ML20055H051

Forwards Biweekly Notice of Applications & Amends to OLs Involving Nshc,Published in Fr on 900627

ML20055H051
Person / Time
Issue date:	07/17/1990
From:	Murley T Office of Nuclear Reactor Regulation
To:	Graham B SENATE, ENVIRONMENT & PUBLIC WORKS
References
NUDOCS 9007250129
Download: ML20055H051 (35)

Text

!

^ *'

July 17, 1990 IDENTICAL LETTERS SENT TO:

(seeattachedlistofaddressees)

The Honorable Bob Graham, Chairman Subcomittee on Nuclear Regulation Comittee on Environment and Public Works United States Senate Washington, D.C.

20510

Dear Mr. Chairman:

Public Law 97-415, enacted on January 4, 1983, amended Section 189 of the Atomic Energy Act of 1954 to authorize the Nuclear Regulatory Comission to issue and make immediately effective any amendment to an operating license upon a determination by the Comission that such amendment involves no significant hazards consideration, notwithstanding the pendency before the Comission of a request for a hearing.

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

Enclosed for your information is a copy of the Comission's Biweekly Notice of Applications and Amendments to Operating Licenses involving no significant hazards considerations, which was published in the Federal Register on June 27, 1990.

Sincerely, origihal signed b%

ThomasI.EnricY Thomas E. Murley, Director Office of Nuclear Reactor Regulation

Enclosure:

Federal Register Notice cc: Sen. Alan K. Simpson DISTRIBUTION:

(w/oenclosure)

Central File NRC PDR JTaylor TMurley/FMiraglia 0GC SECY Mail Facility GPA/CA(3) jy Program Support, NRR Murley LA:P' 2

D :NRR GP l l,,, [)

A o

sam D C utchfield JGPartlow glia 0/ /90 07p/90 07p/90 07 90 07//4 /90 4Vp 9007250129 900717 q/

PDR ORG NRRB 9'

NRC k taxeiin COPY

.;-. - ;L. '

v cc:' The Honorable Morris K. Udall, Chairman Subcommittee on Energy and the Environment Committee on Interior and Insular Affairs United States House of Representatives Washington, D.C.

20515 cc:

Rep. James V. Hansen The Honorable Philip R. Sharp, Chairman Subcommittee on Energy and Power Committee on Energy and Commerce United States House of Representatives Washington, D.C.

20515 cc: Rep. Carlos Moorhead j

L 1

(

31374 Fedesel Redeter / Vol. os, No.124 / Wednesday, June 27,19o0 / Notices 4

t t

NUCLEAR REGULATORY C068 MIS $10N BtweeWy Nouce Apptestons and Amenements to Opereung usensee invoMng No signinoent Hasereo considersuone L Backgmed Pursuant to Public14w (pt) tr! 415.,

the Nuclear Regulatory %=laataa (3he Commission)is publishing this' regular btweekly notice. PL 97 415 revised section 180 of the Atomic Energy Act of 1964, as amended (the Act), to require the Commission to publish notice of any a amendments lasued, or proposed to be I lasued, under a new provision of section

! 1as of the Ac' his provision pants the i Commission the authority to lasue and make immediately effective any i amendment to an opersung bosase upon

' j a determination by the Commission that I such amendment involves ao signtDeant M' :

l hasardsconsiderstica,notwithstanding the pendency before the Commission of i

a request for a hearing from any person.

his biweekly notics includes all notiota of amendments tested, or proposed to be issued from June 1,1000 l

through june 15,1990. %e last biweekly motice was published on June 13,1990 (56 FR 23002).

I 4

Eederal Register / Vol. 85. No.124 / Wednesday June 27. 1990 / Notices 28275 s

NOTICE OF CONSIDERATION OF current copy of to CFR 2.714 which is those facts or expert opinion. Petitioner ISSUANCE OF AMENLMENT TO avaUeble at the Commission's Public must provide sufficient information to FACluTY OPERATING UCENSE AND Document Roorrt, the Gelman Building, show that a genuine dispute exists with PROPOSED NO SIGNIF1 CANT 21201. Street.NW., Washington DC the applicant on a materiallesue of law HAZARDS CONSIDERATION 20555 and at the Incal Public Document or fact. Contentions shaU be limited to DETERMINATION AND Reom for the particular facihty involved. matters within the scope of the OPPORTUNITY FOR HEARING If a requeel for a hearing or petition for amendments under consideration.%

N Commission has made a proposed lesve to intervene is Ed by the above - contention must be one which,if proven %

date.the Commisalon or an Atomic would entide the peutioner to rehef. A determination that the following Safety and ucensing Board, designated petitioner who fails to h such a amendment requests involve no by the Commitolon or by the Chairman supplement whleh satisfies these significant hazards consideration. Under of the Atomic Safety and Moonsing -

mquirements with respect to at least one.

the Commission's reguletions in 10 CFR Board panel, will rule on the request contention will not be permitted to 80.92, this means that operation of the and/or petition and the Secretary or.the aarticipate as a party.

facility in accordance with the proposed designated Atomic Safety and ucensing

%ose permitted tointervene become amendments would not (1)1nvolve a Board willissue a notice of hearing or parties to the proceeding. subject to any elsnificant increase in the probability or an approprl;te order.

11mitatione in the order granting leave to consequences of an accident previously evaluated; or (2) Create the possibility of As nquired by to CFR 2.714. a intervene. and have the opportunity to a new or different kind of accident from petition for leave to intervene shall set participate fully in the conduct of the any accident previously evaluated; or (3) forth with particularity the interest of hearing, including the @i.e.J.ity to involve a significant reduction in a the petitiorier in the proceeding. and present evidence and crou. examine margin of safety.ne basis for this how that interest may be affected by the witnesses.

proposed dete?mination for each resuhe of the proceeding.%e petition if a hearing la requested, the amendment request is shown below, should specifically explain the reasons Commission willmake a final

& Commlulon is seeking public why intervention should be permitted determination on the issue of no comments on this proposed with particular reference to the significant hazards consideration. %e determination. Any comments received following factore:(1) the nature of the final determination will serve to decide within 30 days after the date of petitioner's right under the Act to be when the hearing is held.

rhah of dus notice will be made a party to the proceedia -(21 the Itihe final deta+=tian la that the considered in making any final nature and extent of the petitioner's amendment requestinvolves no determination.%e Commission wiu not property, financial, or obt interest in significant hasards consideration, the normaUy make a final determination the pie-m--h and (3) the possible Commleaton may issue the amendment unless it neceives a request for a effect of any order which may be and make it immediately effective.

hearing.

entered in the proceeding on the notwithstanding the request for a Written comunente ary be submitted petitioner's interest.no petition should hearing. Any hearing held would take by mau to the Regulatory Publications also identify the specific aspect (s) of the place after issuance of the amendment.

Branch. Division of Frwdom of subject matter of the proceeding es to If the final determination is that the information and Pubhcations Services, which petitioner wishes to intervene.

amendment involves e algnificant Office of Administration.U.S. Nuclear Any person who has filed a petition for hazards conalderation. any hearing held Regulatory Commission. Washington.

leave tointervene or who has been would take place before the leeuance of DC 30555. and should cite the admitted as a party may amend the any amendment.

NormaUy. the==laalon will not publication date and page number of petition without requesting leave of the r

this Federal Register notice. Written Board up to fift en (15) days prior to b issue the amendment untu the.

comuments may also be delivered to first prehearing conference scheduled in expiration of the 30 day notice period.

Room p.323. philDpe Building. 7930 the pr"ia= but such an amended However. should circumstances change Norfolk Avenue.Bebeda. Maryland petition must satisfy the spec $ city during the notice period such that failure from 7:30 am to 415 pm Copies of requirements described above.

to act in a timely way would result, for written comm=nts received may be-Not later than fifteen (ts) days prior to example in dorating or shutdown of the e===laad at the NRC public Document the first prehearing conference facility. the Conunlosion may issue the Room, the Gehnan Bull

.2130 1, scheduled in b proceeding. a petitioner license amendment before b Street.NW. Washington.

De filing shau file a supplement to the petition to

' expiration of the so day notice period, of requests for bagis A----

i below,and petiuona for intervene which must include a tiet of provided that its final determinetion is leave to intervene the contentions which are sought to be ' that b amendment involves no By July 27.1990 the licenose may fue a litigated in the matter. Each contention significant hasards consideration. no request for a hearing with respect to must consist of a specific statement of final determinetion will consider all issuance of the amendment to the the issue oflaw or fact to be raised or public and State comunents received subject facility operating license and controverted.1n addluon the petitioner before action is taken. Should the any person wbcoe interest anay be shaU provide a brief explanation of the Commiselon take this action,it wiu affected by this proceeding and who bases of the contention and a aaariaa publish a notics ofissuanos and provide wishes to participate as a party in the statement of the alleged facts or expert for opportunity for a hearing after issuance.no==laalon expects that r

Proceeding most file a written petition oplalon which support the contention for leave to intervene. Requei ta for a and on which b petitioner intends to' the need to take thle action will occur hearing and peutions forleave to rely in proving the contention at the -

very tafrequently.

Intervene shall be filed in acom dance hearing.he petitioner must also A request for a hearing or a petition with the -daalon's " Rules of provide refmaces to those specific for leave to intervene must be filed with r

practice for Dompetic Llosasing sources and documents of which b the Secretary of the==laalaa U.S.

r k

T" in 10 CFR Part 3.

petitioner is aware and en which the Nuclear Regulatory Comuniasion, interestad persons should consult a petitioner intends to rely to establish Washington. DC 30551L Attention:

l l

l

38275 Fedeel Register / Vol. 55. No.124 / Wednesday, lune 27. 1990 / Notices Decketing and Semees Branch, er may signinoant hasarde consideredon esists addreas the diffmacos betwese the whner's be delivered to the Commiseson'a pubhc as stated in to CHL 60.82. A proposed specifkanon for stretsht run fael oil and the Document Room, the Gehnso Buildi amendment to an operating license for e site's current specifuntroneJIben cherece 2130 L Street. NW. Weehington. DC.

facility involves no signiGcant basards do not nesetively effect tboen properties of the abooe date.Where petitions are consideration if operetion of the localty M d wMch eWatly innwn= EDG puf nnonceionsegwnuy.EDG rebewy nled during the last ten (10) days of the in encordance with a proposed te not e acted h ease hngwh M d motice panod it le requested that the einendment would aci(1) Involve a peutioner promp0y so inform the signinoant increene in the probabutty or

[, p"gpy gg Comminaion by a toll free telephone call consequences of an accident previously proposed chanya is annimum ninewsWe t) Western Un6cm et 14400) 326 e000 (in evaluated. (2) Create the poealbuity of a density hu been solcateud ed bhaeoart 14epo) 342 s700k The Western new or different kind of socident from m.=anatreted to be aesbsible and wiu not Union operator should be given any socident previously evaluated, or 13) lisait the EDGE from ettenning 1tos reted Detagram identification Number 3727 Involve a significant reduction in a

@L Any reduction in fuel economy u e cnd the following message addroceed to margin of safety.

toneequence of opereting wie e lower (Project Direcdort petitioner's name and ne licenmes have provided the density fuel ou has been compenuted for by tale hans muunber,date petiuom was following ena.ysis of no significant e soneervative incnese in the estnimurn feel ma' plant same; and pubbcation baserde cons 8Jetstions using the ou inventory requimd to be metntained tn the date and page number of this Federal Commisaico's standards.

I"3 "8' 'Y*" to miusew a dalgo bw's Register notice. A copy of the petition tilThe proposed chanan do set levolw a

"**' **^ * "e" d'y debon for aU EDGE I" *aceedenar wi se requirements M should also be sent to the Of$ce of the signancent incmase in the probebibty or General Counsel. U.S. Nuclear conseqwness of an occident pavtously Regulsiory Gu6de Lt:7. Rnteion t and ANSI walueted.

Nts&tn me chaape d fwl ou nhnang Regulatory Ccamiselon.Washfagton, DC 30554, and to the attorneF or the h pmposed annen widw pony pmeme W W ao deh h a f

the EDGE and wiH result in a signifumat Nuclear power plant Unit No.1) PNigre boensee.

Technical SpeciSenuens UTrj am hmhed to bng.

to the etabibty/rehebihty of the Nontimely filings of petitions for leswe se W Dun! Gamerwer {EDGl Peel EDG fuel d. Hence, the change 2 PNPFe to intervene, amended petitions.

00 System. The occadrois evalented la fuel ou specification wul not involve a supplementalytiuona and/or requests Chapter la of Ibe USAR involve equipment oipificant increcee in the probability or for nearing wiu act be entertalaed and eysteine which are physicaDy lentated commequesome of an sec6 dent previously Jbetala estermination try the from the EDG tmDding and equipment soeb svaluatesk rammimmiaa the proelding officer or the thet the probabutty or occwmnce of as The proposed chanses to pNpFe Te# aloni dies Atomic Safety and IJoensing accidet weinewd pmvtowh is not effeemd specificanos semunemoe mquimmen for

' rd, get the petition and/or request by abenges er feDures of the EDC's and abstr samphas and testing of EDC fuel ou wiB mal neweieind Pwl ou Systma. Pureemen, inalw e ognifnoast immenee en me shouldin ted bened a

the safety funenen of the EDC's is to mitigste probability or consegmences of se accidmet belancing ctore spe in 10 CF1t Chapter 15 occadeota/tremessets whnch hem pmv6owly esaluated in theI the proposed v) and 2.714(d).

(detaus with respect to thisbeen naluskd by othe came end met b empe krwive replwag bl oil usu LF14(e p.,,ent the rrenne of any initieues curnacy specifwd with tests which an either For Cetion, ese the applicatice for event. Although ensuam blackout is not am dimAsw or equally affective to amendment erhich le aveGeble for public currently discussed in the [ Updated EsferF deweting uneeuefectory fuel oD.Tk i

inspectica et the Commissica's Public Analyste Report) USAR, the changw proposed change involves replacing the f

Document Room, the Gelman Building, described do not effect the reliabiuty or

,,q t.,nt for testing eiored fuel ou in 213D L 9treet.NW., Weehington, DC.

ndundancy of the eneite power supply and

,ec,6ence wig Amu pmoyo emfon do act sometbuis to the probabu'T (accelerated extdetion etabthey test) every 9:

and at the local public document room of occurence of a oteties bledoet. Hess, doye wttb o regoiressent to test for octowl for the particular.m.hty levolved.

these abanges wul not efeat the ymhebibey perumleu eencmatmuoms ta escardance N Qaseleed Electric t =a ai-g of eaasrrence of as acendent emelusand wie Asm Dee.es evwy at doye.The a

Campesy.Duqueens Ught Company.

Pr"6ously in the USAR.

propoesd test, ASIM DmS48, addresses the Ohio Edson Campesy.Pseesylvanie We shaage manaimana the shebatty of he actual een&uem of the fuel oil that wiu be f:am my. Toledo Edinem Esocyocy masel Gentore. As $sca esd pumped w the diesel pesamtere in terme of Peerst e

Campesy.Desket No.asada, Puery

• • Yg

• • • 8-

pertacutete (sold) metier which osund impair M saamW eperone a mauMa M Nuclear Penser Piset. Unit No.1. &abe the overen rehabihty of the enehe power C a mfy. m is espply.1be sospense of the Emersecy Dunel pmem na h

g, A TM

70. le Dehaf amendestagenegideridi EL g *d setested to predicting the tendency of fuel ou lar:'*"r" d # u r 2 :.*ot T '"'

'"osee.r

-e-*

g a,- l g ' * - d 6F af,d m o,

e,,ro,r % too,f. %. cts.i us ame.dme.i - re.ieio. ef *e

,e.e.,,,es, o., s.

Technisel Specincenome UTp) for the would tue mitigeted as evalmeted prev 6oudy P*fbC*lew contamineuen of teella storess.

Emergemey Diesel Generator (EDG) Peel and ew senseguaces would be mechenged.

In add ties. ASTM Dm6-70 test resuhe may

• • t *omresely ennuisw wuh assual foci 00 Syeasse.TS 3/4 a.t. to alleur ese of a CsiegerteaDy. the response of the meersemey con &uon beoene met swelm tmd to very grade No. M) feel eG erhieb le lose Diesel Genereiere and the enske pesar esseeptede to ties duringless supply to egelpment maliumcasas es not 4 t en factere each as storage P

n,rm sie,e,

es.o.m efinend by en enese.and es s=stman aa**"* **d 8d ""as"m'*e"w^ou"ld be AEND2*

n p""d """l days m apped a wwy

===ad=== cleo proposes to upgrade senoegmenses would be a

eien, suel ou spaahty probleme experienced at p'NpP s2 deye for AMM Dm&70.The mon la "*" Pr"3"d' **

8'*"

' me IDG earveniamos rs for esapang

,,g

,g gg,g g,,ggg, se January it sees [tst aswept). )=ly 21.1ses frequent testing for actual particulates to the me and Masch 10.1980. these Technical stored feel oc woeld provide better date on m

,._m lefur M--aseWfisant Spcificenes changes em regelred to fuel condition et the ame of test es we5 es Aasards messadursf4se dreersnam dumm-

% su use of Nereight rus feel the tendency ter Israettee et pertleelew a

h N=='a=La= bee postded ou wh6ch to neue.

. _9 to depedeten moder site storese esednienn.The proposed

^

standarde der does% erhetera dertas laag team storess.These desses tests we theretare be nem sammewo#w la i

1 Federal Register / Vol. 55, No.124 / Wednesday, June 27, 1990 / Notices 262'77 estabhohing adegoocy of stored fuel than the the une hmit for obtatrdag test results for new fuel on added to the storep tanke j

prament requiremente.

hoe remaining fuel ou properuet from 14 (4 A1.11d.21 and the quality of fuel oil in h i

ne chanet to repleos the Water and days to 31 days would not adversely effect storese tanks on a peno&c beeis (4 A1.11e).

Sedmont test centrifuge se new fuel ou diesel pnerator rehabibty.

In accordance with Regulsiory Guide 1.137 per the test spectned b. ASN Dg"3-

%e change to remove the requirement to Revision 1. Regulatory Position Cla, the fuel n (ASTM D17pe) with the Clear and Brtsht perform ASDt Derts testing en y et days for oil may be replaced in a short period of time l'

test per A5W Dt17646 to e conservoUve fuel already in storop is bued upon the (about a week) when the fuel oil does not change in that the Clear and Bright test to rationale that the nisjority of fuel oil vocel the specificauon tvquirements %

esore sensitive in determining the presence of properues tested by ASnt Dir'6 (flash potnt.

intent of the surveillance requirements le to weter and sedmont to fuel ou than the Water certeln number. viscosity, h d potnt) do not ensure h fuel oil eausfies b quality and Sedament teet by centrifuge.

change during storep. If hoe properues are specificauone,hrefore. Action U) hea been k

Requituis performance of the Flaab Point withm specificauon when the fuel oille added to allow up'to 7 days to cornet the test for new fuel ou pr6er to ad&ng new fuel placed in storage. they will remain withm evi.og.spectheation condition whether thie l

to the storage tank to detect poselbie specificauon unleu other non.epecificeuon involves replectng the fuel ou or another i

contamineuon of the new fuelle a petroleuro praiucts are added to the storage outuMe medid I

onnservative change & Fleeb point test tanks ne oddsuon of non-opecificauon Based on b above &scussion of the an addiuomalindiceuce that new petroleum products to precluded by TNPf's a ages being evaluated. It is evident that the 1 oille within specthcotion hmite.

proposed new fuel ou surveillance program rev "isly evaluated performance Requiring performenee of the Flash point test detailed above. Over prolonged periode.

"capeodities of the EDGE and their associated I

pr6or to acceptance of new fuel ou wiu reduce stored ful ou can ext &.se and form r-;oay;;=ey;gib,,er,,,,,,,,,

.e,osemmty M ed&ng sad w io 6e fvei,a,ussies w-n e uncant ou already in storego.

concentrations, could impair diesel geneistor These changes therefore do not adverseiy Addmg opuooal caethode of verifytag fuel briormance. Particulate concentrouono and affect the rehabdity o' the emergency &eeel grevu by (1) tee frv 5 Tic Gravity, and v

eterta concentratione are the only gerstm k Mopond to miugets pensWnts/

s *

• evity or charactenauce that will change in stored fuel (2) g testira for accidents.

Specific Grevtty and a m.ag results with oil Peruculate concentrations wul be h ecope d 6e changa descreed abon tre supptwr o certiacata mill not affect the C every 31 days in accordance with have no effect on h EDG Control Systent sebabthey of the emergency seest generatore. EU (+ 16 66 es discussed above. Bactens nees changes han m impact on &e sowc he Specinc Gravity test method to e method n W 4 currendy prevented and will or endr nowntal quehncation d equipent specificauy approved by Regulatory Guide

< vae to be prevented by peno&c removal 1.137 Revtsico 1. and to therefore acceptable of it stor from the storese tanke es required me change cnetes,no cmoe bes betwen safety.nlated Meional power supphee or fa use in determining fuel ou grevity Testing by exieting Technical Specificauone inwrconnectime betwm DiMalonal Diesel new fuel ou prior to addition to the storage 4A1.11c and 411.11d. Considenne that b Gemtom. %mfm. tMe chany mama tas by either the API Gravity or Specific fuel ou properties will not change in storep.

the independence and redundancy of the Crevity sethode and coseparing with the and that fuel ou condiuone which could onsite sefety roleted power supply. Fouowing suppber's certificat6co le justi6ed in that any affect diesel generetor operetios will be approval of the proposed change to PNpP's oseimmination of fuel ou during closely monitored. further testing of stored Techrucal Specification the onginal design trenoportation would be ladicated by fusi ou in accordance with AShi De75 overy daages in appearance. Bashpoint or gravity / 32 days will not provide any ad&tional data requinmente of the sawrgency dweel viscosity. Any contaminatico which would nor improve &esel generetor rebebthty.

pnerator system will continue to be awt. and alter the fuel ou appearance wiu be detected Replacement of the Seybolt Universal safety related systems which require power by the Clear and Brtsht test discussed above.

Viecoetty test anothod currently specified supply from the diesel generatore will be incorrect Dash point will also be detected with the Kinematic Viscosity test method capable of performing their original deelgo price to addition of new feel to the storage does not affect the rehabihty of the fuel ou or factions. mnfom. the proposed changes l

tank as described above. With tests for the operetion of the &esel pnerator because do not involve e significant incresee to the e

and Daeb point as addiuonal the Kinematic Viscosity test method te sta probabutty or consequences of an accident l

tors. a vertheation of fuel ou Specific or specified method for determination of previously evaluated.

Apt gravity by teettag sad osaparing to the viscosity in ASht D075. h scarptance (2)W proposed changa do not awak b esppher's certificsson will provide the crlteria for viscoetty remains the same poselbutty of a new or different kind of neceooary assurance that the new fuel le although expreseed in unite Kinematic accident froen any accident previously ortthin spectAcetion halts. Since comparetive (centistokee) rather than in unite Seybolt evaluated-gravity, as proposed, saa detect (BUS) se currently presented.

h proposed changes do not involn a contamination by a variety of petrolete he change to update pNPP's Technical change in the design of any plant eyetem or l

products taciudsag ")et A type" letfuel and Specification to allow use of current ASD4 component nor do they involve a change in l

since the other types of conhamalaatsoa are standarde, specincauy. ASTM D4067 Se la the eperation of any plant system or f

also detected by teste etbar than vtecoettr.

beu of AS%I D270 75 and ASTM D075 ee in component b proposed changes do not testing for viscoetty le not required if vity heu of Alfl%I De76-77 wul not affect the reduce b level of &eeel pnerator l

le determined wotag this alternate me quab'y of the fuel ou or b relisbuity of b operabibty nor do by function as initiating (IA by tseting and comportag with the chesel generetore to that b replacement evente of any accident Saeed on the abow suppher's eartancation). Therefore, the standards are substantially equivalent to argumente that performance, function. and propoesd new fuel ou surveinamaa program those replaced. & methods for sampling redundancy of the onginal design remain will not adversely aSect the operettom of the fuel ou provided in ASht D4067 ee are unchanged. the chany creetee no new EDGE.

equally effectin as those provided in AS%t potential for an event af such significance to j

Under PNpp's proposed feel ou D270 75 (which has been withdrewn by be considered a design beste accident.

eurveGlance program, the feel ou properties AlffM).%ere has been no aheap to Furthermore since no new tnee of equipment l

which,if act withis specification,would have propertlee required to be tested or in have been introduced and toe new fuel ou l

the meet detrimental and tamediate impact acceptance criteria between the 1977 and will have no adverse effect on oxleting on abeoel generator operation (water and tees est6cas of ASTM D975. While AS'lM equipment no potential for a different type of sediment Sash point, visocetty/previty) are D07640 does provide for alternative methode malfunction le created by thle change.

choaked ier esaln - : to appecable of testing foe sulfur content (ASTM D1552, 8.De proposed changes do not invoin e ASD4 healte immediately prior to accepttag D2622 and D4294). CEI believes that b significant reduction in a margin of safety.

l the new fuel The remaining fuel ou results obtained by see of the alternative N margin of safety as defined in the I

s'reporttee (the "other propertice" of proposed methods will be equivalent to the method bases to Technical Specincation Section 5/4-l TB 4A1ALd.2) are thoes whieb might impact currently spectSed in De75 77 ( ASTM D120).

g enfers to the rebebility of the onette power diesel gaaereter,.A. - -- only om a long proposed survettlanna requiremente supply. %As proposed amendment to PNPP are bes4.Derefore, the proposal to extend 4A1.tadJ and 4A1.11e verify the quality of Technical Specincatione does not adversely

28278 Federal Register / Vol. 55. No.124 / Wednesday, June 27,1980 / Not6ces aPset the rehabibty of the onalte power amendment wodd not (1) Involve e above. the " paste 4ech* lootee to supply Nor does the proposed change affect significant increase in the probability og administratively controlled by precedere and le annunciated as W Out49entce" en any of tM plant setpomis or surgme to the consequences of an accident previously the contml men when he mv. 8 EDG esatrol accxient analysie lumte. The changes in the eva1usted. (2) Creste the poss!bility oi a surM h h b WW"

~i fuel od esophng and testme requimmente do new of different kind of accident froto pn g g % g,gg,,,,,,,,, g y

mot effect Ow capab&ty of the d eeels to perform their funeuon The purpose of the any accident previously evalua Jd. or (3) aneum ht b hv.3 EDG h not rendered A

change a to increase the rehab&t) of PNPI's Involve a sigadicant reduction in a inoperable by tandvertent lockout when rform tes desip hectnea emergerzy &eaal generators. Hence, ttus margin of safety'bave provided the rehed upon to[the perted c serveillance change dass not reduce the mayn of esiety The hcansees performance of the Techrucal Spec 6cataone' pas" following entlysis of no significant proposed by this regte6ae to 75 Servetitence Based on tie previous discussions, the hazards conalderations using the Requtmeent 4A1.tAe.14.b wiB provide

• dditional asserence that the lechoot festere bcensees concluded that the pmposed Commission's standards.

t.mendment request does not mvolve a (1) N pmposed change does not involve a will oPerste es designed, and pment Sv. 8

&esel engine starung oMy when agetred.

I eignificant increase in the probabihty or eigruficent incmase in the probabibty or hs. It le concluded that the prev 6oes)y i

consequences of an accident previously consequences of en acc6 dent previounty evalested levene of rehabibty end evalueted, does not creats the evetus ted.

possibdity of a new or different kind of The probabibry of occurrence of as redundancy are maintained. and the accident previously evalue*ed 6n the perry conseqaences of en occ6 dent prewtemely accident from any accident previously Nucker P we Ment's (pNpP). Updeled eveleeted remain enchanged.

I h

M h@@

W h W chap de act are evaIusted. and does not invoive o reduction in the reqwed mergin of with mpect to the above descrited design the poselbibty of a new or d6fferent kind of l

safety.

change to pNPI's Div. 3 EDC. lius chenee acc6 dent from any eas6/rtt provtoesty

}

The sta!I has reviewed the licensees

• tedeuon of the contml room ewitch " pub-to-evenuated.

i r'o siFntficant hazards consideration lock" lockout featum) to hmited in ocupe to No new poselbilf% et as wM==t is i

G determination and agrees with the the Dtv. 3 EDG control eyetem which by tteetf created by this ebwee se 64 to Ikitted in

(

bcensees' analysie The staff, therefore, cannot cenoe e design beste occident scope to the Dv. 4 EDG esto/smorgency etert The odeban of the Dv. 8 EDC esto/

circuit wh6cb by %4 wanot seese a doetgn proposes to determme that the bczneees*

request does not involve a significant empwy eten lockout feetm to pnmnt an beste ecctdent. & phye6 cal tamanenon of j

• • • ***8'"'I "*" N

• 8 hazards consideretion' reaalte in no signifbcant increeee to the in accoreamos with the artsinal lastaBat6oo "8'N#8" probabihty of a malfunction within he start requiremente This Am=pe ersetos no Jocefion: Perry Pubhc Ubrary. 3753 Main circuit Campered to h wtg6nal eseign. k redec6am M symem et na-p'i=='n I

Street. Perry, Ohio 44081.

modified ctreett providee edditional performance levele soempered to the original l

Attorney for hansee: Jay Silbarg, p.rsonnel seicy prior to h design chansa.

deetgrt Since es new sompasset type is Esq., Shew. Pittman. Potts a piectng the av. s EDG control switch to the introduced by this change.no new potent 6 ale Trowbridge, %500 N Street. NW.

" pull-to4ock" poetnon taineied e Hpcs Det.

for equionent malf-*- are moedeced by l,

o %fvios" annenostica. but did act prevent h design change I

the d"e'l ea8 as I" 'eeetvtag an estol (s)The ymposed ehenge does not involve e l

Weshington. DC 20m t

NRC Proket Arecur: }ohn N.

emergenef start signal This change sendere signinoont vedecuen in the margin of safety.

i Hannon.

the control switch " pull.to4od" poettion The mergin of eefety, es defleed la the The Cleveland Doctric Euminating funcuanal owrecte the m6aleedes "HpG beses of Technical Spec 6Bcation Section S/4-j Company, Duquesne ught Company, Out.Of4ervice" annoncsetion, and provides

a. rsfare to the rehab6bty of the es>ette power for addinonel peroomnet safety by preventtag supphen. As demonstrated la lleems 1 end 3 l

Ohio l'Aaaa Cn=pany, Pennsylvania eunamabc englas onerts when the EDG to above. sehability of the Dtv.S EDG to not Power Campany Toledo 5%aan at denne pwimmence of mmpmmind by tie design abangemenee.

[

Company, Docket No. EdM48, Perry

• • **** 'I **I"Y d'O"*d '* **

the Toraala=1 Spenficaties b not effected. '

"*""""P" Nudear Pirwer Plant, Ur&t No. L Lake added by this change an oostalmed to 1

County, Ohio emeting on, related egetpment 4a.the ne o.aff bas reviewed the licensees'

(

i Date of amem. Neat regoest' March 30, engine -

owits and cootml seem no significant hazards canalderation pan @ whWe identmal e oeer W determination and agrees erith the 1990

"**y licensees' analysia. De sta!!, therefore.

l

",I*",,,,

De.scription of amendmerit request 4

g De Pmposed amendment would reviee to lock feetore e edadmetrouwely eastround proposee to determine that the henammes' Technical Specification (TS by pmoedere end.as desar6 bed above to request does not involve a signifinant 4 B.1 u.a.14.b to edd a control roosn aan=naated es "HPCS Out of Santos"in the hazards consideration.

l

" pull.to-lockout" feature to the bot of Control Roses when the Dtv. 3 EDG oemtrol localpublicDocuperti Aacas Dwielon 8 Emergency Diesel Generetor switch is in " poll 4 4ack" position. Henan-locatiorr Perry Public Ubrary, g753 Main l

(EDC)lockotit feetures requiring the rehab&ty of the component added by this Street, Ferry, Ohio 44081.

change 6e atsanar to that el ne erig6aal Attorneyfor bcensee: Jay Silberg.

verification by that E.He change wm Esq. Shaw, Pittman. Potte &

require verification that the newly tb ab ei vs Trowbridge,2300 N Street, NW.,

installed lockout feeture preventa inaneens 6es suppornas embeyotems, to not Dtvision 3 EDC starting only when adversely abrand by the dealen chaege Washington, DC 20037 required.

4eec.ibed above.Thessare, the probebietty of NRCPropsot Disoccor: jebe N.

f l

Boots fwproposec%o significant occurnace elan eac6 dest prestooely Heemon.

i hazards conexiemuor> clesermination evaluated b not amoreened as a seauk at thw r amaawealth Edison Casapany, l

he C--* has pr<rvided chamoe.

Docket Nos aws and Meda@

l elandards for determining erhether a Thas deeles change does not sempromine hd M or M.

of enE+

County Eties, Uedes 1 and & M l

significent beterde consideration exista "I* '*d *I'd *"*'*** *""gency CouceySlinois I

ea stated in10 CFR 90.97 A diesel gamereters wtthan the plant no "pau-Date ofqppfloationforemendmeats:

l arnendment to an operisting cenae for a tododWemagency man neckout feauro faciltty involves no sign!!icant harmeda is designed lor ese oudy dertag g April 14,1990 l

J consideration if operation of the facility of Div. s EDC w=h=- ecalvtues arhere Descript.iori ofamendeiends regeest.

in och wth a ym 4

' ensety to a esseera. As donertbed he proposed eenewhnante to Operating l

l

"--'-ii-====iiumum--

-Fed 2r:1 Rsglster / Vol. 55 No.124 / Wednesday, lune 27. 1990 / N tices 26279 License No. NPF.11 and Opereting standard. Although the proposed Attorney so licensee: Michael 1. Miller, l.icense No. NPF.18 would revise the Technical Specification penetration Esquire; Sidley and Austin. One First LaSalle County Station Units 1 and 2 ecceptanos criterion is less conserestive National Piana, Chicago, Blinole e0eso.

Technical Specifications (TS) to clarify than the present values, this will be NitC Acung Pro /ect Diremor: Richard the testing requirements for laboratory addressed by station procedume which F. Dudley.

testing of the Standby Ces Treatment will increase the testing frequency as l

,,-awd Edina yIy r

System and Control Room charcoal the penetration values increase.

Docket Nos. 36 378 and 3D.374. I Salle adsorption beds.ne current TS The deleta,on of auxiliary electric CuWy Sea, Units 1 and 3.14Salb mierence is Regulatory Guide 1.52, equipment room (AEER) from the title Can'I. DHaois Revision 2. March 1978.The industry

" control room and auxihary electric standard has been revised, therefore equipment room emergency filtretion Date of applisodionfor amendments:

1.aSalle is proposing to amend & TS by oystem"is not removing equipment but May 16,1990 rete to the laboratory testing only clarifying the nomenclature.

Descripuen of amendmanse regases:

protoco e of the ASDI standard Also analyses has shown that the The proposed amendment to Operating (D3e03). LaSalle is also proposing that control room recirculating charcoal filter 1.icense No. NPF 11 and Operating the acceptance criteria be modified to is not required, therefore, removal of the Ucense No.NPF.13 would revise the meet or be more conservative than references to this filter would not 14Salle County Station Unita 1 and 2 Generic letter 8313 requirements.

increase the probability or Technical Specifications (TS) to revise his amendment request also consequences of a previously evaluated the " single largest load reject" test value proposes J delete references to the event.

discrepancy between the TS and the auxiliary electric equipment room (2) Create the poestbutty of a new or UFSAR by using the more conservative

( AEER) emergency filtrahon system and differnt kind of accident from any UFSAR valva. Also, to clarify the the control room supply recirculanns accident previously evaluated because requiremer.'e for the automatic charcoal hlter " odor eater." The these filtretion systems an intended to bypassing of the diesel generetor tripe licensee states that since the AEER is mitigate the consequences of an on an ECCS actuation signal for not required to be campied for safe accident and cannot, by themselves, Division 3 the besasse is proposing to plant operation, exwpt in the case of a initiate an accident.he licensee states reword the requirement so that it is remote shutdown, habitability -

that no new accidents are postulated to consistent with the 1A$alle Station requirements to the General Design occur as a result of this proposal.

design and the Branch Technical Cnteria (CDC 19) are not applicable to WInvolve a dgnificut mductimin poduon NWISCB17 and Poemon 7 M the AEER. Also, etnce the current the margin of safety because the the Regulatory Guide 1.B.

calculeted design basis post. accident etales Sosis forp nosignificant radiological doses show that they are aD proposed amendment explicit))

h acceptum ch wih h p are kurds casi wode derhum.-

within applicable regulatory criteria kW rquine arm Albugh he Cambda has provided when the rectrealating charcoal Elter la the assumed analytical values for the standards for determining whether a not considad in the calculetion it is charcoal bed efficiencies will etill result elsnificant hasards ocanideration exist:

hP*d in a dose below the units established in in to CFR 80.22(c). A proposed from th Sosis forproposedno significant to CFR 50, Appendix A CDC 10, the amendment to an operating hoense for a decrease in margin of safety from the facility involves no significant hazards bourds considerotion determination:

relaxation of the acceptance criteria will consideration if operation of the facihty The Commlulon has provided -

standards for determining whether a be offset in part by the estabushment of, in accordance with the proposed rocedurahmed controls.The action amendment would not:(1) Involve a significant hazards consideration exists

[evels established require increased algnificant increase in the probabibty or in 10 CFR 50.92(c). A proposed amendment to an operating licenae for a testing frequencies and actions to help consequences of an accident previously facih involves no significant hazards ensure that the Technical Speelfication evaluated; or (2) Create the poes btlity of cond ration if operation of b facihty ' and the analytiallimits are not a new or different kind of accident from

exceeded, any accident previously evalu!.ted; or (3) in accordance with b proposed amendment would not (1)lavolve a ne removal of AEERis only an involve a significant reduction in a significant increase in the probability or editorial change so it will not reduce the margin of safety, cenesquences of an accident previously margin of safety, Also b controlroom The licensee has provided an analysis evaluated: or (2) Creete the possibility of recirculating charcoal filter is not of no sign 1 Scant hasards consideration a new or different kind of accident fron-eddressed in the Technical ag 6Aa= tion in this request for a license==amadsaelt.

any accident previously evaluated; or (3) bans and it has been shown by The licensee states that operation of the lavolve a significant reduction in a analysis to be unnecessary, therefore, LaSalle County Station, Units 1 and 2. In margin of safety.

the removal of any refessoces to this accordance erith the proposed The licensee has provided an analysis filter does not reduce the margin of amendment will not; of no sign 1 Scant hazards consideration safety.

(1) Involve a eigrdnamat increase in

. in this request for a lacense ammadmant.

he staff has reviewed the laconsee's the probability or consequences of an The liranama states that operetion of the no significant hasards r=aldaration accident previously evaluated becease 11 e amtle County Station Units 1 and 2. In determination and agrees with the will ensure that the te&nical accordance with the proposed heensee's analysis.The staff, thersfare, specification load reject test valve is arneadiamat would not proposes to determine that the licensee's equal to or greater than the maximum th(1) involve a signiftmat inasese in request does not tavolve a significent load requiremset for the HPCS pump e probability or consequences of an hazards consideration.

which is the slagle largest Division 3 accident previously evaluated becense LocolPublicDoctrment Room load.This enhancement will help to the station currently ases ASTM D3803-locatiore Pubbe Ubrary of Blinole Valley aneure the reliability and availabihty to 79 which is referenced in ANSI N510 Community College, Rural Route No.1 the ESF Division a diesel generslors teso sad is the curreniindustry Oselsby Runois s1M8.

under all opereting candittana. Also,this

263BB Fedaeal Register / Vol. 55. No.124 / Wednesday. June 27. 1990 / Notices' Emendment clarifies the intent of the Basis forp edno significoni consequencu anociated with evalueted technical specification requirements and horords cons fion determination accidents have remained unchensed.

does not involve any changes to the ne Commission has provided The proposed changes do not enete the tperation of the facility as described in standards for determining whether a powibility of a new or &fferent kind of

• • d d'"' 8" *"y***id'"' P''Ip,,"$'the\\"[ffer I

Y the UFSAR.

significant hazards determination existe

[*pN,D" 0

(2) Create the possibility of a new or as stated in 10 CFR 50.92. A proposed different kind of accident from any amendment to an operating beense _. - _from any existing nquinments. No new Cccident previously evaluated because involves no significant hazards equipnent le being introduced as e nsult of ~ '

the proposal does not involve any consideration if operation of the fecihty thm chansa. As such. b pouibthty of a modifications to the facility or changes

h. eccordance with the propoud new er &ffent kind.of accident from any t) the operation of the facility as amendment would not:(1) Involve e accident previously evaluated wiu not occur described in the UFSAR. therefore, it significant increase in the probability or se a ruultof these chanan cannot create the possibility of a new or consequences of an accident previously The proposed changee do not invoin e

- diff2 rent kind of accident.--

- -evaluated, or (2) Create the possibility of significant mduction in a margin of safety.

(3)lavolve a significant reduction in a new or different kind of accident frota Nee chanan do not alter h mannar in ths margin of safety because the change any accident previously evaluated, or (3) "gN p*i,["' ""("

9 I" **I' @"D "

raises the Division a test load lavolve a significant reduction in a mpoint, or ope ondlet u t ens requirement for initiation of the "alngle margin of safety, altmd or changed as e ruult of hu largest load reject" surveillance test to The licensee has evaluated th' mvtalone. As such, these changes heve to the more conservative UFSAR value, proposed amendment against th significant effect on the margin of safety.

This change does act alter the technical standards in 10 CFR 50.92. He proposed

/P/ ADDMON OR CHANCES OF specification acceptance criteria for the changes have been broken down into INSTRUMEATATlON test. Also this proposed amendment is five distinct categories, based on the h fonowing changa involve h edition an cdminletrative change which does changes made.The licensee provided ofintrumentation u e woult of the guidance att modify the intent of the technical the following discussion regarding all of ginn in. Gente tann as-37 maarens "NUREG c?37 Technical Specificanons", and specification, therefore, the margin of these changes.

NRC Memormadum DM Crutchfield to 7.M.

safety is not decreased.

bAf ADAflNISTRA7DTCHANCESpon"cl'ot'g'att'"d" ne si.fI has r. vie.ed se ucen.ee s e f U-bg a-g- -

no signincant basards consideration

'8#g8'd instrumentation has been added and/or d

h ditermination and agrees with the intent, reqmmet or sogsha As sud, changed to assun that au Type A variables licensee's analysis.De staff, therefore, thle No Significant Hazards Consideratione

. an addressed, and mierence the appropriste proposes to determine that the licensee's wiU eddress these items:

qualifkd instrantsum As such, this No request does not involve a significant

.Page number changa and ad& tion, Significant Hazards Couldmuou wiu hasards consideration.

. Title changes relocations, and ed&tions, addrew the fouow*ng items:

1.com/PublicDocument floom

. Location and wording of notes associated

.Catalame0msem W Rangd Jacot/on: Public Library of Illinois Valley with the PORVs and PORV Block Vdves, changing from narmw range to wide mage in YtoYto Community College. Rural Route No.1, amb e

Ogelsby. Ilhnois 91348.

- Changes in taminology, address the appropriate number of quahfied Atiorney 80 fuenese: Michael L Milner.

. Generetion of new table to be ' seed for -

instrante.

Esquire: Sidley and Austin. One First refmace purpma.

Changing of b Prewartner Safety Vdn N:tional Plass. Chicago, Ilhnois 80000.

. Addition of nota clarifytas cormnt position in&cator to include both a Technical NRCAcfhy Projoef Director: Richard exemptions to performing perte&c specificanon for the primary and h backup surven.

in& cows, F.Dudley.

. Changes proviens mfwence to bees

• Reviolon of the RCS Subcooling Monitor, Copassoowealth Ediaca Company, stae== ante and revision numbers, to delete previously approved manual Docket Nos.86-seg and 36 304, Zico

. Deletion of surveinance frequency onlculauons in bee of stihsation of installed N=elaar Power Statica. Units 1 and 2 motation addmwed appropriately eteewben instrumentation, and Lake County, Illinois in b Technical Specifications.

• The ed& tion of the following

.Reformating or pages, instrumentattan hto the Technical Date of applicolion for amendmenfs:

. Equipment idenufication changes that m specificeuone:

Core Extt 'I%ermocouples, Cont.iamant May 23.1990 typographicalin natm, and Descrption of amendmente requesf:

.locluelon of reporting ate hto Weter I.svel Wide Range, Containment The proposed amendments would add the administrouw escuan vs.,hawt Water level Narrow Range, Reactor Coolant the Technicat Specifications for some of Specifications, required to M ;erformed Inventory Treding System. and Condensate ande an acuon statement Swege Tank level, the accident monitoring instrumentation De pmPoud changa do not woult in a b pmP*d change dow noumuh in e covered by NUREG 0?37* ReguletO'Y significant incrosse in the probabillry er significant incresee in the probability or Calde 137 and Generic latter 83-37. no consequences d accidata psykiady consequnces d edente previouly following inttrumentation will be added evduled.h proposed changa to b enluted.The purpose d b Accident ht the Technical Specifications for Zion:

Ta hawt specification heted above have Monitoring inetrementation is to provide Core Exit normonovples, Containment been determined to be enhainistrative in sufficient information to perform' required Water level Wide Range, Containment asture. The proposed amendment to the -

manual actions, and to monitor and meaua Water Level Narrow *.tange, Reactor Taahatant specifications does not change er t status and behavior during and Coolant inventory Trecking System, and alter any curmat opereter accons, er uowing an accident N laetmmenteum

--- - to for the mitigation of any referonood in the Technical Specifications to Condenoste Storage Tank IAvel. in "pm*vtously evaluated accident.Tbme changes perform these funcuena mut be capable of cddition, the amendments will make save a impact en assumed mergins or providing this information under auumed some adabletrouve chanpa and revb actione durtng an evaluated socident plant accident conditions. Therefore, there must a few other Technical Specincations to seeponse to previously evaluated accidents both be an adequate number of parametere I

make them consistent with the guidance will not be altered as a result of these monitored, and hoe parametere must be provided by the staff, abanges. As such, the probability and monitored by appropriately quahfied L

Federal Register / Vol. 55, No.124 / Wednesday, jun? 27, 1990 / Notices.

26281 instrumentatloa. The probabihty for am ne fouewsng - - - - 1 involves the analysing reactor asolant and containment evalueled amht is M ; ' = of the revtema of the action statements associated atmosphere, and coDoct cad analyse or number and type ed betrumente designated Wim the accident radiauce anonitortog measure re&oecuve 6edmee and particulates for monitarleg purposes, ne probabibty for instrwnents. n6e esseeernent also addresses in plant geoeous efDuents samples ander an acc6 dent to baked to the peecureer events the adeuom of pregnumauc control to suure acculent conditiona neee programe include.

leading to en socident. None of the accident thsee monitonne capabthues. As such this h training of pereoanel. procedures for monitertog imetrument changes addressed No fognificant Hasards Cnnsidersuons will samphns and analyons. and provisions for bere we baked in any fashion to these addreas the following items.

maintenance of esmpling and analysis procereer events.

Ad& bon of acuon statement e regarding equipment. nees chang's peovide eseurence As sad. die probabGity for previously the actions assomated with the Steam that these cepebuttles and programe wili be evolested events beve trasland unchanged Generator Atmosphenc Rehef and Safety estabhshed and maintained. The evouhe of ne eensegmamma of evaluated events are Valve Radsettoe Monitors, and the Vent these changes treviewed as en tmprovement loosened by assertme that the mininvem Stack Noble Gas Ra&etion Monitors.

in the plants overall abutty to essess occident nanaber of passestero require ( to perform Addition of action statement 31 regar&ng con &tiene, and the potential for or

[;

required unammel actions, and monitor and the actione sesoc6sted with the Contamment quantification of rolesees. At ach these L

eesses plant states feuowleg en socident ar*

Hagh Renee Re&enon Monttore. and --

changes do not tvoult in a signtficant e vetiable.

Tk edditaan of the requirement to have reduction in the mergin of safety.

The proposed Amagam de not seeste b poet Aomdent samphns programs capaW of

/D/ CHANCES 7D AEQUIRED NUMBER poss6 bili et e new or di!Ierent kind of obtairung and analysing reactor coolant and N'NMENTS eonident may marW ant HM eentatruneet atmosphere, and couect and he foUowing suesament lavolves changes evaluateel ne changes wilf not analyse or measure re&oactive todinae and to the required number of instruments, and apprese or te plant opersehen that paruculates in plant gaseous effluents paremeters that must be monitored. As such.

sould creets e aver er difiesent kled of samples ander acc6 dent conditions.

this No Significant Hazards Cons dersuons i

d==a no additica of those lastrentate to The proposed changes do not result in a wiu address the fouowing atems:

the saamanal apaanrat6cas trul prov6de significant lacrease en the p obabihty or Changes to the required and adnimum asseres to sagesde to their avaliabdity, conseqeanose of accidents preetously operable numbst of instruments for the thrask the d=h-w of L6ealtang evaluated h rodieuon monitor action Steam Generetor Wide Range hvel Cen&tw 8er Operet6ca. PamaAal Actions, staleinent danges and programs being added I"''

and appropdete Servelunaos Requirements.

to the shaiatretive section of the Tachmiral Changes to the required and minimum N acc6 dent maattertog lastrammanauem is Specifications of themselves have no tapact operable naamber of instruments for the directly tied to occident taltigation, through on the probabihty of any evente that are

^"N2ary Feedwater Mow Rate Meinitoring b-

' '~

^of mammal actions and inputs to evaluated accidents. As each. the lessessment Droegb proper deciales making probabuity for evaluated events has ~-

--- % delstaon the pZR FORV acousuc the ; " 9-of different type of eccident or remained the an== & changes made are monaws fem the Maumi Specdiceuens.

accident canditions propagating in a di!!ering providag ensurance to the availabihty of and meaner wG be prevented.

these morutore or alterneuve methods of Revmon of the pZR FORV Block Valve he proposed change dose not involve a providing compareW infor motion dortng and position In@:ator, increasing the munimum angnificant reducties to a snargin of safety.

following en accident nrogh senartas the he imelesian of these instruments into the availabihty of these parameters and operaW cuanels from o ao 1.

Tedrdcal Spect8 cation wul provide programs, the conseq=meaa of evalanted The proposed changee do not eveult in e significant increase in the probabihty or assuremos that en adeqeets asamber of the accidents ramala the same.

appropriate teatrumente are availeW to ne proposed change does not create the consequences of noc6dets pewiously ovalseted ne above noted instruments mentter seguired plant parametere in the possibthty of a new or different kind of event of an amMant. 9y.i.

acadent from aey socident prvvtously provide monitoring capabihtsee of parametere teatrumsstattee diet to appropriateIy evelaatsel N proposed changee address the impwtant lor the proper aseeeement of plant qualtfled lor 9 e condition.

sovietoes to programs and actico stateenents, status. Nee proposed changes are not asewenos is se that these parametere There is no new equipment being propoemd linked to increasise the probabibty of any accident nees changes do not alter any of erill be eveGable if requiroqL By redecing the ter installattom that could present the total ausdner of Ammaata for the Centala-ant poenibihty 8ar a new or different type of the eseumed talual conditione for evaluated Wide Range Pesseure lastrumente from 4 to 2 escadent, as a reeah of these changes. plant accidents et the Zaan Station. As each the the appropr6ately geahfled teatressete are operetnoes w01 act be altered la any IaeWe probabibty der en evaluated accident hae sedusase. However, the margia of safety bee that osand seeste the pesetbthty for a new or remained unchanged ne consequence of evalented eucidenta oriu maata the same. In somatsed unchanged by strtue of the reqotred different type of eac6 dent. Through ensuring aanber of damamaa regia the same. For the evanability of these parametere dertng an the case of the Sesam Generator W6de Range the kastrumentation betag them7 accident, proper d=* making can be Level, and the Auxihary Feedwater Flow abamges will amenamn, the salsty of the plant essered. Aa such, these changes will act mon!toring lastremasta, the required number thsough the a=nahhakaa=t of maniasces esosts tbs paamshihty for a new or dtSerent of instrumente beve hann=a more restrict vs.

ble levels af partesemar= and type of aondent. la addinen, the potential for For the PZR pORY Blod Valve Poeltion a

der these teatr====*a la the meeM=nt sonditions geopageting ha e dif'ering lad 2cator, the minimum operam number bee Technical spachat6ans Drough the emner will be prevented, become more restrtetive.no proposed estahhah==ar of these maalmum levels, ne proposed change does not involve a change will relax the sainimum opereble tafennetles esquired for appropelate decision e6pnhaas redaction ta e margin of salety, number of channels required for the Steam makbeg dureg and fotbertas en accident can The actions will result in the Generetar W6de Range 1mel and Aux!!iary be essered ServeGlence requirassente are estab '

t of sheraste methods of Feedwater How Monitoring inetnenents be6es specifled for the purpose of L.-

. monitortes the of9 ment rolesee paths for the based on the more restrtetive batts imposed opersbesty. no samaeat actices seescested Annam Generator P - ;' -4c Rehef and on the required number of channels. In arttb the assend apmanaathose will regelre the Safety Valvea. and Vest Stack within y2 hour addition, the Steam Generator Narrow Range plaat to be hate e ebendows esadittoa.

Instend of 30 deye as addressed in the covent !Avel teatrumente provide redundant efter en appropriate itse tresse to Tadaiaal apadacatsoma. no redecanoe to ind6 cation of boet etnk states for both the swetore the tnoperebne instressent(s) to these time frames wt!! provide for as tacrosse Sesem Gemoretor Wide Range lavel operable status. As such these proposed to the reed 6asse to seenitor these paremeters instrumenta. and the Auxihary Peedweter a==gaa to the Taaaaaal Spectfleetions wCl to tbs imhhaty e, ut of em accident. De Phrw Rate instromerrte. As such Lbero to result in en basemen ha the einset mergin of eduantstrative changes being edded to the Z ' g evaileW for A.W these safe *y.

Techn6 cal Spec 18estions involve the eddition parametere.no Steem Generator Narrow JC/ACF50fVANDPROCiRAMAyK of the sequir==== to beve poet Accedent Range tevel tastruments beve e required CNANGES emmplies prgreme empoW of ettaintag and number of 2. and a minheem number of 1.

=

26282 Fedical Regist2r / Vol. 55. No.124 / Wednesday. June 27, 1990 / Notic'io and are powemd from redundant safety anonitortng these parameters. The Steam 7 in b Zion Station Techn6 cal Specifications related powe* supphes in this feehion. It can Generator Narrow Range Lavelinstruments to defined es. leet then or equal to n power be shown that there la sufficient redundancy ben a mquired number of 2. and o minimum with reactivity and temperature stated per evousbie to lusufy a 7 day acuon statement number of 1. In this feehion, it can be shown the specific test. Eta mode le synonymous alone for the Siesm Generator Wide Range that there is sufficient redundancy avollsble with Mode 2. incorporatig specified testa inel and Aux 2hary Feedwater Flow Rate to lusufy a 7 day schon statement alone for from the Special Test F.mempuons in the instruments la reference to h PORV the Steam Generator Wide Range 1svol and Standard Technical Specifications This postuon la&cator, the saled n1sted hmit Auxihary } eedwater Flow Rate instruments.

change wiU require the Accident Monitorms ewitch posiuon in&catore etU suu be Based on the &veretty eveilable fo' instrumenu to be opereW k Modes t 2. 3.

nt.ined in the Techruct'. Specificabons.

monito*tng this parameter. It can be and 7.

Nee in&cators on their own an sufficient concluded that sufficient monitoring m propopd change does w mit in a to prende velve statue in&cataan in the capabili'y wiU be maintained. As such beoed s@aM inemie W b probabuny or Control Roont in this lastuon. the on the redundancy in indication and the consequences of accidents previemely consequences of previously evaluated lower threshold for action statement entry,it M

Mode 7 at 6e h Sm W b accidents wiu remain unchanged Based on has been concluded that the overau mersin of the &veretty evadable for monitoring the safety has been enhanced. in regards to the b"D"MW D*

parameter enocated with the Steam PZR PORV Valve Position inacatore, volve Tunng involvu opmuon et pown lents Generetor Wide Range Level and the posttion indiceuon will be eveileble from the not to emceed 65 of reted thermal power. In Auxjbary Feedwater Flow Rate indica tor, in safety related hmit switches associated with order to ootabheb these con &uoma, the plant addiuon to the safety related bmit switches these valvee. Baseo on the curmnt Technical must tranattion Mode 8. In trenettioning Mode associated with the FZR PORV Position Specificatons, opereuona could continue for 3 the plant le in a ocedition where the indiceuen, sufficient morutoring capability a penod of 7 days bened on the inoperabihty accident monitoring instressets are required wiu be matntained. As euch, b of either a stem mounted hmit switch, or en to be opereW. b probabibty for a consequences of evaluated events will acoustical morutor. lf both of these in&catore previously evaluated eccident has remained remain h same through the enurence thet wem tnoperable opereuona could continue unchanged he addition of this seode has no the nununum number of parameters required for e pertad of ume not to exceed da bours. If.

effect on an events or conditions that are to perform required manual acuans. and the required number of channels or niinimum precursore to any evaluated accWents. By monitor and eseees plant status fobowing an operable channels are not restored within assurtog the operebthty of these instrumente, accident are aveilable.

these ame frames, the unit wiu be placed in in su appropriate modes, the consequences of The proposed change does not create the Mode 4 within the next u bours. The previously evaluated accidents will remain possibdity of e - a or 6fferent kind of proposed changes will allow opersuona to the same.

accident from any accident previously continued for a period of tune not to exceed b proposed change does act create the evaluated N proposed changes wul not 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> besad on the inoperabibty of the poestbutty of a new or different kind of impose or result in plant operance that will stem mounted hmit switch alone. If, se accident from any accident previously chauenge the tntegnty of any fission product required number of channels (same es the evaluated. The proposed change does not barners Post accident monitoring mmtmum operable number) are not motored approve or result in the installeuon of new instrumentauon to dwectly tied to occident within this ume frame the unit wiU be placed equipment. h proposed changes wul act nutigence in regards to essessment and in Mode 4 within the next u bours. In the impop or meuit in plaM opmuon ht wul decision making process N number and event that the acousucal monitor to doW from curW practces. In order to type of instruments specified in the Tednical koperable, the actions required wiD estabbsh Mode 7. the plant must first enter Specificauona. of [htr) own will not result in remainled) the same. As such. It can be I~

^**Iden'

1. 88 the possibdity of a different type of eccident.

concluded that the restoration time frame for instmments am cwnnuy mquired opemW All of these items as proposed, will still beve an inopereble bmit owitch is the same in the in M de 1 As such &is change does am edequete ind cebon available through either proposed change is the same as the current meuh in openbons &Hmat Ima entant As eefety related or diverse indicatiott nrough Techmcal Specifications assuming loss of the the assurance that the required parameters acousucal monitor. Regareng the p2R pORV such, the pmposed change wW am cmete de necewary for appropnate decialon making E!ock Valve poetbon In&cetore, salve Posehdity for a new a derent W W during and following an accident are poeiuon in6 canon wul be available ime the accident from those previously evaluated.

available, e can be determined that the safety related hmit switches secocieled with N pmPosed change does em lavoin a PoeJbihty of a diffennt type of eccident or these valves. Besed an b curant Technical signmcant mduchon in a mar $n of safety.

an accident condinons propagating to a Specificauona, operations could continue fa, This proposed change wW mesh to the 6ffertas manner wul be prevented.

e penod of 7 days beeed on b inopersbuity accident monitoring lastruments apMAad in N proposed change does not involve e of e stem mounted bait switch. If, the table SAS, being required to be operable k significant reduction in a margtn of safety.

sequired number of channels [chmanals)is not Mode 7. The inclualon of this made provides nees changes wdl enhance the safety of b restored wtthin tb Woe frame the unit wul assurance that these instruments would be plant through b estabhehment of mom be placed m Mode 4 wt:htn the next u bours.

maintained operable durtag low power restrtetin etntmum acceptable levels of N proposed changee wul allow opereuena phyelce testing. As such, the margin of safety performanne and evailsbutty for the Steam to continued for a pertad of nme not to will not be sign $cantly reduesd.

Genereter Wide Range 1sval and Auxibary exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> based on the inoperability of Based on the previous discuselona, the Feedwater Flow Rate toetruments in the the stem mounted hmit switch. If b requimd licensee concluded that the proposed Technkel Specifications. N carmot number of chanaals (same as the mintmum amendment request does not involve a Technical Specificauons do not invoka any operable number) are act restored within this a

cant base in tbe probadty a required remedial actions until et least 3 time freme, the unit wul be placed in Mode 4 instruments fsilin the event of 8 failures, a 7 within b mext u bours. In this Lahlon, the consequences of an accident previously day action statement would be entered, la margin of safety wu! remain the same.

evaluated, does not create the the event of all 4 inatnunents fathns. e se

/E/ MODE OFAPPuCARIuTY CHANGE Possibility of a new or diHerent kind of bour echan stawunt time clock to entemd.

The following No Bigruficant Hasards accident from any accident previously N proposed changes would invoke a 7 dey Considerstions addreeese the addition of evaluated; and does not involve a time clock based on e e failure, and the Mode 7 as a required soode for the edaat reduction in the required snargin of 46 hour5.324074e-4 days <br />0.0128 hours <br />7.60582e-5 weeks <br />1.7503e-5 months <br /> time clock would altetna ted. The monitoring instrumentation.

safety' Steam Generetar Narrow Range Lavel h Moue of Appbcebu!ty far Specification etahas mkwed the hoensee,e instrumente provide rednadmat hd cation of SAS, Accident Monitortag lastrumentation hast sink stetus for both the Steam Generator has been revised to include Mode 7. Generic no significant basarde conalderation Wtde Range levelinstrumento and the lattar g3-37 was written to addroos b determ! nation and agrees with the l

Aux 1hary Feedwater Flow Rate knetruments.

Modes of Appbcebility ne deBned h the limnsee's analysis. The staH. therefore.

l As euch, thers to red-daag evallaide tar thandanhsed Tadana=1 epadhtwen Mode proposes to deterinine that the beensee's

(

l

Federal Register / Vct. 85 No.124 / Wednesday, lune 27,1990/ Nstices 28283 request does not involve a significant significant potential for coes thermal-no facility rperating hmits are affected.

hydrauhc instabihty and providm8 effectiv*

h proposed changes merely correct, hazards consideration,

'*** dial ActlONe which promptly ters%ete clarify. Or iroprove consistency of the LocalPubhc Document Aoom

• P'**8"I I" !"***Qe a h and are administrative in nature.

locotion Waukegan Public Ubrary,128 On h basis of th ve B. De changes do not create the N. County Street. Waukegan. Illmois consideration, the sta!! p., poses to find pmlWi oh mw w Mfemm bd of soon that the changes do not '.nvolve a accident any accident previously A ttort:sy to licensee: Michael l. Miller, significant hazards consideration.

evaluated (10 CFR 6092(c)(2)) because Esquire: Sadley and Austin, One First LocalPubhc &cun eat Room the proposed changes do not introduce a National Plaza. Chicago. Illinois 80690.

NRC Acting Project Director Richard locahonMonrw Coi aty Ubra]

new mode of Jacility opeistion or Syvtem 3700 South ( uster Roa involve any physical modification to F. Dudley eyol$1se John Flynn, equipment or features affecting the Detmit Edison Company Docket No FC-4 341, Fermi.2, Monroe County, Michigan aq Detroit Edisor Compen.2000

{Pe stionalcharacteristics of the ue e o1 Mi 44226 Date of amendment request: August 4.

Sogn C.

e changes do not involve a 1988 as supplemented August 18,1980 significant reduction in a snargin of p3erson Description of amendment request Amend the Technical Specification to Duquesne Ught Company, Docket Nos-proposed changes do not affect any include Single Recirculation Loop 84 SM and 56 412. Beaver VaBoy Power facihty operating hmits, the manner by operation at Fermi-2.

Station, Unit Nos.1 and 8. Shippingport, which the facihty is operated, or involve Fosis forproposedno significant Pennsylvania equipment or features which affect the Date of amendment sque April 23.

jeciht F

Co sion h p dd Description of amendment request:

Public Document Room t

dere on ste he proposed amendments would Jocation: B. F. Jones Memorial ubrary, in to CFR 50.92(c)' A ed modify Table 3.5 5 Engineered Safety 083 Frankhn Avenue. Aliquippa, amendment to an operating license for a Features Response Times and Table 3.6 Pennsylvania 18 cot.

factbty in accordance with 10 CFR

1. Conteinment Penetrations, and would Atrorneyforliarnese: Gerald to 92(c) would not:(1) Involve a delete Specification 3/4.8.5.

Charnoff. Esquire, ley & Silberg, significant inemase in the probabibty or Substmospheric Pressure Control Esquire, Shew, Pittman, Potts a consequences of an accident previously System. De proposed amendments Trowbridge,2300 N Street. NW.,

evaluated. (2) Create the possibility of a new or different kind of accident from would modify certain e eered safe Washington. DC 20037, feetums response me or operati NRC Project Director-John F. Stols any accident previously evaluated. or (3) simplificauon and clarity, ehminate a GPU Nuclear Corporatima, et aL, Docket lavolve a significant reduction in a redundant specification, improve No.86-380, Dree Mile taland Nuclear margin of safety.

consistency within the Technical Station. Unit Na.1. Dauphia County, ne licensee has evaluated b Specifications (TSe) and between the y,,,,ygy,,g, proposed change against the TSs and b Updated Final Safety requirements of 10 CFR 80.82 and has determined the fouowina-Analysta Report. incorporate the results Date ofomendment requeet March 23, t.h changes act to prob opereuone of Previously reviewed modifications, 1990 which have been found to carry a significant and add, modtfy, or delete for clarity or Description of amendment request potenual for the formauon of core thermal-consistency certain notations to Table Requests extension of the unit operating hydreuhc instabihtim. As such. opereuon in 8.6-1.

heanse to April 19,2014 to reflect a 40 emphance with the propowd pmytalona Basis forproposedno significant year period from issuance of the full-does not affect any tniusting meAh for Aarords considemtion determinatione power bcense.

[

I,g"g g,,

he Commission has made a proposed Sosis forproposedno significant determination that the amendment a,crords considemtion determmotJont evaluated accident h ACTION requirements are those which effectively involves no significant hasards GpU Nuclear Corporation has requested terminate h potential for thermal.bydrouhc consideretion. Under the Commisalon's extension of the expiration date for instability %e ACTIONS taken lead to regulations in 10 CFR 50.92(c), this Throo Mile Island Unit 1 operating placing the plant in e safer condluon and are means that the operation of the facility license from the present date of M'ay 18.

not thmaelves amociated with an iniustins in accordance with the proposed 3008. to April 19,3D14.%e current Smeter for a ly evalneted socident.

amendment would not (1) Involve a expiration date is based upon the im

,"*ba significant increase in the probability or construction permit (CP) lasuance date consequences of an accident previously of May 14,19e6 At the time the full-a,,,eq.,,,,, g eny,,,yg iy yhwd evaluated; or (2) Create the possibility of power operating license (OL) was issued accident

s. As discuseed in 1 above, the changr a new or different kind of accident from on April 19,1974,it was NRC practice to any accident previously evaluated; or (3) opecify an expiration date of 40 years to restrtet opersuons provtously anowoc.

m abange also provideo remedial ACTtONe involve a significant reduction in a from CP issuance.His resulted in an which act to place the plant in a esfer margin of safety.

effective OL duratien vi 84 years. NRC candluon & ACTIONe caued for are within The Commission has evaluated the regulation * (*.0 CFR 50.51) specifies that d

E proposed changes against the above such Mcenses be leeued for a period of ap e As standards as requimd by 10 CPR time not to exceed 40 years, It has been eacsdent mode or involve any modificenan in 80.31(a) and has concluoed that:

the NRC's prae.tico for the past several the plaat desism. Newfore, the c6ense dow A.%e changes do not involve a years to extend these hoensee. If not create the poselbility of a new or different kind of acc$ dent.

significant incrosse in the probability or requested and justified by b hosnese,

s. De chansen act to tacrease the margin consequences of an accident previously to a full 40 years of duration. GFU et safety by prohibities operatune with a evaluated (to CPR &c.82(c)(1)) because Nuclear Corporation has provided such

.-----.-..__,m._____

Mme Fedesel Register / Vcl. 55, Ns.134 / Wedneed:y, June 27, 1990 / Notices a request sa the beste that the plant was NACProfoctDirector JohnF.Stols Canesquently, no significant (nemu in the

~ desiped fee a 40. year operating hfetime probabibty or the consequenase of an 18988 88 Company, W eccident r.

2, evaluated resulta tram cad the savireestental asessement No. 80458, River Bend Station, Unit 3 gene charga.

suppate the boom asemed 40I'*"

West Feliciana Parish,lauisiana

b. No structures. systerna, or componente ggbg,g g,,,

PU Corporation bas Dole of amendment roguest May 14, are edded or deleted by these chanses; he determined that this proposed extension 1990 the poselbthty of addauonal single talhns

~~

resu!ung in a new or different kind of ~

of the OL expiretion date poses no Description of amendmentagover accident fran that previonely evalueted le signi$sent basards considerations as The Proposed amendment would modify set introduced as a moult of thue chansa.

defined in 10 CFR 50.82.That the " Minimum Tempereture vs. Reactor The che, gee progde gior, conometive

~

determination was as follows:

Pressure Curves" contained in Section tiraite for tempmtum and pressum et higher

1. Operouse of the lecihty la escardance 3/4 4.6 of the Technical Specifica3ons system pressures and no hmite are mmoved I

with the proposed====d===a would not (TS) and the associated Besee. Generic. or asade less conserveuve. Therefore. hee involve a signif6 cant increase in the Letter 8811. "NRC Poettion on Radiation is wou2d not crate & peutbility of e probabihn olisocertence or acasequeases of Ernbrittlement of Reactor Vessel new or d Ilmet kind of accident from any an socident petem neleed N Materials and its impact or es tnt.

• • cMient pmlosely nalued proposed mielen 2 Focuin Opmdes IJoanes dess met affect the safety analysis Operetions*" deled July 12,1988,

s. A larger s2 in RN mults free informed all boensees that the methods appbcation of the Regulatory Guide 1 Ae. Rev.

rad does met tevolve any physical chaegse to a methodology. Conuquenuy, the mvind be ple.e. mer any chaages to the format er described in Revnaion 2 to Regulatory pr e.,.temperstwo curves to be need for mirasses se piant opereueno, and only Guide 1se should be used to predict the Ras Tech. Spec. :/44.s am mm eentempletoe a shaese to the empirstian date effect of neutron radiation on reactor eoneervative. Thus, additional margin is tf the servent license. Therefore, this chasse vessel materials as required by pmided to assun that when the enctor la enselsted to the possibility of incmasing Paragraph V.A. of Appendix G to 10 pressure woesel le stressed under operetins.

1. w onesequences of pmtmly analynd CFR Part to, unless the use of other maintenemos, testing and poeteleted accident cccideem nas change wHl not immeen es methods can be justifled.De May 14 emhtions, the mector soolant premum 1990, amendment request is in response "I ""

av*' 8"

• o briule and d

seastmeted 40 of opersman.

to Generic 14tter 8811.De proposed fr[h bt pe em 2.Operosen of facihty la accordance changes to the 'llis are divided into two chanses would am heolve a sign &mt addles peepened====d===t weeld not basic areas: (1) pressure temperature mducuoa h motginWe4hty.

create the peselbulty of e new or different curves. and (2) neutron Duence as a The proposed amendment will not incesse kind of ascident from any c i

function of service life.

the possibuity or the oenoegeances of a evalued h papend mtsien to ee Aosisforproposedno s/gn/ficant previously evaleeted event and wiu act Ecuaty Operehag IJese dose aos aNest 6e herords consideration determination; arestej e new or difIerent kind of sorident

• • I*D ***I '" **d d*" **""'# " *"F F

De Commission has provided h any petonely calneted. Also, tlw in er tote en at standards for determining whether a mulu of his pmpond change m cierty wi eU ecceptance with ree operonema,and saly asetemplates a significant hazards considerstion exists to the aspiretsen dele of the surrent liesmee.

as stated in 10 CFR 50.02tc). A proposed $ ab!h reactor pressure vessel to he plant te designed and constmeted ler 40 amendment to an operoting license for a perform as ducribed in se USAR Le F**" 8I 8P88ehon. nmfon. this change has facility involves no significant hasarde maintained and thenfm.the proposed es arenWeg a new considereLion if operetion of the facGity change does not involve a etsruncont proviemly evehmen in accordance with the proposed redaction in margin of safety CSU proposee

8. Operates of du feeGity in asserdener amendment would not:(1) Involve a het no significant baserde am tavolved for with the proposed amendoset weeld not significant increase to the probability ce these chansa.

tevolve a stydfinnat seduction in a margin of consequences of an accident previously he staff has reviewed the licensee's sefay.no proposed miston to the recility evaluated; or (2) Create the posalbility of no algntlicant hamaids consideration Operating 1Jonese does not tevolve enF a new or different kind of accident frcen determination. Based on the review and physical seeges to the plaat,w a"F 1any accident previously evaluated; or (3) the above discussions, the staff "h'*8" E' ** I"*"*""M Invoke a significant reduction in a Propows to detamine that the proposed N,",,*,*,YYu'"g","P, *'",,*

hoenes.

margin of safety.The licensee provided changes do not invoke a significani ne e.

iyees does,ged in me psAn en analysis that addressed the above hazards consideration.

am en a co year opereung bre, three standards in the amendment Looolhblic DocumentRoom nerofese, the overaD messia of safety for tw soolication.

Jacotiont Government Documents p aat le mehntakesd.

'Dperation of reg (River send Stotion} in Department,laulalana State University, De NRC staff has reviewed the CPU accordamse with the changes proposed in thee Baton Rouge.14uisiana 70803 i,

Nacies-Corporetion deternalnation and amendmenuevoiva m =6:4==tbesords Aisorneyforlicensee Mark l

agrees with their analysis. Accordingly, haasd open the palestione gim helar.

Wetterbahn, Esq, Bishop Cook. Pwcall the -mmt aan to determine

a. Chassa made trough eis a"

r and Reynolds.1401 L Street, NW.,

l that the amendment irrvolves I",NjM g,g,,de.

Washington DC 30005 i

no t hasards cons 6deration.

.,,,ies e,n the,, suit or in NRCProject Directori Christopher 1.

Lacolh6/icDocument Room eniculational enthodology for in an.

Grimes s

}

Joostlan Governement Pebliestions ductihty tramition reference temperstwo Omit States UtDatles Comp'"I',Decket secties, State ubrary of-ted by asseemos of Revtston a of a

No. 58 488, Em Bend Su&m M 1 Walnut Street and.. m Ith tery Guide 1AE The shoogen.

g,,,,g, g ~" -

,ecognisses en no et revised and shghtly West Felicians Parish, '='Aal===

1 Pamisykemiasnak I"' **"*"**# I'*d I"' "I' 88 """

Date of amendaient regasse jene 6.

f Astarineyfor Acaneser truest I.Maka,

• "8

', "e"*$', au"E teetles, ace necisar eens"umw aseo

{

jr. Regelre, Shaw. Plttenen.Potts a hydreetauc and Description of amendment roguest Trowbridge, aseo N Street. NW.,

, metap/owildewn and low level physice

%e Proposed amendment would add an j

Washtegion DC30037.

testing. and een erstmal operemeno).

addstional smoke detector to Technical i

i i

Federal Rcgistir / Vol. 55. No.124 / Wednesday. June 27. W90 / Notices 28285 specification Table 3/4.35.64 due to the se descrbd in the USAA h maintained and he licensee has providad the proposed addition of a suspended therefore, b proposed change does not following analysis of no algnificant ceiling to the control rod drive tavolve a signincant reduction in marsta of hasards consideration using the

• • Inty CSU ProPom that no signincent Commkekn's standards:

maintenance rebuild facility.

I"" '*

8** '

(1) N proposed change to the subuquent Basis forproposedno significoat d '

hozords consideration determination; elsnificant Crds oons ad&tional functional teet semple stae for I*"'.U'"** I"9"I""*""# ## I*'u"PI*

on

%e Commission has provided deurmineum Bued on b review and b Plan 1 provida an equal basis for a thm standards for determining whether a obove escuselone. the staff pmposee to specified semp e plans. nio proposed chenge significant hasards consideration exists determine that h propoead changa do not I'

O ae stated in 10 CFR 80.92(c). A proposed involve e signncant basards considmuon.

',en

,Sjan amendment to an operating license for a Loco / Public Document Room Ed uon of the ASME Code. Section E f acility involves no significant hazards location Covernment Documents Ad&tionally,if a fatium to lock up or move te consideration if operation of the facility Department. I.eulstana State University, determined to be cawed by manufactume or in accordance with the proposed Beton Rouge. Imuisiana 70003 daign donc6ency, functional testing of au amendment would not:(1)lavolve a Afforney forlicensee: Mark enubbm of the seem type that may be signi!1 cant increase in the probability or Wetterbahn. Esq Bishop. Cook. Purcell sub>ct to the same dact wW contmm to be mquimd by Surveillance Requirement 434.g.

consequences of an accident previously and Reynolds.1401 L Street. NW trrespecove of b subeequent ed&tional evaluated, or (2) Create the possibility of Washington, DC 20005 Pm e new or different kind of accident from NRC Project Director: Christopher L ch y incro any accident previously evaluated, or (3) Crimes probabuity or the consequences of any Hunois Pown Capany and Soyland pQ T

do not ruult in a

of as e ce o provided Power Cooperative. Inc., Docket No. 80-any danse a b phu opmh h an analysis that addressed the above 481 Chaton Power Statlee, Unit No.1, ecope of snubbers to be functionauy teeted three standards in the annendment DeWin County.Bhnois these surveillance requiremente bee not appiication.

mducedaemim em propmed

1. N change made in thle mquat is in Date of amendment request Arru 25.

changee cannot create b poselbibty of a accordance with the opphcebk design.

gggo new or &fferent kind of accident than metenal, and cometructnen standards and escription of mendnmnt mqwste As previously evaluated.

~' ~ regulatory requirements ne revision h the statedinMoses for Technical -

-- --ts)N proposed change toibe A - _ >

result of adding an additional fire detector S ecification 3/43.4 anubbers are ad&uonal functional teet emple else for below h plaaaad suspended ceums to a P

room which presently bee one fire detector required to be operable to ensure that SurveiUana Requhannent 434.e. Sample located in the colhng of that room. m the structuralintegrity of the reactor Plan 1 providee an equal basis for all three change resulte in more conservative haute coolant system and an other safety.

epecmed sample plane his proposed cha to conetownt wie &e ASME N (two detectore required as opposed to one) related systems is maintained during wWch has been tacwpwated W ee 1Ms for fim detection in this room. Consequently, and following a seismic or other event R&tka d ee ASmode, Bedon E no signiacant inmase in the pmbebihty o' initiating dY"8mic loads' Additionally, if a failum to lock up or move is h.maaequences of an accident previously Surveillance Requirements 43.4.e, f, g determined to be caused by manufacturer or

. *wd resuhe from his dance and b provide requirements for daign deficiency, functional testing of all

.a % change Maply adde an

.od I detector (6denticalin au respects functional testing of snubbers.The enubbers of the same type that may be to h existing detectarl below a planned specified functional testing sample plans subject to b same defect will continue to be easpended <=&ng in a room which preeently require a random sample of each type of sequbed by Surveillance Requimment 4344 has a detector located h the ceihas of that snubber to be functionally teeted durbg trmepective of the subsequent additional sample else.bslme, ele pmposed dange room. b outbthty of a new or diffwent each reactor shutdown. If failures are am resuh h a Ngnmcent mdudon in he P

w kind of accident ime that previewly experienced, additional samples must be

"*'8 evaluated is not introduced se a soeult of this functional)y tested. Als PmPo**d Based on the previous discussions, the change.nte change provida more change would revise the subsequent licensee concluded that the proposed conserveuve haute for fire detection and no additional sample size for functional amendment request does not involve a hmite m renieved a unade km conserveuve.

nerefore, this change would not creets the testing required by Surveillance h

m WpebWw posetbihty of a new or different kind of Requirement 45.4.e, Sample Plan 1, fitm consequences of an accident previously accident from any accident previously 10% to 5%.

eva usted, does not create the evaluated.

Josie[orproposedno 4/gn/[/oGat Possibility of a new or different kind of t ne larger number of fim detecton in the hozonfs consideration determinotion:

accident from any accident previously same aree equata a each detectw The Commission has provided evaluated, and doa not involve a protecting an ame with lees volume.

standards for determining whether a nduch b the margb of p4 conseqwdy. b revh d narnber a sign!ficant hazard consideration exists hm's niectoes to be used for RBS TB 3/4JJA le as stated in to CFR 50.92. A reposed no significant hazards considerettors more conservettve. ha, additional margin to amendment to an operating conse for determination and agrees with the provded to assare that when a fire does occ v. It will be detected early. nerefore, facility involves no significant hazarde licensee e analysis.He staff, therefore, tt themse would not tavolve a algathaat condderation if operation of the facility Proposes to determine that the ri 'ucuen in margin of safety.

in accordance with a proposed requested amendment does not involve he proposed amendment will not inaease amendment would not:(1) Involve a a significant hazards consideration.

b poealbsty a &e conseqwoon of a significant incr6ase in the probability or pmvwuely naluted event and wm am eonsequences of an accident previously LocolPublicDocument Room evaluated. or (2) Create the possibility of location: Vespasian Warner Public

'g,",,*l* * *** " d'f*["* N" d

• • • 'd**'

M i,#.org,gggYg a new or different kind of accident from Library,120 West Johnson Street, acceptance criterte with voepect to system any accida'it previously evaluated; or (3) Clinton, Illinois 81727 oompa-aate and design requirements, ne involve a significant reduction in a Attorney forlicenses Sheldon Zabel, ability of the fim detection system to perform margin of safety.

Esq., Schiff, Hardin and Walta,7300

26286 Federal Registir / Vol. 55, No.124 / Wsdnesday, lune 27, 1990 / Nsticis Sears Tower,233 Wacker Drive, consided-(1) e postu!sted PHA in the Based on the prevlons discussions, the Chicago, Dlinois 30608 containment in which a fuel bundle le licensee concluded that the proposed NRCProjectDirector John N.Hannon dropped onto irre&sted fuel losded in the Amendment request does not involve a core. and (2) e postulated Illa in the feel significant Mcrease b the probabnity or Bhools Power Company and Soyland building in wl ich the bundle le dropped onto m9um of an accided Woul7 Pswer Cooperative, Inc., Docket No. 86 tree &eted bl sted in the opent feel etorese eg1. Chotoo Power Station, Unit No.1, rocks. As documented in the tJSAR. b evaluated. does not create ge i

DeWitt County

• illinois postulated fwl building FHA neules in higher Possibili a new or different kind of i

offsite radiological releem than the accident any accident previously l

Date of amendmentirguest April 25 tuleted containswnt FHA. However.

evaluated, and does not involve a i

1990 cavee the NPs00 refueling meet wiU act be reduction in the Inargin of safety.'

Descr/ption of amendment requesti used in the fuel buudmg. the current feel The staff has reviewed the licensee's l

De talescoping mast currently installed buildmg FHA analysis is not changed.

no significant hasards consideretion on the Chnton Power Station Refuel This proposed change does not c.sult la a -- determination and agrees with the Platfo1n main hoist consists of three d con el e wn hag Ucensee's analysis.De staff, therefore, open frame type triangular sechons. In l

proposes to determine that the betfortn main botst incorporates redundant requested amendment does not involve order to reduce the poulbility of feetwee its, dual cablee) so that no greppling the wrong fuel bundle as e eingle component fauun will result in a fuel a significant hasards consideration.

risult of mast bowing and to reduce the bundle drop N design of the pepple le not loco /Public Document Room potandal for contamination of the being changed as e result of this proposed location.* Vespasian Warner Public eptreton due to water dripping from the change. m new meet is almilar in design Library,120 West Johnson Street, open freme mast, the current mast will and function to b currently installed meet.

g be replaced with a solid cylindrical m m meet is dalened to match or enceed telesco st. As uit of the

• U 88Pects of b curmody testaued met hneyfdenw%ebn W additio w ight of the w mast, the AdhonaDy Interlocks on me platfwa

%, W. Ha& and Wana. m m in hoist overload cutoff setpoint and prevent unsafe operatica over the reecnar Soare Tower,233 Wacker Drive, wwwl during control red movemente, prevent Chicago, Illinois 00:08 both of the main bolet loaded interlock muision wie me mmary platform, han NRCP@ DieMSam setpoints specified in Technical trevel of the fuel grepple and interlock

_ Specification 3/4.9A1. Refuehog ympple book essagement with hoist power.

'" nGchigan Pessor Coumpeny, Platform. must be revised. %e licensee The proposed main boist everload autoff Dockets Nos. 89 315 and 38314, Donald therefore proposes to change the main setpoint will still ensun that ancesetwe hiting C. Cook Nuclear Plant, Units Nos.1 and.

hoist overload cutoff setpoint specified forces an not appued to a fuel bundle and

3. Berrien Consty, nGehigan in Survell!ance Requ!rement 4.9A1.a the propout main hotet loaded setpoints wm from 1200 27 50 pounds to 1800 W 80 stm eneum that the associsted interlocks are Date of amendmerrer mgoeste pounds and the main hoist loaded initiated when the wetsht of a channeled bl September 15,1988 intsrlock setpoints specified in bundle le appued to te pple. Freer.ee Description of amendrnents request:

mexsmom twight from w ch a ful bendh These amendments would remove Surveillance Requirement 4.BA1.f from could be dropped remaine sachanged as does references to obsolete survaillanr=

485 W 50 pounds and in Surveillance the abJmum nquired water level above interval extensions from the plant Requirement 4.sA1.h from 550 M 50 stored irradiated fuel.Therefore, the Technical Specifications (TS). These pounds to 700 M 50 pounds (for both).

proposed chanee wiu not increase the Basis forproposedno significant probabuity or the consequences of any refemaces am no longer mquired and Aarords considerofion determinationi accident previously evalosted.

their susnoval would make the TS anom He Commission has provided (2) No new faDure modse will be madeble.

standards for determining whether a introduced as a rueult of this proposed Boeis forprepoor.dao eignificoni significant hazard considers' ion axists change.h new mast is stadlar h design i azards consideration determinct/arr 10 ti stated in 10 CFR 50.S2. A and function to the oermutly installed mast.

JR 50.92 states that a proposed new mesus designed to match or enseed amendment will not involve a =l=ahaat amendment to an operating noe for a t

hazards ddah & pmW facility involves no si mWant hazards i nall of p

act amendment does not:

considerstion if opereLion of the facihty being changed as e neult of thh proposed (i) Involve a al nineant increase in the in cccordance with a proposed chanse. N proposed main hoist overtoed t

amendment would not;(1)lavolve a estoff setpotnt win stiu eneen that exceset,e probability or consequences o'an significant increase in the probability or hfting fortwo are not appbed to a fuel bundle accident previously evaluated, or consequences of an accident previonaly and b proposed snate hoist leaded setpoints (U) Create the possibility of a new or evaluated; or (2) Create the possibility of will still ensure that the eseociated hierlocks different kind of accident from any a n:w or different kind of accident from en initiated when the weight of a chenealed accident previously evaluated; or any cccident previously evaluated; or (3) tuel bundle le applied to the pepple.

(ul) Involve a =I=ahat mduchon to lovclve a significant reduction in a faew or a margin of ea6 t

of t

margin of safe from any accident previously evaluated.

The licensee has evaluated the

% e hcensee a provided the (3)The proposed main hotet overload Proposed amendments against the following analysis of no significant cutoff end mein hotet noeded interlock standards of to CPR 50.32 and has hazards considerstion using the setpointa merely ecosent for the Inopeeeed determined the following-Commission's etandards:

weight of the meet.The proposed main helst Criterion 1 (1) As discussed in Updated Safety overtoed astoff setpotat of 1800 Fr 30 pounds

%e changes are me=4=aatretin in asture.

Analysis Report section 151s. e puel stiu ensures that ancese6ve hiting forces are No requirements of the presentT/Ss are HaaMng Aeddest(FHA)le led to not applaed to e feel bundle. & proposed ehminated er rodeosqL The changes are occuraoa someeq w oco ofe of the feel emain hoist loaded noterlock setpoints of 700 intended only to steamhne the T/Be by cesembly hf ting ma.-haata= wh6cb resulas in 27 so pounde atlU ensen that the associated ohnhtieg someous footnotes wh6c6 esed to the dropping of a rehed fuel ama==hly onto interlocks are initieted when the weight of a clutter the da===at. As such. ee ebenges fuel beadles either loeded in the core or charuwied feel bend 6e is oppbed to the an aceexpected to levolve a sient6 cast stored he opent feel storese recka. he Chapter grepple. As e rosuh, there to no signtScent increece in the probability er esseequences to of the IAAR.two dellement FHAe are seducalom in the margin of eefety.

of a preetously remetyeed socklent.

l Federal Register / Vol. 65 NA 124 / Wedniedey, June 27, 1990 / Nstices 36287 Crimides #

assumptions of the current escadent saalyses.

Seels for ao s/gn/ficant t

h changee w0l set sendt la a la se approved by the NRC via Am==amans a hosords co rotson cladermlastases:10 1

P ant confiproben er opesues.

are.

to the Dalt 1 T/Es %e occ6 dent saarysse CFR 50.92 states that a proposed l

these changee are not expected to create the o..

..c-;.d ecceptable DNBA and reeces' amendment wul not involve a signtncent poselbiu of a new or different kjad of coolant system pneeurtaanon resuhe for the hazarde seasideration if b proposed ecc W wt eey psevleuely analysed er appbcable accidente. It een be someonably g,,,

g gq,

g a

evalseted.

concluded, therefwe, that the cbsage wGl not Criarrilse 8 Involve e signifcest increese in the significant incrosse la the probability or The change me adseiminerense la aatwo.

conseqeennes of a previemely analysed consequences of an accident prewtocely - - - -

j No requirement of the preneel T/Se are occident.The proposed T/S shenge wGI act evaluated; or (11) Creets the poselbility

[

ehmineled or reduced h changes are require any phyelcal medhncettoms to be of e new or different kind of emident intended ordy to streamhne the T/Se by plant act any changes la plant operatin8 from any acddtattreviously evaleeted; i

ehminating ownerous footnotes erhich tend to configuretion. m required time reponse of or (ill) Involve a significant redaction in l

clutter the doeurnent. As each, the changes the lose.of.new tripe le a factor la the results a margin of asfety*

are ese expected to irrvetve e e6snificent of the approprsets occ6 dest analyese, het le reducuon in a margin of seleeg.

r.M an iniustlag event. Therefore, we bel 6 eve

-% licensee has evaluated the The staff has reviewed une hoensee's the change wlD not tavelve o elsnificent Proposed amendment against the no significant basards analysie end incrosse in the probabthry of a...Mi otandards of to CFR 80JB2 and hae r

concere with b hoensee's concluaicas.

anatyeed eccedent.

determined b fonowing:

Therefore, the staff proposes to Criserien #

Criserion f determine that the requested ebenges do As W h Crturian 1 show, Gee Beeed on the safety analysee perferiasd by not involve e signi$ cant basarde proposed T/S change tavelves as physical Weetinghouse for the steem has break core considerebon

• "

• 8 **' " ""I

'"ponn, Meam hoe M mese/saergy oper coalisweeten. Therefore, we rolessee for inside contetrement tatsgrity,

,,,jp gjj, % g g,,,,

beheve change will set eneste the steem hae break mese/enoegy rolessee 10C88/O's:Moode Pmeten Palenske possibibry of a new or different kind of ouuide annu6nsient, feedhas tesek, SCTR, Memorial Library. 500 Market Street, St.

accident inn any previously easJysed o' end IDCA, we beheve enH es proposed T/S joseph, Machigan 4g065.

evaluated.

shany b kreue se eman has break AtJorney for hoeness. Gerald creerrion 3 teoleuen ruponn une and he steen Charnoff Esq. Shew, Put: men, Potta and h proposed cheny b eeneistent irte the pawator stop vane choeure tisme by three

=

Trowbridge,2a00 N barset, NW.

sesempoene of the current soc 6 dent seetyees.

,g g, p,n, d

oct Robert PHerean.

e 68'fi" #

lasasse Middges Power 'a==p==y, update l These emelyses denneestreted The tbseegesend incrosse le se sham Docket No. IET15, Donald C, Ceok ecorptable DNBR and seector eeeleal eyeseen Nuciaer Plant, Uelt No.1. Berrien pf"surizauon soeults, and won appwwed by Bne neown mponse um d not change CounD' hesddges the NRC in support of AmenA= ant 128 to the the deman er opereuen of the plant.

Unit 1 T/Se. Therefore, we bebeve the change Therefore we believe that eie abasse erW Date o/=aada=aa' regeset: May 11 does not envolve a etgrdficent redachoo la e not ersets the ra=^16ty of a new er dicesen 1990 margin of sedety.

kind of scaldest from any pseviously l

Description ofcanendment request:

The staff has reviewed the beeness's anarymd er evaleeted.

j Cr#erm s h proposed emesan=2==nuld change no significant hazarde analyste and i

Bewd on se enfey analysee by Technical Specification (TS) Table 3.2 4 concure with b heensee's conclusione.

l

1. """8

• Reactor Trtp System Response 'nmes,"

Therefore, the staff proposes to

• • " h b sek

• by changing the required response time determine that the requested changeo do b'r ks ide e=====t==" " ',

ty for the reactor trip on loss of Dow frock not tavalve e significant hasa.;is steen has bruk maee/ energy veteeses less than ce equal to CA seconde to less consideretion-outeW sm=s=h==e b=maa break SCTB, than ce equal to 1.0 seconds. This LocalPd5c Documeat Rooms and IDCA, we beheve that the ppynamel T/5 change is consistent with the Ua? 1 Jocation: Meude Preston Palenske change increesses tbs steam itse break accident analyels.

Memorial Ubrary,500 Market Street,St.

teolauoa response elsen and the steem l

Basis forpivposedno significant lowph, w Maan 48085.

pnerator step ulve closase thee by three Aozanfo considemtron determinataon 10 seconds win met bevolve e t'-

~

CFR 80.82 states that a proposed hdens tarenigma Posser Ceaupesy,

, eduction is a margia et safety.

amendment wm not involve e awbant DoA his. 88 816. Demaad C. Cook The staff has reviewed the liconese's hazards conaidaration ilb pooposed Nurtaar Pt.at Umbt No,1, Beeden no awhaat hasards analysis and I

amendment does not:

Cooney,beindi5e" conciare with b locanese's eaa 4==ta=a

)

(1) Involve e aio=**=t increase in b p,,,,f,,,,,s r,,,,,,g; y,y 34, nierefore, the staff proposes to probabuity or consequences of an 1gg0 determlaed that the regeested changes accident previously evolueted; or ofomeadneent sepuset.

do not involve a angnifir==' baserths (11) Create the posefbfity of a new or different kind af accident from any h proposed====A= ant weedd chsage consideration.

l LocalPablic h===e Asom r

.g.erl=te*1 Specificathm (TS) 8/4114, acdde revionely eveloateth or sign && ment h in

" Steam Generator Stop valves no location: Maade Preston Palenske a

require hdl valve closure within eight Memorial ubrary, soo blarhet Bireet, St.

f h beensee bee evahnend b esconde. h TS currently requirse ball Joseph, Michiesa 4s086, volve closure widda See essende.

proposed omoedment egetnet the Nos1beest N=ramar Energy Casapesy, et AM y TSTable m aL, Docket No. 88 336, Mdletoes 3%camme standerde of to CPR 80.a2 and bee "Engineemd Safety Featumeam.pn=

Power Station, Uutt No. 3. New Imados determi,ned the fouowing.

. Times, lease EA, tLh, and 7A woeld be cm,,,,

Odpunty' f'8===P89en't The change tram a sospense ese of eA changed to ssDect the incesased thee esceeds to tA seemede terthe huse af 8ser allowed int senem generecer step webwe. April te,150 Date of tyy'Jaans=== farameadossat-reacter tutpa h aa-aaa'a=* week the closure.

_... ~ _ _ __._. _.

3828s Fedoed Registee / W1. 85, No.124 / Wednesday, June 17, 1990 / Nstices a'

ofannendmenthe March SL 1980, and 188 023," lack of powered from a Cass 1E electrical a

maat Technical Protected Suppreselon Poollavel and power source and for which the SpeciScation 8A1(a) to aBow Temperature ladication to the Event of a associated cabung is protected from fire enrichments up to 4.5 weight percent U-Fire," dated May 5, tees. For plants damage 235 to be stored in the new fuel storage hoensed after lanuary 1,1979 (such as once this proposed modification is rocks and Technical Specification E.8.1 148, Unit 1), the requirements of to CPR complete, the TS reference "(Actually to allow 4.5 weight percoat U 235 to be 80.48 and 10 CFR 80. Appendix R are RHR Pump 'A' Suction Temperature)"

the maalmum fuel enrichment in the invoked by the Standard Review Plan for b supprweton pool water reactor care.

(NUREG 0000). Section 9.5.L dated July tempereture indication on TS Table Dose of Asemanes June 13,1990 1981 and its associated attachment.

817.41 will no longer be valid.

Effective does: June 18,1800 Branch Technical Position (BTP) CMEB nerefore, a chaftge is proposed to TS Amadment No.1146 9.5-1.

page 3/4 g.77 to delete this refe' nce Focility Operatifg Liosase No. DPR-

% remote shutdown system such that TS Table 1.3.7.41 will specify

88. Amaad=aat revised the Technical instrumentation and controls located on

" Suppression Chamber Water Specifications.

the RSP were designed in accordance Temperature" caly.

Do!* ofinitiolnotice in Federal with General Design Criterion (GDC) 19 h RQC system is used to support Register: May & 1990 (55 FR 18411)%e of to CFR 80, Appendix A to ensure that certain methods of safe shutdown of the l

Comminaion's related evaluation of the sufficient capability is available to plant in the event of a fire. In IIR No.1-l amendment is contained in a Safety permit shutdown and maintenance of 80 002, Rev. No.1, for ILS, Unit 1, dated Evaluation dated June 13,1990 b safe hot shutdown condition of the g

No sigruf.Nat hosords consideration unit from locations outside of the main b

k ce' d b lant l

comments rece?'ed No, control room (MCR)in the event MCR could "ul' I" th* ""il' bill'I i th*

l LocalPublic Deussent Room habitability is lost.%e remote RQC system swam apply hne inboard l

Jocation 14arning Rmurces Center, shutdown system instrumentation and

%omas Valley State Wchnical College, controle are also used to satisfy the h'TMsy tr D' fro l

v 574 New Ie= dam Turnpi e. Norwich, alternative al utdown requirements of RSP in support of safe shutdown from l

Connecticut 05380-IrrP CMEB 9 51 for shutdown from outside the MCR in the event of a fire, outside of the MCR in the event of a fire.

ybundolphia Elsstric t'.amm, Deckat Albugh b RSP is poward by No,80452,1&ner6ck Generatug Stauan, TS Tabla 117 41 " Remote Shutdown, electrical Dtvision 1 AC power, the HV-Unit L Montgemory County, System lastrumentation and Controls, 491F007 valve is powered from Psaasylvania TS page 3/4 S.77, curantly indicates electrical Division 8 AC power, and will l

automatically close upon receipt of a

]

Does of amandaient reguset June L temperet in 11 non at RSP is Division 3 isolation signal. However, 1990 actually indication of b water Division a control and wer cables Descr(pdon ofomendment mqueste temperature at the euction of the 'A, wm not pmkekd in oee Bm amas l

he proposed amendment would change Residual Heat Removal (RHR) pum for which b RQC syntam is used to Ae Technical SpeciBcatione (% for (i.e, when b RHR pump is abgned for eupport safe shutdown of the plant in l

tenerick Generating Station (ISS), Unit aston Icoolms)'

the event of a Bro. Fire-induced damage

)

1 to reDect two fire protecuan ou[12R No 80023 for 14S, Unit L to the Division 3 control cables could i

mahocations which the hoensee has dated May 8,1989, the licensee reportd committed to perform d the ht tMs inchcanon of suppmelon 1

produos a false isolation signal which would cause the HV 49-1F007 valve to apcoming afuehag outage.

m am water temperature may be lost in twcs proposed TS changes.The first event of a fire for which shutdown from close. Fire-induced damags to the proposed TS change ro5ects a proposed the RSP is mquired since the 'A' RHR Division 3 pov. ables, frr.3 the same I

fire, could cause a lose of po ver

[

modancation to replace the existing p suction water temperature suppression pool water temperstm*

@cator.TI-61104A,is powered i om a required to reopen the valve. 't in the j

event of a fire, the valve closei and indicatino (actually the wats' non Class 1E electrical power souns temperature at the onction d b 'A' and its associated cabling is not power is lost before the valve :an be Residual Heat Removal pump) at the protected from fire damage. In 12R. 89 F* opened, b RQC system wc uld be l

Remote Shutiown Panel (RSP) with 023, the hoensee committed to perfoim a rendered inoperable. In IIR 1. iso 02, direct temposature indication of the modification during the third refuehi a the licensee committed to perf arm a l

suppreselon pool water.De escond outage to provide suppression pool modification during the third '.heefueling l

PmPosed TS change reflects a proposed water temperatun indication at the RSP ou which would provide mad #u ation to pmvide for the control of which would be available to support cope ility, through a manua' transfer emergency power to the Reactor Core safe shutdown of the plant from outside switch located et the RSP, tu power Isolation Cochag (ROC) System steam the MCR in the event of a fire.%is valve HV 46-1R107 from an emergency supply hoe inboard containment proposed modification will replace the (Division 1) power source.%is isolation valve from the RSP.These

'A' RHR pump suction water emergency power source would be l

modifications are proposed to be temperature indication at the RSP with available in the event of a fire to provide j

perfonned during the next (third) direct tempersture indication of the the abihty to reopen the valve. As part j

refueling o*utage for 148, Unit L suppression pool water using span of the proposed modification, this I

currently scheduled to begin in resistance temperstmo detector (RTU) emergency source will be powered I

September 1990, based on commitments elements from the existing Suppreselon through a normally locked open.

l in IJoensee Event Report (12R) Nos.1-PoolTemperature Monitoring System insta.ntaneous magnetic circuit breaker i

89402,"Unevallability of the Reactor (SFTMS). SFTMS provides suppression mounted in an electrical Division 1 l

Core Isolation Cooling Systems Des to pool water temperature indication in the motor control center (MCC). Also, a insufficient Protection of Various MCR only.%is proposed modification second, normally closed.

Control and power Cables from will provide suppresolon I weter thermomagnetic circuit breaker will be Postulated Fire Damage." Rev. 01, dated temperatum indication w is added as a back-up breaker to provide j

i

__U

Fe' aral Register / Vol. 55. Ns. u4 / Wednesday jun3 27,1990 / N:tices 2828) d the redundant protection spermed by abandown of the plant tree outside the MCR modiacetion wu! ese two opero RTD Regulatory Guide 1.a3.*Eiectric in b event the MCR becomm uninhaldubb deseente trarn SPTMS. Sumcient opere RTD Penetretion Assemblies to Contsinment for any roeson, indudmg fire.

elements will still be eveDeble is enes of Structures for Nuclear Power Plants."

Ul' PP "d "'*LC* * "UI *" two fattun of b primary einewns such that the span RE elements fun N bumcient opmnon of SNS wm wt be abewd for electrical cables and wiring that span RTD elements are still eraDable auch AditkmeUy. b nhab0ity of the penetrate the primary contalmnentMis that b design operetion of SPTMS is evppr,wlon pool weter temperatore second circuit breaker is also required unaUected by the proposed modification.h inchcotMn et the RSP wiB be toipmved s'nce to aneure capability 1o disconnect from new tempentan lastrumentatwo n=p wm b*

b new tempetan loop wW be powerd the Division 1 power bus for any faulted powmd troco an electrical aviston t. cla**

tram e cm it source. in eseocieimi cobung load condition.

tE source.W incrased loaang on this will be protected from fin damage, and the i

As a resuh of this propomad power source wd be neghgible and pnposed nio&fihtien wm prende b modification, a change is pinposed to TS thenfore, wiD have no e'fect en the abatty of opereter with the abatty to select between thle Clau 1E ocurce to perform its intended two RTD demenu on oppoone oldes d the Table 3A4.11. " Primary Containment uppM" ton pod 2 stw a tiene @ d Penetestion Condactor C-..

t g[

d mod &cauon wm Protective Devime."11 page 3/4 6-24 to any instrumYtation with securacie or

'"""* P"I **'" **?^"$'Pafm he e

e add the primary and backup circuit responn characteristice ht an &Serent pe hdi non.

breakers for the Diviolon 1 emergency than the eusting temperatu" p p a d m a m w m n m eter b power ly to b RCC system steam tnetrumentauon. nie proposed modincauas intended function of the erstem involved, but supply in containment isolation win meet appbcable construccon atandards.

,g g

og, p,g,,,

d"l n and materialrequirements.ne new temperstan in6 cation la evallable at the 8

vaiva. HV 491F007, to this tabla. Both breakers are Identhd by a alngle kapmtm instrumentaton lap wm RSp to support aafe shutdown of the plant circuit breaker nmmhar. 52-21331. aince from outside the MCR to the event the MCR b

f becoma =Mabitable for any runon, both breakers are located in the same

,,p.,, tion,,g,g.ney,,g tac!vdin8 fire. Thl8 propowd mod $ cation h4CC cubicle.TS Table 114.1-1 d wiewahtauan,h new tempetm wW am ahn ery 11mlung condmone tw currently hets the primary and backssp inetrumentation loop componente wm be opmdon m turnmance nquiresnente

. breakere (cittatit breaker 30. 62-22713) environmentally qual &ed. qualified e P

for the normal Division 3 power supply Seismic Category I and Class it and to the HV.41L1FOO7 valve, energiud from onsite emergency power g

a,,,, g Boslaforp no significarrf suppbee in b event othine power is lost.

g e eId dow not The licensee's analyals of the trNee A

N" yo f m

The Commiselon has provided alter any enumpuens previounty mede in proposed -aA=- to reflect the standards for determining whether a evaluetms b rediolcocal ceawquemme of modifiestion to provide for trenefer at significant hazards ramaldacation axists an occident. W proposed change does set the RSP to an emergency power scarce as stated in 10 CFR Sa92(c). A proposed afiset bm!ans safety eyeiem settmas er for b ROC system steam supply Itne amendment to an operating licanoe operating parameters, and does not anodify se inboard containment kolation valve involves no mgnifWat hasards add any trutiating parameters that wwld (HV.49-im77),in the event of a fire.

considerationif operation of the facihty caun a signifunt inmae b the penbebnity in accordanos with the proposed o' mn8equeme of an acc6 dent protounty asde h mM WM saa2 h n hd bdow-acendment would not:(1) hrvotre a

"*I"g*d e-ncamecrea.e..ngi dose am lesehe a (1)ne cha

{,j proposed chanas do

+*-i m-- = *e r-6esetF -. -.m., of e _ dd,a not creew

. pedso m,-

mn, ua,

consequences of an accident previously accidem from wry accideM prencarty conuquences of an acci.kt previously evaluated;(2) Create the possibility of a enlusted enisawd.

new or different kind of arrirleM from ne proposed TS chance reflecte a nie propaned TS ehange seDece a -

any accident previously evabatad- (3) proposed awha tion to repleen the extettes modification wWeb som anly affect opsesten involve a hh' rad =etw== la a suppresesoo pool weter ternparetse, of b RQC eystese eteam supply bee tal==d margia of safety, in6 cat 6on et the RSp.nia propaced so*4asament lootatiae velve. im normal The Econeesbe prov6ded a separate mo&fication deae not delate ce noddy electrical power sourm (Devtetan al and has analysis of no s a'h' hasards remote shutdown system pwtection feetures, steersency electrical power eaeree (Destelas a

downgrede any sunport system performance 1). All componente are Gees 1A tonalderstice for each of es two r

accessery for reliabw opere* ton of etytronnerntaDy and

,q=

nahncat6ons with the requod for the equipment, redece erstem ndundaney er and installed in accordance wtth case tR bcense amendmenth boensde independence, or hapoee more sevm testies and setsmic regelremente.

analysis of the proposed amendment requirements.We proposed read.nceuen has Duttog scroal aparation, esperanes wW against the three stensterds in to CFR so impact on thw operation of the R10t be metatained between Dtyts6am 1 and 80.92 for the a.yy. M pool sy tem er Ernda nte propoeed Dtvis6on a electrical equipment by two inched tempera tum anonitoring mndi fica tion la modacation does not change or add say open devices, a breaker to the Dtyt:6am 1 reproduced below-components to the teamte abstdown erstem Mcc and ne breaker a-aar*=d m the (1) h propeesd change does eat anvdn a wMch could feu in a diff+ rent mede them was emeryoney Dtvision 1 power esseee in the Previous y evaleeted The proposed change transfer ewitch; terefore, operettee of the e

algnificant incrosse in b probabEiry or esseequences of as accident previsoaly does not in-otro any change to octpants or Dtviolon 1 and Division 3 elecerleal evehested OPereting parametgre not does It trrvette any equipment to oneffected ne laboard and De proposed 75 shenasi vedeces e potsntial taltiettes everst ht weedd create outboard toelence ve}ves are serusa9y spee.

propseed=== dana =ttaa to replace he existtag the poestbility of a new or d.IIsreat khed of thus, only the ne ctor vessel leolenen esppewwien pool water teasperatore orch front any merh prv%essly function een be affected. Steae the Aser to in&ceuen at the RSP (1.a. the weher evelastei b terminal hon asetemnes the mensel temperature et the eaction ei b W RIGL (3) N proposed change does met invehe o tremeler switch will be locked cioeed wtab the pump) with direct tempere4ure teacatias of eignificant redaction in e margie of ealsty.

transfer swuch ta the '" normal" peetties, ne the suppreselonfool weter.nisyroposed ne proposed 13 change tvDech a probabuity of lailure of the salve to cdese modification wta esswo tlw annabittty of proposed modlibtion to nf see the existing when required to una&cted With the esppeeesten peel esoter ^

suppreselon pool we ter temperates transfer switch to efther pealtion. Division 1 indicatten at the RSP to support asle in& cation of b RSP.This proposed and Division a electrical equipment and the l

28290 Fed:ral Register / Vcl 55, No.124 / Wsdnsoday, June 27. teso / Notiese electrical sentainment penetretion fw the determine that the proposed amendment 1.N pmpeeed ebsages de not halve a power supply to the HV.481poof velve wu!

involves no significant basards signincaat imemos la the pobabuny or emmquaem W as aondent ymvuusly be protected by two esdundant breakers, consideration.

waluated Administrative pescedures will ensure that g,,,j pygjjg g,,,,,3g g,,,

De piplag to be lacluded within the new the amount of une Divisica a cabhng le location: Pottstown Public 1.lbrary. 500 lauon bedary esopha wie &e same exposed to Divistaa t power is kept at an High Street, Pottstown, Pennsylvania eundards and opcificauem m ee wtgind absolua minimust ymeedures wiu also unit the interconnection of Dvision a circuite with 19464.

making up the boundary win be reduced from ~ '

Dvioloe 1 power to the valve. the MCC, the _

Afiorneybrlicenses: Conner and -

boundary.The number of active==raaants

~ R$p, and intereonnecting wiring. Wiring and Wetterbahn.1747 Pennsylvania Avenue, approximetely 1soo to four. nerefore. there circuite in the control comples will not be NW., Washington, DC 20006 will be no tacrm im4be probabibty est the involved De proposed mo&fication does not NRC Project Dlivetor: Walter R.

Isolanon boundary atH be breeched effect the capablbty of the ROC system or Butler The current CRD isolauea boedary the RSP to perform their intended funcoces.

lacludes the lasert and withdre'deos, b Ad&tionally, the proposed modification does Philadelphia Electdc %=p==y. Docket acran ducharp vobme and the 'rtCUs.m r

not increees the probable. consequences of a No. 50-852. lamerick Cenerating Station, rok,cause of the boundary will add some of fire se previously evaluated Therefore, the Unit 1. Mootgemesey County.

the supply header piping bst eriu mot affect proPed chany den not ceuw a sign 2 cant Pennsylvania the exhueg equipment The added piping is incrum in the probabmty or ommqueo" saan diameter (2 or lese) comparable to the of an accident previously evaluated Dole of amendment request:Dne 14, (vlously analyed seem nacharp drain (2) The proposed change does not create 19g0 g,,,,,,,, g, p, g,g, g

the possibihry of a new or di!!erent kind of Descripilon of amendment requeytt inside the ledauen boundary remain within occident from any accident previously

%e amendment would revise the the envelope analysed la NUREC Geol.

N, *. bid a n n uin T*Chalcal Specifications ('!Tw) to add

%mfase the proposed changa do not p pued dee new isolation valves to the table of involve an lacmase to the probabuity or functions, the separet6ae enterta, divistond pown requirements, solemic requirements.

Primary containment isolation valves consequenone d an seddest paviously and environa: ental guahfication requiremenu that must be operable and to delete the evaluated 8,he ympmed abasen do not smek es bresently dqsignated valves on the same poulbuity of a new or different kind of of the RCIC system and the RSP except for es.14merick, Unit 1,la scheduled to the brief time of power transfer during a fire accident ima any accident pwtomh event or testing of the transfer owitch when shutdown for the third refueling outege on S*Ptember 8,1980. During the Y

TS changseWItended a

~

utrem a not Durtag the brkf refuehag outage, the licensee plans to take suedit for the newly testausd leolaties time when these requirements are not met, install eight new check valves (four valva on b CRD commen headers.Deee tk poucuan decend periomh wul k provided to answo that a fault in the Dvtalon pairs of valves) on the control rod drive valva and manaetated piptag are designed a circuitry w'll not affect the Dvision 1 power (CRD) supply headers to tlw hydraulic and tnataued la semphanes with all supply, and energisation of the valve's control units (HCUs). These new valves appucable criterta. In addition, they wlB meet Divkion a control circuitry frofe a Dvision 1 will constitute a new isolation boundary au performenos requiremente servently source la aantrol panele is bmited to the RSP.

for the Integrated lAak Rate Test (11.RT), esisting for the approximawly 1 soc HCU Thus, the normal plant operetin will remain soplacing the existing HCU isolation ledationinundernesA eBest the enh within the envelope of analynd ecoditions-boundary valves.Re proposed changes chany wiu be w reduos es metable penetrations tresa 1300 to four. no proposed and es proposed dann does not create the poselbibty of a new or different kind of to tid are to i.nclude tlw new valves TR changes merely embetitutes one teolaeon inTable 3.651, 'Part A Primary boundary let another and therefose anamot accident from any accident previously ContainmentIsolation Valves and to areets a new or different kind of aaeidaas evaluated.

(3)m proposed chaap den act tavole a remove the current valve numbers for from any puhely evdmud significant reducuam in a marste of safety.

the HCU boundaries, s.no poposed changes do not tavolw a his proposed TS &ange reGects a Basisforp

- nos/gnificonf sign 16 cant reductica la a margie of safety.

proposed modiAcetion to provide the ebulty hosords consi fion determinofion!

As discussed in items 1 and 3 above. the et the RSP to eransfer to an emergency power De Commleston has provided newly lastalled valves and associated peplag earce for Se h17e valw in he eunt standards for determining'whether a meet au apphenble deelga to la e

Poww emme fa his valw h lost significant hasards determination exists addidoa, the - -

a pipe laum hande &e ledensa ka==dary vuonale within as e result of a fire.he proposed randibanos deas est a5ect any haines as stated in 10 CFR 50.82(c). pro g hNURECGeos.'N anfety eyeteen settap or other setpotats, or amendment to an opreting conse

,gg,gg,,,,,,,,,,,,,,q,,,g",,, g, WU b W h c --

Involves no si rnificant hazards instrument accurney and drift requiroceents.

t g

De proposed =aAamation skalatales the consideration if operation of the facility ledenen boundarks.Fw&w.es esismic requirements and the envir===antal in accordance with the proposed

--- of the mD eyews is web 9"^h6't6on requirements for the RCIC amendment would not:(1)Inystve a EL'En es system espabihty ler asemal system and the RSP,and the latent of the significant increase in the probability or epwouos, and control red essem sePareuen witeria and electrical divisional consequences of an accident previously pd.

le unaHocted Derefoes, the

• • '8 ECINye evaluated;(2) Create the poselbility of a poposed abaape to not kevelw a reduction RSP 4 new or different kind of accident from h a masgin of safety, aNecwd by te poposed mahAceuen.

crCom. *be propomd abaap does not any accident previously evaluated; or (3)

De staff has reviewed the hcensee's invi/ve a '7" reduction ta a snargin of lavolve a significant reduction in a submittal and significant hasards safet) margin of oefety.

analysis and concurs with the boensee's ha staff has reviewed the licensee's

%e licensee has provided an analysis determination as to whether the submittal and significant hasards of no significant hasards considerations proposed amendment involves a analysis sad concars with the licensee's with the request for the license significant hasards consideration.

determination as to whether the amendment.De licensee's analysts of herefore, the staff proposes to proposed amendment involves a the proposed amendment against the determine that the ; :s amendment significant hasards consideration.

three standards in to CFR 80.82 is involves no algntAcant hasards Therefore, the staff proposee to soproduced below:

annsideration..

Tederal Register / Vcl. 55, N3.12d / Wednesday, June 27, 1990 / Notices 36291 locolpublic Document Room amendment to eo operating license end en eenstetent with wording provided in NRC CL sp4t.

location Pottssown Public Ubrary,800 involves no significant hasarde High Street, Pottetown, Pennsylvania consideretion if ration of the facility gn

gthe, 19664 in acco.' dance wi the proposed ggy,g % g %,,

Attorneyfor licensee: Conner and amendment would not:(1) Involve a Radimeuvity Modw h dwed nk Wetterhahn,1747 Pennsylvania Avenue, significant increase in the probebility or requirement was steepphed. eince this NW. Washington. DC 20000 consequences of an accident previously monitor a mot e edesee point monitw.

NRCProject Director: Walter R.

evaluated;(2) Create the possibility of a h additional proposed Ad=ianatretive- -

Butler new or dtfierent kind of accident from Centrole being added to Ts dehneets the any accident previously evaluated; or (3) essential espects of the RETS beine relsested to the ODCM et pCp as appropriate, such Phlledd Electric Company, Docket involve a significant reduction in a that the eseociated nquirements and Nos. OH52 and 5m umorick margin og ge$

estabbehed safety margins will continued to Generating Station. Units 1 and 2, ne licensee has provided an analysis be maintained nenfore, the proposed Montgomery County, Pennsylvania of no significant hasards considerations changa do not involved o significant Date of amendment request: May 29, with the request for the license reduction in a marsm safety.

amendment.The lleensee's analysis of he staff has reviewed the licensee's Description of amendment request:

the proposed amendment against the submittal and significant hazards he amendments would revise the three standards in10 CPR 80.92 is analysis and concurs with the beensee's Technical Specifications (TS)in

?tproduced below.

determinaUon as to whether the accordance with the guidance specified A.no proposed changes do not involve a proposed amendment involves a in NRC Generic Letter api'metic significant increase in the probebihty or significant hazards consideration.

implement 6 tion of Program consequences of an accident previously Thenfon, the staff pmposes to Controle for Radiological Effluent aduated.

determine that the proposed amendment Technical Specifications in the Relocatma the procedural details of the involves no significant hasards Administrative Controls of Technical RrrS and meteorological monitoring consideretion.

Specifications and the Relocation of program / site boundary maps from'f5 to the Procedural Details of RETS to the ODCM or pCP, as appropriate, and replacing Loco / Public Document Room Offsite Dose Calculation Manual or to them with programmatic controle which location: Pottstown Public ubrary,800 the Process Control Program." Generic satisfy the appbcable regulatory High Street. Pottstown, Pennsylvania mquimments in the Adataletrative Controls 19464.

~ ~

latter (GL! 30 01 eugitwets that licensees secuan of H. do not a5ect plant opersticas.

Attorneyforlicenses: Conner and (1) implement programmatic controls for b proPueed changes do w increase or Wetterhahn,1747 Pennsylvania Avenue, Radiological Effluent Technical decrease the level of radiologicd effluent NW., Washington, DC 20006 g y

)gg Administrative Controle section of TS, Tyroposed change e remon b NRC Project Dimcior Walter R.

Butle and (2) relocate procedural details of geneone etnuent requirenunts for the Main REIS to the Offsite Dose Calculation Condenar Offgas Pre tmatment Monitor PhHaddphia Electric Compray, Docket Manual (ODCM) or to the Process does not affect plant operations. Als Nos. go.852 and 30353, Umed Control Program (PCP). In addition, the requi ement was mimpphed and should not Gae4 SMon, Wie 1 and 1, licensee is proposing that the following have been specified for thle monitor since y,,'88""T g p,,,

,g, TS sections be relocated to the ODCM.

tha is not a releem point monitor.h (1)TS Section 3/4 3.7J, p'oposed change dou not incmase or Date of amendment mquestlune 14.

decmase ne amount of reblogical efDeent gggo

" Meteorological Monitoring Description of amendment:equest:

instrumentatnon." and

• • nt'n*l-e propmed changa do not smete ne

%e amendments would change the E

(2) TJ Section 5.0 " Design Features,.

Technical Specifications to remove the pae a*

Subsection 6.1J.la and 5.14.1b Site

, c, an requirement that the Average Power Map (e)," Defining Unrestricted Areas admed.

Range Monitor (APRMs) have to be and Site Boundary for Radioactive h proposed n changes do not invoin operable while in Operstional Condition Gaseous and Uguid Effluents."

any phyelcal alterations of plant 5 (OPCON 5). By definition Operetional he relocation of the 13 Sections 3/4 conAgureuone, changee so setpoints, or 3.7A 5.1.3.ta, and 5.1.3.1b to the ODCM operating parameters.h proposed TS Condition 5 is the Refueling condition.

is beyond the scope of CL 80-01; changes are coastetent with all the design with the reactor mode switch in the however, these sections are closely sequirements appbcable to the original abutdown or refuel position and with the related to efDuent release sections of the design, nemfon, the propowd changa do reactor coolant temperature less than not create the poestbthty of a new or diffemnt 140' F.He APRMs monitor core power RETS.%erefore, changes to these TS sections may affect the RETS and

"[d**' I'** **F

• • • 'd**' 8'"""d7 from about 1% of full reactot power to 125% of fuH maetw pown.De APRMs abould be processed in a manner similar C.ne proposed changes do not invoin a are not necessary for maintaining the to the proposed changes to the RETS.

Man 1 Scant reductirin h a mar $n d edety, plant in a safe condition while in accution, the licensee is proposing ne propoemd TS changee am to remove the Main Condenser Offgas. edministratin change. in which h shutdown for refueling because the~

Pre treatment Monitor requirement from procedars! detalla of the RKi1 and are sufDcient levels of protective TS Section 3/411.2.1 (Table 4.1111.21) meteorological monitorias program are controls designed to prevent inadvartent since this requirement was originally relocated to the ODCM and pCP, as criticality and fuel damage.%e eppropriate, and programmatic sentrois Intermediate Range Monitore (IRMs).

misapplied to this section.

estufytag the appbcable segulatory the Source Range Monitore (SRMe),

Bosla forproposedno significant hozords considerofion determ/not/on

%"$$,*"Cce trols d TS. Only Refueling interlocks and plant The Commisalon has provided minor editorial chansa heve been made h Procedures each provide protection to standards for determining whether a b wording of the procedural detans of maintain defense in. depth and therefore significant hazards determination exists RETE. nees minor editorial changes do not preclude the need for the APRMs to be as stated in 10 CFR 60A2(c). A proposed abange the meaning of the procedural detaus, operable when the plant is shatdown.

2B293 Federal Resider / Vol. 55, M. U4 i Wednesday, June 27, il990 / Notices Doels forproposed sto eignificonf during OpCON 8 to suppcrt h selety dealga an RPS ecrea er cested red black tf neutron hazartis consideradon deterrninction; be of the NMS and RPL h SRM 6e not a Dux tacmend to be ceipant hnf an.

The Comrnianlon has provided sakty<eleted embeyenes but le important to nmetas the APM opentniny neu6mmeet P ant safety and le reqwred to be operauenal in OPCON 5 would not effect any safety-l standards for determinlag whether a in OPCON L h SRM auheystem prendes roleted equapasst er agulpawat important to significant hasards detarinination exists

& plant operstor we neutron nux kvele ede ty.

as stated in to CFR 50A2tc). A proposed from cartup condmons to the IRM openting ne APRMs provide core poww amendment to an operstmg bcense range he SRMs and IRMe an des to inforrnatnen to the contro1 room operetar and involves as significant basarda respond to local core eenditions would aho proddes trip signals to the RMCS and considsration if operation of the fadhty indsoets and sospand (entrol sed block or RPS as nquired. Also, b APRMs provide en in occordem with the proposed screaQ to en acadast condsban w alugets input signal to the RRG & absence of an the transient ha tim AMs an act APRM input signal'wW act a!!act thsee amendment would not- (1) Involve a necmary to be opereble in OPCON & he systema dunAg rduahag operstions signiScant increase in the ProbabUity or proposed % change wW not alter b cartent Removing h APRM operebDity in OPCt N consequences of an accident previously

.e that the APRMs be operable 5 wW not effed the response of esfety-nlated evalueted. (2) Create the possibihty of a durmg shutdown snargtn demonstreuene in equipment as pnmously evelasted to the new or di!!srent kind of socident froen OPCON 5 when the made owlts le in MAR. The proposed changn to the TS do any==lant previously evalu tied, or (3) Stanup-not affect any ealsty-related aquipment or involve a eigmficant induckian to e ne proposed n chmage twaald sednas the equipment important to safety.

margin of safety.

APRM operebibty requirernent la OPCON 8 Removing the APRM opersbusty and would not affect the FSAR seatuatloa of requirement during refuehng wW ehminate The beenese has provided an saalysis the inadvertent cuttirahrv due to tbs b APRM input into b RRN Howrvet.the of no significant aazards conairierations withdrewal or removal of the higbast worth RRCS La not in service durtng nfuehng %e Wh the request g,, g gcom control rod or due to the Ansertson of fuel automaue entection neede of the 614S is not amendment. The lar=mmee e analysis of bundles in uncontrolled cella The FSAR required to be operet anal danns refuehng the proposed annendawat ops' ist the concludes thei the h and plant procedures Sirs can be seanaally apareted. if required, three stcndards &n 10 CFR 6022 is provide ensurance that taadvertant enticahty independent of the RRCS, & proposed reproduced below:

does not occur during rabahnf changes to the TS would remove the APRM

1. W proposed changes do act involve e ne PSAR elao prenantad two potential operabihty requeensent dunne refuehng signiAcent leeresse in the probabibty or transients darias refuabag with the reactor opersuona. TS require IRM operabthey and coaaarr-of as arcident pronously shutdown. One transient le tenainated by a wm generate an RPS acram or control rod evalueted.

control rod block and the other by a reactor block If neutron Bux Inaeased to the Not requiring APRMs to be operetionalin scranL Neither translant requires the NMS to appbcable setpoint.

OPCOM 5 will not tacrease the probabDity of mitigete the event Removing the APRM No new types of acetdeuts would be landwar9 eat voector arttlaehty during refuehng operabuity requirement in OPCON 8 would introduced etnos the SRMs and IRMe an opershons. (Rdeshes latertechal (b)d the not ineman the consequences of either evellable and required to be opereW &a Neutron Mennertug Systems) (NMSet (SRMs. transtent since the IRMs will etW be operable OPOON L Soth SRMs and IRMs would IRMs), and procedural restncuans provide in OPCON S to generate an RPS scram or indnate and provtde a rod block or scram assursace that inadvertent criticabty does control rod block if neutron flux inctaseed to signal, es appropnete. to an incmase is not emer due to the etmeltanoons withdrewal the applicable setpotnt%e IRMs function as neutron Aux to mitageto e tranasant event or removalef two oestrel ende er due to the a backey protective system to Ris during Furthermors.6 odd the number of aperable inadvertent anserties of e faal bandle teto a refuehng.

IRM or SRM channels be nem than that core locateen wtth a control blade seasowed.

N consequences d an accident will not required by TE the T3 requim that core

& PSAR Section 15.4.1 discusees the be inesased by the proposed TS &ange alteration activities tc, suspended and a!!

potennel for a control rod witanrwal error because of the existing knee of defense winc' insertable control rode be inarrted into the during refuehng and start up operations. b prevent an inadvertent criticality event com.

discuno6am e=d-da= that the setthdrawal of during refuehng. e4, administrative Finally. the APRMs do not have tenettons one coemel ved dose set require a esisty teetrictions. refueting procedures, ficensed which can oeuse en occident osadshoa.

acusa henasse the estal worth of ens control plant operstars SRMs.h and1RMs.

Themfors 6e proposed TS Asopeo de act rod te met a hamas to cause ersticahry. The FurthermoreMboeld the number M operable creeto the possibinrty of a new er differest ettempted erithdrewed of emo controt roda.

IRM or SRM channels be lees iban that kind of =<wadant drom emy accideal proMowly assummg am aperstar surer and a singhe required by T5, the T1 require thet core evalueted active tailure, would result in a control od alteretion acurtees be suspended and all t %s proposed changes do not involve a blod intusted by the &The safety-related insertalde contrei rode be tusened into the eigracant reduction is a margin of salsty.

IRM J y.._ ophid is regelred by T5 to core.

For b reasone discussed in items 1 and 2 be operetste wMle la OPCON S. le deotened to herefore, the proposed idianges do not above and because the TS Baseo do not gamerate e end ties or=== esem os h6sh result in en tocrease tn ther A J/G 4 or discun er regerm APkM oPerebthey during neutsua iba and to theredere a bedup consegmenose of en meMant previamety OgCON 5 Refusting.the peeposed TS preescarve eyeese for the Itis during refudtag. eveinsted, champee do apt insehe a =de=Se==t The PEAR Secess 148.1 A-two 2.%e proposed &angeo do not ooste the reducuon en a enstgin of andety.

potentaal tressesnt eaa<haaa dartag refuehag possibibty of a new or different kind of ne etas bas re%ewed the keaseve with the macser anuaAawa. ne thret is e accident troen erry eeeldent

--t ehttal ad ab*==' hazarda r-contro1 red wuhdrawal arrer during Refuehog evahested.

al d

with the hoensee4 D * ***

7 t

on erbetber the h escued to e a=====8 er inadverteet while in OPCON $ texcept for detoewn Propoeod eraenduesnt tavotves a reecaer eraanient soused by andtsple operster snargin drosonstrettoe testatgt bowever.1he significant basarde consadoretion.

errore or en=9 = - dane. ah6cb te SRMs end gRMe wtD etiB be togetred to be Therefore, Gee staN proposee to mitiseted by a sessaar screa etsmal. Mthee@ operable in OpCOM s. %e 9tMs en oefety-determine that the g d aineodment metther of thsee two seemse es eesamed to be related and are destened to detect and involves no e6gnthatsR besarda I

snitigeted by the NMS, the NMS subeyeteene respond to increases ta seetree Dem within coneOsestka.

(La,.BRMa IBMs) are asallable and operahls thelocal som reglene. Asry h lecc/ PuM/e Dacitpertf Roorrt to generate a rod block or scram angnal II kneweese to mestree thm edushne kh N*n MC M "

I requima detes refneting would originese et a local eere woe i.e.

he esfetygeisted 1RM odbeyotem dihe rod withdrewel errer er feel bendie tmrton. Mgb 9treet MM Pees 7Ma HMS te toquered by TS to be operational TB vequim EtM opere% titty and wtB geneste 1M64 l

l 1

Feder-1 R: gist:r / Vol. 65. No.124 / Wedn*.eday, June 27, 1990 / Nstices 26293 Attorney forlicensee: Conner and incorpoisted into the Salem Unit 1 and 2 amendment does not involve a Wetterbahn,1747 Pennsylvania Avenue. Technical Specifications.

significant hazarde consideration.

NW., Washington. DC 20006 Generic IMter 8528 established Therefore, the staff proposes to NRChoject Director Walter R.

industry wide required actions based. '

determine that the proposed amendment Butler the generic implications of the Salem involves no significant hazards ATWS events.Noe actions addressed consideration.

Public Service Electric & Gas 'n-p ny' issues related to reactor trtp system LocalPublic Document Room r

Docket Nos. 58 272 and 50 311, h reliability and general management Jcoation: Salem Free Public library,112 Genetsung Stauen Unit Nos.1 and t, capability. ne generic letter did not West Broadwsy, Salem, New Jersey Sh C% h W impose additional reporting oso7g Dole of amendment request May 21, nquiremente beyond those already in Attorneyfor1[censee: Mark J.

1990 existence.

'Netterhahn, Esquire, Conner and Description of amendment request

%e Commission has provided Wetterhahn. Suite 1050.1747 Public Servios Electric and Gas standards for determining whether a Pennsylvania Avenue, NW.,

Company has proposed to nvise the significant hazards consideration exists Washington, DC 20000 Salem 1 and 2 Technical Specifications,

(?O CFR 50.92(c)). A proposed Section 3.3.1. Table 3.3-1. Table Notetion amendment to an opersting license for a NRCPmjectDuector WalterR.

Boun triple pound symbol, to specify the facility involves no significant hazards surveillance results that require consideration if operation of the facility Southern California Edison Company, at reporting under to CF1180.73. This in accordance with the proposed al., Docket No. 80 306, San Onofre change replaces the "immediate" NRC amendment would not:(1) Involve a Nuclear Generating Statica, Unit No.1.

notification requirement for reactor trip significant increase in the probability or San Diego County, California breakers (RTB) and reactor trip bypass consequences of an accident previously breakers (RTBB) that exceed any evaluated; or (2) Create the possibility of Date of onwndment squest June 5.

procedural acceptance criteria or trip a new or different kind of accident from 1900.

forces that exceed the recommended any accident previously evaluated; or (3)

Description of amendment requeste upper limit with a requirement to submit involve a significant reduction in a Proposed Change No. 220, which was a written report within 30 days in margin of safety.

submitted by Amendment Application accordance with to CF1t 50.73. Also, the ne licensee has analyzed the No.183, proposes to delete IJcense conditions required to be reported have proposed amendment to determine if a Condit;on 3.1, and convert its been defined as:

significant bazards consideration exists: requirements into Technical

1. A RTB or RMB trip failure during

1. Do not invoin a significant incmeu la SpecificaMons (H).b foDowing any surveillance test with less than or the probabliity or consequences of an changes are proposed by the licensee:

equaI to 300 grams of wel$t added to accident pmvlously evaluated.

Lcense Condikon 3J./f/

N pmped che det aHect b Thk he odon umiu h W the bmaker trip, or present level of breaker surveillance testing connected toede on each seeel engine to

2. A RD or REB time response or maintenance. ameken faums to souefy

a. coo Kw imaxunum) and hmits the number failure that results in the overall reactor the specified surveillance acceptance criteria of engine starts.etope between diesel tnp system time response exceeding the wul require oppmpriate action as indicated in crankshaft inepectione to fifty (maximumi.

Technical Specification limi'.

the Technical Specincations.

h proposed change tranefers some of This amendment request is a complete Thenforo. it me be concluded that h the aquirements to Technical SpeciDestion rev'elon of the December 27,igeg pmpond change on not involve a (TS) 3.7 " Auxiliary Electrical Sapply," and request The proposed determination significant incrum in b probability or the remainder to lli 4.4. " Emergency power consequences o an accident previously System periodic Testing? The proposed that the December 27* 1900 "9uest ovaluated.

chance permite starte-etops associated with involved no significant hazards

2. Do not cmew'the pouibility of a new or engine openuon at 300 rpm or len to be considerstion was published in the different kind of accident from any ecoident excluded from h lifty stans-etops halt.

Federal Register (55 FR 6117) on previously evaluated.

Ucenn Condiuon 3JJ21 February 21,1990. The May 21,1990 m proposed change dow not advenely This license undiuon requires that a &esel request supersedes the December 27, affect the design or operetion of any system maintenance and surveillance program as 1989 request in its entirety, or component important to estisfy. No oreviously described in Amendment No.1:3 Basis forproposedno sign /ficant physical plant modificauone or new be implemented.

openGonal mangursum wGl rash from N propowd change transfon this horcrds cons /destion determination Following the Salem ATWS events of

"".Nn. It may be concluded that the EuYt g

on r u a in 4

February 22 and 25,1983 PSEAC proposed change does not create the which to superceded [ sic] by the newer tmplemented extensive revisions to the possibih of a new or different kind of requimment.

maintenance and surveillance accident any previously evaluated.

Ucense Condiuon JJ/3) procedures associated with the feactor

8. Do not hvolve a significant reduction in This hcense condiuon incorporates by trip and reactor trip bypass broskers, a margin of safety.

mfmace b recommendauon made by the Since many of these procedural changes

& pmmat margin of safety is matntained, g Di &ewi generator ownere group to perform etnoe breaker maintenance and surveillance a major overhaul on each diaeel engine once were prototypical in nature, they were enung b enaHeckd. N propowd change every ten years, broad in scope and contained very conservative test and acceptance

,,pfe the schni ce criteria. Additionally,because of the gauned a nouficauan reqstremen with h 8"d" [ $

[*[ '*'

safety significance of these events, the normal NRC reporting =~hau-epecined This hoense con &uon requires that oil NRC imposed conservative reportability in 30 CFR 3c33, holes in main burnale 8 trough u en each requirements to ensure timely The staff has reviewed the licensee's diesel creakshaft be inspected for cracks at notification of hardware related submittal and significant hazards sech plant refuehag. It requirm inspection of deficiencies. Dese additional @m L, analysis and concurs with the licensee's additaanal critical areae et each major engine requirements were subsequently determination that the proposed overhaul. It requins that if cracks an found.

l

---

m-memimumm----me.i-iisn--en-mim

-mie

26294 Federd Ragister / Vol. 55. No.124 / Wednesday, June 27, 1990 / Notkes the engine be considered inoperable and the cracks For detalls regar&ng this expenment, accidens frem any maha8 peesteusly NRC be no6fied.

ese Atte& ment 1 to this proposed change.

evaluated?

The proposed denpe trenefees these (3) Engine startgrtop eycles with etigine Aesponse-%

requirements to TS 4 4 speed lees then 300 rpm need not be counted he proposed danges do met affect plant Ana==. Candream U/5) toward meetang hoemee eso&uea 8 41). tf equipment er plant operetHme other than h This beenae canation requires both SCE demonstretse that the stroeses toduced dinels and their operetion. He proposed cyhnder blocks on each engine to be la the crankshaft et startup and coemadown changes are designed to impeove and penodicauy inspected for cracks it prendes an less than the &eco KW oneedy state maintain &eset rebabQ1ty.Thry do not additional tnspection requiremects for the valuet inclode any changes that go beyond the rigM cybnder blaci of &esel engtne no 1 that The required analyals has beso congslated.

lasues oseend to the NRC's nefety has a degraded onwestrwetun. h epecifiee Atta& ment 1 to this proposed change evaluation { dated hvember 31, tese) that if certetri types of cracks are found the pnsents e summary of the modts.

Bened on this in!crenalian the proposed ergpne be consuLrod inopenble and the NRC he crenkeheh stresses deing 6dle speed change wfD not create the poselbibty of a be notifsd, startup (0150 rpm). idle speed operetism (160-new or e 6ffennt kind of accident from any The proposed change tranalere these 200 rpas). and coastdown from idle speed occident prev 6onely evelosted.

requirements to TS 4.4 were analysed name stresses were

3. Quesuon WG eperetton d he loc 9 tty in Ixense Conoition M/8) ceanpared arttb the omakshaft stresses accordance arttb this preposed efiange This bcense condithm specifies :het all prenously emlMated by FaAA ice feu need invoice e segnannam enrheekwiin a mergia af diesel starte far testag and surveillance be (6.000 KW) steady state opers5en safety?

slow starts, i.e. taking mon than 24 seconds.

["Evaluat on of Transient Con &tions en A,spo,me b except where e fast start is required either by Emergency Diesel Generator Crankahahs et h proposed changes aEast only the the plant TS or for speede maintenance San Onofre Wcdeer Generstmg Station Unf1 diesels and their opereuoe.ney are 1, FaAA44-1344.Rev.t4. April 1985) in all designed to improve and maintain the purposaa.

cases, the taH toed stesses een lomad to be rebebihty of the 6esels.%ey do not he prwooed dange trenefers thas requirement to TS4.4.

hqgher-introduce any new salvey tesees. As such, W Laos MAmh emoks es deep m 1/4 they do not knecen e algdhcast vedecean in Bosts forpropeeed no significant enciwon amansty,it he penible a margin of enfaty.

hazards consideration determination:

that impunnes, erhach ensult from angine The NRC staHhas seetewed the As required by 10 CFR SOSile), the apention or o9 manufacture, may heve censee.e ao.

M- _ g m

I2cerisee has provided the followtrig no contrtbeted to creek initiation and conshmo hises and agrees signiftcant hazarde consideretion propagetion 9CE ebodd thenfore review detertainetion:

and make appropriate reviserts to tee thesel with the lirumame*e analpels. Therefore,

1. Questaan-WiB eperstica et die tecnity in ou mainteenson precedures, the NRC stab gunpname to detersdne accordance wtth ene proposed change he dessel eel====rdmn teettag and that the amenchnant selfmest invoiese no involve a sigmficent snerseas in the analysis proondere has beam sevtewed. m significant hazanis consideratsam.

probebihty or r===renose af as accident evideaos wee found to =Am= that the local AaMic Derurnant Room a

prenously evaluasa4 6esel oliesed by Sea Qaedre Unit 1 locatsart MainUhrery.Utdvaralty of Aesponse: No accelera tee stress enescoton eracidag cr balk Cahfornia, P.O.Bam 18867.arvens, W funcnon of the emergency &aael corroeAen processes. A seviser af the oil Cahfornia 9513' generetors is to provide AL poorer lur samplag and analyses methode shows that "b

eccadent rnityanan if o!!aita power to the the total base mand =r and water content of Kocher, AssistantCauesselCounsel,and plant is lost An improvement in the the eu are wtthan -=

% hasittThe rehabdaty of these damsels As therefore cuakahan matenal be the n=a===== Marl James Booletta Esquare.ficathern beneficial te % plant and will not increase hardness value and yteld stength to remet Cahfornia Edisce Cacapany.PD, Box the probahIhty or consequances of an corroeeso in e esifide bearing envir====*

800L Soseatsad.Calliornea $1770.

accident previously evalustact h purpose Key ou paranneters am ereseled No changue NRC pygpect Oweedor$4mT,Larldne os the eh &esel hcenae con &uone was to to the proceares ese ceneidsed===awy (Acting) improve and maintain the rehabihty of the For ed&oomal dotatie regardens the reetow.

&esels by ensuring ht certain operahonal see Attachment 4 to this proposed change TenneesesVaBey Aatboatty,Dodtets netrictions and maintmarn and Based en the above infersnatina, the Nos. 80159,2230 sad 984B8, Browns surveinance recommendatiens which won

% c 7 of bonnes eambnes aMk as Ferry N=rlane Plant. Units t1 and 3, the resatt of b owneze group effort are modified by this proposed change for tung UmestoneCounty, Alaharma

-i tmplemented. b proposed change wm te a appt a-ha= eee acomptable esd wW est enswe that this continues to be b case.

e aversely hopeat demelenhaMey ear D0f8 ol'mandmeestseguesis:Apru 19.

Ucense conomon 34) was imposed by increese the prehehehty er esaparp==r== et 1990 (TS 279) the tGtC on a temporary besis its purpose an accident proweeely evenantesL Descr$nties afaansaament angeesas, was to ensure the interim reliabihty of b Ucense Consktaan 8J438 esquiree the

%1s amanAmaat sevises Browas Ferry

&esel crankshafts while the ?GLC eres implementabon of a maprehenalve abssel TechnicalSpeci6cahons Uqdd eeunp6etmg its review of the owners 3 oup engine malntenance art survedience Radwaste Elament Flow &4easureement.

crack propegotion analyets for h progrant & proppene change makse title

%1s amendmaM reanoces teler0BCS 8o crenkshafts Stace trea.&NRChas requiresent a past of the Techstes!

fixed in ne roteaseler which is ao completed Lts review and documented b Specific.ua== With ehle aberge, the diend remauung &esel rebebtitty teenes tn a eefety inspecuam aqdreament inund en enestag longer used lo saceitor the liquid evaluation _ jdeted Movember 21,itse. TD1 Techrucal Specificetion 4.4.F orul heeone redwasto aHhsent Goer sete as acted 40 Diese crurasheft Crotting Problemi superheim and we heu.aad The saatm Tahle 3.2.D of amTachaical The selety evennetkn1eeds to the chaags se esendered mM=tas etive. ad tsel Specifications for Unita 1.3 and 3, touwhis endeskne:

not tasmonee the prehabttity or eene% wee Basis far aoaigalficant (1) Operetion of the seeels op to troo WF of an acc6dealpreetemely seekasted.

/tazards deterraisodios 68""'Pt* W 8r8'* k8ngtent b propeesd chaages eeneates to license he f'ammlanlan has provided 41 A asnksh=# inepectwo intensi of f!Ry con &eans 24) through a4e) e elee etandards for der =M"I whashar a start 4 top cycle. La acceptab6e for the long ed===%e and erm een escrease the eWomat hazards Mmtios aMs term. If SG dessenetntee that h eddy probabibty or consequences of aa arrMagt as stated in 10 CFR acLa2(c). A proposed curvest tesehns (EC9 te&seque com detect te prevkudy eseleeted.

mil deep==^=

3. Quesues; WG er==sta= ef the isolkty is amendment to an opersung hamam nemma

" neuhebe,eabewn ecoordemos with this prqposed change messe involves no abrate-haaside then aCr es osymble of disseeng s na esop the poestbOLty et e meer er 4t!Isrent11ad af considere11ans !! aparation af abs lackhty 1

Feders! Register / Vel. 55. No.124 / Wedneeday, luna 27. 1990 / Notxas 28395 I

in occardanos with the proposed Duecr:prien of ar==d==at sepassas-swane of ovesponsertset6ee poema-= ese amendment esoald act (1)lavdvs a BFN Units 1.3 and 3 technical provided in the been.De RHR sestao la est significant lacreaar la the prr.hab0ity or speci$catione (T$s) are behus ebmiped required becease there is no bish sammy consequences of an ecuadest pn3riously to: (1) revise Table 3.2.B and unaltag potential to breach the torus in the enid evaluated, or (2) Create the possibikty of Conditions lar Operatkin (140) SAR.21. j gfan GE a new or different kind of accident from 3.5.E.1,3.5.P.1,3.5 G.1 end 3AD.1 to Standard T$e (NtJREG 0123) en accident previously evaluated, er $3) clarify eqstpment operebPJty Change 2 is a more sonservettve involve a signifscant seductasa in a requirements when the reactoris in the requtmment.De RPT erstem Festdes en merpa of safety,10 Cf1t 30.r1 regaarse cold shutdown condition or during autometic trip of both recirculation pumps that at the time a leaanas rapseste an performance afinservica hydrostatic or after a krblae trig og a generator need reject, amendanent,it arest provide la the ankage tests;(2) revise the maximum

%Is reduction in Coer lacreases the sere Commiss;on its analyses, using the opera ting power level allowed with en - volde end providee imunedacte megetswo standards in Section 50.92, on the issue inorarebie Rectpcaalataan Pump Trty nectMry to mdece the newny of the cf no signfficant hammis consideretion.

(RPT) system (s) from 65 pensat to at transient.%em ass two RPT eptma If bash.

Therefore,in accontence with 10 CPR percent power; and (3) carvest two RR eyetse are inowmble w if one RN

, system le knoPerable for mon than y2 houre.

60.91 and 10 CFR 50.p2, the Beimoee has typogrephical errors la Table 3.2.B.

i

. performed and provided the following Basis for edao eigrt/ficant

"**',"g",,"

,3g v b g6 4

enalysis:

hozords cume, on 4.m um.=""

De proposed value of 30 percent poiser is 1 The propoemd mah does mat The Commission has provided eoneistent with the BFN RPT analysts ord b involve a signincent hcrease in the standards for determining whether a BFN IJpdated Final Safety Ama?ysis Report.

probabiliry or consequences of an accident significant besarda consideration exista

%erefore, thle change tedves me =f-a---

=ia,.-.

[

as etotad in10 GR 50Jt:(c). A proposed inoesee in the p ' '_ % ee -----

prfo-d he menstortes leap med dass amendment to en operatinglisamme of en accideas revimmaly sma)yend.

act affest the hurtman, apsseman,er involees no signintent hasards Chenge 3 le as adminnaaresse chmugr that queh&setum ei any --pa===aa assosassed conalderstiene if operstka al the factbty cenah tyynyoptecal emes.

with the sedwaats syeaam. nam ase ao in accordemew wtth the psoposed 8.De poposed thange dess % del occidensa previous alustad which would amendment would poet (1)levolve a

• ["g*

en

' gg - _-__

s'@t inavese in the probebM_er evaluated Change 1 does not inv.olve 8

8 ne,r. posed s.,da rd.us.et

=aa me=' ar - a=*'e=t. --e

-s,imit =erdw-ver me eu evaluated, or (2) Create the possib!Bty of operance from thet curreo9y pecesed Me create 6e poss(btDty d a new or qE5e.mit kind of asedsat prev 6aanly evolunted he a nm er sliHarent kind of accident from changes am sten 6cetleas to ne to heesar epgredme of the emeang ::- '. mhand an accident previously evaluated, er (3) performaame of regehad 75 teths web er Dow awasartig laearussmaananen has no Involve a algnificant sedactronin a reacter la the sold abasdoum r=ade==- The impact se any omisty sehnad f==a= af margin of anfety.10CFRIa81sesparea swthods of performa-are consistent with the redwesta ayesam er tu nasociated that at the thne a hemmaae roquante am bdustry pastes.

equipment amendment,it must provide to the mange a wW ensure het when beeRFT systems are lamperehls er when oma BPI

3. The proposed mes-hnant does o%

Commih b 8"h ", on the issue b8 h system is tnoperable more than y2 hous, tzvolve any migeficent mductice > e usargh standards la Section 80.92 reactw pown le dnappd 2 a levd osumieuct of medpey. Time spyeding of bar = _ ",

related cc-r--a= enit est erme the of no significant hazards consideration.

with b analysis priormed for he RPT scoopenase launt nur esy anc*.asma ammiyuan to

'llerefore,in accordance with to CPR hetanetian.

be exameded, ser dens it e'ange say maaseen Basi and 10 CFY 3aE2, the licensee hea Chansp 3 eserests two typographical surers of asinty.nis shaage u;41 have no aflaca en perionnad and providad the following so the T5e wm be asse constatent.

the -tzamane or flow rates of analysis:

8. The proposed changes da not innehe e radioactive emuents and wm enhanas TVNs 1, m pr,p d,kaag== de aat beebes a sign!!ncant seduction in the amargia of enfaty.

ebil to monitor Dow retee to serurv signalmana hisseess la he pebender ce Chaags t clarmas egnfp-aan operabDiry camp 'emer with to GR 38.

consequentaa el on mondeal powianaaly poquiresments with tbs teactor la One enk!

The plaff boe reviewed 6e $cenese's

, valuated Gange 1 ebanha espalpment sheedews mandahan er durine pad-namen el no significeral besordo ceneideretion operebthsy seqpartensata with the esectar km tnearnse hydrostatic and lankage lasta.

determinaties and spare with the the sold awa e eaah or destas

. Sumdaat enkty ann 6p===t is ati!! avenable licensee's neelysis. Thessiseu, he seeff performance el taaervisa hydmetasia and to ensuse the fuel remains covesed,ones ha proposes to deterndne that the neakase testa. With 6 ructor to b onid alw event ollmakas k does not sedians b appbcetion for amendments bryolves no shutdown ea-h pinary system energy equipement availabia to mLtionaa mi amea a is uninima! and 6 contmle rata ese imented and es mesh dona act aduon 4tm mangia of sign!!icent hazarda considerations, Reacter peasure la==any me==pha u enfaty.

gg g

except darias perfosmanas oflamentos change a is unsee asaansattwo then the

%,,,. g na g %, g hydrostatic testa. inservica leakage tasta, and cument TS, When the RPT systeals Stmet, Athens, Alahnaam 35411-Intepeted1aak Rata Testa 01JtT1.Mia inopesebla b naami=== allowed seasser Momeyfor hoenses:Gemoral change wouldinhIbit b dryweA high power will be sedmand. nia is eenaisteet Counsel,Tesnessee valleTAnthority, penause insmammits whidi asumian a deemst wtth es andrets partanned ter me RFr 400 West Rammmit Ftkl Drive, Ett 933, primary eysaam leala Wuh minisiet eyeten - Insenastaan and the FSAR and does set KnoxylBe,Tammessee sygott.

enessy and no steam g--=S= dde &meteen eeduce the mangia ei saisty.

NRCProject Disorder-Prederick J.

le not required The High Pseemire Canisat Change 3 is an adsdaistrothus abange Hebdon.

Injectica SIPCI) and Raacter Core belation which does not enduce the maasta af safety.

Coolins OtCIC) syntame are not esquimd 8bta5 bas Wed Mauman's T-Vainoy Aashadty Dachats because them is no assam eupply to operase no Mgnmenet hamude "Nthm Moe,O N et,S H g8 med50 35 Emeuse them and Ree& dual Heat Remove!(RHR) and Ferry Madeer Fleet, Umke 1.3 and I, com sprey em operebk and espeter of de6enannetion and agrees with the 8 "'*he*P ' ""' dl**l* ** paeset licemase e ensheia.Therefore, the saa5 DunestoneCommty Alabeano Pridh b

6 fuel bout binne omossered.m a-a

, proposes to sisterudne that the Dude of===d====* sogenents: May 14, c,_

-uma ayuamm Ds) and smahat applicetioe for mem-d-ede invebees se sees (Isago)

. v ivee en nas negared benmuse elseremer.

eignificant beseeds r===ista saiana, i

l

{

i 38296 Fedeeml Register / Vcl. 55, No.124 / Wadnesday, June 27, 1990 / Notices Local Asblic Document Acom consideration. brefons,in occordance applicauon for amendments involves no l

Jacodon Athens Public Ubrary, South with 10 CFR 80.91 and 10 CFR 80.92, the significant hazards considerations.

l Stmet. Athens, Alabama 85611 heensee has performed and provided the LocoIPublic Document Room Attorneyforlicensee: General following analyele:

/ocation Chattanooga.Hamuton County Coursel. Tennessee Valley Authority.

TVA has evaluated the proposed technical Ubrary,1101 Broad Street, Chattanooga, 400 West Summit Hill Drive. Ett B33, specincetone (Ts) change and he*

Tennessee 37402.

Knoxville, Tennessee 37902.

detersuned ht it does not repreent e Attorr:ey forlicenar@nral ARCPrefectDirector Pmderick].

gcent Quan Counal. Tennessee Vaney Authority, j

o

-d on 400 West Summit Hill Drive, Ett B33, Operetion of Gequoyah Nuclear Plant (9QN)

TenamesseVaBey Authority Decket in accordance with the proposed anmodment Knoxville, Tennesseg 37902.

l AWC Project Duvetor Prederick ].

Nos. 86 327 and 80 328, Sequoyah will not Nuclear Plant.Valts 1 and 2.HamDion (1) Involve e significant imoresee in the Hebdon.

Cosmty,Teasessee

'g,agmes d en %t Tennesame VaBey Authority, Docket No.

I y

Date of amendment squeste: May 21.

TVA's proposed change to TS Table SJb 2 80 328. Sequoyah Nuclear Plant, Unit 2, i

l 1990 (TS 9014) does not change the contatament teoletica Hamilton County Tenneesee Deecripuan of amendment requests:

function for koe valsn. no salve Date of amendment requests: Mey 21' he Tennessee Vall Authority (TVA) chanpout from air. operated FCVs to 1990 (TS 200) proposed to moddyb Sequoyah soienoid.opereted ITVs was evaluated under DescWpuon of amendment squest Nuclear Plant (SQN). Unite 1 and L TV A4 to CFR 8038 procas TVA's evaluettoe determined that an underv6ewed he Tennessee VaDey Authority (WA)

Tuhalcd Speciacadone (TSa).The oefety question does not exist.This proposed to modify the Sequoyah d changes revise valve

$stum in H Tabb 42, chanpout le required to suppaet TVA's Nuclear Plant (SQN). Unit 2. Technical commitment for Regulatory Guide 12 Specifications (TSa) on containment Containment leolation Valves.%e comphance. Th lastauabon of FBVe with Type A or integrated leak rate teste somenclature of14 sem ling valves in totaDy encland red swuches pwides (CilJtTs).De pruposed change is to add I

the '!Tr table would be aged from environawntal quhficanoe of thm valves

" ' g""'gy""** D9"#

l

• g"I".6.1.2(b) regarding accelerated Bow control valve (TUV) to flow soeultms in taproved rehebuity for CIV (SR)4 solenold valve (PSV). he Unit 1 valves position todacatina duttas and following an CI1JtT test schedulee. he two testa l

were changed in the recently completed accidentsTh closure haes for the FSV Unit 1 Cycle 4 refueling outage. %e Unit design also pmvides improved holenen Performed on Unit 2 during the Unit 2 2 valves will be replaced in the

'"ponse times. In addinos.10 CFR sa Cycle 2 refueling outage (November l

Appendix ) leak. rete criterte for the FSve 1964) and the Unit 2 Cycle 3 refueling mpcoming Unit 2 Cycle 4 refueling will a t be compmmised by this change outage (March 1980) were closetfied as outage scheduled 2 begin in Ocuber Consequently. TVA's proposed TS change failed tests. In accordance with SR l

1994 does not i..cmase the probabihty or 4.6.1.2(b), these two consecutive failures 8

I88 * 'd*** p'"I'**IF require an accelerated test frequency.

,,"'dets onein Ng $8 g

TVA e proposed TS change mquesta an l

its submittal.TVA provided the (2) Creets the peuibthty of a new or a

o esPmPosed ddie awident ime any

[g',

pr,1

,y g, g.2. I e U lt 2

_The chany la valves to aamadated with TVA's proposed change does not introduce Cycle 2 and Cycle 3 test failures.

4 plant marbhabens that support TVA's the poulbthty for e new or different kind of Without this change, the accelerated somminnent for upgreding SQN Unita 1 and 2 accident from thoes previously analysed. %e test frequency would requin a Unit 2 to meet the guldshmee of NRC Regulatory proposed TS chany was evaluated ander the CII.RT in the upcoming Cycle 4 refueling l

Gelde (RC) 12. "Instnamentattoa lot a.ight to CFR 80.50 process. (he function of these outage which is scheduled to begin in Water. Cooled Nuclear power plante to containment teolettaa valves is not being October 1990.

l Assees plant and Emvtreme Condit6ces During abanpd.)TVA's evaluation desersained that w,,,, Zed no significant Sosisforp I

uon determinadone in i

and Followtas en Accident."-

there is not hopect to sove comiawt De 14 ott.eperated FCVs as heted in SQN Integrity er contatament teolanon tune. No its submittal.TVA provided the l

Ts Table s&a are belas replaced with FSVs.

new failure moda are introduced to the foHow ing information to support its SQYe current FCVs have bait switches that system and/or componente, themfare no new are not savtreamentaDy goalifnable. The

,mandysed accident ecomertos are created by Proposed change to Unit 2 TSe:

t TVA has evaluated the Type A test results valve stroke le too eme11(3/8 tech) to beve this change.

in coeluncuan with the parucular condations funct6onal and environmentauy.quehined (s) tavolve ea-inereduction in a halt swildes. Therefore. these valves wQl be margin of safety."

that caused each of the Unit 2 CIUtT fa!!arve and hu determined that the inanseed l

wplaced with FSVe that are totally enclosed The proposed eenge fman FCV to PSV to surve anaa frequency would be l

m and have reed switches toternal to the valvo.

Table 3.6 2 will not affect the metainment biappropriate. he leakage test results from lius changeout at SQN le required as part of teoladon funcuoe for theos valva. Time each of the Unit 2 failures were below the

{

TVA's commitment for comiplytag with RC change in valve design from air operated to manwum analysed leakap hmh (W lt im (refer to IJoense Ceediuon EC.(241 of the solenold operated provideo an should be soted that SQYe TSs contale a l

SQN Unit 1 Facihty Operating unenee DPR*

environmentally quahliable valve.resulting conservative leakage hmit of 455 la Test Pr and ucense Coodluce 1A(14) of the SQN to improved CIV postoon indiceuon voeulta, along with problem identificatloc.

Unit 2 Facility Operettag uneese DPR 79)-

poetace6 dent. %1e valve chanpost wtH act have demonstrated that a general

,I The Commiselon has provided impact the 8. and 10.eecond maxtmum containment leakase problem does not exiet.

etandards for determining whether a isolauon tune requimment in TB Table SJs.t The perucalar enomuono that canud each of significant hazards consideration exists Therefore the poposed change does not the Unit CIUtT failurse were positively as stated in to CPR 80.82(c).10 CFR reduos the naargin of safety.

f 80.91 requires that at the time a licensee he sta!! has reviewed the licensee's e Ian dira i b me requeste en amendment,it must provide no algnificant hazards consideration of b CIUtT failures to preclude recurrence.

l to the Comnueston its analyses, meing determination and agrees with the A detailed description of TV A e corrective l

the standards in Section 50JB2, ce the licensee's analyela. Therefore, the etaff actice plan to provided to the tuetifiestion for leeus of no significant basarde proposee to determine that the chane provided below leubmittal). Band on

__j

Federal Regleest / Vol. 83. No.134 / Wednesday, Jere 27,1sipD / Notices 2G297 the improosasah new eestehad hs TVA's No meditesem le hets made to EPIPs contein conservative eveempeone cui esupled eth the foot has he any eyeten as a nouit of this stessa.

to be used for setpoint calculations such feHed met was below the massamm

'Ilm proposed radaa from the husessed as worst case dispersion factare.The emetysed inekaan, TVA has doissalmed that frequency regidrement ter Type A teste dans proped changes M nntilauen and inarnaaise the troeuency of the Type A test la mot aller say acddent analysis er say seemedance with Elt 4 A1.Rb) would met sesemptions esed to espport the anddest promas vant setpoints, Hi and Hi Hi, provkiea -...

" ;incrosse to the treel analysis. TVA has implemasted a especese IePasent sabotaatial redoctione (W l

el sonadenes for descostrating Ualt 3 oction pies that to notended to prowet on the order of 2000) from the carnetly

(

coensisement recurmace of pewtosely identilhed opptveed setpoint values specined in b addaans a obsee.TVA has probisme het were assuenaered the NA.1&2111. Decense the TS action eumleeted the hardships and hpoet of met two Type A test en Unis L statement a!!o9ra & more conservetive perturning an increeeed troquency CILAT the poulbshry of a new er ddlerust klad of setPoint, NA 142 have been oP8 rating t-duttag the Unit a Cycle 4 refuelles saaess.

meddest is met arosand, l

TVA estimates the eset for estep teettas, and (3) Involes a eip1Gaani reductiaa ls a with lower setpointe based on b EPIPs.

recovery to be approximahley 32eD.eutL This mergin of safety.

- These setpoints were calculated with den not enchale ;--A -

power emot The marsta of safety by the the use of the Xe.133 dose converekm l

amodewd web the g. to oder addntonal alloweble sentninment nest its.73 3.a) factor spect$ad in Regulatory Gaide downtime. Omriest eethmetes of he sweently esseelmed in TSe remotas 1.100. Aleo. the ventilation verit and replansmant power seat destas the imE and

,

• The as left [CW)lenkeer enlee process sont monitore have been winter months (Unit 2 Cycle 4 refuehas will etdi asse this hatL The asamme of the

& to muldply ee concentredon estase ps) whsdaled tram Osuher to pahimne enmaammd dwho te gnwim

" 31 two Type A tests af SQN Unst 3 tedssanos that bY the flow reta. Releases would Decemberisso)wouldbe Tom meneta'ry a ganaral =amat== ant leakaga prehlem dans therefore be reported in 10 curies por milhoe Consequeedy, base options. TVA eseeldove the request for reRef not exist.TVA's corrective action plan second (micro C1/sec), a unore relevant tree the T5 IIt te he oesnomfunBy predset.

directly addresses the identifled probleen maamure than the currently spechd 10 '

N Commission bee provided 8'eas to pmeent eacermaca Therefore. them curies per cubic centunatar (micro Ci/

standards for determining whethera is e algruncent ruheta ki he marsk of ecy signincant hasarde eeneideretion eufste

• • d sta5 has reviewed 6e M I

D ***IUT 'edwater peasp turbine as stated in 10 CFR 50.E2(e).10 CFR exhaust mondtor and the maka steen d

monitor setpoints would aloe he svelsed 3,,,,e,.,,,,,an,dr',w,,te,te, wee to cha pe * *e mPe. mee 8021 requires that et the tkne e licensee 6am

.,_. wme nent, R meet,,vvide

,, e to the Commiselon its analyses. weing propom h dormine het he monitore would be asededif the the standards b Section 30.82. on the application for aseeh brehe so secondary system was arverely issue of no eisnib-t baserde signhant hasards seasideratione, contaminated and the terbins+ewered consideration.Derefore,in accordance y py g %,,g g,,,,

annihary feedwater peep er the mehe with 10 CFR 8031 and 10 CFR 50.92, the locarden Nttanoege-Hasdien County steam safety relief valves were need.

Scensee bee gesvided the foDowing 1.ibrary,1gD1 Eroad Street, htsmusega, N Hi setpoints are based on the stas analysis:

Tennesses 37402.

area emergency artterta spec 1 Bed in the TVA has evenseend the proposed enkeleet Athnser#rh Comenal NA 142 EPIP 4s7 and the Hi HI I

opedscatism (TS) eksess ami hoe deenradmed Counsel Tennessee Vaury As&W setpointe based on general energency l

400 West Summit Hill Dries, L11 Bas,'

criteria. De setpoints were calculated arteesh establahad in so cra saaa(ca. Opassues og KnoxvGle, Tennessee 37502.

using the Xe 133 dose convere&on factor wl6 m,ah Wel== Plant (SQN)in

a==A==

/SCP)ojistW Dhessor:Preslerisk J.

opecified in Regulatory Guide 1.100 and seauey

%.,===t====swe not Hebdon dispersion factore from EPIP 4.10. Flow (tileeoln a mismar==t temmens h the rates for main steam and auxHiary probabOMy er euesogesums of am sandent Yksinia Electric anni Power Campany, feedwater pump turbine exhaust remain previously m Docket Nos.sHas and 58 338 North

---+-j g,ein the original emicale6en.

The regnested shamse done ese engehe a Anna Power Statism Limits No.1 and 3.

go j,f,fp,

,,ajgnjfjcang physical =damm-to any phmst syeamm Emes County,Vbginia M cons

'on dirArrarinatiarr

• • [,[g*",'g*',"es"salesensd JMa nf h=* segesedr biay 18, W Commisefon bes provided d'"

l A

east frequency b hesed se the fact that the 1EW standards for determining whether a meamwed es.leend leakage reten Ier both Mesenktion a===A=aust sequest-signtScant hasards considers 6cn exista Ueft 2 CIUtTo were below the setety analysis N propeesd would update 6e (to CFR BO.32(c)). A prvposed hmit of 1A 14. The empismesteese of TVA's high sange eElvent enantter alarm amendmerit to an y...e license for a e

8h* oet emmes )he pubisme ties smalmd setpolate in Tabis 3.M of the Nut facility involves no afsnifiestit bassrds sorreceve seeks en h tseemdsd er emprest Anna Pweser Station, Llules No.1 and consideretion tf operation of the facility h the timet aType A met leemes TVA's No. 2 (NA-142) Teeknical ag=ces-tisme in accordance with the proposed U ",,',*8", M Yg,,'", g" (TS).The high range e(Deest momhere amendment would not:(1) Involve a and k "--d a he ame appsepsham and associated T1B won focussisted he significant increase in the probabDfty or than perfonnanos et two sensemafve sosponse to NUREC.er37==*4==t consequences of an accident previousty successfut T3pe A leakage teste tia, monitsstag requirements. The purpose of evaluated; or (2) Create the poselbility of increased f.

J A gamura!==*=8====e the "Hi* and "75 W alsrens wee to alert a new or dfHerent kind of accident frost laakase problem does not exlet the control room operators of the any accident previously eva} sated; or (5)

• • • 8" " '8hr**8 " "

test impending ased to declare e site eres er Involve a sign!Acant reduction in e b the TSe h me behg shmem4 Thedme, general sawrgency.N crtterte for margin of sa9 sty.

d*Cl*Fint 8 888r 88's 8r b licensee has evaluaIad the hasemee en a

esmeegesmosa of as assident passionely emervaier m ki the NA 112 proposed change request asatmat the emetyeed.

Emtsenc7 Plan inrplemenths standarda provided above and has (2) Ovete the posedbety of anew or Procedme (EPIPoh wittels beve been determland that this change wiB not:

dLiterent kind eressessertese say revised elaar the origine! eetpotat (1)invoin e signmcentincream in the calculations were somspleted.near prehebinty or eensequence of en occident er previously analysed.

~

T

26298 Federal Register / Vcl. 55. No.124 / Wednesday June 27, teso / Notices malfunction of equipment important u, safety up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.he proposed change proposed change will not increase the cs ymytously evaluated in the (Updated) [s]

stipulates that one train of containment probability of an socident. Routine FinalSafety Analyets Report.The change sprey remains operable during power surveillance testing confirms system caly [4fectj the serpoints of the high range operabihty. Deleting unnecessary

["h%""g","d N,N " *j

opers tion. The proposed action statements for the containment cochng challenges to safeguards equipment will y

setpotnts band on current Emergency Plan system specifications are similar to not increase the consequences of an implementing Procedures lohouldj taprove standard TS for Westinghouse plants.

accident.

cperator awarenese ad themfore will not The Proposed change to the shield (2) he amendment would not create incresee the conseqwnees of an accident.

building ventilauon. auxiliary building the possibility of a new or different kind (21 create the poulblilty of a new or ventilation and control room of accident fromany accident previously i

d ffemnt kind of occklent or a malfunction of postaccident recirculation system evaluated, since the proposed change is a diffmnt type than any previously specifications removes the requirement the result of a reanalyses of the control evolueted in tt.e lupdated) Final Safety to demonstrate the opposite train _.--room operator and offsite dose Analysis Report. The only safety function operable when one of the two trains is consequences.No system or lent

',Y' $*,*,E,", (

made, or found to be inoperable.De modifications are involved; t tefore, ti go,,

cannot create a new or diffent accident.

Licensee states that past performance of the proposed change will not cmate the (3) involve a reduction in a margin of these systems has demonstrated that possibility of a new or different kind of safety.no revision will provide the operator routine surveillance assures system accident.

with more meaningfulindicaticu and will operabihty; and that testing the opposite (3)The amendment would not involve therefore not tavolve e reduction in a safety train for proof of operabihty a significant reduction in a margin of marytn.

unnecessarily challeages the equipment. safety, since the proposed action The NRC staff has made a preliminary Basis forproposedno significant statements associated with 11131c.2 nyiew of the licensee e analyses of the hozords consideration determination!

stipulate that one train of containment proposed changes and agrees with the ne Commission has provided sprey shall remain operable during bcensee's conclusion that the three standards for determining whether a power opereuon. Stipulating one train of standards in 10 CFR 50.92(c) are met.

significant hazards consideration exists containment spray remains operable Themfore, the staff proposes to as stated in 10 CF1L 80.92. A proposed during power operation assures drtermine that the proposed amendment to an operating license for a cmendments do not involve a significant facility involyn no significant hasards ennformancaja tha11SARand control room habitability awumpton and hazards conalderation.

considerstion if operetaon of the facility represents an overallincrease in safety, i

t LocalPublic Document Room in accordance with a proposed b pmposd change h an addiuond

(

. Jocotion:%e Alderman Library.

amendment would not:(1)lavolve a rwtricuan in W.hnical Specincauons, Manuscripts Department. University of significant increase in the probability or and emfore, wG not ruuh in a j

l Virginia. Charlottesville.V a 22901.

consequences of an accident previously decrease in the margin of safety.

l Attorneyforbcensee: Mi nel W.

evaluated. (2) Create the possibility of a

%e d change of115 3Ab't' Maupin. Esq Hunton and Williams, new or different kind of accident from gab 4 12.b wiH aheninak P.O. Box 1535. Richmond, Virginia 23212. any accident previously evaluated, or (3)

' 8*'

ards NRCProject Diivetor: Herbert N.

lavo!ve a significant reduction in a

[

ung el dud ow margin of sai testing requirement is consistent with The bcensee e addressed these j

Wla== ale Public Servlas Corporation.

Westinghouse Standard Technical

• • P"Vid'd I" O' I*U0*I"8 Specifications which have this type of

["h%famendment would notinvolve Docket No. 50 305. Kewaunee Nuclear Plant. Kewaunse County, mquimment only for se omrgency a significant increase in the probability power system. Since operability of the Dose of amendment toguest May 15.

or consequences of an accident SBV. ABSV. and CRPR systems is 1990 previously evaluated, because the dmonstmted by surwWance Description of amendment squesti proposed change of Tli 31c.2 concerns me. remving eis requimmot ne propond amendment would revise the containment sprey system which is m ee ecuan statments wiu not the Technical Specifications

)3.3.c.2.

not a precursor to an accident analynd resultin a decrease in a margin of SAb13Aba and 3.12.b to the in the Updated Safety Analysis Report safety.

cction statements for the containmant (USAR). therefore, the proposed change Based on the previous discussions, the coohns. shield building ventilation.

would not inemese the pmbability of licensee concluded that the proposed cuxiliary building ventilation and occurrence of an accident. no resultant amendment request does not involve a control room postaccident recirculation doses are less than those originan significant increase in the probability or systems.

approved for Kewaunee and less consequences of an accident previously he proposed change to the the to CFR Part 100 offsite hmits. and evaluated; does not create the containment cooling specificauon within the CDC 19 guidehnes for control possibill of a new or different kind of f

incorporetes the results of reanalyses of room operetors. On this bask, the accident any accident previously t

the control room operetot dose and proposed change will not result in an evaluated; and does not involve a effsite does consequenen fouowing a increase in the consequences of an reductionin the required margin of design basis accident. The new analyses accident.

safety, take some credit for the containment ne proposed change of TS SAb.t.

The twn=l==<='s staff has aviewed spray system to remove radiolodine SAb1 and 3.12.b concerns the ehk1d the licensee's submittal and agrees with from the containment atmosphere, building vent!!adon (SB system.

the licensee's conclusions for the three whmu the previous analyses took no auxiliary building ventilation standards.

ly. the Commission credit for this attribute in done (ABSV) system, control room has made a determination that calculation assessments.De existing poetaccident recirculation (CRPR) the amendment application does not specificadon allows both trains of eystem which are not precursors to involve a significant basards containment sprey to be inoperable for analyzed accidents; therefore, the considersuon.

,----c,

r

, Federal Register / Vol. 55, Ns,124 / Wsdnesday, June 27,1990 / Notic2s 28299 localPubhc Document Room rcnulnments wal continue to demonetrate Brief description of amendment locolion: University of Wisconsin pump opersbuity.

request The amendment adds a

2. Cnete h sibthey of a new of clarifying note regardmg frequency of Library 14aming Center,2420 Nicolet d2ffennt kbd o occident fram any the nuclear source range Drive. Green Bey, Wisconsin 54301.

pm o up instrumentation togic Channel Testing Attorney forlicensee: David Baker, p

bi ins,

in Table 4.11 of the Technical Esq., Foley and Lardner, P.O. Box 2193, system configuration changes in order to Specificat.ons.%e amendment also Orlando, f1onda 31082.

perform surveillance tutins which adversely NRC Profect Director: John N.

effect system funcuanal performance corrects a typographical error and Hannon.

s. Involve a signincent reduction in a renumbers a subsequent note in Table anagn of safety. Vertfication of pump 4.1 1.

Yankee Atanic Doctric Company, operibibty is maintained. The Ineervice Date ofpublication ofindividual Docket No. Bo.4ct, Yankee Nuclea' Testir.g Program at YNPS will contmue to notice in Federal Register: June 5.1990 Power Station Franklin County-enoun that pump operetional read nese (55 FR 229'75)

Massackueetts crtterta are consistent w1th the 6,, ants g,,,,,y,,g,,,,y,,g,,,gu,,,,,,,,,

o d

Date of omendment request Apr019, ue conducted in Comment period expired June 20,1990:

1990 as supplemented june 7,1990 accordance with plant Technical notice period expires july 5,1990 Descripoon of omendment request:

Specificahons.

(original notice erroneously stated that The proposed amendment would modify ne staff has reviewed the licensee's the notice period ended June 20.1990).

the Technical Specification Surveulance no significant hazards consideration locolPublic Document Room Requirement to bring the High Pressure detertniristion analysis. Based upon this location: Hartsvule Memorial Library.

Safety injection (HPSI) and LPSI pump review, the staff agrees with the Home and Fifth Avenues,Hartsville, surveillan:e frequency requirements in bem's no significant hazards South Carohna 29535 line wtth the Standard Technical analysis. Based upon b above NOTICE OF ISSUANCE OF Specifh:stions for Westinghouse s

e sta Posu to AMENDMENT TO FACIUTY Pressurized Water Reactors (PWRs)

OPERATING UCENSE contained in NUREG-0452. Revision 4.

in olv griific t while prodding for re estabhahment of consideration.

During the period since publication of ASME XIinservice testing reference LocolPublic Document Room the last biweekly notice, the values as provided for in the code.

g,jg.'Greenfield Community College, Commission has issued the following 52 mquins suminance of 1 College Drive, Greenfield, amendments.%e Commission has these pumps only when they am being Massachusetts 01301 determined for each of these tested t e

ins ca 8

A ttorney for licensee: Thomas Dignan, amendments that the apphcation q,

h tE Esquire, Ropes and Grey,225 Frankhn complies with the standards and Boiler and Pre"*" V'"'I Code in Street, Boston, Massachusetts 02111 requirements of the Atomic Energy Act effect for each specific plant.--

NRC Project Director: Richard H.

of 1954, as amended (the Act), and the on deYr Wauman Commission's rules and regulations. %e haz cnse i on:

fm

%e Commulon has provided PREVIOUSLY PUBUSHED NOTICES s

req by c

db standards for determining whether a OF CONSIDERATION OF ISSUANCE Commission's rules and regulations in 10 s:gnificar a hazards consideration exists OF AMENDMENTS TO OPERATING CFR Chapter 1, which are set forth in the (10 CFR 10K(c)). A proposed UCENSES AND PROPOSED NO license amendment.

strendment to an operating bcense for a SIGNIFICANT HAZARDS Notice of Consideration of issusnce of facili involves no significant hazards CONSIDERATION DETERMINATION Amendment to Facility Operating es per e of the facility AND OPPORTUNITY FOR HEARING License and Proposed No Significant ne foDowing notices won pmviously Hazards Considerstion Determination amendment would not:(1)Involvs a significant ino case in the probabibty or pubbshed as separate individual and Opportunity for Hearing in a tices. The notice content was the connection with these actions was consequenose of an accident previously same as above.%ey were pubhahed as pubhahed in the Federal Register as evaluated;(2) Cream the possibibty of a individual notices either because time indicated. No request for a hearing or new or different kind os accident from did not allow the Commiselon to wait petition for leave to intervene was filed an accident previously evaluated; or (3) f r this biweekly notice or because the following this notice.

Involve a significant reduction in a action involved exigent circumstances.

Unless otherwise indicated, b margin of safety.

The 11oensee addressed the above Uey are repeated here because the Commission has determined that bse three seen, lards in the amendment biweekly notice usts all amendments amendments satisfy the criteria for appucation. In regard to the three issued or proposed to be issued categorical exclusion in accordance standards, the licensee provided the involving no significant hasards with 10 CFR 81.22. herefore, pursuant consideration, to 10 CFR 51.22(b), no environmental following naalysis:

TW change k requated in order to revue For details, see the individual notice impact statement ce environmental the Hyst and LPSI pump survehace in the Federal Register on the day and assessment need be prepared for these requirements to Sectice 4.8.2e of the YNPS page cited. This notice does not extend amendments. If the Commission has Technical Specifiestions. As sech, this the notice period of the original notice, prepared an anvironmental assessment i

proposed change would not under the special circumstances

1. Involve a synificant increase in the Carolina Power & Usht Company' Provision in 10 CFR 51.12(b) and has probebility or consequences of an socident Docket No. 50 281, H. B. Robinson made a determinaum based a bat previously evaluated. This change only 8taam Electdc Plant, Unit No. g, sessment, it is so indicated.

rev6ees the survehace ; ;.

--tafor Darlingtoe CountyMtb h

"',For further details with respect to the these pumps.The purpcas of thue survehace requirements 6s to pie, that the Date ofomendment request Msy 25, action see (1) the app 3 cations for pumps are operab6s. The revised survah 1990 amendments, (2) the amendments, and

- Federal Rghter / Vol. 55, No.124 / Wednesday, June 27. togo / Notices' l

23300 (3) the Coennieslan's related letters.

Overpressure Protection System (L10P)

Nerth Carolina. Charlotte (UNCC Sefaty Evaluations and/or set points. In addition, the new Station) North Camline 2a223 Environssental Aaesoamente as methodology equires related changes M iaP m Capon 6on,e A indicated. All of these hems are in: (1) recalculated limiting material Docket No.96302, Crystal River Unit evallable for public inspection at the reference temperature (RT sub NDT). (2)

No. 8 Nuclear Generating Plant. Citrue Commiselon's Public Document Room.

modified LTOP anable temperature,(3)

Can'Y' Florida the f41mma Buildas also L Street. NW,.

the selection of instrumentation for Wcshington, DC, and at the local pubhc monitoring RCS averese temperature.

Date of application for amendment >

document rooms for the particular and (4) mvisions to the 15 Bases. Some February 13,1990 facilities involved. A copy of items (2) administrative changee are made such Brief descripuen of amendment his and (3)may be obtained upon request as:(1) rewording to clarify certain amendment changes the Technical cddressed to the U.S. Nuclear specifications, (2) deleting redundant Specifications to aBow etimination of Regulatory Commission. Washington.

surveillances, and (3) removias the the automatic simultaneous operation of DC 20665, Attention: Director, Division reference to criticality limits in TS the motor driven emergency feedweter af Reactor Projects.

3.4.9.L s.4A2 and Figure 3.4-3.

pump and thelow pressure injection Arisons PubBe Santos Company,et al.

Dofe ofisevanos:May at1990 system when offsite power is not III'#

available, and changes response times

-(,g"'dd88#M8Y31'1880 Docke Nee.STN 84838,81N M for the low pressure and high pressure I'y y,, gpg injection systems.

and STN 86538. Pale Vesde Nuclear

.fj

• ",g,e,"g Technical Date ofissuance: june 41990 Generating Station (PVNG8), Unit 1. 2 gg, and a, Marisope County, Arineos gpeg,r;,,g,,,,

Effecun date: june 41980 Date ofappliootionforamendments:

Date ofinitialnoucein Federal Amendment No.:130 March 8.1990 Register: October 4,1989 (M FR 40824)

Facility Dperatim Ucense No. DpR.

Brief description of amendments:

% Commiesion's related evaluation of hee amendmenteremove the 3.25 limit the a==ndment is contained in a safety

72. Amendment avised the Technical on the combined time interval for three Evaluation dated May at 1990.

Specifications.

conaeontive surveillaam intervals in No significant hosoids consideration Dose ofinida/notiet in Federal Teclinical Specification eat and the commentsisosired:No _.

Regleter: April 4.1990(55PR12591)he casociated Bseas. The huit of as percent

- Lab 7o 727trDocumentRoom Commission's related evaluation of the extension for individual survallian=

location:CameronVillage Regional amendment is contained in a Safety intervals is retained.

Library.1930 Clark Avenue.Raleigh.

Evaluation dated June 4,1990.

Date ofinsuance: lune 1t1980 North Carolina 27805 No significoat hasards consideradon comments rece/ red:No.

Effecem dote:45 days fra the date Duka Powerrwapany,Doast Nos.go.

See and 88870 M&uire Nusteer localpublicDocument Room t Nos.:45,85, and 22 Station. Units 1 and 2.Mecklenburg Locotion: Crystal River Public Ubrary, see N.W. First Avenus, Crystal River, Facility Opefuting uoense Nos.NPF, County, North Carolina df.NPF d1 andNPF 74: Amendments h ida 32829 changed the Technical Specifications.

Date of applicouanforamendments, Date afin/fialnoucein Federal November 28,1908, as revised February Florida Powee and Ught Conspesy.

Dedet No.99 a13, St. hade Ptant, Unit Register: April 4.1990 (55 FR 12589) N 15.1980.

Coeunlosion's related evaluation of the Brief slancription of amomiments:b No.1, St. Lumle County, Florida amendments is contained in a Safety amendmen'.s modi 8ed the Technical Date of 8ppicadaoforamendments:

Evaluation dated June it1990 Speci8 cations by revising the Decainba 5.1989 No s%n/ficant hasards considerotion adminstretive control requiremente for Bne descriphonofamendment:This comunenar scelwd:No.

the McGuire Safety Review Group tlacorporetes avised am ImentPublicDocumentRoom (MSRG).

Pressure /lamperatum units and the Jacotion: Phoenix Public Ubrary.

Date o[ve dote:issoonce: June 8,1980 results of a revised now temperatum Businese and Science Division,12 East Effecti June 8,1880 overpressure protection analysis late McDoweB Road. Phoenix. Artsona 88006 Amenchnent Nos.:110 and 92 the Technical SpectScations for St. Lucie Facility Opero beense Nos. NPF #

CeSan Peer & Ught Congemy.et al.

andNPF-12 to revloed the Unit L Decke No.88 400,h Hards Technical Specifications.

Date ofissuance:Inneit1890 Nuclear Peer Plant.Unu Awake and Dose ofinidalnoticein Federal EffectiveDate: June it1920 MmGeneties NereCasehna Regleton February 8,1989 (se FR 9105).

Amendment No.:106 Doneofcpplicationforamendment:

Sinoe the date of the inttial notice. the yac;yjfy op,,,g;,g y,,,,,y,, ppg.

June 30, tees, as supplemented licensee revised the application by letter 87: Amendment revised theTechnical November 27. tees. Febreary 1.1990 and dated February 15,1990. The revision Specifications

• Apr0 so,teso.

providedincreased spectacity with Date ofinidalnodoein Federal

= - fsleseripden ofzint:This respect to the quahfications of the Regleten December 27.198H54 m Brie tacorporatee change. to the MSRG and did met alter the mee t'g let predicting reactor Comuniselon's lattial deterndnation of no 53204)W wmaion,e related evaluedom of es e-tis vessel material embelttlement for the significant hazards consideration. The contained in a Safety Evaluation dated f

Shearce Harrie Nuclear Power Plant.

Commiaolon's related ovaluation of the No s&nificant hasords cons /derotlan Unit t (Harris) Technical Speci8 cations amendmentsis ecstainedin a Safety comments seceived:No.

(73).The revtstems affect the pressure-Svelueuos dated lune 8,1800, LocalPublicDocumentRoost tem ture haaltatican on the Reectae No significant hasards oaasideration location: Indian River Junior College Systein (RCB). the hoetop and comments received:No.

cooldows rates for the RCS. and the lace / Public Document Room Ubrary,320e Virgine Avenue, Pt. Pierce.

assoaistedleurTemperature JoceUon Atkins Ubrary. University of Piorida.

~

• t 4

Federal Register / Vol. 55, No.124 / Wsdnesday june 27. 1990 / Notices 28301 Florida Power and Ught Company, ladiana Michigan Power Company, blwas Michigan Power Company, Docket No. eMas, St. hade Plant, Unit Docket No. eH16, Dona ld C. Cook Dockets Nos. so.315 and 50 318, Donald No.1, St. hide County, Florida Nuclear Plant, Unit No S. Berrien C. Cook Nuclear Plant Units Nos.1 and Date of applimtion for amendment, County, Michigan 1, Berrien County, Michigan December 15,1989, modihed by letter '

Date of application for amendment:

Date of application for amendments:

deted April 34,1990 October 25,1989 February 6,1990 Briefdescri don of amendment:This Brief description of amendment:Thle. Brief description of amendments: Tbis'

amendment es the St. Lucie Plant, amendm6nt changes Technical amendment revises Technical Unit 1 Technical fications (TS) to Specification (TS) 3/4.4.9, "Pressare/

Specif cations (E) by implementing a enhance diesel generator reliability,It Temperature umits " to limit the Core Operating timits Report (COLR) in also makes St. Lucie Unit 1 TS for maximum beetup rete to co' F/hr and to accordance with Generic Letter 88-16,

" Electrical Power Systems A.C.

provide revised heatup and cooldown

" Removal of Cycle-Specific Parameter pressure. temperature (P-T) limit curves.

Umits from Techn' cal Fpecifications."

Sources" similar to St. Lucie Unit 2 TS.- - - The maximum hestup rete is currently ~ Generic Istter 88-16 a Date of Assuance: June 7,1990 Ef7ective Dode: June 7,1990 limited to 100* F/hr.N revisions am speelfic parameters, such as moderator Amendmen!No. 103 based on a reanalysis of reactor vessel temperature coefficient and the heat flux Facility Operatire Ucense No. DPR.

sample materialin accordance with hot channel factor, to be removed from 87: Amendment revised the Technical Regulatory Guide (RC)1.99, Rev 2.

the TS and maintained in a COLR. NRC Date ofissuance:May 24,1990 will be informed of changes to the l

Specifications.

Effective date: As of the beginning of operating limits. Changes to the Date ofiaitialmotice in Federn!

Register. lanuary 10.1990 (55 FR 933)

Cycle 8 operating limits will be made uring NRC Amendment Nos. 123 approved methodologies for the D. C.

The April 34,1900 letter added two tests Facility Opmung Ucense Nos. DPR-Cook Nuclear Plant.

to the proposed Technical Specification

74. Annendrnent mvised the Technical changes and also provided clarifying Date ofissuance:May 23,1990 f

t/Fe date:As of the beginnina of Do fin ialnoticein Federal Cy[e d t a inlual determination e'no signiAcent hazards Register: April 4,1990 (55 FR 12504h The Commission's related evaluation of the Amendmenis Nos.t122 considemum b Pas'i='i%n's related amendment is contained in a Safety FocL'ity Operatingtimiises Nos.

waluation of b amendment is contained in a Safety Evaluation dated Evaluation dated May 24,1990.

DPR.58 andDPR 74. Amendmen,ts No significant hasards consideration revised the Technical Specifications.

June 7,1990.

comments se elved: No.

Date ofinitialnotice in Federal No significant hasards considention LocalPublicDocumeniRoom Register. March 21,1990 (55 FR 10538).

commentereceind No.

/muonMaude Pnston Palenske b Commission's related evaluation of LocalpublicDocumentRoom Memorial Ubrary,500 Market Street, St.

the amendments as contained in a Safety Imum IMian RivMunlw College lo*eph, Michigan 49085.

Evaluation ds&d May 23,1990.

J Ubrary,2309 Virgina Avenue. Ft. Pierce, Florida.

t=Amna Michigan Power mnpany, No significant hasards consideration e

Docket Nos.eH15 and 50 318, Donald comments received:No.

In&ana Michigan Power =ap==y'ald C. Cook Nuclear Plant, Unit Nos.1 and localPublic Documenf Room c

Docket Nos epis and eM16, Don 2, Berrien County, Michigan location: Maude Preston Palenske C. Cook Nuclear Flaat Unit Nos.1 and Memorial Ubrary,500 Market Street. St.

2 Berrien Csenty,Midigan Date ofapplicationforamendments:

Joseph, Michigan 49065.

• f yg,,"c,ipt n of amendments:,

Nartheast Nuclear Enerzy Company, et Datocfappkdonfm amndments:

Nwembe as, tese.

These amendments allow an extended al., Docket No 80 423, Millstone Nuclear 8tiefhpuce ofamendants ourveillance interval of 18 months for Power Station. Unit No. 3. New London bee amendments raise the trip set the visualinspection of the ice County, raaaarticut P$th ung of February 21 and M 15,1990 Date of applicati or amendment:

we v

the Bus Looe an1 e

of Voltage ana 4KV Bus Degraded the lower talet doore of the ice Briefdescripuon of amendment The Vontage actuation relays.

,aag,,,,}ssuance:May 20,1990 amendment modifies the Technical Date ofissuance May 25,1000 Date of Specmcanons (%) as foUows$)b Effectim dateMay 28,1990 Effectim date:Msy 20,1990 Amendments Nos.1137 and 124 Amendments Nos.1138 and 125 cycle.apecac opemung limits an i

removed from a number of TS and Focility Operatist Ucannes Nos.

Focility Operating ucenere Noe.

D'R.deandDPR-74. Amendments DPR.58andDPR-7d. Amendments incorporated in the Core Operating rr vised the Technical Specifications.

revised the Technical Specifications.

Umits Report (COLR) ae defined in TS l

Date ofinitialmoucoin Federal Date ofinitiolnoticein Federal 1.42 and the reporting requirements associated with the COIR are also Register: March 21,1990 (as FR 10538).

Register, March 21,1990 (55 FR 10638).

b r==aitaalon's related evaluation of The Commission's related evaluation of established; (2) an editorial change to 73 4.811 and 4.812 is made to improve the amer @ents is contained la a Safety the amendments is contained in a Safety readability, and (3) a change to TS 3/

Evahahlssd May 25,1990.

Evaluation deted May 29,1990.

4.e.1is msde to correctly describe a No significant hasards consideration No significant hasords consideration method for immobill. ting a manual commentsisoeired:No.

comments received: No.

"*I "'

LocalPublicDocumentRoom LocalPublicDocument Room Jocouan:Maude Pmeton Palenske location:Maude Preston Polensae Date ofissuance: June 15,1900

^

i Memorial Ubrary,000 Market Street. St.

Memorial Ubrary,500 Market Street, St.

Effectin dote: June 13,1990 Joseph, Michigan teoss.

Joseph, Michigan 40065.

Amendmrit No. 50

i i

26302 Federal Register / Vol. 55, No.124 / Wednesday, June 27, 1990 f Netioes Facihty Opemung License No. NPF.

The Commission's related evaluation of Effeepre dole: Wy 30,1990 G Amendment revised the Technical the amendment is contained in a Safety Amendment No. 40 Speci$ cations.

Evaluation dated June 6.1990.

Facihty Opemug Lloenee & NPT.

=

Date of amtsalnouce in Federal No significant hozords considemb.on 39 This einenttmaat revised the Register. April 18,1990 (55 FR 14513) comments received No.

Technical Specifications.

The Commission's related evaluation of Loco / Pubhc Document Room Date of fnitio/ notice in Federal the amendment is contained in a Safety locouon: Minneapolis Public Ubrary, Register. April 18,1990 (55 FR 14514)

Evaluetson dated June 13,1990 Technology and Science Department.

m enmmiasion's related evaluation of No signifscont hoznids cmsiderouan 300 Nicollet Mall, Mmneapohs, the amendment is contained in a Safety commenu received: No.

Mmnesota 5540L Evaluation datedptry 30,1990.

LocalPubhc Document Room Pacific Gas and Decade Company, No signifimat hosords considemuon locouon: Learning Resources Center.

Docket Nos. 56 275 and 50 823 IhaW comments received No htnes Valley State Technical College.

Canyon Nuclear Power Plant Units 1 LocalPublic Document Room Ne W h.Nomch, and A San Luis Obispo County, location: Pottstown Pubhc Ubrary. 500 Cahiornka Egh Street. Pottotown. Pennsylvania Northeast Nuclear Energy Company, et Date of application for amendments:

19464.

al., Docket No. 50436, Millstone Nuclear April 18.1988. as supplemented by letter Philadelphia Doctr6c Company, Public Power Station, Unli No. 2, Now tendoo dated December 11,1989 (Reference Servim Doctdc and Gas Cosnpany uW' I

LAR 864).

Delmarva Power and ught Company, Date of opphoouon for amendment Brief descripdon of amendments:%e and Atlantic City Dectnc Cosspany, March 2L 1990 amendments revised Technical Docket Nos. 80 277 and BB 278, Pead i

Bnef descripuon of amendment The Specification (TS) Sections 3.0.4. 4.0.3.

Bottaen Ateenic Power Statloa, Unit Noa.

amendment adds a new Technical and 4.0.4. and the associated TS Bases 2 and R. Yeek Cesaty, Penney vama Specificaban Section 3/4.7.11 " Ultimate secuona, which define the applicability Heat Smk" by a requirement to maintain of hmitmg conditions for operetion and Date of applicadonfor amendments:

an average weter temperature less than surveillance requirements. %

March 8,1990 as supplemented on April or equal to 75 degrees F at the intake amendments also delete the exceptions 26,.990. The supplemental letter structure except when the reactor is in to 73 3.0.4 in a nurnber of W. h TS Proposed editorial and administrative the cold shutdown or refuehng changes are in accordance with the revisione to the 3 changes proposed in condition.

recommendations of Generic lattet (CL) the original submittal.%e staff has Date ofissuance: June 12,1990 87 09 to provide greater operational determined that these sdditional Effecute dota June 12.1000 flexibility and preclude unnecessary changes do not affect the proposed no Amendment No.; 145 plant shutdowns and to allow passage significant hasards determination.

Facihty Opervum License No. DPW through or to operational modee as Brief description of amendments:

si Amendment rensed the Technical required to comply with Action These amendments changed the Specifica tions.

Requirements.

Technical Specifications to remove Date ofinicolnouce in Federal Date ofissuance; june it 1990 cycle specific parameter limits in Registar April 18,1990 (55 FR 14512)

Effecove date; June 11,1990 accordance with the guidance provided

~

The Comnussion's related evalustion of Amendment Nos. 55 and 54 in NRC Generic latter 8818 and to taake the amendment is cantained in e Safety Tacility Operoung License Nos. DPR.

miscalianeous adatnistrative changes.

Evaluation dated }une 12,1990 doandDPR-c Amendments changed Daar ofissuonos: May 21,1990 No significant hozords consideration the Technical SpeciRcationa.

Effecun dote:May 21,1980 comments received No.

Date ofinitialnotice in Federa' Amendments Nos ' the and 156 localPublic Document Room Register: May 8,1089 (64 FR 18948). %e Facility OperounWeense Nos. DP&

lomuon:14arning Resources Centat.

Comm6*alon's related evaluation af the W andDPR4a Ammarimants revised the Nmas Valley State Technical College, amendments is contained in a Safety TedMcal SpMScaboos' 4

574 New London Turnpike, Norwich.

Evaluation dated June 11.1990.

Connecticut 06300.

No signifroant hasorale canaideradon R

Ap

& 900 FR 17)

Northern Statne Power campany, cQan h Commise6co's related evaluation of Docket No. ONa3, Monticello Nuclose locouon Cabrds PolytedMc State the amendments is contained in a Bafety Generatms Plant, Wdght Ceaaty, UdverEty Ubewy, Govenmed Evaluation dated May It 1990.

Mino**ota Documents and Mapa Department. San No significant haamde consideradon Date of application for amendment:

Luis Obispo California 93407, commente rece/esd No March as,1000 LocalPublic Document Room 1

Bnef description of amendment.

Philadelphia Electric Company, Dockat loccuoa Government Pubhostions o

Revisee Apoendix A Technical No. EM52, Umorick Generating Station, nection. State ubrary of Penneylvania, Specincetiene to ehminate requirement Unit t % y j County, (REGIONAL DEPOSITORY) Education for automatic leo 6ation function of wide Pennspvania Building. Walnut Street and "f

range gas monitore.

Date of applicosion for amendment:

Commonwealth Avenna, Box 180L Dote ofisesonce June 6.1990 March 20,1990 Harrisburg, Pennsylvania 17105.

=

Effective dote hme 6.1980 Bnef descrrption of amendmaat;his

=maah made seversl Power Authertty of N 8 tate of New Amendment No.2 74 t

Docket h 34388,inham Not Focilsty Operoung License Na DPL ariministrative changes to the Umarick.

22. Amendment revised the Technical Unit 1 Technte=1 Specificetiene to No. 8, West & ester County, New Specificationa.

eliminats differences between the Unit 1 I

Date of uubalmodoe in Fedesel and Unit 3 Technical Specifications.

Dole of apphootice for assertsmant:

Register. April 18,1990 @5 FR 14514)

Date ofissuancer May 30,1990 March 23,1990 G

=

Federal Regisier / Vcl. 55, No.124 / Wednreday, June 27, 1990 / Notices 26303 Brief descripuce of amendment he 1990 and May 7,1990, %e May 7,'1990 maximum 30 months. As the result of amendment revisse Technical netter provided informauon concerning modifying the surveillance interval.

l Specificattes Table 4.18 " Frequencies the schedule for resolution of the main changes were made to the ESFAS for Equipment Tests." na change would steam isolation valve slow closun time instrumentation setpoints in Technical il revise testm' g to specify control rod and did not increase the scope of the Specification 3/4.3.2, Table 3.34.

movement of at least 10 steps to assure original amendment request and did not Finally, the amendments revised San control rod movement. A two week affect the staffs original no significant Onofre Units 2 and 3 Technical l

surveillance intervalis also changed to hazards determination.

Specification 3/4.3.3.5, " Remote 31 days.

Brief descriphon of amendment This Shutdown Instrumentation." to increase Date o[ issuance: June 5,1990 amendment increased the allowable the interval for refueling interval Effect/ve dote: June 5.1990, to be closure time of the main steam isolation surveillance tests which are currendy implemented within 30 days valves from 5 seconds to 8 seconds until performed every 18 months, to each Amendment No.:90 restart from the sixth refueling outage.

refueling. nominal;y 24 months and I

Focility C emiing uoense No. DPR.

The amendment for Unit 1 was maximum 30 months.

64: Amendment revised b Technical processed as an emergency technical Date ofissuance June 8,1990 Specifications.

specification change in accordance with Effective date lune 8,1990 Date ofinlualnotice in Federal 50.91(a)(5)

Amendment Nosa 88 and 78 Register: May 3,1990 (55 FR 18413) The Date ofissvonce: May 30,1990 Facility Opemting License Nos. NPF.

Commission's related evalvetion of the Effects ve data : May 30,1990 10 and NPF45: Amendments changed amendment is contained in a Safety Amendment Na 91.

the Technical Specifications.

Evaluation dated lune 5,1990.

Facility Openting Ltcense No. DPR.

gg, og,,,y,,,g;g pg,,3 No significant hosoids considemtion 75:his amendment revised the Register: February 7,1990 (55 FR 4275. 55 comments received: No Technical Specifications.

FR 4278 and 55 m 4277)' he staff localPublic Document Room Date ofinitialnotice in Federal requeeted addiuonalinformanon to locatiort White Plains Public Ubrary, Repster. April 26,1990 (55 FR 17883) supplement the original applications.

100 Martine Avenue, White Plaina, New ne Commission's related evaluation of J

his ini emation did not affect the l

York.10810.

the amendment is contained in a Safety Proposed no al=nhat hasards Evaluation dated May 30,1990'demtion consideration determination as l

Power Authority of the State of New No significant hosonis consi previ usly noticed, no Commission's York. Decket No. 58 833, Jamse A.

comments rece/ved: No related evaluation of the amendments is FitzPetrick Nuclear Power Plant.

Loco / Public Document Room Oswego County, Nm York location: Salem Free Public Ubrary,112 contained in a Safety Evaluation dated l.

Dots of applicadon for amendment Weet Broadwey, Salem Now Jersey J m 8,1990 No significant hasards consideration january 12.1990, superseded Apru 30, 08079 comments received No.

1ggo Docks as as loc o. Main Ubrary Uni ersity of am men ovos the cy c

Doofre Nuclear Generating Station.

Cahfo:nia. P.O. Bor 19857. Irvine.

paratar limits from the Technical U*its and 8, San Diego County.

California 92715.

Sp 'aficatiene and pieces them in the gg Cote Operating umits Report in Toledo 5Aaaa Ceempany and b acardance with guidance contained in Date of applimuon for amendments:

Cleveland Doctric Bluminaung Generic Latter es.te, laouary a,1990 and supplemented Company, Docket No. 36448, Devie.

Dole ofissuance:May 3L 1990 March 12. March 19 and May 2,1990.

Seeee Nuclear Power Station, Unit No.1 I

Effecuve data:May SL 19eo Brie descriptson of amendments:he Otun County' Okto Amendment NcJ182 amen nts reviasd San Onofre Unita 2 Facility Openting Locense Na DPR.

and 3 Technical Specification S/4.3.1, Date of applicotion for amendment:

se Amendment revised the Technical

" Reactor Protective lastrumentation." to December 1,1998 Specification.

lacrasee the interval for refueling Brief deecription of amendment %e Defe of fn/tialnouce bt Federal interval surveillance tests which are amendment revised the Technical Regleter March 27,1990 (55 FR 8234) curtently performed every 18 months, to Specifications to reduce the reactor and renoticed April 30,1990 (55 FR each refueling. naminally 24 amonths and protection eystem reactor coolant low 18042) ne (Wnmiaaion's relatad maximum 30 months. As the result of prer sure trip setpoint from greater than l

evaluation of the aman'imant is modifying the surveillanna interval, or equal to 1983.4 peig to greater than or l

contained la a Safety Evaluatjam dated changes were made to the Reactor equal to 1900 pois and correspondingly 1

May 3L 1990.

Protectjve instrumentation setpoints in modified the reactor protection system l

No significant Aaeards considemtion Technical Specification 2.2.L Table 21 variable low pressure setpoint.

comments recehod No 1; the High Imgarithmic Power Level Date ofissuance: June 4.1990 LocalPublic Document Room response time in Technical Specification Effecure date: 80 days after issuance 8/4AL r ble 152; and the calibration Amendment No.149 lomtion: Penfield ubrary, Stato a

University College of Oswego, Oswego, tolerance in Tachnicat Specification 3/

Facility Opemting Ucense No. NPF4 New York.

4.3.1, Table 4SL Amendment revised the Technical Additionally, the amendments revised Specifications.

Public Sardos M & h Campany.

San Onotre Units a and a Technical Date ofinidolnotice in Federal m y,,,,ggg, g,g, Specification 3/4.3.2. " Engineered Safety Register: Apell18,1990 (55 FR 14518)

Sudea, Usk No.3, Salem m

Features Actuation System (ESFAS) h Commiselon's related evaluation of lastnamentation." to lacrease the the amendment La contained in e Safety Dole ofcaplicadon for ce andment-interval for survstilance tests, which are Evaluetion dated June 4.1990 April 4.1990, and supplemented by cumntly performed every la months, to No significant hasards cons /demuon lettare dated Apr012.las0, Aprilao, each refeeling. aa=* ally 34 smanths and comments reaWred No

Z 26804 Federal Register / Vcl. $$, No.114 / Wednesday, June 27, 1990 / Notices =,

Loco!PublicDocument Room Virginia Electric and Power Company, et $3213) The Commission's relsted locatirn: University of Toledo Library, at, Docket Noa. EM36 and 56 839, North evaluation of the amendmentis Documents Department,2a01 Bancroft Anna Power Station, Units No.1 and No. contained in a Safety Evaluation dated

' Avenue. Toledo, Ohio 43006.

8.Loulaa County, Vhrginia june 14,1990.

V:2mont Yankee Nuclear Power Date of applicationforamendments:

No significant hczads considention commente received No.

Corporation, Docket W.IM71 September 30,1986, as supplemented 1

dPu er' A m

- Vcreant Yankee Nucasar Power Station, Apat1 amen ents increase the allowable and Northgate Streets, Richland.

^ ** "*"

Date of applicationforamendment endchment of fuel assemblies irrodieted Washington 99352.

• February 26,1990 -

at NA 1&2 to 43 weight percent U 235.-

Washington Public Power Supply Britf descdpuon of amendment:%

Date ofissuance:}une 6.1990 gy,,,,, g,ey,, y,, guyy,y,eg,,

proposed chan6e mvises the Technical Effective dote ]une 6,1990 Project No.2 Benton County.

Amendment Noss127 & 111 Specification to add hafnium as an Washington cdditional absorber materialin the Facility Opemtirig Ucense Nos. NPE.d andNPF.7. Amendments revised the Date of applicationfor amendment:

control bladu*

Technical Specificatic::.

February 5,1990 N *$ I"*'*" I*** I' '***

Date ofinitialnoticein Federal Brief description of amendment:%is Effective dete June 5,1990 Register: November 16,1966 (53 FR amendment revises Technical Amendment Na 123 46163)% Augutt1S,1989letier Specification Section 3/4.6.1.1,"A.C.

Todlity Opemtig Ucense Na DPR.

provided supplemw talinformation Sources," by revising surveillance

28. Amendment revised the Technical which did not chAv;e the staffe inleal requirements applicable to the Specifications, no si.nificant hasa.de unsideration emergency dinel generetors. Changes Date ofinido/nodwin Federal determination.The Commission's am made to the specification of diesel related evaluation of the amendments is generator testing inquency in Register. March 21,1990 (55 R 10646)

' b Commission's related evaluation of contained in an Environmental accordance with the test schedule

- the amendment is contained in a Safety Assessment dated May 30,1989 and a considerations set forth in Generic Evt.luation dated June 8,1990.

Safety Evaluation dated June 6,1990. '

!Atter 84-14.

N@nifinnthasards unsidendon Date ofissunace:May 31,1990 N2 significant hasarde consideration "QYfN*' goo, M

entiha 6 comments received:No Amen k224 MTnuc Depa ent.

rbve'rsity of 15 h

low n o I 21 n

n Main Strat, Brattleboro, Vermont 05301. Virginia, Charlor.esville, Virginia 22901.

Specifications.

Vennoot Yankee Nuclear Powee Washington Pu slic Power Supply Date ofinitialnotics in Federal Corporetion. Docket No.BM71 Systam Docket No.BM37, Nuclear Register. March 21,1990 (55 FR 10648)

Vcrmont Yankee Nuclear Power Station, Project No.3 Benton County, ne Commission's related evaluation of Vernoe, Vermont -

Washington -

the amendment is containedin a Safety Date of applicationforamendment:

Date of applicadon foramendment:

Evaluation dated May 31,1990. -

No significant hazards considemtion March 9,1990 October 27,1989 and April 5,1990 bpe ti Se a

a ca dd f w

ek an rths ts, a,

Coolant System Pressure / Temperature valves to the Type C leaks test program.N revision also removes the Limits by revising the curves which set Washington 99352.

f rth the pmssum/ temperature limit Washington Public Power Supply requirement for leakage rate testing of two valves which are now outside the linee. Specifically Figure 3.4.6.1 will be System. Docket No. 90 397. Nuclear insertM in the technical specifications.

Project No.2 Benton County, antainment boundary.

Existins Figure 3.4.6.11 and Figure Washington Ate oflasuance: June 4.1990 3.4.6.12 will be removed. Existing Figure Effsedve dote: At the time of 3.4.6.1 1 had set limits applicable during Date of applicadon for amendment:

shutdown for the 1990 scheduled the early life of the plant and was no February 27,1990 and supplemented by loager applicable. References to the two letter dated April 13,1990.The April 13, refueling outage.

Amendment Na122 figures in the index, in specification 3/

1990 submittal did not substantially racility Operating Ucense Na DPR.

4.4.6 and in the bases section 3/4.4.6 change the action noticed or affect the

28. Amendment revised the Technical have been revised to refer to the single.

initial propoud no significant hazards Specifications.

new figun.h bases have also been determination.

amen { description of amendment:ne Brie revised to reflect that nickel rather than Date ofhiddnodesin Federal phosphorous is the metal reported with nt nvises saf limits to be Register.May 2.1990 (55 FR 16415).b nector vessel toughness test results.

app ce during the a cy Commission's related evaluation of the cmendment is contained in a Safety Date ofissuance: June it.1990 Power operation. Specifically the Effective dote lune 14.1990 amendment revises the ladex of the Evaluation dated June 4,1990, Amendment No.:#7 Technical specifications (TS) to include No significant hasarde consideradon FacilityOpentim censeNaNPF.

nference to four curvu which an belag u

comments moeirod No 22 Amendments changed the Technical added to the TS.%e new curves ZoculPublic W-mitRoom Specifications, provide limits for the maximum everage r

hation* Brooks Memorial 1 ibrary, 224 Date ofinitia/ notice hv Federal plans' heet generstion tote (MALPHGR)

Matn Street, Brattleboro, Vermont 06301. Register: December 27,1999 (54 FR and L :rar heat generstion rete (IlfGR)

.-J

i i

Federal Reg lleter / Vol. 66, No.134 / Wednesday. June 27. Spoo / Notices 98305 l'or two new types of need feel particulate testing that was adhessed assemblies to be inserted into the core, on a temporary basis by beense N asaendment wvises the dotatuam of ame.ndment Fe issued by the NRC on critical power totio (CPR) given la 15 Februe IL teso.

r LO.The revision makes the definition Date taponon June 4,1990 raare general to include CPRe calculated Affect voter June 4.1000 i

for the new fuel designs to the lead fuel Amendment No.: e6 eesemblies.

Facility OperatingL kenee No. NPF.

N amendment revlees TS 9/4.t.1.

21: Amendment abanged the Technical

• Averese unear Heat Generation Rate."

Specifications.

to make the hmiting conditions for Dcae afin/holmodoein Federal operetion, action etetemente, and Regleter:May11990(58 FR1M19)The )l surveillance requiremente apply to the Commiselon's related evaluation of the f new fueldeelsne la the newlead fuel amendrnent is contained in a Safety

?

weembues.7wo new Agures are added Evalueuon deted lune 4,isso.

tot 131411 to set forth the MAFHIDR No significoat hasarde considercuan

?

hmite for the new lead fuel emessablies.

commente neceived: No.

The amendment revises TS 8/418.

Local Ashlic Docurnent Acom

" Minimum Critical Power Ratlo? to Jeoouon: Richland Oty ubrary, Swift Incorporate new hs Its specine to oycle and Nortbgete Streets, miekland six.

Weskington gDSSL m atuendment revlees 78 3/414.

Deted et asekvh. :.: -,M this aint any "unear Heat Generation Rate." by et jume, tesa rewording the halting somalition of for the Nuclear Regulaten Comanselon

=

opereuon to obow bowit appbes to all Dennis 14.4 baAhand fuel types in the core.Two new figurse pirosser, Division of Asender Pro /este J#. A'.

are edded to give lhlGR halte for the Feedipecialpro# cts Ofpce e/ Nuclear two new types of lead fuel assembhos.

Asector Asyufotloa

/

7% 5.8.1 to revloed te prov6de for the (Dec so-tors: Pued 6-aMa E46 aml use of lead fuel aseembbes.

sausa sens sum.ee o Bases eactions are revloed to abow the bases for the tedialeal er=asamtione as revised.

Date ofineuance:May SL 1990 Effective dcts:May 31.1980 Amendment No.:M focuity Cpe.vtievJeonee No. NPf-21:Amendmente abianged the Technical,

Specincations.

Date ofinluelnodcein Federal g

Regleter. Apr0 4.1990 (68 FR 13ect)N Commiselon's related evaluation of the

=

amendment a contained in a Safety Evolustica deled May 31,1990.

No significant heeards consideration ca tmentereceired:No.

local Anblic Document Room E

Jocation Richland Oty Ubrary, Swth and Nortbgete Streets, Richland. ~

Weahingtoa 993&L E

Weeblegten Pubus Bewer Sapply Systma, Decket No. 8D 4e7.Neeleer

=

Pso)ent No.8 Bentes County, Wa hiar.-

E Ibte af amhaa88== Jer amendment-Merch 30, taso

?

a= fdescriptien of===e"=st1%ie Brie

-- revisedTedialaal E-P Specifleeues s/4A1. %C. Seerese," by replecisms the sereothence sesquirements

• ^

eppucable to the fumiau for the entryoney diseel generatore.

Speci8cally,surveihenes ; L _ ;^4 B

411.11b, s. and d was sepissed.N F

new teste skeeld embanes the Sepply System *e abuity to detect ammatiefectory 1

fuel oil. this ammandmaet permansatly ruolves to connera oeur duelou F

a,.

5 U.i UNITED STATES seet oms man -

NUCt EAR R890LATORY COMMIS810N

" M,",'* **

WASHINGTON, D.C. 20066 neune,. w orriciAL sutiNass

{

' PENALTV PDA PRIVATE USE 4XC 9

4 t

4

_ _ _ - - - - _ - - - _ _ - - - - - _ _ _ _ - - - - _ - - - _ - - _ - - - - - - - - - - - - - _ - - _ - - - - - - - -