the current Cycle es qattemente for the ulety triection piping.

involve a eigmfacent increase in the 11 tefuehng outage. The new epectficatione 1 he note statn that the baron scocentre'ica r obebihty or connournces of any seddent for then systems do not increen the

h. the ufety injectic n pipba from the p eviously esaluatedt potentialconocquencn of an occ6 dent or i

t.fuehng meter storese tank to cold les Reeponse: No probabihty of en accident.The proposed t ;ection vehes MOV-650A. B and C does not The F.mergency Core Cooling Fyetem change providu additional ECCS s) stem have to be maintained when the esfc*y (ECCS) is designed to protect the core and to evallebib'y H compared to that required tr}ecNon piping to isoleied from the RCS far mitignie the radiological consequennes in the under the estehng specificat6one. and euures shutdown conditiont The Daois Section le worst design besw LOCA and MSLB. The the components er, operated in accordena revised accordingly.

LCCS also functions for less severe accident with the design basis.

7. Eueting Specification 313. Nmimum condihone The proposed change will The incorporetioti of Spenfication 3 3 8.

Doron Concentration in the Refoehng Water trtresee the optrabihty requirements for the

" Status of ECCS Componente.* will enhance b orese Tonk (RWST) and Sa'aty injection ICLS. and therefore wdl not increne the oefety by providmg requirements for FCCS (51) Lines end Minimum RWST Weter iotential consequenen or probabihty of en train operebihty and specific component

\\ alume." 1e renumbered se Specification 3 3 4 accident requiremente. This wiu therefore. not with the ume title. Minor thenges to cron.

The p oposed change revises Technical increase the potendel adverse consequences r*ferences heve been made, anu e fipecification Section 3.3 by organising the of. or probabi'ity of en accident The clarificehon regardmg boron concentration in eaction by ECCS sutveyetems and defining proposed change wiu etedy to the operating

$1 lines duttna shutdown candiuono to added trein elignment and MODE operobihty personnel th aquiremente of the Technical es discuped in the previous sectior6 tequiremments within each subeection. Nr Specificadons for the ECCS and provide the

& Etteting Specificauun 33 4, Wmimum action statemente and secuon UH. are in meene to effecthely determine the required bolution Volume llydraatne Concentration in o zordance with the STTk The revised statue of the FCCS componente to esaure the the H)dretme Tank.* bee been combineJ epecincetuses en beeed on trotn.elignment.

systeme are operable.

es e

48478 Fedevel Resister / Vol H, E.182 / W:dneeder. October 3, tsoo / Nohoes

/

i N potenhet fare snees addstxe tresseerst requiremerde a the imeof modes af he proposes change artil sesee lecties is decrened by peenitting tooleteos of the ogereLion, I

feedeeter pusve hawn the seiers tapusma New ourweUsees sesidsomeele thees been the Weetarghause 6teNderd IedelCaI 8 3. the FCCS hodfaatamme. tame 4 stent enth systern et en RCS prenure af au0 geg truarpweled frein the STS to poetasse e SpecMcabane (STS) The p't' posed charge allowsag entweerd tune to setde te the e prout to reukag the Wpug futut of )staan sentattuneet (nepectana, and eestem 513 wtt) incorpore te current S7S pulJance lato volve status hoes seesspuessato one es bpecalu.etgari 3.31 Overpresounsataon ole e impemesaset eser to eatstnog epeedeneek the Techtdcal Spectflutione tsy providAng a tulo peng u aat a canorts eau at en oak! be no osatamment tuspecten w&U toewe the 72.hout eetion etatement awpeteled with an hmtted by the shul off head of the feeds e ter inoperoble telety inteetion trein end purers to about I14 pe$ pusuture h euctson toth of the eecicosistene passays la feedm eter puesp breeters to be in the tiel

c. lear of dabru N ECGS our,314ence ortu removing the setnoe etetement regetroenent to help soeure the IJ C6 le maintetoed opereWe. test r,dundest traine w6uch bee c.eused poubon 61d1 auures the pusnpa cannot Survemance of maleen hated teesde the unnecessary entry ento $pectfacetion &JD.3.

opetete. and does not adversch e!!ect any containament bee not been tecJuded esame De potential for new socidrots has not teen sefet) related equlpment nerefore these thenges will nouncreen the potentiel ercene to these arose le restrtsted, med also lo increceed and r umler af plant transiente hielt empmem of operetaone pmusinet ne much would ben any potectal to couer an conseguenen or. increase the probeWt) of new sun etikereres wiD med increpe the scudente joic) te not inutesed l'y stue en occident.

ne &serepanry in esistirs Speuticelion potentaal conequences of any acetdent and tha"Fe-8.3 LD stith requerd Leolation of the do not tricreese the probabthty of as The opereb!bty requiremente for the safety econdent injechon optem w60 require one trato of unld contamment sprey eyetent with a lauarporetaan of eegetate sectause Anto the jeg g,ee.on, vie the cheryng eyeteer to be recheatstion purnp out of service het teve terrowd. AddihoneUy.oped!d requiremente proposed specdicatsam lar the component operable 6a MODE 4. coneasteet with h STS.

he ve been incorynrettid to nem the coussag eyelese and euritelnaant spray ud W tk eng Wrwou for eletea.s le coesistent with the S7E ne ILG operahus to WMES 1 through 3 71ue contamment oprey flow hmmg velves are ineintemed in the correct positions Dese provleions of the amtg spec.ifacettune haie dup M w mm ik potuW lor been snelateined in the new eechare and any new er ddtmot accident, etene u two cher su have a sign & cent impact in augmented with more deleued roquirements.

ensures the operabihty of eueting eyoterne.

improvmg ufety by enunna the centsinment ne component cooling watet system SMicatson 818 requarne leoisteos of alw sprey s) stem h oper*Me nerefore thne spedliceuon includes the emov mo&facetsen gg, ggg P""g g,, g changes do not tacreen the potential beira installed in the Cyc.le 11 refuehns (onsequences of en occident er probabnity outage and the thanment of component 7{' [,P,',

j' of en acetdent cochne e eter pump G 15C with Trein IL Tbc pois and @ed We machtg M pois.

1 Curwnt adminletrottw centroh require new action sie traient to allow the removal TM addnne W e W pai sneman fw todete j

entry into Ste'etf cation 8 0.3 whenever from operetaos of one coinponent coohng of tb aaMy $ctuan and feedwatet pump i

contatnment oprey flow hmiting sahn CV.

water heat eschenper for an esteAled penod mul reduce the potential for a mesa addition 817 and C%516 are fotmd to be inoperable or is band on the prehminar) results of a transient to low temperstm cundatioria i heres et one comporwat on the hot leg ce probabthstac hk Aueenment (pRA) W which usey escoed the capabihty of the cold leg reactreute tion path is laund to be prehmanary pRA tuttnined the lose of Osupreum Wuon 6 tem and.

imtereble In this emt tk shvidtrwa proceso enuet commerme within one tour W componest cochta weter scenaric.s and consegmtly, b Appen&s G hmus fw h addition of the n hour action otetements of concludtd that the r sk of core damese wee reactw nuel. T1ue change don not increen the Imi wt!! reduce the twed to enter not sigrufuntly increwed by the new h pownuel fa e new occident enice H wm

$pecthcetion 3 0.8.

specifatwr5 We m to the process of escure the isoletion le omopleted prior to performing e deteued PRA to support these toeching h wetrictsn hmits of the heetupf The inmrpershon of the M hout action prehminary senclusions.11esed on b cooldown eweve, statement le wtthin the Fuutehnee of the STS preliminary resulta these e;wchehons will Consistent with the corrective actions and don not contnbute substantiallg to not increen the potential consequences of en pwded in la sea:4? Unit 1 CV417 and unsuilabthly of the IXX7 De proposed change removes the need to enter esent, or b probabiht) of en occadent CV418 Fellore Mode on Laos of instrument The increase in b ocuon otetement tim, Speufcouon 8 (La by prouding action bmit for the contelament toolstion from the Att? the proposed change will require talves stateeiests for ei etenne with redundant troisse safety inketon sequencer soluAennel doe, CV417 and CV418 to remain open for to anow cantmued plant operaten for up to 901 &oeble h containment tooletion containment oprey by requirms the vah es to W operable and capable of tving closed

?2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> T1ue to consistent with the function %e r.hanye rwnova e discrepancy duttna the 'ectreuladon phen. Action cosumption of sogle failure relautma la the within the esistmg specthcottone, $ince the statemente have been provided to assure the corre optmdang action staternents of the STS, coutelnment hlation signal will still be ulves are malateined in accordance with h and is constsient with neumpUone of the operable directh fro:e the contstament specification. A cJerification of the train ertuletit analyses in CAaptet 15 of the UF5AR.

trenomittero, and the okt sequencar cAannel shgnment of components of the Recirculation Use of the M hour actmo etelement e 111 will be opereble, h charp only ceduces a Sutem and eyetem operabihty le provided in signifkandy reduce the einmber of potentaal portion of dnersity of the in? winun e omgle plant transiente required i.ndet the one hour tram. The opersuon of h conainment W Bools for Section 3.31 % change escures the containment sprey e) stem to action etetement of Specifacetion 3a3. The isolation function is not signifuoly operable u required and doce not create reduction in plant trenewate will not increue impacted by this change. and thereia et the letenhelIor an occadent, or adverse does not tocrues the protietahty of an potential for an new ine of accident The estension of k action etetesient tune occident ce the potential consegeences of an hmit far one component cochng heat consequences ne incorpuretion of h n socadent boar eetion otstement wJ1 benefit overall sifetb The prtwud chage den not degrade any eschenger has bei n reviewed to deterraine if ne STS one hour action ots temen te for phpical barners wtach could altet h there is a signhaat increase to the etsk of low male operet ons be6e alor twee consequences analysed in the UFSAR, and core damage durias this tune. Preliminary Incorporated in the proposed thsnge. In &

therefore the propoud change does not results of the PRA andicete the effect on the lower austn. MDDE 3 et en RCS pressare trnolve a significant incrtow in the nok due to e potentiallon of component hos than 800 peqt. the conuquesce d en probabihty at conaequences of any accident conhng has been found te be oms;1, and does previously eu!W A.

not significantly increase the potentialla en etudent are lese ervere. The acamn statement allowe to hours to toeth MODE &

1 Will opereuon of h fecihty in accident initated tg o.ther low of b This tune hmit to screpted due to the reduced accordence with this pmposed change crtete ournponent conhng weter system the possibihty of a new or different Lind of he propaeed change increues the effects of an occklent from thcoe condations, accident from ariy accident prmously operabthey requiresnente for the ECCS and a d the etable reactkiry condition of k core evaluated?

gis os detailed guidance on the operetate of and reduced decay heei retnoiel Response: No r, quired cornponente. neoe changes improve the operation and usure b endebibty W 1

i I

Feder:I Regleter / Vel. St. NA 192 / Wcdneadry Octolcr 3.1990 / N;tices 4K'9 i

the BQN ne incmee in FCCS operebihty not signibndy reduce the amesin of estety.

eIlluents solid.redioactive wastes.

due mot eller care pareewters. or degrade since it only effects one trem. and the environmental monitoring. and f.uion product bemere in any mennet whkei redundant train wiu rema6a fully operational associated reporting requirements are would ruelt in a new, or ananalysed ne change will permit tricreued operationel concurrently being deleted. De mdHior6 flesibilit.in etwrdance with the provisions 1 Will operetion of the facility in of Spect ce16on 3.y. and reduce the potential procedural details which are to be e cordar ce with thle proposed change for plant tronalents which could result treen deleted are being incorporeled into the involve a etsruncont reduction in a energin of implementsag a plant shutdown undet the Offsite Dose Calculation Manual selet)?

cumat eis bour ocuon statesnent.

(ODCM) or Process Control Program Response No ne proposed Technical Specincetione for (PCP) as appropriate.The Technical ne ufety analysie for design hem operation of the ECCS are in accordance with Specification definitions of the ODCM eccidente bas cosoledad that the ECCS wiD the provleanne of the SW end the safety -

and PCP are also revised to reflect these provide nflecnol onre coohng (for IDCA).

anelple contained in the UF5AR bection 18.

changes. Die amendment request is and boron injection [for MSLD). to remata ne propt>wd change soeures the ECCS will kin 8 pmPosed as an impronment to within acceptable timite with an usumed be thgned and emersted es required by the worot case single active felture.ne proposed ufety entlysee.no proposed terw6en does the esistmg Technical $pecifications se change will metntain the ECCS componente not alter the ruults of the current selety recomrnended by Generic Letter 89 01 and power suppitu in en altenment analpis. or decrease the effecrieenses of the and consistent with the Cornmission's coneletent with h current enelyste Technu.a! 6pecdacet6one in ammtaining the Policy Statement for Technical cesemptions and provide for o;ieretional analyste lun to and anus phora. auch as the Specifications impros ements.

flesitahty within the analysia. The overall peak cladding tes2perature. DNBR. or the Bosis forproposedno significonf impact wdl not be e sodaction to the mersam peak contattunent prepure herefore, the hosotds consideration determinotion of safety sad to an inaprovement jegj the proposed change will not tavolve a The Commlaalon has Erovided esitting specalicatione.

eignificent reduction in a margin of eefety.

standards for determining whether a As en esemple, the propneed thenge will The NRC staff has reviewed the require contelnment sprey fiow hmiting analysis and, based on that review, it significant hasarde consideration exista as stated in 10 CPR 50.92(c). A proposed velvo CV 6tr end CV ste to remenn open la' appears that the three criteria are amendrnent to att opereting license for a proper contelament oprey system flow to tahd. nmfore, he NRC staff facility involves no significant hatards coeurs containment peak pressure remains within the oefety analysis. The volves aleo proposes to determine tgat ge consideration if operation of the facility wal be required to tw operable such that they amendment request myolves n in accordance with the proposed con be cloud for recirculottoa. This will not significant hasards consideration.

amendment would not:(1) involve a deoroase the marsin of niety. and pom Loca/ Pubhc Document floom both the conteinment oprey tiow and locotiott Main Library. Liniversity of significant increase in the probability or recirculation flows will te within dulen Cahfornia. P.O. Box 19557, Irvine, consequences of an accident previously evaluated, or (2) create the possibility of margine.

Cahfornia 92?11 e new or different kind of accident from A cienficat6on regarding the recirculation Attorneyforlicensee james Broletto.

system le geovided as e emit of runt Esquire. Southem California Edi.on any accident previously evaluated, or (3) comnutmeate to operede the het les recirculottoe erstem. In eddihos. the Company. P.O. Box ano Roserne ad.

involve a significant reduction in a propoud chanse enti provide trein California F1770.

margin of safety. De licensee provided defuunone MODE operebilay requiremente

. NRC Pm/cci Director: James !L Dyer, an ans1yeia that aMtweed tW abave three standards in the amendment and the usociated action statemente Acting consistent with h 5% It also m til decrease application. ne licensee's findings ere Wolf Creek Nisclear Operating as follows:

the potential for e mus addit on trenaient en the ItCS by mbling the timely teoletion of Corporation. Decket No. 36 482. Wolf Stonderd J.laro/ves o Significant the feedweter/sefety 6ntect6cn pumpe woe, Creek Generating Station.CoffeF

/ncreose in the Prvbobil,ty or cherome will not demese the margin of Cosamty, Kaasas Consequences of on Accident ufery ard wiu asem the ECCS compooeone Date of omemfment request August Previously Evolvoted.

cre eve 61eble to leicl es soeumed in the ufetF nm m proposed thenee ehere only the of detail and change provideo relief feten Description of amendment request.

fogt and lace the prov.sions of the current Specif6cetaan The hcense amendment request radioactin effluente, eotid tedsoective weste, requiries 3DJ entry. and subuquest plant proposes to implement Technical and redrotecal environnwntal morutorms.

ohutdown. De current Specificataune wm Specification changw as described la ne dinge as adambtrouve 6a ute and generally wntten pnor to the toeuence of the NRC Ceneric Latter BNF1.

dou not involve any change to the

% eennshouse tris and do not conteln action

" Implementation of Pmgrammatic cont,,,, tion se operation of plant statements for many of the Eccs required Controls for Radiological Effluent eqaipment. There ~re. this proposed change components, la most instances the proposed Technical Specifications in the does not increase the probabilay or

,'h Administrative Controle Section of the consequences on any previously evaluated eterdard octaan sistements wiu reduce the Technical Specificationa and the acet ent.

Relocation of Procedural Details of Standard 2. Create the Possibility of nud to enter 3 0A and the correspor. dirts potential for shutdown tiensients nie wilt RET 11 to the Offsite Does Calculation a New or Differenf Kindof Accident j

not dectense the mergin of ufety and will Manual or the Procoes Control from any Previously Evoluoted.

I reduce the number of potential shutdown Program?'in accordance with the Stnw this proposed change does not j

tre nswate.

guidance of Genorte letter gNFt. the imin any change m me conngurobon m tumed W gmuan of any plant equipment ne change la the scelan statement tirse proposed change adde new it d u a t arente the penihdary of a new or bmit lur me contamanet 6mlehen funces d eming programmette requtremente[ologloaldifferent ktad trose those proteously the segmencer a:shcheemole fisme e boers to ya radioactig elBumte and re evaluated.

hours. corresponde to the time limit approved enetrummtal monHwing to the StandardJ.lavolve A Significant for the sequencer in Amendment No. M.

Opershoe without the subdianaal a5ects the Ahtlw Controle esction of the Reduction in the Aforg/n of Sofety.

j diveretty of one the portion of the Teeltetise19peelnestions. Eristing This proposed change relocated procedural containment teolation train, and does not Technisel SpectBoettons containtng detail from the TechnicalSpectfleetione to dieeble the eGeceed trein.De dones does precedural dotate en eedlooctin the OOCM or pCP. However. new 4

l a

40480 Federal Regialer / V:1, as, No.192 / Wednesday. Oct:ber 3,1990 / N:tices wimir.istrative controls are edded to the Gulf States Utilities Cesapany, Thurant Cornmission's rules and reFulations in 10 Ter.hnical Specafications which usure the No. 364ss, River Seed $satiss, thdt 1 CTR Chapter 1, which are set Ivrth in the proper control and memtenance of these West Feliciana Partak, h=da'a==

license amendment.

Cocumente and prendes an equitslent level of assurance that activsties involving Dok c>fopplicolionfor amendweed.

Notice of Consideration of issuance of st 22,1M Amendment to Facility Operating A[c/ description ofomendment Ocense and Proposed No Significant radioactne ef!)uen's sohd radioactne weste, and radiological environmental monitoririg Hazards Consideration Determination are conducted in full comphence with 0"'*

e i

S e ation 3/

and Opportunity for Hearing in 3d., Ultimate Hest Sink." to inaresse rega! story requirements nerefore, there le connect on with these actions was no reduction in the me gic of estety.

g eh allowable ulumsk heat sg published in the Federal Register as The p uposed chante docs not invohe any ectual cher.ge in the methodology used Ari the temperature from 82* F to as* F,Tbe indicated. No request for a hearing or roposed change wotild allow the b leave to inten ene was filed fscensee to use the ultimate heat alnk to

{g g

control of radioactive effluents, eohd r:dioactive weite or radiological environmental 6 onttontig This chang, cool plant equipment w hen it is g

provides for the rslocatmn of prmdural necMsary to remon the normal senice Comminion has determined that these detail ov'elde of the Technical Specifications water system from senice for required amendmerits satisfy the criteria for but adds arp opriate ednanistratae cor.trole maintenance and when norrnal service ca tegorical exclusion in accordance wate with to CFR 61.22 Derefore, pursuant of 95,r tempereture nears its design limit

'R WW$ p m hd to proude continued esestance of comphence to appbcable regulatory F and adequate temperature requirements This proposed thenge e.omphes differentials are unobtainable.

P g

with the ymdence provided ty NRC m Dele ofindividuolnotice in Fmletal assessment riced >e prepare (c,r ese Genenc tener anci.

Register: August 31, two(55 FR 35743) amendments.If the Commission has The staff has reviewed the licensee's E*piration dote ofindividuol notice, prepared an environmental assessment no significant harards considerations October 1.1Ensa under the special circumstances determination. Based on the review and Loco /Mlic Docu,nent Room

• ovision in to CFR 5112(b) and has the above discussions. the staff lxotion: Government Documents g

ind td en o ana S Uninr Hy,

"{o'r I proposes to determine that the proposed c{a h r det is wi respect to the changes do not involve a significant "8

oction see (1) the applications for hazards consideretion.

Southem Califomia Edison Company, et amendments. (2) the amendments, and loco / Public Document Room sl., DocLet No. 80 206, San Onofra p) the Comminion's related lettcra, l.ocation Empona State Unise.sity, Nur.laar Generating Station, Unit No.1, Safety Evaluations and/or Wdham Allen Whi'e 1.ibrary,1200 San Diego Count), Cahfomia Environmental Anessments as Commercial Street, Empona, Kansaa Date of amendment request luly 3.

indicated. All of these items are OM01 and Washburn timversity School 1M. as supplemented August 22.1W0.

available for public inspection at the of Law Library. Topeka Kansas twe:1 Frief description of amendment:

Comrcission's Public Document Room.

Atierney forlicensee: Jay Silberg, Amendment Application No.185 the Gelman Dullding. 21:01. Street.

Eaq., Shaw, Pittman Potts and proposes to change Technical N.W. Weshington, D C., and at the local

'Irowbnd e, 300 N Street, N. W..

Specification 3 4.3. "Austhary public dxument rooms for the t

Wa shington, D. C. 20037 Feedwater System." to allow the particular facilities involved. A copy of NRCPrv/ect Director Christopher 1.

minimum system flow requirement to be items (2) and (3) may be obtained upon Gnmes reduced from 1 5 gpm to W gpm.

request addressed to the U S. Nuclear P'AE\\ IOUSLY PUBLWlED NOTICES Date ofpublication ofindiriduolnotice Regulatory Commission, Washington, OF CONSIDERATION OF ISSUANCE in Faderal Register' September 10,1990 DC.T555, Attention: Director. Dnision D5 FR 37273).

of Reactor Projecta.

II S Rf O

m riod e pires to e 1 o

g7 C et C i CONSIDER ATION DITERMINATION Loco / Public Document Room

[#'

Ol nj AND OPPORTUNITY FOR llEARING location: hiain Library, University of The following notices were previously Califomia P.O. Bos 19557. Irvine, Date of opplicction for ornendmeate published as separate individual Cohfornia 92713.

August 13,1990 notices. The notice content was the NOTICE Or tSSUANCE Or ame ifmen*

sa ne as above.They were published as AMENDMENT TO FACILITY d es t

n0 individual notices either because time OPFRATING LICENSE effective full power year (EFPY) heatup did not allow the Commission to w att and cooldown curves and rates based Durin the period since publication of on the Fuidance provided in Regulatory the last kiweekly notice, the for this biweekly notice or because the Guide 1.99. Revision 2. In addition, cetion involved exigent cirtumstances.

They are repeated here because the Commission has issued the following adjustments were made to the low biweekly notice hsts all amendments amendments. The Commission has tempersture overpressure protection determined for each of these (LTOP) miti ating system including lesued or proposed to be issued 6

amendments that the application changes to the power operated relief involving no significant hatstds complies with the standards and valves (PORVs) lift setpoint and the consideration.

requirements of the Atomic Energy Act reactor coolant pump (RCP) start For details. see the individual r.otice of1954, as amended (the Act), and the controls, The supportirs 13 Bases were 1~

in the Federal Register on the day and Commission's rules and regulations. The also modified to be consistent with the page cited. This notice does not estend Comm!ssion has made appropriate above TS changes.

the notice period of the original notice.

findmgs as required by the Act and the Date ofissuonce: September 18,1990

\\

L l

i radotal Regleter / W1. 55. No.192 / Wednesday October 3,1990 / Notices 40481 1

Effectise doser Septemter 18.1te0 diser pancy between the TS and the Brief descrQtion of amendment:The AmendtnentNo.: 1a6 UTSAR by using the more conservat.ve.

amendment wdl prdvide en esception to facihty Operating L! cense No. DPR-UPSAR salue Also, to clanfy the specification 4.0.4 for entry into Mode 3 b3. Amendment revised the Technical requirements for the autornatic for surveillance requirement 4.7.1.12.

Specifications.

bypsting of the diesel generator trips

" Auxiliary Faedwater System Date ofinitiolnotice in Federal on an ECCS actuation signal for Operability." This W change will allow Regieten Augut17.1930(55 PR 33790)

Division 3 the licensee !s p*opoolna to the plant to prcr ess to Mode 3 without The Commission's related evalue tion reword the requirernent so that it is first demonstratin4 outillary feednetet of the amendment is contained in a consistent with the LaSalle Station operability.

Safety Evaluation dated September 13.

design and the Branch Techrucal Date o/hsuance: September 19.1990 1990.

Position BTP ICSB-17 and Positloo 7 of Effectire date: September 19,1WO 1,'o significant hotords considention the Regulatory Culde 19.

Amendment No.: 151 comments received No Date ofissuance: Septembet 13.1990 Focihty Operotwg License No. DVR.

Lxcl/thhc DocumentIbom E'fective date: Septernber 13.1990

61. Amendment remed the Technkel locetforr Calvert County Ubrary. Prince Amer'dment Nos.:75 and 59

$,g.dicauons' P

Freder1ck. Maryland.

Faciliry Opemting License Nos NPY-Carchna Power & Ught Company et al.,

11 and NPF.18: The amendments revised Public commente requested as to gg proposed no el. ificant hasards tb er3 f. g[

"*M.rd considerettom es ($$ FR 32715 dcted Dodat Nos. 50-328 mi 30 324.

Brunswick Stasm Electric Plant. Unita 1 p,

/*

ice n tad 1. Brunomick County, North Peg: sten junt 27.1990(55 PR 26279)%e August 10.1990). The notice provided an Cadna Commission's related evaluation of the opportunHy to subnut comnients on the amendments is contalned in a Safety Commission a proposed no sigmf4 cant Date of opphrotionfor cmendments Evaluation dated September 13.1990 herards consideration determination.

Marth 14.1990, as supplemented Augu st No sism/mor,t Actords considemt/or, No comments heve been receh ed. The 9 and 29.1990.

commente received: No notice also provided for an opPortumty Bnef Descir; tion of otr.cndment it h Local Pubhc Document Room to requeet a hearing by Septemtwr 10.

amendments change the B to (1) permit locotion: Public Ubrary of Illinole Valley 1990, but indicated that if the the removal of the rod sequence c mtrol Community College. Rurst Route No.1, Commission makes a final no significant 1

system and (2) reduce the rod worth Oglesby. !!!mois 61M6 hazards consideration determination minimiser cut off setpoint fr"a 2M NRCProject Director: Richard J.

any such hearing would take place after rated thermal power te M rated Barrett issuance of the amendment.N thermal power.

Commission's telated evaluattan of the Dcte ofissuance: September 11.1990 Commomm ealth Edson Comeweb amendment and fmal no significant Effective date: September 11.19t 0 Dociet Nos. 80 2H and 84265 Quad hasards consideration determination le Amendment Nos. 144 and 175 Cities Nuclear Power Station. Unite 1 contained in a Safety Evaluation dated facility Opemting License Nos. DPR.

and 2, Rock Island County,Illinoi*

September 19,1990.

71 and DYR-82. Amendmente tesise the Date ofcpplicationfor amendments:

LocalPublic Document Room Technical Spectfncetiona.

July to.1990 location: Russell Ubrary,123 Broad Date of motfalnotice w Federal Brief description of amendments:

Street, Middletown. Connecticut oms?.

Registan April 18.1990 (55 Dt 14501)

Reviolon of Technical Specifications to Detroit Edison Com Docket No. 30 The August 9,1EWO and August 29,1990, reflect a High pressure Coolant Inlection 841. Fermi.2, Monroe bty, Mit.higan letters provided supplernented (llPCI) area fire protection modification information that did not alter the staffe which replaces epot. type heat detectore Date of applicotton for amendment initial determination of no sigdcant with a linent heat detector.

November 15.1988 as supplemented heterda consideration.%e Date ofissuonce: September 13.1980 November 16.1989.

Conutission's relsted evaluation of the Effectire date: September 13.1990 Brief description of amendment:%Is amendments is contalned in a Safety Amendment Nos. 136 and 122 amendment revises u list of required Evaluatien dated September 11.19po.

Focihty Operating ucense Nos. DPR.

accident monitoring instrumentations to No stdnificant hazards consideratios 29 and DPR 30.h amendmente revised ehminate confusion with the Technical comments received. No.

the Technical Specifications.

Specifications (M) and better reflect the Locollbblic Document Room Date ofirutio/ notice in Federal as built conditions of the plant.

location Urdversity of North Carolina at Register: August 6.1990 (55 nt 32324)

Dole ofissuonce: September 10,1990 Wilmington. William Madison Randall The Commission's related evaluation of Effect/ve dote: September 10.1990 Ubrary,001 S. Collrge Road.

the amendmente le contained in a Safety Amendment No.:56 Wilmington. North Carohna 26403 3277 Evaluation da ted September 13.1990.

Comanoed The Compem No sigm/ scant bomids considemtm 7,

th Ucnae & NPF.

Docket Nos. 3D.373 and 16374. LaSalle comments recaheHo

43. N amendment revises the Technical Specifications.

County Station Unita 1 and 2 LaSalle j,f,

'y Date ofinitiolnotice in Federal

'"*D'

,y ggg Hennepia Avenua. Dixon. !!hnoia 61021.

Register. May 17,1999 (M FR 21306) N Date of opplicolionfar onwndmenia:

NRC Prweet Director-Richard J.

November la,1989 eubmittal provided May 16.1990 Barrett additional clarifying information and did Briefdesceptionofamendments b not change the initial no sigmficant f

~16eut Yankee Atonde Power hasards consideration datermination.

proposed anundment to Operstmg Ucense No. NPF.11 and Operating Company, Dodet No. 30413. Haddam The Commission's related evaluation of

/

Ucense No. NPF.14 mould tevise the Ned Mant, Middlesex County.

the amendment la contained in a Safety P

LaSalle County Station. Unita 1 and 2, i

. Evaluation dated September 10,1990.

Technical Specifica tions (TS) to revias Duse aif wf=s=for amendment-No significar,t hoacide consideration the " single largaat load isject" test value July 28,1990 comments receited No.

3 l

40482 Federal Regnaler / Vel, 55, No.192 / Wednesday, Oct:ber 3,19uo / N:tices LocalPublic Document Room Duhe Pewet Compsey Deshet Nos. no.

LocalP blit%cument Room locolion: Monroe County Ubrary Ste and 8634, McGuire Nualeer location TorrJmson Ubrary, Arkansas 5 stem,3?00 South Custer Road.

Station, Unlia 1 and 1, M '_,

Tech University Russellville, Arkantas 3

Monroe, Michigan 44161.

County, North Caroline 72M1 Detroit Edison Company, Dociet No. 80-l Dole of off icction for amendnents-Mor6de Power and Ught Company, 341, Formi 2, Monroe County, Micalgan July 13,1NO Docket No. 30 385, St. Imcie Plant Ucit Bri description of amendments ne No.1, St.1 male County, Moe6de Dole of opplication for amendment:

amen mente delete a portion of the September 27,1909 surveillance requirements of TS 4.5.2.d Date of whcotion for amendment.

March 9. N Brief description of omendment: This regarding periodic venfication that the amendment revises the Technical suction isolation valves of the Residual Bri descriphon c/omendment We Specifications (TS) b) addma a remote-Heat Removal (ND) System amen ment revises Technical manual pnmary contairment isolabon automatically close or a Reactor Specificauons 2.2.1, Reactor Trip valve, e6socisted with the installation of Coolant S) stem signalless than or equal Setpoints, and 3/4.3.2. Eng!neered Safety enhanced pnmar) containment ws!Pr to M0 psig These amendments,in effect, Feature Actusuon S stem level instrumentauon. to the valves authonse removalof the ND instrumentation.Th changes lower the listed in TS Table 3.651, Prtmary Autoclosure interlock (ACl) circuitry.

React Protection System generator Contamment isolat on Valves.

Date ofissuance: Septernber 11,1990 level.1 w trip setpoint from greater than Date ofiss,nnre September 1J, two Effectie r date: September 11,1990 qubo D

Effectin e dote: September 13.1WO Amendment Nos.:1:2 end 94 an o 5 narrow Amendment No.: fu Focihty Operatin License hos. N1,0 9 range.The Autlhary Feedwster System setpoint for the steam Tm shty Opemfirs License No. NPF-

"r h Ihp IIcations gennator lenblow trip is lowered from 41 The cerendment rnises the T echnical Specthcations.

Date ofimlio/notiWn Federal its current value of greater than or equal p

g, gg pg to 26 0% narrow range to g cater than or Date ofinitio/ notice in Federal Kegister February 15,1990 (55 FR 5523)

The Commission's related es aluation of equal to 194% nanow range. He The Comminston's retated evaluation of the amendments is contained in a Safety changes also reduce the Auxiliary the ame*idment is contained in a Safety Evaluation dated September 11,1990 Feedwater 5) stem response time on low Evaluation dated September 13.19W1 No significent hosonfs consideretion ateam genuator level. Additionally, the comments received. No.

changes revise the allowable values for No sigmficant borords consideration LocalPublic Document Room steam generator and feedwatet header comments received: No.

locofion: Atkins Ubrary, University of high dillerential pressure for austbary Loco /Pubhc Document Room North Carolina, Charlotte (UNCC feedweter initiation.

lication: Monroe County Ubra '

Station), North Carolina 282.23 Date ofIssuance September 11,1990 System. 3700 South Custer Ron,

Effective Dore: September 11,1990 Monroe, Michigan 48101.

Entorg) Operations, Inc., Docket No. 80 Amendment No.: 106 Duk e Power Company, Docket Nos. 30 813, Arkansas NucJear One, Unit 1. Pope Facility Operotmg License No. DpR.

County, Arkansas 309 and 50 379, McCulte Nuclear 6h Amendment rnised the Technical 6tation, Units 1 and 2, Meclienburg Dcte of omendment requeste August 9, Specifications.

County, North Carolina 1989 as supplemented on March 30 and Date ofinitiolnotice m Federal June 15,1990.

Register; Apnl 4,1990 (55 FR 12592 The Date of applicction for amendments:

Brief description of calendment: ne Commission's related evaluation o the Aptd 24,19J0 amendment added limiting conditions amendment is contained in a Safety Brie description of omendments:The for operation and reporting requirements Evaluation dated September 11.1m a nen ments relocate tabular listings of to the Arkansas Nuclear One, Unit 1 No significant hosords consideration

)

containment penetration conductor Technical Specifications ( ANO.1 TS) cornments received: No.

i entcunent protective devices from the regarding Seismic Monitoring LocoIPublic Document Room

'l Se to Chapter to of the Final Safety Instrumentation and changed the exiting lxotion: Indian River lunfor College Analysis R(port," Selected ucensee sun elllance testing requirements for Ubrary,3209 Virgina Avenue. ft. Pierce, Commitment Manual."

clarity and to achieve consistency with Florida.

Date ofissuance: Ss ptember 18.1990 the ANO 213.

Effective dote: September 18.1990 Date ofissuance: September 13,1990 Geo gle Power Company, Oglethorpe t

Power Corporation Municipal Electric ff,fe1) ehmbu 13.1990 Authority of Georgia, City of Dalton, Amendment Nos.:114 and 90 facility Opervti License Nos. NPF.9 0***'lectric Gener'ating Plant, Units 1 U*'k *' N * * **'*** * *0 *****

• and NPF.th Amen ments revised the Facility Operating Ucense No. DPR.

V o le E Technical Specifications.

51. Amendment revised the Technical Date ofinitialnotice in iederal Specifications / license.

an 2. Bude CouMy, C@

Register: May to.1990 (55 FR 20353) The Date ofinitialnotice in Federal Date of applicationfor omendments:

Resteter: November 1,1989 (54 m 4e139) Marc.h 1,1990 Commission's related evaluation of the The March 30 and June 15,1990 Bri description of amendments:The amendments is contained in a Safety supplements provided clarifying amen ments revise administrative Evaluation dated September 18, th0.

trdormation and did not change the Technical Specification 6.7.4.a by No significant hosords considerotion proposed finding of the original notice, removing the parenthetical reference to comments received: No.

The Commiselon's related evaluation of the Baron Recycle System from the LocolPublic Document Room the amendment is contained in a Safety description of systems included in a location: Atkins Ubrary, Univerelty of Evaluation dated September 13,1990.

program of leakage inspection and North Carohna. Charlotte (UNCC No significant hosords consideration testmg.

Station), North Carolina 28223 comments received: No.

Date ofissuonce: September 18,1990

1 Federal Register / Vtl. 65, N,192 / Wedn:sday Octzber' 3,1990 / N: tic;s 40443 Effertire dole:Se Amendment hos.:ptember 18,1990 SSW e stem, the removal of the SSW Memorial Library,500 Market Street, St.

35a 15 pump m senice would require Joseph. Michigan 49085.

)

. Focility Opetolins ucense Nos. NPF.

declaring the inverters inoperable which O and NPF 81: Amendments revised the would require tant shutdown be lowa Electric Ught and Power Company.

Docket No. 50 331 Duane Arnold Technical Speciflestions.

initiated in 24 ours.

Date ofinitialnotice in Federal Date ofissuance: September 17,1990 E**'EY' C*'* Lina Cou"'Y' i***

Regleter. April 18.1990 ($$ FR 14506)

Effective date: September 17,1990 Date of applicationfor omendment The Commission's related evaluation of Amendment Nat 45 July 27,1988, as revised June 29,1990 the amendments is contained in a Safety facility Openting ucense No. NPF.

Bri description of amendment:The Evaluation dated September 18.1990. No

82. The amendment revised the amen ment revised the Technical significant hatards consideration Technical Specifications. Public Specifications to conform with the 1

comments received: No, comments requested as to proposed no guidance of NRC Generic Letter 8841.

LocoIPublic Document Room significant hazards consideration: Yes.

..NRC Position on ICSCC in BWR location: Burke County Library,412 Notice of consideration ofissuance of Austenitic Stainless Steel Pipin."

Fourth Street, Waynesboro, Georgia the initial application was published in Additional changes updating oc edules 30830 the Federal Regleter on September 5.

for the 10 year inservice inspection and Illinols Power Company and Soyland fe "IE*I**

ived on th n ce h pu ! c Power Cooperative, Inc., Docket No. 80 d

b' C1, Cilnton Power Station. Unit No.1, f,h$',$ g"[t r h ch Date ofissuance September 19,1990 DeWitt County,Illinola requested emergency handling of the Effective date: September 19.1990 Date of applicationfor omendment:

luly 11.1990 application. %e Amendment Na:100 November 20,1989 Commission's related evaluation of the racility Operating ucense Na DpR.

Description of omendment request amendment, finding of emergency

49. Amendment revised the Technical De amendment exempted two circumstances, and final determination Specifications, containment isolation valves from of no significant hazards consideration Date of/nitio/noticein Federal monthly position verification to reduce are contained in a safety Evaluation Register: July 25.1990 (55 fit 30301) The personnel radiation exposure, dated September 17,1990.

Commission's related evaluation of the Date ofissuance September 18.1990 Attorneyfor licensee: Sheldon Zabel, amendment is contained in a Safety Effective date: September 18,1990 Esq., Schiff. Hardin and Waite,7200 Evaluation dated September 19,1990. No Amendment No.:46 Seare Tower,233 Wacker Drive, significant hazards consideration racility Opemting ucense Na NPF.

Chicago, Illinois 80006 comments received: No.

82. The amendment revised the LocalPublic Document Room LocalPublic Document Room P blic loca ion Cedar Ra id bli Li rary, ofin tiol ofices Federal b

1 % tJohnso et, 500 itst treet.,, ea ap s.

Register: July 11,1990 (55 FR 28478) na Clinton, Illinois 61727 Commission's related evaluation of the towa $2401.

amendment is contained in a Safety Indiana Michigan Power Compan.

Nebraska Public Power District, Docket Evaluation dated September 18.1990.

Docket No. 80 316. Donald C.

No significont hasards consideration Nuclear Plant, Unit No. S. Berrien No. 84 298, Cooper Nuclear Station.

y,,,g, canary,y,yr,,y, comments received: No County, Michigan LocalPublic Document Room Date of applicationfor amendment:

Date of amendment request june 1, location:The Vespasian Wamer Public hiay 14,1990 1990 library,120 West lohnson Street, Bri descr tion of omendment:%is Bri description of amendment: The Clinton,Illmois 61727 amen ent c ges Technical amen ment changed the Cooper Nuclear Illinois Power Company and Soyland Specifica4on (TS) 3/4.7.1.5.1.b, Steam Station Technical Specifications by:1)

Power Cooperative,Inc., Docket No. 80 Genuator Stop Valves." to require full Deleting the existing limit of 3.25 times est Citaton Power Station, Unit No.1' valve closure within 8 seconds. TS the surveillance interval for three DeWitt County, Illinois Table 3.3 5," Engineered Safety Features successive surveillances,2) utilizing the Response Times," has been changed to suggested wording of Generic Letter 89 Date of application foromendment reflect the increased closure time. In 14 to define the 25 percent surveillance July it 1990, as supplemented addition a number of editorial changes allowance, and 3) incorporating the S ember 12.1990 have been made to TS 3.3 5 for seggested wording for the Bases from scription of amendment request' readability, the Generic Letter into the Cooper

%Is amendment revised the Action for Date o/ issuance: September 18.1990 Technical Specifications.

the Divisions 111 and IV inverters to Effective date: September 18,1990 Date ofissuance: September it.1990 require only that the Hi h Pressure Core Amendment No.:135 Effective date: September 11,1990 Sprey aystem be deeler inoperable Facility Operating License Na DPR' Amendment No.:134 cnd the appropriate ECCS Action

74. Amendment revised the Technical requirements be followed.

Specifications.

Facility Operatin# License Na DPR.

The initial amendment request was Date ofinitio/ notice in Federal

46. Amendment revised the Technical-supplemented by the licensee's Registee: June 27,1990 (53 FR 26287). The Specifications.

submittal dated September 12.1990, Commission's related evaluation of the Dofe ofinitiolnotice en Federal which described a change in amendment is contained in a Safety Regleter: July 25,1990 (55 FR 30302) The j

circumstances due to a problem that Evaluation dated September 18.1990.

Commissica's related evaluation of the developed with the Division Ill No significant honords consideration amendment is contained in a Safety Shutdown Service Water pump. Due to comments received No.

Evaluation dated September 11,1990.

the essential support provided to the Local?uMic Document Room No significant hoserds consideration inverter's heat removal system by the location:Moude Preston Palenske comments rece/ red No.

t 4

4Ms4 Fedacal Resister / Vol. SE, No.1st / Wedneeder October 3, teso / Notloes 1

kcalpublicoocvaant hvn Northeast Nuclear Campmer,et Refweece Department,71 Souta location Auburn Pubhc ubrary,114 al., Docket New Emus, Nuolant Franklin Street, Wilkes-Baste, 15th Street. Auburn. Nebraska ta305.

Power Statien, Unit No.4.Nea hunden Pennsylvants 18701.

Northeast N or Energy Company, County, M Philadelphla Electric Company, Public i

Doc' set No. spas, Milletana NurJear Dole of applicotlanfor aswsubumt-Service Electr6c and Ces Campany Power Station, Unit No.1, New imadan June 28,1pe0 Delanaeve Power and ught Connpany.

County, Ceanectimt Brief deecription ofso endment he and Atlantic City E3 ectr 6c Company, Dose of cpplicationfor ornendment/

amendment changes Millstone Unit 3 Docket Noa,88 277 and 30 23, Peach 4

echnical Specification ("!$) 4 4.8, Bettaa Aleade Power Station Unit Nos.

TSpecific Activity," to allow reactor June it.1990 3 and 3. York County, Panas)lvania 1

Briefdescription of amendment ne change to the Technical Specifications startup without prior determination of E-Dole 0/0PP icationfor amendments l

would add a sequirement to ensure the bar(a measurement of the specific actlygty of all isotopes in the reactor December 28,1000 as pupplemented on operabibly and per6 odic testing of a coolant that have half hvos greater than February 16,19e0. N supplemental modtfacation made to the 14A to 14G t!e bnaker*

10 minutes).

letter provided administrative Effecta[e date: September 19, tesoDate o issponce September 19,199 information.The staff has determined Date ofissuance September 12, timo that this information does not affect the Effecure dote: September 12,1990 Amendment No.:55 proposed no sigrdficant hasards Amendment No.:45 Facility Operating License No. NPY.

determination.

Focility Operoung License No. DPR.

49. Amendment revised the Technical Brief description of amendments:

21. Arnendment revised the Technical Speelfications.

These amendments changed the

)

Specifications.

Date ofinitioinoticein Federal Technical Specification to reflect the Date ofinitialnotice in Federal Register: August 4,19e0 (55 i R 32329) addition of high high radiation trip Registen July 25,1990 (55 F1t 30$03) ne The Commission's related evaluation of signal requirement for the control Comminion e related evaluation of the the amendment is contained in a Safety circuitry purge and vant teolation valves amendment is contained in a Safety Evaluation dated September 10.1990.

located on lines larger than two inctes Evaluation deted September 11 teen.

No avn/ficonthosords considemtion in diameter.

No significant hatords considemtion cornments received: No.

Date ofissucnce: September 7,18u0 comments received: No, LocalMlic Document Room kcciPublic Document Room location:laarning Resources Center, Effecun dote: September 1,1980 location learning Resources Center' Thames Valley State Technical College, Amendment Nos.:the and 158 Thames Valley State Technical Coll'8

574 New tondon Turnpike, Norwich, Facility Opemting Licenee Nos. DPR.

574 New tondon Turnpike, Norwich Connecticut 0n300.

D

56. me nts rmed the Connecticut 06300-Penns>lvanna Power and usht Northea > Nuclear Energy Company, et Company, Docket Nos. gikae7 and 36 myfemn Fedd Itegister: May 2,1990 (55 FR 18412) N al., Docket No. Stk423 Millstone Nwtaa, see Susquehanna Steam Electric Station, Commlulon's related evaluation of the Pom er Station, Unit No. 3, New tendon Units 1 and 1, Luserne Countyi County, Connecticut Pennsylvania amendments is contained in a Safety 1

Evaluation dated September 7,1990 Date of amendment request: lune 13.

Date of application for amendments:

No significant honords consideration

\\

1990 February 12,1990 comments reorired: No Brief description of amendment:ne Briefdescription of amendments:

kcalPublic Document Room amendment changes Millstone Unit 3 Temporary extenslen of allowable locotion: Government Publications Technical Specification (TS) 4.0.2 by Limiting Condition for Operation for Section, State Library of Pennsylvania, deleting the requirement that the Service Water System from 3 days to 7 combined time interval for any three d8F8-(REClONAL DEPOSfTORY) Education Building, Walnut Street and consecutive surveillance intervals is not Date ofi88uonce: September 20,1990 Commonwealth Asenue, Box tool, to esceed 3.25 times the specific Effectne date: Unit 1, as of date of liarrisbury. Pennsylvants 17105, surveillance interval issuance and must be implemented on a Date ofiscuonce' September 19,1990 ne. time basis only during the refueling Pomer Authority of N State of Now E//ective dote: September 19,1990 outage scheduled to start on September York, Docket No. 50 206. Indian Point Amendment No.: 54 8,1990. Unit 2, as of date of issuance Unit No. 3, Westchester County, New Tucihty Opemtir's License No. NfT.

and must be implemented on a one-time York

49. Amendment revised the Technical basis only during the refueling cutage Specifications.

scheduled to start on March 9,1991'

'""' " '"EE *'"

Amendment Nos.:100 and 68 Date ofinitialnotice in Federal Focility Opercting License Nos. Npr.

Registen July 25,1990 (55 FR 30301) ne 14 and NPF.22. Noe amendments Briefdescription of amerrdment:%e Comtrission's related evaluation of the revised the Technical Specifications.

amendment revises the Technical s.nendment is contained in a Safety Date ofinitiolnouce in Federal Specifications to remcVe cycle. specific Evaluation dated September 19,1990.

Reg' ster: August 30,1990 (55 FR 33992) parameter limits from the Technical No significant hazards considercuon ne Commlulon's related evaluation of Specifications and Io reference a Core comments received: No.

the amendmenta is contained in a Safety Operating Limits Report.Noe changes kcolMlic Document Room Evaluation dated September 2419eo are in accordance with NRC Ceneric 1xotion 12arning Resources Centar.

No sigruficant honords consideration l' U ** **

~

1 names Valley Stste Technical College, comments received:No Date ofissuance: September 11.1990 574 New London Turnpike. Norwich, Loco / Public Document Room Effective dote: September 11.1990 Countcticut 06360.

location: Osterhout Vree Ubrary, AmendmentNo.:103 i

Federal Reglatec / V:1. 55, No.192 / Wednesday. October' 3.1990 / N:tices 40485 1

Pacility Opervting License No. DPR.

P//ective dole: Units 1 and 2: As of the Sacramento Municipal Utility Distric.t.

64: Amendment revised the Technical dste ofissuance and shall be Docket No. Sb.312. Rancho Seco Nuclear Specifications, implemented within 60 days of the date Generating Station, Sacram ato County.

Date ofinitio/ notice in Federal of issuance.

California Registen July 25,1990 (55 FR 30309) The A'mendmeniNos.114 and 90 Commission e related evaluation of the Date of opplication for amendment:

amendment is contained in a Safety facility Otw?: Hits License Nos. DPR.

December 28,1989, as supplemented Evaluation dated September 11,1990.

70 and f&MS. These smendments March 16,1990 No significant hotords consideration revised the Technical Specifications.

Brief description of amendment: This twe ofinitialnoticein Federal amendment revised the license

1. 1. $,'fNfh##

i nt Room Registen lune 27,1990 (5! m 26293) The condition concerning the Fire Protection location: White Plains Public l.itstary' Commission's relatd ev luation of the Plan and added administrative controls a

100 Martine Avenue. White Plaina. New smendments is contained in a Safety to the Technical Specifications (TS) in York,10010' Evaluation dated September 10,1990 support of the Fire Protection Plan as Power Authority of ne State of New No significant hotords consideration described in Generic Lettet 8010.

comments received: No

" Implementation of Fire Protection York, Docket No. 56 344. Indian Polat Unit No. 3, Wutchester County, New LocalPublicDocument Room Requirements." dated April 24,1986. It Yk location: Salem Free Public Ubrary,112 also removed the Fire Protection West Broadway, Salem, New Jersey requirements from the TS to the Fire Date of applicationfcr amendinente 08079 Protection Plan as described in Generic july 26,1990 Letter 8842," Removal of Fire Protection Brief description of omer:dment: The Public Servios Electric & Gas Company.

requirements from Technical amendment revises the Technical Docket No. 86 311, Salem Generating Specification." dated August 2,1988.

Specifications to incorporate a cycle-Station, Unit No. 3. Salem County, New Date ofissuance: September 10,1990 specific change regarding the I"Y substitut\\on of two falled fuel rods.

Effective date: September 10,1990 located in assembly T53 at the core Date of applicationfor omendment:

Amendment No.:115 center, with two stainless steel rods, February 23,1990 and supplemented by Iocihty Opetaling License No. DPR.

Also included in this amendment la a letters dated lune 28,1990 and August 8, 54: Amendment revised the Technical correction to Technical Specification 1990. The supplementalletters did not Specifications.

page 5.3 2 which incoporates text increase the scope of the original Date ofinitio/noticein Federal previously approved by Amedment No-amendment request and did not affect Register: July 25,1990(55 TR 30310). The so but inadvertently deleted by the staffe enginal no significant hazards Commission's related evaluation of the Amendmeat No.101.

determination.

amendment is contained in a Safety Brief description of amendment: This Etaluation dated September to.1990 fYct YoYe pet $et amendment modified the Subcoo1 Lng No significant hotords consideration Amendment No.:104 Margin Monitor (SMM) TechrJeal comments received: No.

Facility Operating Ucense No. DPR, Specifications (TSs) and included TSs LocciPublic Document Room 64: Amendment revised the Technical for the Reactor Vessel Level location: Martin Luther King Regional Specifications'olnotice in Federal Instrumentstion S) stem (RVUS) with Ubrary,7340 24th Street Bypese, Date ofiniti Interim requirements. The RVLIS Sacramento, California 95822.

Register: August 8,1990(55 FR 32331) technical specifications include a NRCProject Direc Nn T. Larkins, ne Commission's related evaluation of footnote terminating the applicability of Acting the amendment is contained in a Safety the Interim action statement at the end Evaluation dated September 19.1990 of the Salem Unit 2 6th refueling outage Tennessee Valley A-Docket No significant hasards consideration (Fall 1991) wben RVLIS will be Nos. 5645a,50 200 at '

' 4 Browns comments received: No upgraded. In addition. Tables 3.311a Fe7y Nuclear Plant, Umta 1,2 and 3.

Loco /Public Document Room and 3.3-11b have been combined into Limestone County, Alabama location: White Plains Public Ubrary, Table 3.311.

Date of applicationforamendments:

100Martine Avenue, White Plains New Date o/ issuance: September 10,1990 April 19.1990 York,10610.

Effective date: Unit 2 to effective as of Briefdescription of amendments:

Public Service Electric & Gas Company, the date oiiesuance to be imp 1emented Then amendments revise the Technical Docket Nos. 56 272 and 86-311. Salem within 30 days of the date ofissuance.

Specifications deleting reference to a Generating Station, Unit Nos.1 and 2.

Amendment No. 95 fixed in line rotometer as listed on Table Salem County, New Jerwy facility Operating Ucense No. DPR*

3.2.D. for redweste liquid effluent Date of application for amendments:

75: This amendment revised the monitoring instrumentation.This instrument has been replaced as a c calS

capna, consequence of a plant modification to May 21,1990 and supplemented by letter dated luly 18,1990.The supplemental Date ofinitiolnotice m Federal improve the licensee's ability to letter did not increase the scope of the Regiate May 30.1990 (55 FR 21979) The measure radiological liquid effluent original amendment request and did not Commimon's related evaluation of the discharges.

a!!ect the staITs original no significant amendment le contained in a Safety o

harards analysts.

Evaluation dated September 10,1990.

Date ofissuance: September 7,1990 i

Effective date: September 7,1990 Brief description of amendments:

No significant hozords cdnsideration Amendment Nos.:175,178,148 nese amendments relaned the comments received: No facility Operating Licenses Nos. DPR.

J reportability requirements for the Local 8ublic Document Room 33 DPR 52 and DPR.68: Amendments reactor trip and reactor trip bypass locorson Salem Free Public Ubrary,112 revised the Technical Specifications.

breakere surveillance testing.

West Brondway, Salem. New Jersey Date ofinitioinotiae in Federal Date ofissuance September 10.1990 080?9 Reglater: June 27.1990 (55 FR 26294) The t'

~

' Federal Register / Vd. 55, No, ta: / Wednesday, Oct:ber 3 1990 / N:tices 40486 1

Commianlon's related evaluation of the locc/PublicDocument Room This amendment revised the amendments is cotitslued in a Safety lxotion: Greenfield Community Canese, Technical Specifications. Date of Pvaluation dated September 7, t wo.

1 College Drive, Caventaald, No significant baserds censiderofion ktassachusetts M301.

individual notice in i ederal Ri gisten comtnents rece/ red:No September 20, im (55 FR 38763) l.oco/Pubhc Document Room NOTICE OF ISSUANCE OF locatiore Athens Pubbc Libtsry, South AMENDMFSF TO FACUJTY laxtion perry Public Ubrary,3751 Main Street, Athens. Alabarna $5611.

OPERAUNG llCENSE AND E1NAL Street. Perry, Ohio 44001.

DETERMIN ATION OF NO Virgirda Electric and Power Cornpany, et SIGNIFICANT llAL8JLDS NODCE OFISSUANCE OF at, Docket Nos. 80 330 and !,0-339, North CONSIDERATION AMENDMENT TO FACILfTY Anna Powor Station, Unita No.1 and No.

OPERATING LICENSE AND FINAL 1, Louisa Couety, Virginia b

f DLTERMINATION OF NO th e ya du SIGNIf1 CANT ltAZARDS Date of cpplication for cceendments:

lune 20.1W notkces ofissuance of amendments have I

Eff (;

ggyn Brief doct:ption c/cmendments:The been lasued for the facihties as listed y

below. These noticea were previoudy (EXIGENT OR EMERGENCY amendments odd an NEC standard far protection hennse condition to the pubbshed as separa te individual CIRCUMSTANCES) operatir.g hc enses and relocate fire notices. They are repeated here because During the period since publication of protectiun reymrernents from the TS to this btweekly notice hsis all the last biweekly notice, the the NA 1&& 14 dated Final Safely emendments that have been issued for Analysis Report.

which the Commisalon has made a final Commisdon has lasued the following Date ofissvoncc/ Septemlet 13,1990 determination that an amendment amendments. The Comminion bas E/7echt e dJter Septernber 13,1990 involves no significant hazards determined for each of these Amendment Nos,t 140 and 1:3 condderation.

amendments that the apphcation for the facility Operatiry Licerse Nos. NPF-4 In this car.e a prior Notice of amendment cornphet with the standards and NPF-7. Amendments revised the Consideration of I suance of and requiren,ents of the Atomic Energy operating licenses and the Technical Amendment and Proposed No Act of 1954, as amended (the Act). and Specifica tions.

Significant llasards Consider =tian the Comminion's rules and regulations.

Dote ofimtia/ notice in Federal Determination and Opnortunit) for The Commission has made apprepnate Register: August llearing was issued, a bearing was findmps as required by the Act and the De Commission,8,1990 (55 IR 3:333) a related evalua tion of requested, and the amendment was Commission's rulee and regulations in to the amendments is contained in a Safety issued tefore acy heanns bccadae the CFR Chapter 1, which are set forth in the bcense amendment.

Es aluation dated September 13,11*0:

Commisdon made a final determination Because of ed ent or emergency No significant horards considerotton th61 the amendment involves no F

significant hasards conOderation.

circutnstances associated with the date

$c buaentRoorn Details are contalced in the individual the amendment wa needed, there wse c

location:The Aldemian 1.ibtary, notice as cited.

not time for the Commiuton to publish, for public c mment before issuanco, its hianuscnpts Department. University of The Ciculand Electric illumisating usual 34 day Notice of Consideration of Virgmla Charlottesville, Virginia :2301.

Compary, Duquesos LJaht Cornpany, Yetkee Atomic Electric Company, Ohio Edison Company, pennsylvania "gf[

• [

8 j

Dodet No.30-000. Yankee Nuclear Power Company, Nedo Edison Determination and Opportunity for a Fow at Station. Franklin County, P*" {,'

p(N Comminion he either!ssued a Federal licaring. For exigent circumstances, the Massachusetts t

a Date ofcrplication forcmendmen y, Ohio Register notice prwiding opport.mity for lune,25, w90 Do!c of opplication for ernendrnent:

pubhc comment or has used local media Brief description of amendmen nis December 19,1989, as supplemented Io provide notice to the public in the amendment r.hanges Techr.ical htarch 30,1990.

area surroundmg a heensee's facihty of Epecificat;ons by specifying enly the Briefdescription ofcmendment the licensee's app!ication and of the tank level and deleting the redunhnt request %e amendment removed cycle-Commluion's proposed determination p:llons values for the Safety injectian specific parameters from the Technical of no significant hazards consideration.

Tank (SIT). Also, the Bases" for Specifica uons (IS) Sections 3.2.1.

The Commlulon has provided a Section 3/4.6.4 will be revised to show

( Average Planar 1.inear lleet Generation reasonable orportunity for the public to that the SlT reserve is increased from Ra te). 3.2.2 [htinimum Critical Power comment, using its best efforts to make available to the pubbe me 40.000 gallons to $2,0n0 gallona.

Ratio) and 3.2.3 (lJeear tient Generation communication for the pw,ans oftic to resp Date ofissuance: September 10,1990 Ratel and placed them h the Core Effecta e date: September 10,1990 Operating IJmits Report (COLR). It also quickly, and in the case of telephone Amendment No.:136 modified section L3.1 of the TS for fuel com* rents, the coc ments have been racilsty Operuurg License No DPR, descriptions and added a definition for recorded or transenbed as appropriate

28. Amendment revised the Technical the Col.R to the 'IliThe amendment and the licensee has been informed of Specifications, also added a reporting requi ement to the public comments.

Date ofinitio/ notice in Federal submit the COLR to the NRC staff for in circumstances where failure to act R:gister: August 6,1993(55 FR 32335)

Information and review.

in a timely way would have resulted, for The Commission's related evaluation of Date ofissuonce: September 13,1990 esample,in deratittg or shutdown of a the amendrnent is contained in a Safety Effectice date: September 13.1990 nuclear power plant or in prevention of Esatuation dated August 8,1990.

Amendment No. 33 either resumption of operation or of g

No eignificant hazards consideration facility Operoting License Na, NPT.

plant's licensed power level, the increase in power output up to the comtnents recrierd No SS.

Commlulon may not have had an V

i Federal Regleter / Vcl. 55 Ns. 502 / WMinsday. Oct:ber 3.1990 / N: tic:s used opponunity to provide for public any person whose interest may be comtrient on its no signincant harards affected by this proceeding and who bases of the ctfntention and a concise determination. In such case, the license amendment has been lasued without wishes to participate as a party in the

• statement of the alleged facts br expert opportunity for comment. If there has proceedmg must file a written petition opinion which support the contention been some time for public comment but for leave to intervene. Requests for a and on which the petitioner intends to less than 30 days, the Commission may hearing and petitions for leave to rely in proving the contention at the intervene shall be filed in accordance hearing he petitioner must also provide an opportunity for public with the Commission's Rules of provide references to those specific comment. lf conunents bas e been Practice for Domestic Ucensing sources and documents of which the requested it is to stated. In either es ent.

the State has been consulted by Proceedings"in 10 CM Part 2. If a petitioner is aware and on which the request for a hearing or petition for petitioner intends to rely to estabbsh telephone wheneset possible, leave to intervene is filed by the above those facts or expert opinion. Petitioner Under its regulations, the Commission rosy lasue and make an amendmeni date. the Commission or an Atomic must provide sufficient information to Safety and Ucensing Board, designated show that a genuine dispute exMs with immediately effective, notwllhstanding by the Commission or by the Chairman the applicant on a materialissue oflaw the pendency befoie it cJ e request for a hearing from any person,in advance of of the Atomic Safety and ucensing or fact. Contentions shall be limited to the holdmg and completion of any Board Panel, will rule on the request matters within the scope of the required hearing, where it has and/or petition and the Secretary or the amendments under consideration. De determined that no significant hazards designated Atomic Safety and utensing contention must be one whh.h. il proven.

consideration to involved.

Board willissue a notice of hearing or would entitle the petitioner to reief A The Commission has apphed the an appropriate order.

petitioner who falls to file such a As required by 10 CFR 2.714, a supplement which satisfies these standards of 10 CF R 50.92 and has made forth with particularity the interest nfetitinn for leave to intervene sha!! set requirements with respect to at Ieast one a final determination that the contention will not be permitted to emendment involvea no significant harards consideration.The basis for this the pedtioner in the proceeding and how participate as a party, determination is contained in the that interest may be effected by the nose permitted to intervene become documents related to this action.

results of the proceeding.The petition Accordingly, the amendments have been should specifically explain the reasons parties to the pracceding. subject to any limitations in th: mler granting leave to why intervention should be permitted intervene, and have the opportunity to issued and made effective as indicated. with particular reference to the participate fully in the conduct of the Unless otherwise Indicated, the followint f actors:

Commleslon het determined that these petitioner's r@ u(nder the Act to be1)the nature of the hearing, including the opportunity to amendments satisfy the criteria r present evidence and cross examine c:tegorical exclusion in accordance made a party to the proceeding:(2) the witnesses.

with to CFR 51.22.Therefore, persuant nature and extent of the petitioner's Since the Commission has made a to 10 CFR 51.22(b), no environmental property, financial, or other interest in final determination that the amendment effect of any order w(hich may bethe proceeding; and 3) the possible impact statement or emironmental involves no significant hazards assessment need be prepared for these amendments. If the Commission has entered in the proceeding on the consideration,if a hearing la requested, prepared an environmental assessment petitioner's interest. The petition should it will not stay the effectiveness of the under the special circumstanm sho identify the specific aspect (s) of tha amendment. Any hearing held would provision in 10 CFR 51.12(b) and two subject matter of the proceeding as to take place while the amendment is in made a de:ermination based on that which petitioner wishes to intervene.

effect.

assessment,it is so indicated.

Any person who has filed a petition for A request for a hearing or a petition For further details with nopect to the leave to intervene or who has been for leave to intervene must be filed with nction see t) the applicatwo for admitted as a party may amend the the Secretary of the Commission. U.S.

emendmen(t (2) the amendment to petition without requesting leave of the Nuclear Regulatory Commission, Facility Operating IJcense, and (3) the Board up to fifteen (15) days prior to the We^lngton, DC 20$55 Commission s related letter, Safety first prehearing confarence scheduled in L w ting and Services' Attention, Branch, or may Evaluation and/or Ervironmental the proceeding. bM such an amended b Alvered to the Commissien's Public Assessment, as indicated. All of these petition mrat satisfy the specificity D wmeM Room, h itema are available for public inspection requirements described above.

2120 L Street. N.W., %@ashington, D.C.,msn ButI at the Commission's Public Document interested persons should consult a by the above date. Where petitions are Room, the Celman Dulldmg. 2120 L current copy of to CFR 2.714 which is filed during the last ten (10) days of the Street, N.W., Washington, D.C., and at anilable at the Commission's Public notice period, it is requested that the the local public document room for the Donment Room, the Gelman Building.

petitioner promptly so inform the ptrticular facility involved.

2120 L Stract. N.W., Washington, DC Coramission by a toll-free telephone cr.ll A copy ofitems 20555 and at the Local Public Document to % estem Union et 1.(800) 325-6000 (in obtained upon requ(2) and (3) may be est addressed to the Room u the particular facility involved. hiissouri14800) 342 6% The Western U. S. Nuclear Regula tory Commission, Not later than fifteen (15) days prior to Union operator should be given Washington. DC 20555, Attention:

the first prehearing conference Datagram identification Number 3737 scheduled in the proceeding. a petitioner and the following message addressed to Director, Division of Reactor Projects.

shall file a supplement to the petition to (Project DLroctor): petitioner's name and e

The Commission is also offering an opportunity for a hearing with respect to intervene which must include a list of telephone number; date petition was thiissuance of the amendments.By the contentions which are sought to be malled. plant name: and publication November 2,1990, the licensee may file litigated in the matter. Each contention date and page number of this Faderal 8

q a request for a hearing with respect to must conalet of a specific statement of Register notice. A copy of the petition issuance of the amendment to the the issue oflaw ac fact to be taleul n, should also be sent to the Office of the subject facility operating license and controverted. hi addition 6 petitioner General Counsel, U.S. Nuclear shall provida es brief sc.planation of the Regulatory Conunission. Washingtun, 3

e

suas

. Federal a* slater / vet. Ss, N2.182 / Wednesday Octyber 3.

eso / Nrtices i

DC aossa, and io 'the eitor ey for the ne Nee.:s9.nd e7 leeneee.

\\

facility openthig License Nee. NPr.

Nonumely flunge of petitione for leave 14 and NPr.22:Amendmente revised the.

to intervene, amended petitions.

Technical Specificaticas.

supplemental petitions and/or requeste Public commente requeeled b to for hearir9 willnot be entertained i

obsent e setermlaation by the proposed no signancent hasarde.',

consideration: No.%ese amendmente Comunloelon, the prealding officer or the werecathorised by telephone on Atomic Safety and Licenelag Board. that $*Ptember 8.1990 and con 8rmed by '

the petition and/or request should be letter dated September IL 1980, anted beoed upon a balancing of the Tectore specified Ln 10 CFR 2.714(e)(1)(l).

The Comcileolon's related evaluetion.

2 of the amendments, consultation erith -

(t ) and 1.714(d),

the Commonwealth of Pennsylvania and Mienst Nur. lear Energy CompeeF*

finalno significant hesards Decket No. 86 348, Milletone Nuciee' conaldereuen determination are Power Station. Unit No.1, New London contained in a Safety Evaluetion dated County. "

ut September 13.1980.

Dotr ofopplication for amendment:.

Attorneyforlicensee: }ey Silberg, Saptember 11,1960 Esq Shaw, Psttman, Potte 6 Trowbridge

\\

2MD N Street N.W., Weekington. DC Briefdescription of amendment:%

31037.

a mendment modifies the Technical Locolpublic Document Acom.

Fpecificetions by changing the iocation: Deterhout Free IJbrary, containment sprey interlock trip level Reference Department, r1 South setting in TS Table 3.1.2 from between Franklin Street. Wilhee Berre, 4 5 and 8.5 pels to between 2.0 and 10.0 Penns>lvania 18071.

vig.

NRCProject Dimctor: Walter R.

Date ofissuonce: September 17.1980 Butler EffeclJte dote: September 17,1990 DateJ et Rochville hiaryland, this aeth day Amersdment No.:46 of September isso.

Focility O erotisqr License No. DP9t.

For the Nuclear Regulatory Commission P

21. Amendment revised the Technical Deente ht. ceuishneid, Epect*icatione.

Public commente requested as to Dawesor. Duvision ofneoctor projecno lit. IV, Vand proposed no 6 ficant hasards Amero%ecioIPrviecie OITice e/Nur/ror r Asychon I

1 enton's roleled evaluetion fuoc.so as:M Filed m2-est ses eel cf the amendment and finalno signliicant ha4arde consideration t'etermination is tantained in a Safety Evaluation deled September 17,1990.

LocalPublic Document Room 1 yotion: Learning Resources Center.

Th.rmee Valley State Technical Colle 5*3 Now London Turnpike, Norwich, ge, Connecticut 083e0.

Attorney for licensee: Gerald Ca tfield, Dquire. Day, Berry & Howard, Counselore at Law, City Place. Ha-tford.

Connecticut 081:2 349e.

NACProjectDirectort lohn F. Stols Pennsylvania Power and Light.

Company Docket Noa. EH87 and so.

38B Suarguehanne Steam Electdc Stat 6en, Cabts 1 and 3.Luserse County, Pennsylvania Date ofApplicotton}bramendmen:

September 4.1600 Briefdescription ofomendment:%

emendmente changed the Technioni..,

Specifications to provide milef from the provielone of Section 3A1.1 (A.C.

Sources.Operetion) action b. by a

persantting a one. time extension of the j 1;miting condition foe operation (LCO) i froun 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 15 days.

g Dole oflasuonce: September ta,1993 Ef)%ctive Date:$eptember 8,1890.

a j

UNI 78D STATBS n., mass n.

NUCLEAR RESULATORY COMMISSION m '*" g a*

WASHINGTON, D.C. 3M

- naam m. em oppciAL susedess PONALTY POR PANATE Ust,4300 l

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