ML20056B439

Forwards Biweekly Fr Notice of Applications & Amends to OLs Involving Nshc,Published on 900711

ML20056B439
Person / Time
Issue date:	08/08/1990
From:	Murley T Office of Nuclear Reactor Regulation
To:	Graham B, Sharp P, Udall M HOUSE OF REP., ENERGY & COMMERCE, HOUSE OF REP., INTERIOR & INSULAR AFFAIRS, SENATE, ENVIRONMENT & PUBLIC WORKS
References
NUDOCS 9008280285
Download: ML20056B439 (22)

Text

'

n August 8,1990

' IDENTICAL LETTERS SENT TO:

(See attached list of addressees)

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

20510 bear 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 Commission to issue and make immediately effective any amendment to an operating license upon a determination by the Comission th6t such amendment involves no significant hazards consideration, notwithstanding the pendency before the Commission of a request for a hearing.

In addition, the legislation requi'vs the Commission to pe'iodically (!'ut 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 infor' nation is a copy of the Commission's Biweekly Notice of Applications and Amcndments to Operating Licenses invohing no significant hazards considerations, which was published in the Federal Register on July 11, 1990 (55 FR 28471)

Sincerely, Original signed bg Thome.s I. Earley Thomas E. Murley, Director Office of Nuclear Reactor Regulation

Enclosure:

Federal Register NotTce cc: Sen ' Alan K. Simpson DISTRIBUTION w/o enclosure:

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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 Honarable' Philip R. Sharp, Chairman Subcommittee on. Energy and Power i.

Committee on Energy and Commerce

~

United States Mouse of Representatives Washington, D. C.

20515 cc: Rep. Carlos Moorhead i-

l l

Federal Register / Vol. 55, No.133 / Wednesday, July it.1990 / Notices 284'71 Sheookty Nottee ^ ;M.,e arid Regule tory Commission. Washington, admitted as a party may amend the Amendmente to Operating Woenees DC 20555. and should cite the petition without requesting leave of the involving No Significant Hazarde publication date and page number of Board up to fifteen (15) days prior to the Considerettone this Federal Regleter notice. Written lirst prebearing conference scheduled in comments may also be delivere l to the prW% but such an amended L Beta g n e d Poom P 223, Phillips Building. 7920 petition must satisfy the specificity Pursuant to Public Law (P.L) 97 415, Norfolk Avenue, Bethesda, Maryland requirements described above, th2 Nuclear Regulatory Commission (the from 7:30 a.m. to 4:15 p.m. Copies of Not later than fifteen (15) days prior to Ccmmission)is publishing this regular written comments received may be the first prehearing conference biweekly notice. P.L. 97 415 revised examined at the NRC Public Document scheduled in the proceeding, a petitioner section 180 of the Atomic Energy Act of Room, the Celman Building. 2120 L shall file a supplement to the petition to 3

1954, as amended (the Act), to require Street, NW Washington, D" %e filing intervene which must include a list of 9e the Commis&lon to publish notice of any of requests for bearing and petibons for the contentions which are sought to be cmendments issued, or proposed to be leave to intervene is discussed below, litigated in the matter. Each contention F

issued. under a new provision of section By August 10.1990 the licensee may must consist of a specific statement of 123 of the Act.nis provision grants the file a request for a hearing with respect tne issue oflaw or fact to be raised or Commission the authority to issue and to issuance of the amendment to the troy ed. in ad m ke immediately effective any subject facili operating license and p

d xp of e emendment to an operating license u o any person one interest may be bases of the contention and a concise a determination by the Commission at aflected by this proceeding and who such amendrnent involves no significant wishes to participate as a party in the statement of the alleged facts or expert opinion which support the contention hasards consideration, notwithstar' ding proceeding must file a written petition rely in proving the contenb,r intends to and on which the petitione i

'.hs pendency before the Commission of for lesvu to intervene. Requests for a on at the a ruest for a hearing from any person.

hearing and petitions for leave to

' Itis biweekly notice includes ali intervene shall be filed in accordance hearing. The pe'itioner must also notices of amenUnents issued, or with the Cor. mission's " Rules of provide references to those specific

' irces ind documents of which the proposed to be losued from jene 15,1990 Practice for Domestic Ucensing through June 27.19e0. %e last biweekly Proceedings"in to CFR Part 2.

getitioner is aware and on which the i

notice was published on June 27,1990. ' interested persons should ct'nsult a petitioner intends to rely to establish current copy of 10 CFR1714 which is those facts or expert opinion, Petitioner t

NOTICE OF CONSIDERATION OF available at the Commiulon's public must provide sufficient information to ISSUANCE OF AMENDMENT TO Document Room, the Gelman Building, show that a genuine dispute exists with FACILITY OPERATING IJCENR8? /.ND 2120 L Street, NW., Washington, DC the applicant on a material issue of law PROPOSED NO SIGNIFICANT 20655 and at the local Public Document or fact. Contentions shall be limited to HAZARDS CONSIDERATION Room for the particular facility involved. matters within the occpe of the DEITRMINATION AND If a request for a hearing or petition for amendments under consideration. %e OPPORRTNITY FOR HEARING leave to intervene is filed by the above contention must be one which, if proven.

I The Commission has made a proposed date, the Commiulon or an Atomic would enutie the petitioner to relief. A dstermination that the following Safety and Licensing Board, designated petitioner who falls to file sech a emendment requests involve no by the Commission or by the Chairman supplement which satisfies these significant hazards canalderation. Under of the Atomic Safety and ucensing requirements with respect to at least one the Commission's regulations in 10 CFR Board Panel, will ru'e on the request contentbn will not be permitted to 50.92, this means that operation of the and/or petition and the Secretary or the participate as a party.

facility in accordance with the proposed designated Atomic Safety and Licensing

%ose permitted to intervene become amendments would not (1) Involve a board willissue a notice of hearing or parties to the proceeding, subject to any significant increase in the probability or en appropriate order, limitations in the order granting leave to consequences of an accident previously As required by to CFR 2.714, a intervene, and have the opportunity to evaluated; or (2) Create the poolb!!!ty of petition for leave to intervene shall set participate fully in the conduct of the a new c-different kind of accident from forth with particularity the interest of bearing, including the opportunity to any accident previously evaluated; or (3) the petitioner in the proceeding, and present evidence and cross. examine involve a algnificant reduction in a how that interest may be affected by the witnesses' margin of safety,%e basis for this results of the proceeding.The pv.tition If a hearing is requested. the proposed determination for each should specifically explain the reasona Commluin will make a naal emendment request is shown below, wh[ intervention should be permitted 4

detennination a the inue of no na Commission is seeking public wit particular reference to the significant haards consideration. The comments on this proposed following factors:(1) the nature of the final determination will serve to decide dttermination. Any comments received petitioner's right under the Act to be when the hearing is held.

within 30 days after the date of made a party to the proceeding: (2) the publication of this notice will be nature and extent of the petitioner's If the final determination is that the considered in making any final property, financial, or other interest in amendment request involves no determination. The Commission will not the proceeding: and (3) the possible significant hazards consideration, the normally make a final determination effect of any order which may be Commission may issue the amendment unless it receives a request for a entered in the proce eding on the and make it immediately effective, hearing.

petitioner's interest.The petition should notwithstanding the request for a Wntten comments may be submitted doo identify the specific aspect (s) of the hearing. Any hearing held would take by mail to the Regulatory Publications subject matter of the proceeding as to place after luuance of the amendment.

Ihanch, Division of Freedom of which petitioner wishes to intervene, if the final determinatien is thet the trJormation and Publications Servicer, Any person who has filed a petition for amendment involves a significant Office of Administration, U.S. Nuclear leave to intervene or who has been hazards consideretion, any hearing held

~

as473 Federal Register / Vol. 55. No.133 / Wednesday, July 11, 1990 / N tices would take olace before the inuance of 2120 L Street. NW., Washlagton. DC.

system. E& life :! the RCCAs will t

eny amenda-nt.

and a..he local public document room also be extended.

Normally, the Commissia will not for the particular facility involved.

(2)b pmposed change wulnot insi.e the amendment until the Doest Nos.

create the possibility of a new or expiration of the 30< lay codos period.

Alabama power Company $8. Farley different kind of accident from any Howewar, should circums:ances change ad m M during the notice period such that failure Nuclear Piant. Units 1 and 3. Houstan accident previously evaluated because to act in a timely way would result, for County Alabama the RCCAs will continue to meet their functional requimments.%e RCCA will example,in deratina or shutdown of the Dots of amendments rogueste June 12' remain inserted in the guide thimbles of f:cility, the Commission ma[e;ma the1990 bf 1 Mi" beenee amendment before t Descriptica of amendmerge requeet with he w I ts-cxpiration of the 30<ta notice period.

b proposed amendments redefhe the gag '

e provided that its final etermination is fully withdrewe position of au rod CRD is """ffected I this ch 8

I ht the amendment involves no cluster control assembly (RCCA) banks et Ipe&dicaUy aposm""oning signthcant hazards considerstion. %e to minimise lae=h=d RCCA wear, he e

final determination will consider all fuDy withdrawn paa! tion is eurmatly the RCCAsis boended by the Parley public and State comments received defined as 228 steps above sod bottom.

sahty ana y a and thmfom wW not g

j before action is taken. Should the ne proposed changen wiH aDow the propagate to a new or different accident.

Comodoenon take thle action. lt will RCCA banks to be desipated as fully (3)he proposed change will not blish a nottos ofissuance and provide withdrawn between stepe 235 and ag1.

lavolve a signihant reduction in a pv opportunity for a hearing after inclusive. nie allows reposit6oning of margin of safety because RCCA oce, b Comm! salon expects that RCCAs to d'stribute the wear that may Mpoemaning has an insignificant effect a need to take this eetion will occur be caused by core flowinduced a control rod drop time,brefore, rod very infrequently.

vibration.

drop time will continue to be bounded A request for a hearing or a petition for leave to intervene must be filed with kr/s forpmposedno sipi%t by that assumed in the Farley safety the Sea *tary of & Commisalon,IL.

hazc.rds considemt/on determinot/on, analysis.bre will also be mimmal i

3, ;ommission has provided impact on core physics charceteristics.

{

Nuclear Regulatory Commisslor, standards for determining whether a no Kay safety parametore considered in Washington, DC 30555. Attention:

sir.dficant hasards consideration exists reactor reir* such as those used te the i

Docketing and Sonicos Branch.,or may ce stated in 10 CFR so.g2(c). A proposed calculae 9tmed to verify be delivered to the Commission a pu tdc amendment to en operating license shutd a and peaking factors Document Emm. the Galman DuW.

involves no significant hasards were eu a and shown not to 2120 L Street, NW., Washington, DC. Ly ths above date. Where petiticos am consideration if operation of the facility vie.ny safety analysis assumptions, filed during the last ten (10) d rys of the in accordance with the proposed The a.iect is negligible since the top notice period, it is requestod tiat tne amendment would not:(1)lavolve a region of the core has such low worth, petitioner prosnptly so inform the significant increase in the probability or consequently, the resultant power Co==Imalen by a toll fme telaMone call consequenceso8an accident previously distribution perturbations are minimal evaluated; or (2) Create the possibility of and can be accommodated with ofr'i e new or different kind of accident from available margin. Also, by keeping the W

I U

@ uld be W any accident previounty evaluated; or (3) tip-to.tlp distance during overlap iny lve a signlEcant reduction in a operation the same for b proposed D gr I atification Nu r3737 end the following messags addressed to margin of safety, definition of fully withdrawn, axial (Pio/ect Director): petitioner's name and Alabuma Power Compar (the power behavior as a function power tele bone number; date etition was licensee)has reviewed the ;oposed level will be maintained.

i malfed;flaat name: and blication changes and has determined that the The licensee has concluded that the date an page number o this Federal.

requested amendments do not involve a proposed amandmants meet the three Register nouce. A copy of the petition significaM hazards consideration for the standards in 10 CFR 80.92 and, abould also be sent to the Office of the following reasons:

brefore, involve no significant hazards General Counsel, U.S. Nuclear (1)De proposed change will not consideration.

l R:gulatory Commission, Washington, increau the probability or The NRC staff has made a preliminary DC 20555, and to the at;orney for the cmsequences of an accident pmvinely review of the licensee's no significant

licsneee, evaluated because RCCA repositioning hazards consideration determination Nontimely filings of petitions for lesve will not result in any design or l

to intervene, ernded petition,,

regulatory limits being exceeded with and agrees with the licensee's analysis.

supplemental petitions and/or reauests respect to Se safety analyses Accordingly, the Commlulon proposes l

for hearing will not be entertained documented in the Farley Final Safety to determine that the requested 1

ebsent a determination by the Analysis Report (FSAR).no assumed amendments do not involve a significant hazards consideration Commiulon. the presiding officer or the control rod drop time and reload safety prtsiding Atomic Safety and Licensing analysis parameters remain tendmg LocalPublic Document Room l

Bo rd, that the petition and/or request in addition, since the change does not locat2on Houston Love Memorial shruld be granted based upon a impact any conditions that would 1.lbrary,212 W.Eurdesbaw Street. P.O.

balancing of factors specified in 10 CFR initiate a transient, the probability of Box 1300. Dothan. Alabama 36302 2.714(a)(1)(i)-(v) and 2.714(d).

previously analped events is not Attoracyfor licensee: En.est L Blake.

For further details with respect to this increased. Also RCCA repositioning Esq Shaw, Pittman. Potts and action, see h application for will reduce the poulbility of rod Trowbridge. 2300 N Street. NW.,

l amendment which is avallable for public cladding failure. thereby minimun. %

Washington. DC 20037 inspection at the Commlulon's Public chance of absorber material being AWCPNfectDiivetor Elinor C.

1 tbm=*at Room. the Celman Duikling.

Introduced into the reactor coolant Adensam

l-l l

l Fedecal Regletor / Vol. 56, No.133 / Wednesday, July 11, 1900 / Noticu ass'p3 Alabenwa Powne ra=y, Dodet Mos.

operabili of the staties betteries are conaservences of an accident previously r

80-%s and sHed. leespb M. Feeley still be on the recomrnendations of evaluated; or (2) Create the poselbility of Nuclose Plant, Unles 1 and I, Hometas IEEE Standard 400-1980, "IEEE a new or diffwent kind of accident from County, Alabama Recommended Practice for any accident previonely evaluated; or (3)

Dode of amendments sequeste }une is, Maintenance. Testing and Replacement involve a significant reduction in a 1000 of Large Lead Storage Batteeses Ier margin of safety.

Descripilom of oseendmente roguest.

Cemoting Seations and Subeteetons" he beenses has provided the De Proposed amendment revise,

%e betternes are attu sogehod to following analysis of no significant Technical Specifications 4.s.2.1.2.c.5 and demonstrate the abOMy to amery leed' hazarde considerstion using the 4.83 a

• r a no delete the ulvelent load requimd ede duden boele ersecy Commiselon's standards.

profiles provided in table that are ombtions, Cawqwntly, agins of ne proposed danse does not ruult in a associoted with the battery service test.

safety am ac1:wdeced.

elsnificant imameos le the probability or h ucensee has concluded that the omwquene e et accideais previonely The tables would be toplead with a stalement requartog that the botterise be pr* Posed aerandmenta meet the these evalusied. Commonweehh Edmon hee standards la to TR BBfla and, conducted an extenelve seriew of b tested by subjecting them to an themimMn no W hasasde documat=un nlated to the toegrHy M b equivalent load rollie based on consideration.

Zion Stellan's Unit t and a Reactor Vmels.

ordckpated beh operations mquired The NRC staff has enede a prelladnary %ese reviewe included the following wer and k>ss.of.

during Ic.es.of offaits ~

mview of the boensee's no signNiennt do===tec Reacter Veneel Serveillance coolant accident con tions.

besude coMMedon dN&

Capselen Heatup and Cooldown Curm, Basis forpr Nutmn Fluona Analysis. Reactor Venel hazards com,opesed no sign (ficant and 88es with the licassee'8 analyals Prwourised Thermal tibock. Fracture deroflon determination AccorM, the h=h proposes hinhanico Analyels, and the Final Safety

%e Commission has provided to determine that the sostuested Analysis Report.%e roeutta of these reviews of andards for deteredning whether a no Am*Dd8Be888 do not invo ** a significant conctoded that the most hmittng weld s!pificant hasards esmonderat6cn exists hasards essaideratian.

neutron fluence hee ameined enchanged, por as stated in to CFR 80.83(c). A proposed LocoIPu6he Dessneient Room both Reactor Vessels, the eenet hmiting weld amendnW to an opmting henne location: Houstoo4mee hismor6el is WF m his wold has been used la all involves no significant hazards Ubrary, 212 W. Bordeobew Street. P.O.

appeopetete c=wattons. As such, this consideration if operation of the fac'lity Box 13es, Dothem. Alabama sesos change is cemetdered to be adsuntetrative in accordance with the proposed A florney jbr licenses: Ernest 1. Blake, since it is manly oormcting then ernre of amendment would not:(t) Involve a Esq., Shaw, Pitanan Potts and omission and a traanposition error that has ban shown to have no impact on plant significent increase in the probabihty or Trowbridge,2300 N 8treet, NW oPersWn or safe 4 con %w of an accident pmvfously Washington. DC 20037 e proposed change dou not crate b evaluated; or (2) Create the poestbuity of NRCPropect Director: Ehnor C, Pow a w or ht kind d a new or different kind of eccident from Adensam accidat on; dat pmvimly any accident previously evaluated; or (3) involve a signiftcent reduction in a Counsnonweahh Edison Cosapaay, e=W W W densde conwes

• "" **' "'""d d** 88

• d**""** ' y' Docket Nos.5Ntes and et 404, Eien a ' of sef A bema detCompany (the Nudoar Power Station, Unite 1 and 2,

['Q

• • • "*d' licensee) has reviewed the proposed I'ake Causdy,ilnsole De most healting weld hee been used in all changes and has determined that the Date of application for amendaients necessary calculation.These changes are restweeted amendments do not involve a Aprd 25,1990 being made to conect administratave errors, significant hesordo consideretion for the Description of amendaients request As such the poulbaity for a new or different following reaeono:

De proposed amendments would type of acclaent le not belag introduced.

We pmpond change de not inmin e 1, he penposed change will not cornet inconsistencies la the Reactor increase the probability or Vessel Toughnese Tables (Tables 3.3.21 d7% dl cum ch'dit "d

rey commequences of an accident previously and 3.3.2 2) in the Technical has been concluded that the snargin of safety eveluetaL The change le administrettve Specificetione for Zion. Units 1 and 2.

will remain nochanged. Die concluion to in nature in that Technical These inconsistencies consist of the based on the sect that the luniting weld Specifications will still require testing of omission of three weld materials from location used in b calculation of operational the batteries based on expected loads the Unit 1 and 2 Reactor Vessel limitsuons, such as the tientup and during IDSP and 1.OCA coalitions.

Toughness Tables, and the interchange Cooldown Curves and Preuurized nermal Since it is still required that the betteries of the lower and intetunediata shell shock, has r-nal=ad b same.

demonstrate the abdity to cairy the matwiele la the Unit 2 data table.ne, Based on the above discussions, the design basis emergency loads, the changes are considered to be licanase concluded that the proposed response of the piamt to previously adminletrative in nature and do not abr arnendment request does not involve a significant increase in the probability or evaluated acesdants will not be affected. current %.ihg hmitations.

2.no propeeed change does not Basisforproposedno significant

- consequences of an accident previously create the poesibuity of a new te hasartis c9nsideratian desarminallan:

evaluated; does not create the diff-rent kind of accident than any The Comraission has provided possibility of a new or different kind of accident previously evaluated. Since no standard 2 for detennining whether a accident from any accident previously change la being made to the design, signif;u.at hazards camawretion exists evaluated; and does not involve a operation, semintenance or testing of the as stred in to CFR SEL92. A proposed reduction in the required margin of plant, a tww anode of fauure le act arn'indament to an operating beense for a

safety, created. A new or different kind of facihty htvolves no algaificant hazards The staff has reviewed the licensee's accident cowid, therefore, not result.

consideration if operation of the facility no n=*=at hazards ccosidaration

3. He proposed change does not in acmedann with a proposed determination and agrees with the reduce a margin of safety, Sarveillance amendment would not:(1) hevolve a licensee's analysis. H ' ndf, therefore, requirements for demonstrating the significant lacrease in the probability or proposes to detennine that the licensee's i

38474 Federal Register / Vol. 55, No.133 / Wednesday, Jaly 11, 1000 / Natices request does not involve a significant ntabliebed to amure that the lowest level of accident from any accident previously hasards conalderation.

funcuanal espebthty and performance evaluated; and does not involve a 89*1"d I" **Ie oPmden of he focui Loccipublic Document floom g [" "M %,, " reduction in the required margin of locotioru Waukegan Public Library,128 safety.

N. County Street, Woukegan, Blinois

,,q Cadiuon I,ar opmum b not awt.'Umush N staff has reviewed the licensee's 80085.

these actions. the consequenose for em no significant hazards consideretion Attorney tolicensee Michael L Miller, accident would roman within the tiraite determination and agrees with the Esquire; Sidley and Austin. One First estabhebed in the Final Safety Ana'.yene licensee's analysis %e staff, therefore, National Plaza. Chicago Blinois 80000.

Report. ne remedial actione spectly an proposes to determine that the licensee's NACprofect Director: Richard J.

alloweble outase time period not se anosed r request does not involve a significant Barrett d*Y'-

• "P'*

g, phu lowl of basards consideration, e--wealth Edison t% apany, desredation without Yfunctional locolpublicDocumentRoom Docket Nea. gHes and IHet. Elas cambiuty.nle level of degradition is location: Waukegan Public Library,128 Nuclear Power Station, Units 1 and 2, conservettw based on tlw estety function of N. County Street, Waukegan, Illinois take CountI' Illinois tlw entem, and me nuowaW outage une 80005*

period epectned for other Engineered Safety Date of applicctionforamendments:

reeturee of stallar enfety signincance.

Attorneyforlicensee: Michael L April 27,1900 Surwithnos regelremente beve been Miller, Esquire: Sidley and Austin One Description of amendments sequest opectned to ensure that the oystem and First National Plaza. Cidcago, Illinois

%e proposed amendments would add a comPonente m tweed wlaoly.new teste

80000, specific Technical Specification to win assum facul apr "

l g,

,,g d g.

ung Cadi NRCpro/ectDirector: Richard J.

address the containment sprey recirculation function in the Technical rw opmuone.nh spciacauan hu been Barrett derived usine the analpes and evaluations Duke Power thp==y, et at, Docket Specifications for Zion, Units 1 and 2.

included in the Final Safety Analyele Report Nos.EH18 and BM14, Catawba me will provide new IJmiting nis propowd change does not meste the Conditions for Operation (LCO) to possibinty of a new or different kind of NuclearStation Unt:a1and 2. York eddress the functional requirements of accident stom any socAdent previously County. Son Cda the containme. ' spray system durtor the evaluated. It does not levolve the addition of Dole of amendment request }une 7,

'9*'

recirculation phase of cperetion.

g*&h,,,,,g,,4g,,,,g,,iramthose

'c 1990 Wsforpq, uendnoeign%nt

,q,,p,,,

on,,mtion of the Descriptionofamendmentre(w >

hasards consiaerotion determ! notion:

facmry 2 a maanar different

%e proposed revision to Techn), W W Commission has provided addrweed in the Final Safety Analyeu Specification (TS) 8.7.5b. would h',

standards for determining whether a Report.

the Standby Nuclear Service Wate significant hasards consideration ex.ists ne proposed change does not invcive a Pond (SNSWP) average water ae staled in to CFR 80.92. A proposed sisnificant mduction in a of safety, tempersture from e6.5' F to 92* F and the cmendment to an operating license for a his chaon le being pro to provide a facill inyt,1ves no significant hazards F de ng Cond1 Hon For elevation at which it is measured from u

gp _,Syste m 640 feet to 863 feet.%e associated TS cons erstion if operation of the facility in accordance with a proposed during the recirculation phase of a lmee of.

Bases 3/4.7.5 are also revised to reflect Coolant. Accident (LOCA). He alloweble this change.

amendment would not:(1) Involve a outase tinw perioda m consistent with thou h licensee has determined, based significant incman in the probabillt,v or used for eyetens of almuer safety consequences of an accident previously signb.ance at TJon Station. In the on analysis results, that monitoring for a svaluated; or (2) Create the possibility of recirculation mode of operation, the Reeldual madmum kmperature of 92* F at an c new or different kind of accident from ilut Removal (RHR) Pump System, a part of elevation of 563 feet in the SNSWP any accident previously evaluated; or (3)

Cm ins S m @CCS),

g g

g lavolve a significant reduction in a g,

ter, or belo F whi is margin of safet Contaia= ant Sprey Recirculation Phase suf%ient to provide an adequate source System from the coneala= ant metrculation ofcool water to diestpate the heat he licensee a provided the sump.nmfon. tlw aDowable utage time generet during a postulated lowof-following analysis of no significant pertodo have been selected to be consistent hazards consideration using the with the RHR Panp System.no coolant accident (LOCA)in one unit and Commission's standards.

Containannt Sprey Recirculation Phase cooldown of the other unit nie proposed change does not result in a System includes a requirement to verify at 30818forpt,oP088dtlo8/ allt, cant 8.

elsnificant increase in the probability or least 3 RCPCs an operable. Analyses have hozords considerot/on determinot/on; consequences of accidente pmytously been performed demonstrating that a total

%e f%==laa!cn has provided evaluated. no probability for an accident le loss of contain==nt sprey during es standards for determining whether a independent of the changes being propowd.

recirculation phase, would not result in a significant hazards consideration exists a

ne Containement Sprey Recirculation Phase also$c.nt incruse in containment preneure.

System function le not a procursor to any na ROvCe can accommodate the assumed (10 CFR 80.92(c)). A proposed cccident assumed in the Ftnal Safety poMECA heat loada. IA$e of containment amendment to an oEerstinO license for a Analyste Report. The function of the opry recirculation function does result in an facility involves no significant hazards Containment Sprey Recirculation Phase increase in temperature and pressure, bag consideration if operation of the facility Eyetem le to mitteste the consequences of an these increases are wou within au design in accordance with the proposed j

eccident.nenfore, through the limitatione and margha, amendment would not:(t) Involve a utablishnunt of a IJmiting Condition For Band on the previous discussions, the significant increase in the probability or l

Opmtion, the consequenese of an accident licensee concluded that the proposed consequences of an accident previously i

wiu mmetatlw esme. no enance amendment request does not involve a evalustad; or (2) Create tb.e possibility of l

I'j"d['M * "*" te of the significant increen it. We probability or a now or different kind of accident from g

containment Sprey Svetemh"."n"the consequences o! uraccident previously any accident previously evaluatsd; or (3) l nct,colauen o(opmuon w evaluated 4.. L-create the Involve a significant reduction in a l

IJmiting uen For Operetion has been possibillt-new or different kind of margin of safety.

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l i

)

I Federal Register / Vol. 55, No.133 / Wednesday. July 11, 1990 / Notices 28475 ne proposed revision would not The Comminaion has provided introduced by allouring the use of M involve a signiftcant increase in h standards for determining whether a HP! system as a newee af inventory for probability or consequences of at significant hasards oonalderaties emists boll off due to a lose of deoey heat eccident previously evaluated because as stated in to CFR 80.a2(ch A psoposed removal.%e proposed amendment will the SNSWP does not hittate any ani=aA===# to an operating license ter a not change the overall design and accident, and the change would ensure facility involves no a6pnifie==' hasarde eyetera function of the HP! system.his that a sufficient volume of weter is consideration if operation ca the facility change will allow the use of the HPl maintained at or below the required in cccordance with the proposed pumps and valve (s) as a sources [ sic] of temperature so that the SNSWP can amendment would not:(1) Involve a water for leventory replenishment in a meet its design basis of providing an significant increase la the probability of loss of Decay Heat Removal event. He adequate source of cooling water to consequences of an accidsei previously HPI valve availability is omriently dissipate the heet generated during e evaluated; or (2) Create the possibility of allowed as an inventory seerer durins postulated LOCA in one unit and i, new or differest klad of acddent from fdl M nW h E N lea l

cooldown of the other unit.

any acc6 dent previously evaleanad; or (3) l The proposed rettelon would not involve a e6satficant seduction in a n rmalmdeumlowTemperatwo create the possibility of a new or margin of safety.no hosesse proviled C-r-

= tion was evaluated and a different kind of accident from any an analysis that addreseed the above Safety Evan==tian Report issued la accident previonely evaluated because thrwe standards in the amendment assedaalse with Amendmnt Nanbw 96 ell essential equipment would function, application. De floonsee stated that the to the ANO-1 Facility Operating Ucense, ce nuded, and the licensee's analysis changes do not invoin a signfBeant De Procedural controle in place enews wnld eneure thet the design basis of hazards w L.M for the IM.g that - r.

. tion does not occur the SNSWP is met seesming a reasons:

by using the velve only after all other r

trmperetwo of 92* P et ens feet.

(1) involve a say=An==* Inceseos in sources of inventory addition have been Furthermore, no new modes of operation the psobability or oossequences of en exhausted, and, then, with operator are introduced.

accident previonaly evekssted.

sttention focused on LTOP Fina, the proposed revision would The chmage allows ese of the WI considerations.

not in a significant reduction in a system to mutigene a less of Decay Heat (3) involve a significant reduction in margin of ecfety because the doeten Removal event without v6eleting the margin of eefety*

beeis of the SNSWP cae still be met and Technical Spacinaationes no Tenhaical the essentiel equipment would function.

Speci8catsoe [ sic) coerently seentre the De proposed change allows use of as needed.

HPI blod volves to be elseed dunas the HP1 pump and associated valve (s) as Acnordingly, the Conunisolon low preeawe opereboo W prevent a new a source ofinventory addition to the proposes to determine that the temperature

• " = event.

RCS in a IAse of Decay Heat Removal anneschecate do not hivolve a significant ne proposed cheese would not event.This change dose not involve a hasards ana=6d= ration.

significantly increase the probebCity of significant reduction in the margin of h/ PhrMic Docunent Room a low temperatere overpreneurination safety and in fact w'llincrease the locedon: York County Library,134 East accident because of the avellebikey of magia of safety by adding an additional Black Street, Rock Hill. South Carolina the Electromatic Relief Valve, which is source as r=ca===nded in Generic 29730 reset for a value associated with low letter No. 8817.no HPl valn Attorneyforhansre:Mr. Albert Carr, pressure Duke Pown Company,422 South controle

' times, med preeedwal avalleMlley le careetty ellowed for RCS requhe the throttling el fdl and vent and other evolutions.ne Church Street, Charlotte, North Carolina HP1 flow coasteleet with the available procedural controls ensure that.

2A242 vent path. Additionally, once cooled overpressurization does not occur by NRCPrwect Director: Duvid B.

down e._ : _h manway is seenoved using the vain only after all other 7

Matthews to provide a vent path to preclude RCS sources ofinventary addition how ben EnWy 'W'sas Nuclear One, U.dt 1, Pope {*ressurinetson due to a loss of decay nhmeted, and, kn, e oper m inc Dodat No. 80 113,Ankan

[

'% mt ed%

etiention focused on LTOP County, Mansas considerahna-affect the consequences of accideota Date of amendment trquest May 22.

which have prevsoesty been evaluated.

The NRC eteif has rev6ewed the 1990 he proposed change makes available.

licensee's no sigrdficant bezards Description of ar<ndment requesti without violation of Technacal consideration L. 4.ation analyels The proposed s.nendment would mod fy Specification, the HPI system as a and agrees with its conclusion.

Specification 3.1.2.10 of the Arkansas source of makeup for a hees of leventary herefore, the staff proposee to Nuclear One. Unit 1, Technical condition while in Decay Heat Removal determine that the requested SpeciBcations to allow the use of high Operations, and therefore increases the amendment inveives no significant pressure injection for emergency RCS ability to mitiente the consequences of a hasarde r&.tlen.

makeup durmg decay heat removal loss of Decay Heat Removal ev'ent. This Loco /Fublic Document Room operations as recommended by Generic change to the Technical Specification location:Tomlinson ubrary, Arkansas letter 6647.nis modification would will not alter the plant capabilities o' Tech University Russellville. Arkansas a--

-te will placed in the tional Condition spedfled operoting license le anchanged and the Provide an adequate level of salety and edll - by the A requiressants while still -

requiremente of the cumnt enfoty analyene presently allow contiamed operation for an adowtng surveillance to be..L _ ' la a am maintained; therefore, ne new evente r

enlunited perMd of time once the higher timely mannar.

have been introduced by the proposed Opereuonel Coedition is obtaland The RBS Another area of conflict with regard to changes.

Technical Specifications have been reviewed Specincations 4.0J and 4A4 is when 8.nie request would not involve a cad CSU hee confirmed that all current surveillanas requtmmente can only be elsnificant reduction in the snargin of ulety remedial ACTON etatemente do peevide en completed after entry into the Operational because:

1 cceeptable level of eefety far continood plar.1 Condition when they apply'.nese Technical ne proposed changes to Specification SA4 operation for an pahnf ted period of time and Spec 1Scotions currently contah. an exception aHw p% mp udw Mm M i

thmfon, no change to the plant neponse to to Specincetion 4A4, As identifled la the e with t cny event me described in ttw safety analyste Generic Letter, the proposed ediance to which contenanc.gg,he ACTION

,,q,g,,,,g.

,opg g report resulta.

Specification 4As will permit a delay of up to

,g g.,7 g,,,g oPeng gw an Resolution to the second proWem area 34 hours3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> la the a ltombility of the ACVON unhmited PerW of Has as pmviously eddreend in Generic letter 37 Og revises requirements to a ow aQ ~te time for approved. Startup would still be prohibited Specification 4 A3 by allowing up to e M hour the completion of the m

- where wbon b ACHON requireewate provide no time hmit to complete a miend surveillance epocine exception to the requiremente of 4A4 r==

at acuan Iw matinued plant requirement befom the unit le required to am required.

opersoon.b proposed change to initiate the requirements of the ACTION Consistent with the guintamaa provided in statement. Surveillances are required to the Generic letter, this le noosptable since Speciacation 4A8 aHowe an oppropriate time demonstrate that eyetems or componente are the change to 4A4 resolves conDicts with f# perfaming a missed surveillance before operable. Since the large ma}ority of 4A3 and allows the plaat to be plamd in the shutdown requiremente apply, nie proposed surveillancee are successful the am fact Operetional Condition prescribed by the time limit le based span appropriate

(

that e serveillance is missed doce not Technical Specificatione and thereby, conalderation of plant conditions, adequate indicate ht e system or component is maintaining the conditions assumed in the planning, evellability of personnel and the

(

inoperable. no proposed M hour delay le current safety analyste, time to perform the surveillance. As based upon considerations to allow adequate ne proposed change to Technical recogniend by the NRC Staff in the Generic plannin6 resource (personnel, material)

Specification Table 8.3J.11. ACTION y2 le 14tter,it le overly ananarvative to assume etssing and perfor=== of the rarve111ance editorial only. As eve, this proposed change that systems or componeots are inoperable or to allow sufficient time for es gulatory cannot increase the robabluty or the solely because a required surveillance has tetion (temporary waiver or lio noe consequences of any accident previously notbasei a - f nerefore, allowing cmendment)if the surveillance ien not be evaluated. STARTUP le the approprieto sufficient time to perform the survel11ance performed nie time hmit also ellows for defined Operational Condition for RBS.

reduces the risk of plant speet while completion of surveillances that wcome 3.nis request would not create the performing the missed marvediam and appbcable as a consequence of Cc wretional possibthey of a new or different kind of therefore, does not significantly reduce the Condition changes imposed by At *f10N accident from any accident previously 12argin of safety, requirements. Consistent with the guidance evaluated because:

ne finalproposed changes to provided in the Generic latter, tbs propowd ne proposed changes to Specification 3A4 Specification 4A4 are clarification only to change is emeptable slace it is overly are to allow placing RBS in a higher permit passage through or to Operational conservative to sasume that a system or Operstional Condition only when continued Conditions as required to comply with component le inoperable ec'.e:y due to e

- compliance with the ACTION requiremente AC110N requiremente even though a miend surveillance and the proposed change will maintain the plant within the surveillance requirement niey not have been reduces the potential for plant uput when eseumptions of the current safety analyela.

performed. De proposed revision would also ACI10N requimmente do not allow edequete Therefore, the proposed chansee do not affect permit mode changes when a surveillance time to perform the mined surveillance. ns the design or configuratice of RBS se requirement has not been met and can only time hmite of AC110N requirements wouli.

assumed in the curnet safety analysia.

be completed after entering into the become appbcable if it le determined that the The propoeod changes to Specification 4A3 Operetional Condidon where it le applicable.

affected equipment le inoperable and are to allow sufficient time to complete This poposed change does not a6snificantly therefore, the plant will be requimd to t4 inedvertently missed surveillances. If the reduce the margin of safety, but in fact, placed in a condition (configuretion) althin equipment in question le determined to be potentially inaeases the margin of safety by the curant sefety analysis as re,ared by the inoperable, comphance with apphcable permitting entry into lower modes of Technical Specifications.

ACTION requiremente muet be completed.

operetion se required to comply with pe.olutton to the third problem area thereby placin4 the plant in a condinon ACT10N requiremente, addreseed in Generic 14 tier 37 00 revices within the current safety analysia.

The propomd change to Technical Specificahon 4114 to address conflicts ne proposed changes to Specification Specification Toble 3 3.7.11. Action 73 le between Specificationa 4J0.3 and 4A4.ne 444, when coupled with the proposed editorial only and therefore, cannot reduce changes to Specification 4A3. will allow a the margin of safety. STARTUP is the first eroe of cen!!!ct arisee becaun s

Specification 4A4 does not allow entry into change to the plant Operetional Condition

.ppropriate defined Operational Condition ao Operational Candition when the when the associated surveiltence requirement for Iws, apphcable surveillance have not been has not been astie!!ed within the specified Beawl upon the above considerations, the performed.His requirement can result in a interval orovided the requimmente of th*

proposwl changes do not result in a confbet when a mode change is required by ACTION statement are initieted if the significant incrocos in the probebility or the ACIlON etatements and the survedlance component is found to be inoperable or consequees of any acddent previously requirements that become applicable have within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the surveillance has not evaluated do not caete the poselbt'ity of a not twen performed within the required been completed. As discussed above, new or different kind of accident than intervals.no proposed che.nge to compliance with the ACI1ON aquiremente previously evaluated and do not result in a Spci* cation to ?tetse that it shall not will place the plant within the current safety significant reduction la the margin of safety.

prevent peseage through or to Operational analysis.

Therefore, GSU proposee that no sigmficant Conditions required to compty with ACI10N The proposed change to Technical hazarde consideradone are 'mvolved wM etatements. A etmilar provision is almady Specificat on Table 3.3111. AC110N '3 is approval of the proposed changes.

Included in Srcification 3.0,4. His provision, editonal only and therefore, does not "Ihe staff has reviewed the licensee's when coupled with the propowd change to introduce any new operstmg or faibre Specificauon 4(L3 allowing e delsy of up to modes STAR 1VP is the appropriate defined no signficant hazards consideration 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> w perform the surveillance before Operational Condition for RBS.

determination. Based on the review and applying the shutdown requiremente of the With each of the proposed changes the the above discussions, the staff ACr10N e*stement, allows the plant to be design and configuration required by the proposes to determine that the proposed

i, 38478 Federal Regleter / Vol 55 No.133 / Wednesday, July it.1980 / Notices changes do not involve a signiacent a new or ddlerant kind of eend==t from' the Susquehanna Steam Electric Station hasarde eensidesat6on.

any seddest, mo, evalasted; er (3) Unit 1 Tschaloal Spectaeetions by LocalpwMe Denement Room involve a signl8 cent reduction in a adding several new cN ~mment location:Goverossent nar===its margb of safety, loolation valves to Teila GAS-1 related Department Ioulalane State University, ne hcensee has pmvided its analysis to "Prbnery Cantainawn!leolction Beton Rouge,lauloiene 7 eses of no significant hasard comelderatione Valves".%s new valves are belas Addo

)behoensee:hierk using the Ca===l= ton's standards:

added is an existing penetretion to Wetterha Eeq, Bishop Cook.Purcell (1) Ahhough velves 1HGott, and 1HGoty pesenti esperaties of th;nantal-mant and Reynolds,1401 L Street, NW.,

am===-e to be cleasd dedag ensident radiation maatters froalhe hydrogen /

Washingtan.DC 30005 cadutoes, the supend chase should not oxygen analysere and from post-NRCttojectD/tveror:Gristopher L y"g4

%=""a y

h accidset sampling system. All three Crimes k spes pestian des w administren,,

monitoring systems presently sham a Bunele Power Caesynny and Boyland controle employed over these valves and the common containment penetration.

power tsmy=== Gee, hee., Dedat No, SS-lect that they em aaly opened to pedeem leek Aasiefor nosign/ficand -

i l'

est CBates power Sto6en, Uutt No.1.

rete testing of their sostelmat pentrenen, hasards tion dessienhietma:

DeWitt County,IReele Dnen inaroesetheprobahutty has pelded L * = =' h a>3e - iaerea i i-

1. ve*dr W """*

r'ee;sd.

(11uncatk.a of the ear,.m laterval (10 CFR stLSE(c)). A proposed

@ of.ameadnest rupeeg.

for valves IHCete sad 1HG017 from every 31 amendment to an operating liaan== for a a

woukt add g

tw Ivolves e e loomote e days to every se e, derieg seid eheodown, facility involvte no atyn1Acant hasards does est asset the

' er up hti a of any consideration if operation of the faculty Tw.imical SpecMoe8on SurvvHlam component, system, or structen and in accordance with tlyi proposed l

Requirement 4A1.1.6 wtuch exempts therefom wul not areste the possibGity of eaF

=W would not (1)levolve a certain containment teolation bund new ar diserest kind of oceident from anF signhaat teorease in he pr=haha% or flanges, valves, and deactivated accident evaluated.

automatic valves fram the requimment (slm cheese does not affect the conomimecos of an accident presely that the posttion of these valves emot be coo'a'===w rete or ite -- -

t.

evaluated:(f) Create the poselbQfty of a verified every 31 days, to emeum that Since the same valve lockhs program and new or h kind of an'idant from administraeve osotrole wul continue to be any accident previously evahnsted; or (3) containment integrity le==i=a=6=.4 utihud, the probab'hty of the test comection Involve a algnincant reduction in a nie exempden wee approved to allow bileNeoges,' valves, M,y,og,,,,,, ",,,,,,,i,,,,,,e % to t$

g b staff has m6ewed the lia====='s and deactiveted automatic valves which

,,g.

,y am locked or eseled and are ceUy row should occur, request and concare with the feBewing located in areas with high Based on the pmvlous discuestons, the beels and conclusion provided by the fields, such as the prbnery containment, licensee concluded that the proposed licensee in its April 17,13eo submittal.

drywell or the steam tunnel, to only be amendment request does not involve a

'h* propowd changa do not vert 6ed when the unit is to cold significant increase in the peobabuity se Lloveiw a e@lficantimemene in es shutdown and sediation Aelde are conseguemose of an soc 6 dent -- - ',-

proh hnny er=====q=== el an accident greetly reduced shes to the absence of e, elected, does not create die P"*"'IF ***I"d'd-h "ad'8"*"

piplag tem redioactive attagen-poselbill of a new or dtiferent kind of

"""" ""d" "' Id"""I " 0"*'

Containasmt tenistaan valves,1HGo16 accident say accident previously h

and1HGoty are abe added to this evalneted, and does not involve a exemption. hey em locked and reduction in the margin of safety.

accidsens and % let me SBES ~

administratively controlled as vent and

%e staff has reviewed the tieaan=='s contehusses.When te en abeelsee==== ee drain velves for hydrogen recomibiner no signtAa=d hazards considerstien addenas of any emeses of addiennel return and supply pecstratione. Dey are determination and apees with the equipment een be enid to teoreese the physicallylocetad in the auxiliary licensee's emelyels, he staff, therefoes.

probd,uity of essenense et se easident. the building, adjacent to the steam tunnel, proposes to deteramine that ties addities of this equipment dose not incrosse where the radiation Gelds ceased bY requested amendment does not involve the probaneter of am a-ad== by en essent tedioactive altrogen in the main stessa a significant hasards consideration.

greater em the escorteisty b the crisiaal knee and emessor water cinemap lines Localptrblic Document Room accident probabeity emelysse med thus no create en envisenment sinust to that locatiorr Vespealan Wamer Public

'i a8ta=* 6 cheese in f

inside the steam tunnel, but are not in Library 120 West Jahnaam Street, probabimy son be esid m heve accermd due the tunnelitself-Clinton, Bhnois 81727 to thle modecanon.

Sosis forpreposedmo a(grr/ficant Attorneyforlacemose ShaldenZabel, h to as spectAc condition of thle

"*d 8 " 88" *' "*I' " 88" ** 8 " * ""*'

Aosortfr cons /driation drerrat/ notion:

Esq Sddff.Headia and Weise,7200 he Commiselon has provided Seere Tower,235 Wacker Detve,

• • ' "*dd 88 *ny accident analyste evaluated in &e FRAR and the small elas (l')

standards for detmnining whether a Chicago, Bitnote 30006

$'."My evalented previamely

_,hF e

cast consider tien existe MtCptofectDissesor John N.Hanaco be thorne amendment to an operating license for a Pennsylveala Power and IJsht facility levolves ao magneAcame hasafde Company, Dukat No.ES as7, h W M W ebangeunu ide nos W of du lacui 8""T==" Steams Elssede Staden, simply hees te new teoletism valvas. pio in wt proposed Unit 1. Leserne Cemety, Ptsumsylvemie cheese to operational estel amendement eroend not:(1) involve a Dateofamendmentreguset Apr017 Bened en he above, ao mig =enea=8 ineroam algmencast tecreene he the prehabuity er 1990 h thepeshabGity er enesegamensof en consequenose et en assident,a i

Descrydsen of ah sugessia me,samme p,e,tensly evelseesd alB esser due evaluated; or (2) Create the panelbolty of ne proposed amment==st weaki change to the proposed disage.

i l

- Federal Register / Vol. 55. No.133 / Wednesday, July 11. 1990 / Notices 28470 4

n. Creew the - N of a new or stem on the forward side of the new or different kind of accident from difteeni kind d econdent' free any accident efetform and is used for transporting any accident previously evaluated; or (3) p

• pmtoestymiwhd and orientating fuel assemblies and involve a significant reduction in a As escussed la I obe, noeles la &e control rod guides for reactor, store margin of safety.

'I rock, and shipping cask (fuel essem lies

%elicensee has provided an analysis du:p precuos.No hturm of he doden o, only) placement. Two aniliary holsts.

of no significant hasards consideration too locations for instaustion have beso each with a 1000 pound operating with the request for the Itense identined by any design ertterion that would cepac!!y are provided on either side of amendment. De licensee's analysis of t

indicate the existence of any mechanlem for the platform.%ese bolsts are used to the p oposed amendmeat agatr.st the i

ersetion of an socident or malfunction of a perform non-fuel core component three standards in 10 (ER 80.92 is different type than previously analysed in the activities involving core power monitors. reproduced below.

c ntrol rods, control rod aquide tubes, 1.no proposed chang do not involve e vok a dpinuM ndwoon la e fuel support casting, r4 Son source significant increase in the pe;.babihty or

,,,g,,g,,ggy As spectaed 2 I eW es new deden wtU holders, and,peneral servicing aids.

consequenees of an accident previouly med all apphoeblo design standards and le Procedurauy. the main hoist is evaluated.

l therefore consistent with the estabhshed required to be used for the handling of he mala holst normal stoplimit switch margin of safety that le defined by fuel assemblies or control rod guide le proposed tobe mloca on the main hoist socia-t lategrity requirements.

tuba. During the transfer of fuel gruppw mast such that main hoist motion will no Techance! SpeciBoebens directlF assemblies and double control rod guide stop not higher than elm (e)laches from its

)

affected by thle modificettom. 3A1.1 " Primary tubes between the reactor vessel and current posidon.nis position is well within j

the hoist design operating range. No other Contelament lotogrity." 3A12 " Primary the ePeat fuel p"1. a potential currently phyelcal changes will be performed on the Containment taakage." and SA8 " Primary exists for component contact with pool /

main hoist or the refuehng platform as e Containment Isoleuce Valvu" will be cavity structures (e.g portable refueling. rwult of this 'Ili changs.We main holet will sationed b having the isolation velves meet au apphcable surveillance requirements, shield) due to lack of clearance.his operate la the exact samt manner after the Mee these requirements will show that could cause equipment and/or carried switch retoottion u it did prior to the the non has no significant adverse component damage, proposed change. Derefore, handung of fuel tapact on any margin of safety.

Therefore, the licensee proposes to will not be has any differently than that Based on the above considerations, change the SRs for the main hoist to wbfch is done presently and that which wee the Commission proposee to determine allow the normal up stop limi' switch to consided in the bl handling accident. The that the proposed changes involve no be repositioned to provide more mair hotet will not be any more hkely to drop significan; hasards consideration.

clearance between a main hoist grapple, a carried fuel sammbly or the meet unably

' I'" b '""*" "I***

• loca1Public Document Room carried component and pool /covity De has pla main ho t location:Osterhout Free 1.ibrary, structures. This will maintain not leu

.g,

m.

so,

g Reference Department. 71 South than 6 feet 0 inches of water over the top faches highei than that which is prwently Franklin Street. Wilkes-Barre.

of active fuel with the e at normal permitted unting a greater poulble drop Pennsylvania 18701 water level. which correspond to distan<.e for a bl assembly.This situstion Attorneyforlicensee Jay Silberg.

epproximately 6 feet 6 inches of water willu ete fueland grapple meet drop Esquire. Shaw Pittman. Potts and above the top of the carried fuel distences of not more than 31 bt 11 tnches Trowbridge,2300 N Street NW.,

assembly. Also, the licensee proposes to and 4e ht e tachu. respectively. Nwever.

Washington. DC 2m37 clarify the main hoist SRs to remove the the fuel handhns accident sesumes drop NRCPmfect Director: Walter R.

refercnce to control rods, since the main distaces of 32 ht 0 inchu and 47 ht e Butler hoist is not used for handling of contml tachsamspetwely.Thefm. the mlysis a SAR Sedan 15;F rods and add the phrase "not less than" p

Niphk Elutric Compaan Dock before the uptravel stop distance.

condition that would exist after the main

,d db Noo, so asa and 30 453.Umord Also, the proposed TS ch a wiH hoist normal up stop hmit switch is reised.

Generating Station. Units 1 and 1.

tem ve the requirement for a el Rwtricting mbling platform auxiliary M

C% Pemylvania loaded auxiliary hoist interlock by hotetloods to lees than that of a ful Date of amendnet request: June 22.

prohibiting the hiting of a fuel asambly assembly will have no effect on the 1990 with the auxiliary hoist, and also permit ukelihood of tN fuel han< time accident. The Description of amendment request:

less water above the top of a carried fuel handling accident acenario which Technical Specification ('IS) changes are component. Part of the proposed produced the greatest bl damaga l

proposed for the refueling platform main auxiliary hoist TS change will clarify the considend the drop of a fut aseembly and hoist Survalliance Rersirements (SRs) requirements by adding the phrase not grePole meet maammhly from the refueling P atform while over the mactor.The fuel l

and the auxiliary hoist SRs to more leu than" before the uptravel stop HM8 M canP e nt accurately reflect their actual use. The distance.

88 ad the following provides a general description Basisforproposedno significant pp by of the refueling platform and associated horards consiaemtion determination eignifloant portion of the total drop mau holets and the proposed changes for the The Commission has provided censidered in the occidr:et scenetto. By SRs.

standards for determining whether a

-- ;", the auxntsry hoiste m The refueling platform to used to significant hazards determination exists procedurally prohibited from handhns fuel transport fuel and reactor core as stated in to CFR 50.92(c). A proposed and they have no mut enembly.nsit r.omponants to and from the refuel floor amendment to an operating license potential dmp meu and any resulting energy would be much leu than that for the main pools and cavities, and as a work involves no significant hazards platform from which underwater consideration if operation of the facility hotet. Since the auxiliary hotete play no role I,b "*

'N

$8 b activitiu can be conducted. ne in accordance with the proposed El f age o refueling platform hen thrw holets amendment would not:(1)lavolve

• of the analyzed accident.

through which many of these activities significant incree e in the probability of Removal of the auxiliary hotet fuelloaded f

are accomplished.The main hoist consequence o' an accident previously tr,*erlock leature through lood switch l

assembly is suspended from a trolley eveluated:(2) C: = ate the possibility of a recahbration will not adversely impact the

2850 Federal Regieter / Vol. 55 No.133 / Wedneed:y, July 11. 1990 / Notices R

knearleshsIRisk he Ris earve to sufficient need cepest be basulag feel Basisforproposedno sign!fico.tf meetst asumet af en entrol sale and sewehbes emi een senkn.he imod hazan/s conalderofion deterndaatiam the opesemos of the enhankap pleelsene to especity of the main heist to aut eSmused by Ihe f*="h has Pmide,d ruinierne operational z that possent the pospesed De pocheelei drop atandards for dekrmining wnetha a m

the reactor from becondas critical chartag_

distances and emangles ist e inst operesses. A hoest with a see Fl go ea===hly and the ymppio mest asemanhly sign $wd bamos considerstica exista poemde we est he skin to basse (Le, d

the postulated fuel headling socident as stated in to CFR 50.97 A proposed lift or transport) a Inst less rematn bomided by the analysis amendment to an operating license for a

(

poemdsk pesi see e.dy be welb1be presented to die PSAR. Tne potential lor facility involves no signihcant hazards meia heest and its essesteemd anest radiomettw rdenses a fast handhang conslucration if operation of the facility essembly whka willaan he by b accident weeld===h by the 21 accordance with a proposed change.brefor. the absense of a feel-aestysts presemned in the PSAR.

amendment would not O) Involve a noeded laterloch =a the eindliary hoiets wi!!

PhyelesDr. tis especHv ed eash===ihm signincant lacrease in the probability or not increase the Bkelihood of an inadvertent boist is met Idag altase:1Maes ao me i

criticality due to fust handlias errors.

changes are being undertakaa and the heiste consequences of an accident previously h proposed change wC allow the will be saatatained in the same maars evaluated; or (2) Creete the possibility of refue:Ang plationn aux 111ery hoiste to raise However, to retaforos admin streeve sentrole a new or dfHerent kind of accident fIom their tende not more than sta ts) toses bisher presently b piece to ensure lue: ensembtles any accident previously evaluated; or (3) than pma.nt!y avating a groeier are bandled in a este and out tro5ed manner lavolve s algnificant reduction in a possible drop fw any carried utthains only tie anste hotet pepple sumst margin d safety.

aa"'1===rt Howvur since a propowd sammeldy; the=== man heist leed sweeshoe Tb Lanese has evaluated the change metreets the semalloed to 100 will be seest so Gnat a fasi assumWy een est propomed aumendment ageinst ilte pounds, half of the cwasat vehse, the suergy - be handled.De potenhal amagy anneb standards provided above and has sveisshie wttb wtdch to sense feel damage from e dropped omdhary helse omrned would he less than the surrent vales.

-raa a weald he less them that wblah is strpplied the following htformation:

herefore, the total energy evefleble from as currently eve 11able and therefore to h== dad GI 8's )mnes A. FitxPetalck N ser Power Plent he occordance with th!s texseery heist dropped component wtB by the current FSAR analysis W poissual conttaue to be less than that prodused from far radioactive releases foI!owing a proposed esmoament wo rfd not twoln a the mate helst drop soonerto esaussed in the component drop la also boended by the signikant hasarde cenetdmtion, as defbed f3AR emetyees of a feel hendtlag accident.

current PSAR analyvie, in to CFR 50.92, eina the p vposed charqee would not nerefore, the proposed changes to of die mete and eaxillery hoises do no,the SRe Ptnelly, the oudhery hotets are

1. heolve e inscificant tmrease in the -

i precedureBy Wahlh6ted trem fuel handlms i

acevities ema he propeesd changes to the involve a reductan in a maargin of salsty, probetalsty or carwegeences of an accident tunihery hoiste SRe wiD setoforce these The staff has reviewed the twaa=.e's P*io"*IF "*3"***d N PNPoal chan*e is punty editorial h nature and cornetly restrictione. nerefore, en tsadvertent submittal and signFrent basarde attionmy enut destag refuelhas as discuswd analysis and concurs with the licensee's deternuning IPS operabliity.ne proposed in die ySAR wS est he e8seted.

deterudnaths as W whebt N change does not altar b frequency of in summunary. Gia proposed ehemsee to b main and auxthery heist SRs do not invote pro eme ingse e inspecuen; nor does it replace any en temmer in dw peebebthry or significant hazards conald-stio:L procedures.He proposed change doas not consequences of en =ML=a prwtously Therefore, the staff proposes to hnpact m>r eher arry parameter which is e ed evalmaassL determine that the proposed amendment in determintag the hkelihood or enerity of an L he proposed daugme do not creets b involves no significant hamde occident documented tn the ISAlt er NRC pouththey of a aser er defierent kind of consideration.

etaff's SER [ Final Safety Analysis Repart or accident tres any -en=t r - - A hico/Public Document Room the Safety Evolustion Report). W proposed 0'"8' "' " ' #"mty or consequences

W **"'

w ahnsend.

location Pottetown Public IJbrary,500 increase in the probeb b maata boost moramal op step huit switch liigh Street. Pottstown, PenneYiranla of an acedent previonely evaluated.

b its psayased immeon wel fumet 6en b 'he I

L Create the possibuity of a new or cxect emme masseur as it does now (La., the Atrortreyforlicensee Conner rad different kind of acchient from bee etrike pieer en the 30 kich meet

• wW Wetterhahn,1747 Penneyhrente Avenee, previously svaluated m propom! cLange opente b heat swind leur asus). No other physical chamese are to be partnrmed en the NW., Washington, DC 2000s clearly identifies the circuit breakers used for j

rtiuehng pleth:ss se a meelt of then proposed NRC Propxt Director: Walter R.

deterwining IPS operabihty, nis change le cheoge. De safeehus platform controllogic B Mler purely editorialin nature and does not impect circuits will met be ahmed. no head!!ng af CP*r*00nal procedures or anatutanance Power Authodty of the Stats of New schedales.n6e change wooid in no wey fuel and b #

of enderwat,,

acurteae will met te dune any diflerend; York nark at No, sNt33, Jennae A.

leen b plant in an unanalyud coachtwn.

from these pseeently perh-=a FitzPaidck Nurlaar Power Plant, b proposed chanae to the sumillance

& proposed TS 4-p== to the SRs be the Oswego, New York requfrements does not alter any accident cuxmary bedoes W est moefy or muh in Date of amendment request March 13, m

any hentwese dessus to the safsehme platfarin er ate suaHanry hetene. No nfuehng i hrecise a significent reductico in the 1990 pletforms omstral logic certadte will be altered.

Wh gomenda'ent requad masgiu of safety. %is change is purely

%e handhng of core compameets and the The proposed sawndment would correct edtto,talla nature and does not relen any performance of underweter activtt6es wGl not Technical Specification 42.F.6 e change admmistrative controle or limitations m be perfarenad d Deremey imm those presendy the location of the circuit breakers change cermeta the technical specifkaurme performad.

deocribed in the monthly surveulance by clearly identifytag wh.ch circuit breakers are nM iw aneets the unh

% endure, the proposed unesqree to the SRs test for the Low P&re Coolant mquinments Me W W (mow of the amen and esodhary h,emas do not create injection SK.8) Sye tout ladependent persted valvej IPs. nis charige dar, not l

b peestbdity of a esw or 45erent kmd of Power Suppbes GPSab Prearndy the alter the intent of the survetIlance l

sccident fnno any,

• evemented.

surved. lance teet ladierMe that the requirement and therefm t as ao impact on 3 he proposed champos do not turvolve a significant reduction tu a snargin of safety.

battery charger breake a are locoed et b margin of eefety.

no TS Bases for the vedmehog platform the output of the battery chargers.They The staf7 bas reviewed and agrees state in part that the opersbensty regaremente are.bowever, located at the ACinput with the licensee's analysis of the will ec.eum ht a refoehng sletform hoost has side of the IPS bettery chargers.

significant hazards considerstmn l

4 Fedesel Register / Vol. 65. No.133 / Wednesday, July % 1000 / Nodcas abett determin-tlan. Based on the review and le) second stans delay relay to the high steam messer Anahmsety of The State of New the above danceassion, the staff flow aa' add =ise logic. no sensequences of York. Donket No.m.833 tedlem Potet to determine that the proposed a swam kne mptem man with the tin

• Nedser % Uelt Ma.8.

0818F *"been analysed.no anatyete West 6emer Coasty,New Yes h

does met intelse e signinoant coundmotion.

shows thet with resord to enre nopease the local Ashlse th== mat Jtoomt to e ennsie j _'

M af a m e d m nt W lams 4.

MEb

• ba *t*Namt peak 19 @

location: Stees University of Now York

• i

• • '8d"' F dr*" ** **"

Descr(pilon of onedent agaset Pen. eld uhrery, Reference and a

Department. Oswego. New d7

• Ng*gh D' 0888"gP see to nrvi Astorney forlicenseur Mr. Charles M.

M.$ 42.42 vs 47 paisk

4. " SAFE'!Y INJECI'lON High Sasam con Pratt.1ssa Broadway, New York New nerdere, is can be concladed that these as Flow h 2/4 Sesem Lines Coincident with York scirls, out a significant inasese la the probabuity or leie Te er Low Steam Une Pressure")

NRChefectDerecsarRobert A.

consequences of an socident pmteuety ofthe hint 3 Technical Capra m tested.

8Pocifloations/fbe Technical (2) Does the propeeed beense amendment S ciaceitans would be revised to Power Aastbority of The Stats of New

,,eets the poselbany d e new or different nge Iba painimum number of York.Dodat No. 9MB. ladian Point kind of eensdeat eram any aestemet piovtsesly - operable channels af the high steam Nedser Genere8ag Unit No. 3.

evaluatedt flow circuitry. ineen "2 ebennels in each Westchestee Conanty, New York ne addition of redundant eme deinF of 3 emomhoes"to t/steamlinein a

DoJe of assendssentsugesesteJune 6 mleys to de high amen eeu umsident assic each of 3 steem times " and the mialaism does not arente the pensahday of a now er d

e of

' -- from "I" to "1/

et lirEin ses of$ eteam lines."

Descriptiaer sqf amenskneat sequest-

.g[g,,'g",g,,",'0**',

1. E p,,

g,,,

ne licensee proposes to revise Sech" which will he asi-aanuy destened, m These changes would make this.

3.5 (Tsble 3.5r1 and the Basis) of t) e deoiped as wiessend a eagle faamm m "Pactrication consistent with standard Indian Phit 3 (IP.8) Technical failun mode for the time deley esimye is a methodology which permits the Speciteetione.%e Tochtdoel shart of the relay and which reseles en idown minismaan ma'enAmar of operable aikan=ala Specineatious are being revloed to fume for the edested teen of Enghnessed to be oss less lhets the number af include up to a six (6) eeoond thne delay safeguards toteshis the installed shamaele.Dese eenges for safety injection (SI) actuation for the esmoognummme of a dueled ylache would senke Gds spedfication more high steam Bow Manal. Opereting Eagnemed Sadnammis tysesak nh weeld consistent wiib Westinghouse Standard I

exD'irience has demonstrated that this prevent the aSusted train hose leitneths the TechnicalSpecifications.

't has caused laadvertent actuation Enginmed Sainwds System itswme. 6e c' En er.d aearing saloguards due to

,,,, d' y,,,,,

s*[* hazado consideration determination:

Basisforpnqposadao sigptificant at i

lastrumentatlan lag in the steam flow une rupture seemt.nardare, e new g The Commissaon has provided and steam prwsure si tnals.We snerent kind d noeldesit h met eented.

etandards lor determindes whether a t

introduction of a tisme delay will (3) Does the proposed emsedmont invdve significant hasards coesideration exists compensete lor the ins:rumentstion lag.

e stentftcant redeetion to a margin of eefetyt as etatedin 10 CFR 50.82. A proposed thus evolding spurious Si ectuations.

W proposed amendment does not invdve ammadmant 8.o an operating license for a Ecsisforpipposediu sigrufscant e stenificant reduction to a masstn of estety-foo611ty involves no nigdficant hasards hazards coas1datution determmotion Addms up to e stx tel osaand time deley to consideraties if operation of the facility The CommwH has provided the high steam flow colacident logic has been -

'n accordance with a propneed standards for determining whether a analysed from both a com respann and amendment would not:(1) Involve a significant hasards consideration exists contetnment integrity perspective.W gg, %, g g as stated in 10 CFR 60.92. A proposed ans a we me m DM kn consequences of an accident previously amendment to an operadng license for a facility involves no signdicant hazards the apphble DNER hmit.c-w evaluated; or (2) Create the possibility of containment Integrity, the containment peak e asw or diferent kind of accident from consideration if operation of the facility accident preneum resulting from a etsam hne any aa:ldent previously evalua'.ed; or (3) in accordance with a proposed tipture, assuntag up to a six M) acond SI involve a significant reduction in e amendment would not:(1) Involve a time delay le 42At sig, whis la below the margin of safety, significant increase in the probability or conteinment desisn preneum of 47 peig.

The licensee has evaluated the consequences of an accident previou:ly The staff has reviewed and agrees proposed amendment against the evaluated; or (2) Create the possibility of with the licensee's analysis of the standards provided above and has a new or different kind of acadent from significant heterde consideration supplied the following information:

any accident previously evaluated; or (3) determination. Besed on the review and (1) Does the propoud license amendment Involve a significant reduction in a the above discussion, the staff proposes involve e significant incman in the margin of safety, to determine that the proposed change probabihty oremnesquences of an accident he licensee has evaluated the does not involve a sJgnificant hazards previously evaluated?

proposed amendmen: against the consideration h pmpond -wl-nt does not invah e standards provided ab ve and has l.ocalPubhc Document Room cons ce sp v u1 alyud e

location: White Pleine Public Library.

accident. Neither the probabl!!ty nor the t

e licen e ame ament mvolve a significent tncmen in the 100 Martine Amme, White Plains. New w..#m af e steem line repture event is pmbeb6hty or consequences of an occident York tomt.

aneewd by mdectag ee mWman number of I

prettensely evelasted Afronwyforlicenseet Mr. Charles M.

operetda cineansie to 1/sesem hne in each of ne amendment does not involv' Pratt.10 Columbus Circle. New York.

3 steam kna and myteens se mwamn d'e 8I - - - -

, en 1/steem bae in each aa acent 6mcrease in the povbebthty or New ygggtalg, 7 - ~ of an accadent previcealy of 3 eieemlines.Carrent administrouve evalus'ind, m probabihty of a eseam hae NRC Project Director Robert A.

mquiminants pies the revised minsmum l

ruptum event is unaffected by addmg a six Capre degree of redundancy would ensure thei the

{8482 rederal Rogister / Vol. 55, No.133 / Wednesday, July 11, 1990 / Notices Lgh steam flow bistables in failed channels Bas /sforproposedno sign /ficant sneasuru together with the continued e

a*o placed in the tripped condition. His hozords consideration determinativat opereUon of IP3 in accordance with the action places the circuit in a enfe con 6 tion The Commission has provided Technical Specifications assure that an elace the output of this part of the circuit is standards for determining whether a adequate margin of ufety la prentved on a satisfied. lf a steam line rupture were to occur with the circuit in this configuration a significant hazards consideration exists continuous basis. Therefore, the proposed change does not ruult in a signihcant steam hne isolation and safety injection as stated in 10 CFR 50.92. A proposed reduction in a margin of safety, signal would be genrrated as intended.

amendment to an operating license for a The staff has reviewed and a ees (2) Does the proposed hcense amendment facility involves no sigmficant hazards with the licensee's analysis of [e create the poulbuity of a new or different conalderation if operation of the facility significant hasards consideration htad of a cident from any accident previously in accordance with a proposed determination. Based on the review and amendment would not:(1) Involve a the abon discussion, the staff proposes duction of the minimum number of operable channels to 1/ steam line in each of significant increase in the probability or to determ'ne that the proposed change s etsam lines. and revision of the miriimum consequences of an accident previously does not involve a significant hazards degen of redundancy to t/ steam line in each evaluated; or (2) Create the possibility of consideration.

nf a sieani hnes. does not crate the a new or different kind of accident from Loco /Public Document Room poulbuit i a new or different kind of any accident previously evaluated; or (3) locotion: White Plains Public 1.Ibrary.

• i accident m any occident previously involve a signifiert reduction in a 100 Martine Avenue' White Plains'liew I

evaluated. nis annndment does not involve margin of safet jk htft etE a'ffected by The licensee as evaluated the ttorn yforlicensee:Mr. Charles M.

oa thlec noe is only med to miti8 ate the Proposed amendment against the Pratt 10 Columbus Circle, New York, consequences of e steem break event.

standards provided above and has New York 10019.

Wrefon, e new and different kind of supplied the following informatiom NRCProjectDirect.:r: Robert A.

accident is not creeted.

(1) Does the proposed license amendment (31 Does the proposed amendment involve involve a significant increase in the CaPta e significant reductiota in a margin of safetyt probebility or consequences of an accident Tennessee Valley Authodty. Docket The proposed amendment does not involve previously evaluatedt Nos. 50-259,50 300 and 206, Browns a algnincent reduction in a margin of safety.

%e proposed change does not involve any By ensueg the bistables of failed channels changes to the design or operation of IP3 Ferry Nuclear Plant. Units 1.2, and 3 aN tripped as required by this amendment, which may affect the probability or ty, Alah M 1, the system will always be configured such consequences of an accident evaluated in the Umestone County, Alabama that it will mitigste the consequences of any FSAR. lP3 was designed and constructed on Date of amendment request May 18, steam line breek, even when assuming any the basis of a forty (40) year life, m sLnsle fauum. %erefore, this amendment accidents analyzed in the FSAR were 1990 (TS.N.2) does not insolve a significant reduction in postulated on the basis of a 40 year life. No Desenphon of omendment requests:

safety margin, changes will be made that could siter The amendment revises Browns Ferry The staff has reviewed and agrees postulated scenarios regardag accident Technical Specification requirements for with the licensee's analysis of the initiation and/or rnponse. Existing the Residual Heat Removal Service significant hazards consideration surveillance, inspection, tuting and Water (RHRSW) and Emergency deterr.lination. Based on the review and maintenance practices and procedures ensun Equipment Cooling Water (EECW) that degradation in plant equipment.

Systems as follows-the above discussion, the staff proposes structurns and components will be identified

1. Umidng condition for operation to determine that the proposed change and corneted throughout the life of the plant.

does not involve a significant hazards

%e effect of asins of electrical equipment. in (LCO) 3.5.C.11s revised to refer the user consideration.

accordance with to CFli 50.4e has been to Table 3.5-1 for RHRSW pump Loco /Public Document Room bicorporated tr.to the plant maintena.nce and operability requirements prior to startup l-location: White Plains Public Ubrary, s urveillance procedures. mrefore, the from a cold shutdown condition.

17 Martine Avenue, White Plains New probability or consequences of a postulated

2. Table 3.5-1 is reformatted and York 1000 accident previously evaluated in the FSAR revised.

Attorneyforlicensee:Mr. Charles M.

EM n t inCMand e8 8 te8 ult of the pr pond

3. Clarifications. corrections and Pratt,10 Cohuubus Circle. New York,

• *[j$>es the proposed license amendment additions have been made to the bases Now York 10019.

crnte the pouibihty of a new or different section 3.5.C for RHRSW and EECW.

NRCProjectDirector: Robert A.

kind of accsdent from any accident previous)y Basisforproposedno significant Cepra evaluatedt hazards consideration determination:

ne proposed change does not invutve any The Commission has provided Power Authority of T'ae State of New changes to the physical structures, standards for determining whether a Yotl, Docket No. 50.zas, Indian Polnt components or systems of IP3. Existing significant hstards consideration exists Nuclear Generating Unit No. 2, surveillance, inspection, tuting and (10 CFR 50.92(O). A proposed Westchester County, New York maintenance practices and p.aedures will amendment to an operating license for a Date of amendment request: June 11.

$""f" y"

[ ti hepc

, facility involves no significant hazards a

1900 IP3 to accordance with these approved considerationif operation of the facility Description of amendment request; procedarcs and practices will not create e in accordance with the proposed The proposed amendment would extend cew or diffennt kind of accident.

amendment would not:(1) Involve a the duration of the Indian Point 3 (3)Does the proposed amendment involve significant increase in the probability or operating iicense to forty (40] years from e senificaat reduction in a margin of ufetyt consequences of an accident previously the date ofissuance of the full power

%en are no changes in the design, design evaluated;(2) Create the possibility of a license. The plant is currently licensed oQpen ln[3 new or different kind of accident from ass a we the p

for forty (40) years commencing with inspecuon. tuttng and mamtenance practh:ee an accident previously evaluated; or (3) lasuance of na construction permit.The and procedures provide sasurance that er.y involve a significant reduction in a current expiration date of August 13 degredation of egipment, structuna or margin of safety. In accordance with 10 2000 would, therefore, be changed to components will be identified and corrected CFR 50.92 TVA conduced an analysis December 12,2015.

throughout the lifetime of the plant T ese of their proposed amendment 3

\\

i l

Federal Radster / Vol SE. No,133 / Wednesday, July 11.19e0 / Notices sees 3 (paraphrased below) and coacheded that not asset the abikty of the RHRSW Booie forp.. Mno significont -

it does not involve e signian==s hasards systaa to periosa its sitimate safety ha anfs consideration determination:

- censideration.nis eenclusion was function er removing heet from the ne Conanteenon has provided based upon a determinatioe that the primary soster of the RHR erstem.%e standards for deteralaing whether s -

operation of Browns Ferry in

====amant dom, not physim5y enedify significant hasards consideration esiste conformanna with the proposed any oquipment or adpast setpoista. De (10 CPR 50.93(c)). A proposed amendment:

m ---_ M changes clarify the number amendment to an opereting license for e (1) Would not significantly increase of RHRSW pumps required to be facAl involves no significant hazards the probabuity or consequences of an operable, dependag trpon tbs number of cons tion if operetion of the facility socident previously evaluated because units fueled, to enswo that an adequate in accordance with the proposed the proposed amendment merely.

water supply will be avaliable for the amendment would not:(1)1nvolve e c

clarifles the RHRSW operability RHR systems to perform theirintended significant increase in the probability or requirements prior to startup from a cold safety L Mosi. As a result of the consequences of an accident previouth-shutdown condition (LCO 3.5.C.1) by proposou abanges, the number of evaluated; or (3) Create the poselbillty of referring the user directly to Table 3.51.

RHRSW required to be ble s new or different kind of accident from Table 3.5-11s currently referred to for when o y one unit is fueled any accident previously evaluated or (3) pump requirements during operation.

actually increase over existlag 'IT Involve a significant reduction in a reg _irements.

margin of safety,in regard to the first u

Revisions to Table 3.5-1 will ensure consistency wie the requirements of the ne staff soviewed the TVA,a criterion, t',* Boonsee steted that:

RHR system (140 3.5.3 ) for operation application and analysis ofno 1.no pe eed change does not with only one melt fueled. This change significant hazards % tion. Based sisninomat annese he probabhy or t

ensures that an adequate supply of upon this review, the staff proposes to consequeni e of an accident previously determine that the====d-aats do not evaluated.no purpose of Technical RHRSW is available to supply the RHR j

pumps and to support EECW during involve significent hasards SPecincetton 3.1A3.s is to assum that a considwetions relief pet omiste for the reactor coolant startup and operetion. The LooolMINDocument Room eyenom whommer he had is on the meta l

administratin changes to Table 3.51 will prevent confusion and clarify for loooflon.* Athne Pubbe 1.llrrary. South weseL An operable relief pet protects the Athos* A resetor esolent system from potenual felle l

the operatore the required number of Afromyforh.lahma 38611'l due to overpressure.Because the rehef valve eensee Gera acts in response to an overpensam event, ao RHRSW pumps necessary to support Counal.Tennessa Valley Authority.

change la to probability of the onrpmuure plant operations dependmg upon how 400 West Summit Hill Drive. Ett B33, event oceerstes wtB result.ne consequences manY units are fueled.The bases Knoxville Tennesome 37902.

of se en event will not be changa wulcladfy ud conect ee NRCPio/ectDuector: Frederick J.

incmased the everpream bases consistent wie the anangement flebdon Pressosion Isaselen has been assumed by the and opereLion of the eyetem. Present us g o, t,,,,,,,,,,,,,,,,,,, p,,,,ci;,,

already allow reoucing the number of Virginia Electdc and Power Company.

system. Tednient spectacetions relevsat to RIDtSW pumps required to be opersble Decket Nos.30 300 and 55,381. Surry h low esapersame everpreuure protection whenever one or more of the units are Power Station. Unit Nos.1 and 3. Surry system are provided by Technical defueled.The proposed TS changes County. Virginia SPectilcatica 3.1.G. No physical chenent merely clarify the arrangement of modiacation le botne made to the facility, nor l

RHRSW pumpe required without Date of amendment topssis%y 22, an any openung pmcedme betnr mind, affecting operability or surveillance 1990. as supplemented June 15.1990 in regards to the second criterion, the requirements.

Description of amendment vests licensee stated that:

Currently. Section 3.1.A.3.a. of 2.h pioposed change will not creete h (3) Would not create the possibility of Technical Ep=cenantions (M) mquires poselbluty of a new or different kind of a new or different kind of accident from that at least one.-

tw safety valve accident frem emy occident ymtously c-any accident previonely evaluated since be op6 table whenever the head le on the evaluated.h dance to Technical the proposed D changes do not add any

,,,c.or vessel, except during hydrostatic Spedammene alem not inntw a physical new equipesant to the plant or require tests.The % and their Bases imply that Ch*858 to 88 IMdity or h8 oPmung procedures. No accident or malfunction, other any existieg equipmed % be openled this operability requiretnent is intended p

immeis

,c or coo ant m a is th in regard to the third criterion, the pump operability are consistent with the 350* F. t)> mactor is subcdtical, and ee FSAR manlysis of demgn basis accidents reactor i.oolant system is connected to

"'*"***'d*"*"""*

(Chapter 14) and the operability the residual heat removal system. Since M9"IM" IO' O*

this TS was written, the Sorry plant has In paragra p Pond change had a low temperature overpressure ourpresoun preesction function for b a conflict. La certain operational modes between 100 3.5.B.1 (RHR system) and' protection system installed. and reactor coolant syste'n (below 350* F) is o

oppropriate TS have been written for provide.1 by the low tempmture Table 3.51.TVA's amendment does not this system.%e proposed amendments overpressure protection eyotem. Technical intsnd to introduce any new mode of would delete the pressuriset relief valve SpectScabane minent te te low operation, normal or abnormal.outside operability requirements of Section ternpmtum ourpmese protectin system the plant's design basis.

3.1.A.3.a. on the besis that they are no an provided by Technical specification i

(1) Would not involve a significant longer necessary since the low

$0h"*c,3;Ih33ff

• d"*

I" reduction in a margin of safety because temperature overpressure protection Becaun no chasses am proposed for 4

the proposed U changes are consatent system provides the necessary Technical Specincation 3.1.G. thm is no with the et'eting BFN Safety Analysis protectiort reducuon in b angin of urety for a low Report. No adverse esfety impact or The proposed amendments would also temperature

...s.

. event.

reduction in safety margine occurs du correct a typographical error in Section The staff has performed a preliminary to the proposed changes since they do 3.7.

review of the licensee's proposed

3M84 Federal Register / Vel. 65. No.133 / Wednesday. July 11. 1990 / Notices change and egrece that the criteria of to facility involves no significant hazards

. Loco /PublicDocumentRoom CPR 50.92 are met. The staff also consideration if operation of the facility

/ccotion: Swem Ubrarv. College of believes that the above 3 criteria are in accordance with the proposed William and Marv, Williamsburg, met for the correction of the amendment would not:(1) involve a Virgi tia 23185.

typographical errors as these are significant increase in the probability or Attorneyfor heensee: Michael W.

tdministrative changes. Furthermore, consequences of an accident previously Maupin. Esq., Hunton and Williams, the staff believes that the proposed evaluated; or (2) Create the poutbility of Post Office Box 1535. Richmond, araendments are in accordance with 61 a new or different kind of accident from Virginia 23213.

I FA 7753. nerefore, the staff proposes to a4.ccident previously evaluated; or (3)

NRCProject Director:llerbert N.

determine that the proposed involve a significant reduction in a Berkow emendments involve no sign!!icant margin of safety.

PR SIMBUSHG NOEES hazards considerations.

The licens" has reviewed the Locxt/Public Document Room OF CONSIDERATION OF ISSUANCE locofiore Swem Ubrary, College of b

OF AMENDMENTS TO OPERATING men o 50 2 n fg l

IIL and Mary. WilliamsburF has determined that the uest does not b

NO 3

haza e Attorneyfor'l/censee: Michael W.

Tr:[p ration of the gaseous weste rystem CONSIDERATION DETERMINATION l

ti n t-Maupin. Esq., Hanlon and 'A"lliamt NU NNY Post Office Box 1535, Richmond.

in accordance with the proposed change does The following notices were previously Virginia 23213.

not involve a etsnificant increase in the published as separate individual NRCPro/ect Director: Herbert N.

probability or consequences of ad accident notices.The notice content was the Berkow previouly svaluated.The propoud same as above.They were published as Vir5 ola Electric and Power Company' Technical SpecfScat2n. Like the cumt individual notices either because time 1

ts e co tr on Docket Nos. 30 300 and 50 381. Surry n n5/

did not allow the Commission to wait g

Power Station, Unit Nos.1 and 2, Surry weste system to prevent an exploelve ses for this biweekly notice or becretse the County, Virginia nitxture.The proposed specification la more action involved exigent circumstances.

Date of amendment requests:May 25, directly applicable for Surry than the existing They are repeated here because the 19p0

, specification because it is intended for use in biweekly notice lists all amendments Description of amendmentimoests bydrogen rich systems, which is the case for issued or proposed to be issued In 1984, Technical Specificatici(TS) the surry gueous waste systen Specifically, involving no significant hazards 3.11.B.5. " Explosive Gas Mixture," was me proposed change addrewn weste ses consideration.

dded to the S TS Tb dditi f

8Yetem rupture prevention measures rather For details, see the individual notice Np n th Yx efetya e!hiYle in the Federal Register on the day and

s. No his TS was be on Sec on 3.11 3 of t

page cM M noke &u nM med NUREG.0472, Revision 3, " Standard made by these changes. Furthermore, since Radiological Effluent Technical the proposed changes provide preventive the notice period of the original notice.

Specifications for Pressurized Water rneasures directly applicable to the plant Georgia Power Company, Oglethorpe Reactors." NUREG 0472 providas three

asign. no elgnificant increue in the Power Corporation, Municipal Electric optioru for the explosive gas mixture nbability of an accident will occur.The Authority of Georgia, City of Dalton, epecification.

proposed change prevents exploelve mixtures The specification currently contained for hydrogen rich gaseous waste systems Georgia. Docket Nos. 50-424 and 50 425, in the Surry TS,3.11.B.5, is the fl.st

• • i' tent with [sJiandard trjechnical Vogtle Electric Generating Plant. Units 1 and 2 Burke County Georgia eption in NUREG.0472 Section 3.11.2.5, ISIP'**gg**

which is applicable to systems designed

2. The proposed change will not create the Date of amendment requeste May 25, poulbility of a new or different kind of ggg0 to withstand a hydrogen explosion. A accident from any accident previously

1. '#IO##### OO" #I####d**"I system is designed to withstand a evaluated. N revised specification and the P

hydrogen explosion if it is designed and existing specification both addrue the ame requette These amendments would tested to 20 times its normal operating issue: prevention of exploelve concentrations modify the Technical Specifications (TS)

yeesure, of hydrogen and oxygen in the gaseous weste to add a note to TS 4.8.1.1.2h(0)(c) that

'Ibe waste gas decay tanks at Surry system. No accident or event other than a allows the emergency diesel generator tre designed 'o 150 psig and operated at potential saa explosion is relevant to this high Jacket water temperature trip to be up to 115 pelg. By this criteria, the proposed chango bypassed.

gaseous waste system at Surry is not

8. The revised Technical Specificatico does Date ofpublication ofindividual d: signed to withstand a hydrogen

" """ I ' 'l8"Ifi'*"' "d"**I

• I"

• notice in Federal Register: June 22,1990 explosion, and therefore NUREG.0472, margin of safety.The propoud change (55 FR 25756)

Section 3.11.2.5 is not the appropriate

'$ vin"t an ekoe"ve areh]'

Erpimtion date ofindividualnotice:

p a

application for the Surry TS. Therefore, forming in the genou weete systen N Comment period expires July 9,1990; th2 proposed amendments would proposed change merely providee a notice period expires July 23,1990, incorporate the third option in NUREG.

specification which is directly applicable to LocalPublic Document Room 0472, which pertains to hydrogen rich plant specific dulgn charseteristics and location: Burke County Public Library, systems not designed to withstand a consistent with (Sjtandard [T]echnical 412 Fourth Street, W.ynesboro. Georgia hydrogen explosion.

[stpecifications.

30830.

Basis forpmposedno significant Based on the staff's review of the hazards considerat on determmation:

licensee a evaluation the staff agrees Yankee Atomic Electric CompenY' The Commission has provided with the licensee's conclusions as stated 9,eyat No. 50 029, Yankee Nuclear standards for determining whether a above.Therefore, the staff proposes to Power Station Franklin County, Massachusetts significant hasards consideration exista determine that the proposed (10 CFR 50.92(c)). A proposed amendments do not involve a significant Date of amendment requeste May 31, anendment to an open. ting license for a hazards consideration.

1990

Federal Register / Vol. 55, No.133 / Wednesday, July it.1990 / Notices 38488 Description of amendmer,t request:

Environmental Assenments as LocalPublic Document Room c

his change incorporates v ording from indicated. AU of theseitems are location: Calvert County IJbrery, Prince Standard Technical Spectilcations into available for public inspection et the Prederick Maryland.

YNPS's LCO Specificatlans 3.10.3 and Comminion's Public Document Room.

3.10.4. This wording allw physics the Gelman Building. 2130 L Street NW.,

Carouna Power Weht

. et at, DockeWo. SHgg, Shem testing to be conducted wit.4 the number Washington, DC, and at the local public of OPERABLE Power Range al document rooms for the particular E**I* M**"'aM L 8'unewiek Comdy, North Caroun Intermediate Power Range Nautron Flux facilities involved. A copy ofitems (2) channels being determined by the LCO and (3) may be obtained upon request Date of applicationforamendment requirements of Technical Specification addressed to the U.S. Nuclear February 28,1990, as amended April 4.

3.3.11nstead of the specific number of Regulatory Commission, Washington, 1990 y

channels presen0y specified.

DC 30555, Attention: Director Division Briefdescriptionof amendment he Date ofpublication ofindividual of Reactor Projects, amendment changes the minimum 2467 Baltimore Gas and Beatric Company, cruical powenano safey hanimm144 f55 l

y, y,

Expiration date ofindividual notice:

Docket Noa. SH17 and SH18, Calvent July 20.19eo Cliffs Nucieer Power Plant. Unit Nea.1 ddd 2 h cm A m de o

4.oco/Public Document Room and 2 Calvert County W specif es the fuel types located in the location: Greenfield Community College, Date of applicationforamendments:

core for the upcoming cycle. Fuel type 1 College Drive. Greenfield.

May 2,1990 CE8x8NB-3 will be added and fuel types Massachusetts 01301.

Briefcisecription of amendnents:

8x8R and pbx 8R will be deleted. Fuel NOTICE OFIS8UANCE OF These amendments would modify the type GE8 will be mnamed as fuel type AMENDMENT TO FACI 1JTy Surveillance Requimment 4.4.10.1.1 by GE8xBEB.

OPERATING LICENSE revising the existing footnotes on pages Date ofissuance: June 18,1990 3/4 4-28 and 3/4 4-20 to replace the June Ej7ective date: June 18,1990 the ubhcau a of

',g"[Pedd &c I

1990 and June 1991 dates with a Amendment No.1142

'h follows reference to the applicable Unit 1 and Facility Opemthw Ucense No. DPR.

g t

Unit 2 mfueling outages.

71: Amendment revises tha Technical amendments.De Commission has determined for each of these The Nuclear Rsgulatory Commission Specifications, licati (NRC) luued license amendments (Nos. -

Date ofinitiolnotice in Federal d

ts that the Yrds 123 and 106) modifying the Unit 1 and 2 Register. May 16,1990 (55 FR 30351) The m 11 e ith the stan Technical Specification Surveillance Commission's related evaluation of the

^

requirements of the Atomic Ene Act of 1954, as amended (the Act), a the Requirement 4.4.10.1.1 to link the amendment is contained in a Safety Commission's rules and regulatioas.The empletion of the mactor coolant pump Evalurtion dated June 18,1990.

@@) Qwheelinspections to the RCp No significant hasards consideration Commiulon has made ahpropriate findings as required by t e Act and the motor overhaul program.%e original comments received No.

Commluton's rules and regulations in to schedules called for completion of the LocalPublicDocumentRoom CFR Chapter 1. which are set forth in ti.e RCp motor overhaul program and location: University of North Carolina at license amendment.

flywheel inspections to coincide with Wilmington. William Madison Randall '

Notice of Consideration oflesuance of the completion of Unit 1 Refueling 1.lbrary,001 S. College Roed.

t Amendment to Facility Operating Outage (RFO) (June 1990) and Unit 2 Wilmington, North Carolina 28403 3297.

D l

a na ea n e ti n 1

ua e be n a

De kat N

gHae, t

and Opportunity for liearing in Brunewick Steam Bectric Flant, Units 1 gg pubis accomplish certain unrelated hardware and 2 Bruswick County, North in th e as l stions, repairs and various,

u a

indicated. No request for a hearing or petition for leave to intervene was filed

.a.letration actions. %e new Date ofopplicationfor amendments:

schedules for Unit t RFO and Unit 2 March 15,1990 following this notice.

Unless otherwise indicated, the RFO are fall 1991 and spring 1991 BriefDescription ofamendments %e Commission has determined that these respectively, based on a Unit 1 startup amendments will: (1) revise Technical amendments satisfy the criteria for in July 1990 and a Unit 2 startup in late Specification (TS) 3J.1. Table 3.3.1 1, fall of 1990.

Item 10. to cormctly indicate the -

categorical exclusion in accordance

+

with 10 CFR 51.22. %erefore, pursuant Date ofissuance: June 19,1990 minimum number of operable channels to 10 CFR 51.22(b), no environmental Effectire date: June 19,1990, to be per trip system (this change is for Unit 2 impact statement or environmental implemented within 30 days only); and (2) revise Technical assessment need be prepared for these Amend:nent Nos.: Unit 1,143, Unit 2.

Specification 3.3.5.7, Table 3J.5.71. Item amendments.lf the Commission has 126

5. for both Units 1 and 2 to correctly prepared an environmental auessment Facility Opemting Ucense Nos. DPR-indicate the minimum number and types under the special circumstances 53 and DPR-op. Amendments revised the of fire detectors required operable.De provision in to CFR 51.12(b) and has Technical Specifications.

proposed changes are requested to made a determination bar.ed on that Date ofinitio/noticein Federal correct prior typographical errors, aaseusment it is eo indicated.

Resisten May 16,1990 (55 FR 20350) he Date ofissuance: June 20,1990 for further detalls with respect to the Commission's related evaluation of Effective date: June 20,1990 action see (1) the applications for these amendments is contained in a Amendment Nos. 143 and 174 amendments. (2) the amendments, and Safety Evaluation dated June 19,1990.

Facility Opemtirw ucense Nos. DPR-(3) the Commission's related lettm.

No significant hasards considemtion 71 andDPR-d2. Amendments revise the Safety Evaluations and/or comments received: No Technical Specifications.

1

26406 Federal Reister / Vc' M fio.133 / Wednesdey, July n.1990 / No+Jtes

,a

~. _ _ _ _ _

Data cf fnfric/wfker - %f Commonwea?th Edisco Company, Technical Specifications.The bgisten ApH118,mo' c

,w Docket Nra. STN 56 436 and STN w supplements did n01aher the The Commisaloir reist

.ejon of 457, Braldwood Station. UnR Noa.1 and Coramission's initial determination of no the anr.2datents is omb.14d in a Safety 2, WI!! County,Imnots sign 1?icant t.azards consideration. %e Nleettoo deted pace 20.12.

DaJegqpbodonfer armae Commission's related evaluation of the No tntafficunilmrort/s cortsidemthm A ugust 14.1890, e applernea6ed Mesde amendments la contained in a Safety comments receired. No.

19.1990.

Evaluation dated June 14,1930.

MihblicDocumentibow DriefdescopMa ofamendmente NodcasIbawds consHamun

/ccaricer Univararry of North Cardraa at These anierwh apprpe chaages e ca menu m ke m Wilming'an, Wdham Madison Randall the Techakad Spmifwatkw to reduce y M h & m en & am ubnr not S.Cdh e Road, the aand er of rammbers of the Onaite lation York County Ubrary.13e East Wilmlr too.?4urtin milna 2M034N7 Nuclear Safety Croup 10NSG) fram four D

Street. Rock 1011, South Carolina members to three members. The CaruUna Power & Ught Company.

Technical 9pectftcation required flouston Ughting & Power Comspany, Dockat A Matt IL B.Rahlasun functions of the ON9G nre not changed City F%Ec Servb Bead c(San Steara Dechts Plant. Unit No. 2, by this amendment.Those redew items Antonio, Central Power and u ht s

Dathout== County, Sow 6 Carolina beted in Te&ateci 8pectftcation t.2A1 Compsay, Oty of Austin, Tuxes, Docket w

m** ** nM o 3 Nos.H and HM Texas Dane of applicadonfor amendment ONSG.

y,g' g Project, Units 1 and 2, Metagorda Date o/isowsoe Jane 27, t990 County' Texae Briefkscripuan of amendme.st:The Effecure date:la: mediate.

exigent Technical Specifications Amma'ascatNos:M and M.

Ne of mendment repestOctober amendmaat askia a darifying note racility Gaemtiqg Lacae Nos.Npp 25, m regsrdmg frequenc,y of she andcar 7:andNPF77: b aamdrmaa rwined Brie descrriotion ofamendments %

nource range iner maentation %gic the Technical Specifirawas.

am ta changed the Te&nical Channel Testig"In Table Lt.2 of the Date o/aurialmouce sa Faderal Specifications by denamg the TschahlSpedcations &

Register: March 21,1990 45 Mt 30D9) surveillance k*srvals in Noens 3 and e of amendment also corrects a The March 19,1990 submittal prowded a Table ts-t in terms of e6ectree full typographhl strur and twannbers a typogrmthal correction and Ad not Power days rather than calendar days.

subseqtreat note in Table 4.11.

change the intial no agnuh.ard hazards Date (===~ June 22, tsoo Date ofrasannce hme 11,1s00 cmkloratbn determinatim h Ufec h & W 12, m t//dvdaasirm n m Commissias'4 related evelustion of the Amendment Nos:17 and 7 Amendment No. Irr amendments is conta!and in a Safety hcIhry Q>erotrag Monnee Nee.MRr.

Evaluatisa dated June 27, aga Nand NPF-an Amendment emeed the Facility Om'roting Ucense No. D111 No s&ificarst hazania enmlamuon Technical Spectfications.

33. Amendment tevises theTechniral conuneau received: No.

Date ofinrtiotnotice In Fedomi Specifications.

Localrublic DocursonJ Roa:n Reg 6 sten May 16,1900(56 FR asse)He Public commate repostaf as to location: Wikington Towaship Pubhc Commisekm's retated earatestion of the ppposedno a/,gai/4 cant hazants Library,201 SJaskakse Street, amendments is contained in a Safety coms.sAvuton: Yes (551112Es dated Wilmingtea.1111noas 604e1.

Evehration dated }ene Z2,19so June 5,1990). ht notice provided an Duke Pewer Company,et el. Dodet opportuulty to trobmit comtnents cm the Nos. StH13 med 98-414,Ostrwbe CommissionN proposed no significant Nedear Station. Unite 1 and E. York "8

hazants ennsideration determination.

County, Sooth Cah Loc tion:WhartenCounty}unior liege. ]. M. fledges Learning Center, No comments have been received.The notice erroneous!Y Erovided for en e of

. a/ mea unk N Bohng Wghway,Wrarten, Tuss opporttruey to reqet a bearms by /uue April 23,1990, as supplemented May 17 7728ted Amttu Public Ubrary,810 and June 4,1990.

Guadalupe Street, Auctin. Texas 757tyl 2a Int Notice period actually enytr" july t,19M W notice in&cated that if Brief description of ameadascab:%

""l* P** *' E' "'P** *E 8'M amendmanis reviso'IS 314.Q.11. 'Tuej Power '. A. ler,"n-L=* No. 46 the CemW makn a fmal no r

fladigV&ior FuualSA.,

signi&oM bamrtla consideration and its associated Bases. W revialan 46L h h Sta6an. Nt No.1 determina%n any end hearrns would changes the carbon adsorber test Dem Cmq Emais uka plan efter Wine of th*

method to ensre that ike fuel pool Def

• of4T reoffenforamendment d

emendment. W Co rmt ssion's related ventilation filters hate a lune 30,19es svaluation of the amendment and the decontaralnation effider.cy of g: ester Description of amendment reperte fin:1 determination on no stgnificant than or equal to 95% un,ter all The amendment to Table 3.541 of the bsz:rds r.rmsidemtion are contained in pcstalated operating co2ditions.

Clinton Power Station Technical s Sately Fxaluaikm dated June E 1990.

Date ofissuance:]cna 14. m Specifications added certain valves Atwnwyfarlicensac:R. E. }ones, ETfective date: June 14.1990 associated with cnntatnment General Counaal. Carolina Power &

Amendmant Nos.:75 and 69 penetrations 17,35,30, and 42 to the list Light Company, P.O. Box 155L Rale 4;h, facih?y Opemhns Ucense Nos. NPp.

of cotstainment isolation valves.

North Carolma 27002 35 andfer.52. Amenomants revised the Date ofissmmcwlune 25,1930 Lom/ W A m e m Technical Specificatlana.

Effective dcte:}one 25,1990 Imoon:ltartsetlie idea ortal Library, e ofinlualnotice in Federal Amendment No.:37 p m g y gg a _ gg,, 4 Restster.May L1990 55 TR1 giga)h Fucility Operating Ucense No.RPF.

South Carolina N5 May17 and June 4.m, supplementa 62, h amendment revised b provided clarifying word changes to the Technical Specifications.

-. ~-

l -.

Federal Register / Vol. 55, No.133 / Wednesday, July 11. 1990 / Notices 28487 l

Date ofinidalnoucein Federal increase the Safety Umit Minimum inservice Testing (IST) for the power Regleter. March 7,1990 (66 FR stas) The - Critical Power Ratio for cycle 2 reload, opereted relief valves (PORV's), main Commluton's related evaluation of the Date offsevance Jae 19,1000 steam safety valves and the pressuriser amendment is contained in a Safety Kffective date: June 19,1990, ofto safety valves respectively in accordance Evaluation datedJune 25,1990 startup following the first refue with Section 4.0.5 which specifies the No significant Aascide consideradon outage IST la accordance with ASME Section commentsioceived No AmendmentNo.16 XI Code Edition and applicable addenda LocalPublic Document Room Facility Operatin License No. NPF.

as required by 10 CFR 80.66alg).

locodon %e Vespasian Warner Public as Amendment revises the Technical Date affaeuance June 18,1e90 Ubrary,120 West Johnson Street, Specifications.

Effsetive date: June 18,1990 0

Clinton, Illinois 81727, Date ofinitialnoucein Federal g,,,g,,,gyo,;34, aunis onh[t ev of Fac#ity Operoung License Na DPR.

Imag leland ushtias a=raay, Dodet

85. Amendment revised the Technical No. SHIR, Shoreham Nuclear Power the amendment is contained in a Safety Station, Unit 1. Suffolk County, New Evaluation dated June 191890.

Specifications.

Y**k Significant hasarde sonsideration Date ofinlualnouctin Federal Date of opplicadon for amendmenti commentsreceired No Register. April 18,1990 (68 FR 14512)

February 20,1990 LocalPublicDocument Room he Canaission's related evaluation of Brief descripuon of amendment:%1s location: Reference and Documents the amendment is contained in a Safety amendment made changes to the Department. T afield Ubrary, State Evaluation dated lune 18,1990, i

Administrative Controle section (Section University of how York, Oswego, New No sign /ficant hasards consideration i

6) of the Technical Specifications; York 13126.

comments received:No.

- Loco 8Public DocumeniRoom moved existing procedural detalls N

k * *'

P*'

location laarning Resources Center, involving radioactive affluent No. st Ue, Nim Mu'e P Romas Valley State Technical College, monitoring instru,nentation, equipment Nuclear Station, Unit No. 3, Scribe, New 574 Now london Turnpike, Norwich, requirements and control of liquid and York l

gaseous effluents, and radiological Connecticut 083e0.

monitoring and esporting details from Date of applicadonforamendment Northeast Nuclear the Technical Specifications to the November 9,1989, as superseded April al., Docket No. es eas Millstone Offette Dose Calculation Manual 10,1990.

Power Station. Unit No. 3, New Imedn (ODCM); moved the definition of Briefdescription of amendment:%1s solidification and existing procedural amendment revises the Tec.hnical County, Connecticut I

details from the Technical Specificauons Specifications which contain cycle-Date of application for amendment:

to the Process Control Program (PCP),

specific parameter hmits by replacing December 11,1989 as supplemented by added record retention requirements for the values of those limits with a letter dated March 2,1989.

changes to the ODCM and PCP, and reference to a Core Opereting umits Brief description of amendment %o updated the definitions of the ODCM Report for the values of those limits.

amendment modifies Technical and PCP consistent with these changes; These changes are in accordance with Specifications (TS) 3/4.5.1, simplified reporting requirements and Generic Letter 88 " Accumulators," to increase the administrative controls for changes to Date o/ issuance: June 19,1990 allowable out of-service time (for the ODCM and PCP.

Effective date: June 19,1990, to be reasons other than a closed discharge Date o[ issuance:Jur.e25,1990 implemented within 30 days isoletion valve) from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Effect>ve date: june 25,1990 Amendment No.:17 Date ofissuance: lune 18,1990 Amendment Na 5 Facility Openting Ucense Na NPF.

gjy,,gjy, gag,;yg,,,g,,,gg Facuity Operaung License Na NPF.

BR Amendment revises the Tecludcal Amendment Nat 51

82. %is amendment revised the Specifications.

Technical Spectflcations.

Date ofinitialnotice in Federag FacHuy Opemung License Na NPF.

48. Amendment revised the Technical Date ofinitialnouce in Federal Regleter. May 16.1990 (55 FR 20362) %e Register. March 21,1990 (55 PR 10540)

Commission's related evaluation of the Specifications.

The Commission's related evaluation of amendment is contained in a Safety.

Date ofinitiainotice in Federal the amendment is contained in a Safety Evaluation dated June 19,1990.

Register. February 21,1990 (55 FR 6109)

Evaluatior dated June 25,1990.

Significant hozards consideration and May 16,1990 (55 FR 20363) The Na significant hasards consideration comments swceived No Commiselon's related evaluation of the comments received:No.

LocalPublic Document Room amendment is contained in a Safety Loca,'Public Document Room location:Reforence and Documents Evaluation dated June 18,1990.

location: Shoreham. Wading River Public Department, Penfield Ubrary, State No significooti:azards consideration Ubrary, Route 25A, Shoreham, New Univeralty of New York, Oswego, New commenta received: No.

York 11786-9097, York 13128.

LocalPublic Document Room Niagara Mohawk Power Corporation, Northeast Nuclear Energy Company, et y gj,Y,f,"Te lh'8 a

e Docket No. 50 410, Nine Mile Point al., Docket No,56-338, Millstone Nuclear 574 New tendon Turnpike, Norwich,

Nuclear Station, Unit No.1, Scrlha. Now Power Station, Unit No.1, Now I =<l=

Connecticut 06300.

York County, Connecticut Date of application for amend:nent:

Date of application for amendment:

Philadelphla Electric Company. Docket Nos. 50 352 and 50 553 Umerick December 4,19e9.

March 19.1990 Brief description of amendment:%ie Briefdescript/ca of amendment:%e Generating Station, Units 1 and 1.

amendment revises Section 2.1, Safety amendment cha.nges the Technical Montgomary County, Pennsylvania 1

Umits, the associated Bases, and Specification Sectioa # 4.9.3.1.d,4.7.1.1 Date of application for amendment:

Section 3/4.4.1, Recirculation Syatem, to and 4.4.2 by specifying the surveillance November 17,1900

m Fedesel Regidar / WI. 53, No.133 / W.dnesday, July 11, teso / Notices eWpdon af sessisdrasne N IJbrary SM S.W. Nrrimes Street. P.O.

having to phoe the ydent en a made to ebensed the Tadmical Bax 11st,Partiend Oregon erse, wMch wedd denund b awh

{

a l

seppe Mus Se CCW er W eyenema.

Docket No.2d' **d E 08'"m"an*F'.

By mutnta6ning reedor ovoient eyeneun Vh3"'M PE g

y et aMac. SuuryPower na tSR) 4.1AMead he h

}

,gg y

Unli Mo.1, Burry County, Virginia.

te p rs bese 350* F but lees then

,y,tj,'ble as an ad of I

Ddes (CROlearse asummelater shed Dute ofopplication /pr r h *-

valve testing emes per1s munke and Jennery 4,2est as duriSed March as decay bent wmorsi*

specifice teet me==pa"maa tutterna, (bi and Apri A4isso I

The amendment also included several modify I timining Oamdstien of Opetua Brief description of omandnme W (140) 3.1.3Aale to alicor the rects,.

amendment presides a came-time miscellaneous revia!ans to correct OPeretor twenty (20) mJantas to restart a extensian to perfarna localimek rate typographical errors, correct tripped CRD pump provided that reacter tunting (Type C teses) et no Cycle 3D inemanhe encies, and clarify the intent of pressure is greater than or te 800 refnehas entage, oncently anedmied 6er censin sectedcal spahha, e

pels orifreactor preasme is than October lass. in the earest that the Cyde Defe offseuance:hme 22,1990 900 pels, the operator w1D inunediatah 10 refusimg catageis deisyed by move Effective dote lune 22,1990, to be l

place the reactor mode switd in the than 2 months beyand the camest impinumameed within 30 daya Shutdown pealtion and ic) charise the 3 projection of Deber test tMs approval Amendment No. 87 J

month accumulatorpressure sensor for deferral sueuld become towelad and gjg gg gg ypf,,

channelcalibration (setpoln4 BR the !!cemmee would hous se seekta

.M Amendment weised the Tedmical 413Ab.1.b. from *1r70 plus or ainus 15

• PFr*l ^* *18"Ptlas from ee W tk ns' pelg" to " equal to or greater than 955 leakage test requirements set furth ta to D te 8/laDi /noticeinFederal I

peig,a CFR Part 50 Appendix j was also issued Doc ofIssuance:Msy 22.1100 in connectbn with the amendmsr1 RegWeWarch 4 mM105e) gff,ciWora May R 990 D2te oflasuancerjane 22,1990 The Canndaalon a related evalaalbn of Amendment Na 39 and 8 Ufective date lane 22,1990 the amendment a contsined in a Safety AmendmentNa 142 Evaluation dated June 22,1991 Ebole%Ner'Ethtrlacenae No. Den.

Na skalficant hazards ca.u,idotution age 32 Amendment mvised the Tedunnal commentsreceimd No.

g, m g,,cg,,,,,,

Specifications.

Locolhablic.Dxument flenar me,afinmiddnadarla M

&leofJullialnoominFederal locofion:Umversity of Ussommeln 1

Register: December 18, asas W Reglete F 21,isso(t6 FR 81M)

Library Learaiqs Cester, Mas Naouiet 51258) & Comadaslan's relatad The Mards 20 s April a0m 30 letters Drin. Green Bay. %ndn Hmi.

evaluation of the amendment la M

contained in a Safety Evaluation dated o

,,gy, Wolf Creek Noc!sar Operating Maya wea determination of no attestBeant hazanie Corporation,, Dock et No. 54452. Wolf No s/gr4Ticant horottle consideration cesiderstbah Canadshe's row Creek Generanns Station, Cdiey

1. 1. Qyf, nah he anneneuds

%Jana j

,,, g,o, lo~' tion:Pottstown Public 1.lbrary,500

• "[,"

g, Door ofemendment request: Merca 2, n

thgh Street, Pottstown, Pennsylvania Safety Eeaisation dated June n tesa Briefdescription of amuML %

I" No si nifiaarrthazards amsideration S

amendment revised the Techrscal Portland Canoni Bactric Ceegwry at comments receivect N al. Docket No aM44. Trojos Nealeer loco /Mhc&cammetRoorn SpecificationTable of Cantents and j

Plant, Columbla County, Oregee locanon:Swem Lebrury, Casiege of TechnicalSpecification Survel'!ance Willitm and Mary, Williamsburg.

Requirement 4A4.1 to delete references Dave efatnendment request October Virginia 231a6 to Table 3.tt-1 which was previously 241eso rernoved frorn Technica1 Specifications J

Briefdecription of amendmmt Wlaconsin Pu,vi<. Servko CorporaSon.

in Amendment 23.

l aaj,ofg,,ana my44 m

{

requese The ernendsment chanstes the Docket No. 543st. Kewaunee Nuclear qanhScaliso requirements, as specmed Power &nt,Kewsunee County, in Tednical Sped 6 cations IL31 that Wisconsin WI" O'M*J Y M i

numat be smet by the Radiation Hrotection Date of applicotlanfwaswenimene EbcDity Operatirs Ltcense No. NPF.

BranA Marmeer.

February 18,1990

42. Amendment revised the Technical Date of Jessmace: lese 18,1er, Brief r,!secription efca enarme rc The Specmchs.

4)seche sloelune 18,teso amendment de&eenal TS 4.3 cconcermag Amendment No.i tal reactur codsat systan leisk testing and Date ofinrict notice in Federal Focilitiat Operatiag License Na NPE-weld examination requirements that are Register. April 4.1900155 PR usoS) The 1: A===danesst revised the Technical covered in TS 4.2a which requires leak Commission's related evahiation of the i

Specl8 cations.

testing and intervice inspection be am=*===nt is omtnined in a Safety Dade afimhtmodce n Faderal conducted in accordance with Section Evaluation dated May 3a 199a Registar. April 18,1990 (33 FR 14518)

X1 of the ASMEBouer and Pressure No s&r:77corrt hamnfs considav:,on

& Commission's related evaluation of Vessel Code.The amendment also comments received No.

the amendment is contained in a Safety revised TS 3.3.d.2 and 1.1a.2 to len/Puhhc DommentIbn Evaluation dated June 18,1990.

eliminate the requirement 40 place the location: Empor3 State Users 1y, No signl/icant hozartfs cons'derution plant in a cold abatdown conhn upon Wurma Allan Whte lAbrary,lato comments recefred: No.

a long-tervaloes of one erala el Carmeertal Street, Empoem Ennse Imos/Mhc Docuinant Room comporrat coobag water (OCW) or 06801 and O Jubar's University School locotton Portland State University ser%c= orster (SW). This wtil;re rent of Law Litrwy, Topda, basas 9te21

I Federal Regleter / Vol. 55 No.188 / Wedaeeday, haly it. SMS / Nelleen m

y~,.

Yankee Almeis Elsekts r'a==p==y, inued before say heeseos em Docket No. 55 GeB Vaakes Neelear Commlasten made e detenehmeten Power Stenen FrenWim Caumty, that the aht involves no Masonskesette significent hasards considereHon.

Dude of qpplicollom foramendment:

Details are anotakned la the laevidua' April 12. and April 20,18e0L notice as cited.

Brie en ripuan of amendment This Imag leland % Casspesy, Dadet amen at of. sages the Technical No,58.g33,8besobem Nuclear Power Specifications

) as follows:

Station Unit 1, Suffolk Ceauty,New

1. W title o the Tarhaie=1 Services York Supervisor has been changed to Technical Services Manager.

has of appliceWasforW

2. A new poaltion la establiebed January 5,1800 as ogpleasamted by erutled Malatanance Support letter dated Apr0 5,1suo.no o

supplementalletter did not change the Supervisor.

originallatset of the appl 6eetles

3. Another new poaltion is estahlfahed entitled Operetions Support Supervisor, and did not afleet tis stelre as 4.The number of SROe on shiftis significant hemorde determiastion.

- increased from one to two.

B^ descri)nden of aseendsomeDie IL De limitation that operating aseen revised ph g.S to die personnel work only eight hour ahlfts is Sharobaa lleemse die being removed to allow eeine operating reclaestfication of certeen vetal arene personnel to work twelvc-bour shifts and other vaadinantless which allows during plant operations.

1.!!40 to reduce the eine of ths

&te ofisevance: Jane 18,1980 Shoreham facility's security force, Effect/re date: June 18,1980 -

&ie of1sevanam'jans 14, tego A - lz--iNos:1n2 AmendmentNo.:4 a

' facility Cperatin Licaese No, DPfl.

Effecure doen: lune u,1eno

.7ac Amendment revised the Technical facyj,y % gj,,,,, y, pyy.,

Specifications.

at: N Asemithment revised du boense.

N'* *f A*l'"I**O** A" F*0**I Date o Regleter: May 18,1500 (68 FR sones) ne - g,g,,,,.findMdnel nottce hr Fedsnel

. June 21,1980(58 FR asser)

Commiesian's reisted evalestion of the IIstad et Reekettle, Maryload, this and day amen &neet is contained he e Sedety ofpolytesa Evahnet6cn deted pures 18, test For the Nealear Replanary t'e No sfgelflicant hasarde cane /dwarden Demetsht.Cr=a=ha M commenen sweeind:No Duector. DMaion ofAnesterhaniecse-Lif,lV, Localhablic!McammentRoern VandSpecialhunheceu agico apacieer locatian: Cavafneld Community College, AsseenrAsymiselm 1 College Drive, Greenfleid,

[Dec.sowis7ee pued 7.ts set tes am]

Maseachnaatte 01301.

.n eso,,,,,,,,,

NOTICE OFISSUANG OF

~

AMENDMENT'ID FAOtfrY ONRAT1NOIJCENSE ANDFINAL DET/'.,RMINATION OF NO 81GNIFICANT HAZARDS CONSIDERATION During the period since publication of the last biweekly notica, Indivalual nodoes of issuance of amendmanu have been leeued for the facillun as listed below.Dese notices were previously published as separate individual notices.ney are repeated here because this beweeUy nottoe lists all amendments that have been leeued for whic.b the f%nmieston has made a ftnal determination that an amendment involves no significant hasards cona6deration.

la this case, a prior Notice of Consideretton cf laa aaara of Amendment and Proposed No Significant liasards Consideration Determinaties and Op tunity for Hearms was lassed, a ring was requested, end time amenossent was

- 4 9

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m ncau man NUCLEAR RIOULATORY COMMISSION

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• WASHINGTON, D.C. 20655 osmunm av

= OFFICIAL BUSINESS PENALTY FOR PRIVATE USE. 8300 f

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