ML20045B026

Forwards Commission Biweekly Notice of Applications & Amends to OL Involving No Significant Hazards Consideration, Published in Fr on 930512

ML20045B026
Person / Time
Issue date:	05/20/1993
From:	Murley T Office of Nuclear Reactor Regulation
To:	Lehman R, Lieberman J, Sharp P HOUSE OF REP., HOUSE OF REP., ENERGY & COMMERCE, SENATE, ENVIRONMENT & PUBLIC WORKS
References
CCS, NUDOCS 9306160109
Download: ML20045B026 (26)

Text

{{#Wiki_filter:_ l' + p naug UNITED STATES f [ j NUCLEAR REGULATORY. COMMISSION

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s WASHINGTON, D.C. N0001 j May 20, 1993 The Honorable Joseph Lieberman, Chairman Subcomittee on Clean Air and Nuclear Regulation Comittee on Environment and Public Works United States Senate Washington, D. C. 20510

Dear Mr. Chairman:

i Public Law 97-415, enacted on January 4,1983, amended Section 189 of the Atomic ~ Energy Act of 1954 to authorize the Nuclear Regulatory Comission to issue and make imediately effective any amendment to an. operating license upon a determination -by the Comission that such amendment involves no significant l hazards consideration, notwithstanding the pendency before the-Comission of a j request for a hearing. ~ In addition, the legislation requires the Commission to periodically (but not less frequently than once every 30 days) publish notice of any amendments issued, or proposed to be issued, under the new authority above. Enclosed for your information is a copy of the Comission's Biweekly Notice of Applications and Amendments to Operating Licenses involving no significant hazards considerations, which was published in the Federal Reaister on i May 12, 1993 (58 FR 28050). Sincerely, Thomas E.dfurl lirector [\\ 0ffice of Nuclear Reactor Regulation

Enclosure:

Federal Reoister Notice cc: Senator Alan K. Simpson i ?Me% ' 2gFo g '\\\\ { PDR Q

,$* '%e f. .t UNITED STATES j. j NUCLEAR REGULATORY COMMISSION )^ f WASHINoTON, D.C. 20 % 5 0001 \\; v / May 20, 1993 The Honorable Richard H. Lehman, Chairman Subcomittee on Energy and Mineral Resources Comittee on Natural Resources United States House of Representatives Washington, D. C. 20515

Dear Mr. Chairman:

Public Law 97-415, enacted on January 4,1983, amended Section 189 of the Atomic Energy Act of 1954 to authorize the Nuclear Regulatory Comission to issue and make imediately effective any amendment to an operating license upon a determination by the Comission that such amendment involves no significant hazards consideration, notwithstanding the pendency before the Comission of a request for a hearing. In addition, the legislation requires the Comission to periodically (but not less frequently than once every 30 days) publish notice of any amendments issued, or proposed to be issued, under the new authority above. Enclosed for your information is a copy of the Comission's Biweekly Notice of Applications and Amendments to Operating Licenses involving no significant hazards considerations, which was published in the Federal Reaister on May 12, 1993 (58 FR 28050). Sincerely, Y g Thomas E.

urley, irector M

Office of Nuclear Reactor Regulation i

Enclosure:

Federal Recister Notice cc: Representative Barbara Vucanovich

s* ** Coq f,

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UNITED STATES 'f ' j NUCLEAR REGULATORY COMMISSION W WASHINGTON, D.C. 20lili6-0001 's May 20, 1993 The Honorable Philip R. Sharp, Chairman Subcomittee on Energy and Power Comittee on Energy and Comerce United States House of Representatives i Washington, DC 20515 l

Dear Mr. Chairman:

Public Law 97-415, enacted on January 4,1983, amended Section 189 of the Atomic Energy Act of 1954 to authorize the.uclear Regulatory Comission to issue and-make imediately effective any amendment to an' operating license upon - a determination by the Comission that such amendment-involves no significant hazards consideration, notwithstanding the pendency before the Commission of a-request for a hearing. l In addition, the legislation requires the Comission to periodically (but not less frequently than once every 30 days) publish notice of any amendments issued, or proposed to be issued, under the new authority above. Enclosed for your information is a copy of the Commission's Biweekly Notice' of Applications and Amendments to Operating Licenses involving no significant i hazards considerations, which was published in the Federal Reaister on i May 12, 1993 (58 FR 28050). Sincerely, l k[OfficeofNuclearReactorRegulation homas EC 4url irector-A i

Enclosure:

Federal Register -l Notice i cc: Representative Michael Bilirakis l i ?

I i The Honorable Richard H. Lehman, Chairman Subcommittee on Energy and Mineral Resources Committee on Natural Resources United States House of Representatives Washington, D. C. 20515 j cc: Representative Barbara Vucanovich i The Honorable Philip R. Sharp, Chairman l Subcommittee on Energy and Power Committee on Energy and Commerce United States House of Representatives Washington, D. C. 20515 i cc: Representative Michael Bilirakis I i .b 7 i ~ l .i l ? i 5 i e f

s' 3-28050-Federal Register / Vol. 58. No. 9Ci / Wednesday.~ May 12. 1993 / Notices - ) UNrTED STATES NUCLEAR REOULATORY raamanarm 0 A ;' and am so Faduty Operating IJossess levolving - l No Signiacant Hazards Considerations L Background Pursuant to Public Law 97-415.the U.S. Nuclear Ragulatory r==l==i= (the Co==i== ion or NRC staff) is, 'f pubushing this regular biweekly notice. Public iaw 97-415 revised esclion 189 [ of the Atomic Energy Act of1954, as l t amended (the Act), to require the - Gommission to publish notice of any,. 1

===ad-*= issued, or proposed to be '1 imed, under a new pmvision of section. 189 of the Act.This provision greats the Commission the authart to issue and - r -I make immediately e veany amend==nt to en operating hcones upon a determination by the ' f Co==i-ion that such amendment involves no signi8 cant hasards 7 consideration, notwia=*=ading the - pand==cy before the an-l==sa= of a r r*iLuset for a hearing from any person nas biweekly noticelaciudse all 5 notices of amendments issued.er. proposed to be issued frass April 19. ; - 1993, through April 30:1993. The last biweekly notice was published, on April 28.1993 (58 FR 25851). Notice of Cassideratism ofIssummes of A===d===*= to Facility Operating I h. Proposed No SigniScent j Hasards Consideration Deessulmation, i and r;; ^ , for a Heartag The Commission has made a determination that the.. amend==e requests involve - -) - no signi hasards consideration. Under the Commission's regulations in -l 10 CFR 50.92, this means that operation.-

i of the feelhty in accordance with the i

propcoed amendment would not (1) tavolve a significant inasess in the ' Probability or conseiguences of an anddest previously evaluated; or (2). create the possibihty of a new or ' diBerent kind of accident from any _. aandset prestously evaluated; or (3) L involve a signi8 cent seduction in a '. mergin of seisty.The basis for this proposed deteradastion for each. t

====d===* request le shown below., The %==t==ia= is seeldng public r r==-te an this proposed determination. Any ca--ts received. within 30 days aAer the date of publication of this notice will be - considered in making any Anal-l deter-aames= Normally, the Commi== ion will not issue the===d==nt until the j i l

4 Federal Register / Vol. 58. No. 90 / Wednesday May 12. 1993 / Noticas 28051 expiration of the 30-day netice period. Panel, will rule on the request and/or contention will not be per:r.itted to However, should drcumstances change petition; and the Secretary or 6 participate as a party. during the notica period such that dealgn. sad Atm* Safety and Ursrumg hoe permitted to intervene become failure to act in a timely way would Board willissue a notim of a berms or parties to the proceeding sub)ect to any result, for example,in darating or an approprises order. umitations in the ordar granting leave to shutdown of the facihty.the As required by 10 CFR 2.714, a intervene, and have the opportunity to Commisem may issue the hcese petition for leave to intervene shall set dpate fully in the condud of the amendmect before the expiration of the forth with particularity the interest of 8, including the opportunity to 30<!ay notics period. provided that its the petitioner in the pr= adh and Present evidence and cross-examine Enal determinsum is thet th* how that intanat may be aMadd by the witnessee. amendment involves no signfScar:t results of b pr-D* m pentim If a bearing is requested. the N-a== will make a final hazards omsideretion. N Enal should==-rhny e piak b reasons determinauon on the issue of no wb int' ttted determination wi!! consider all public witb paervention should b ticular refem to sf gniStant hazards consideration. N and State comments received before Snel determination will sern to decide action is taken. Should the Commission following factors:(1) the nature of the when the hearing is held. take this action,it will publish in the petitioner's right under the Ad to be If the fmal determination is that the Federal Register a notice of issuanc* made a party to the roceedm6;(2) the andm%est innlves w and provide for opportunity for a nature and extant ofthe 's s%nmm* hazards consideration, the heanng after issuance. na Commission property NW or tatsrest in CommWm may issue the amendraent expecs that the need to take this ecum the proceeding; and (3) the possible and make it immediately aflective, will occur very infrequently. eEsct of any order which may W ""d"8O' "9"*** I" ' Wntten comments may be submitted entered in the proceedin8 on the hearing. Any hearmg held would take by mail to the Rules Review and peudone's bunst. "Tb petition should a wismana f 6e omdment. Directives Branch, Division of Freedom also ide=tify the e aspect (sl of the if the final determination is that the ofInformation and Pub!Ications mbfect matter o as to amendment request involves a Services. Office of Administration.U.S. pe unnar to intmana. signincent hazards consderetim. any w Nuclear Regulatory remi==on' d dte Any Parse who has Elad a pection 5" hearing kid would take place befcre Washin on. DC 20555. and sha ti 88" 18I"t* N " "

• the issuance of any amendment.

the pub cation date and page number of admitted as a party sney amend the A request for a hearmg or a petition this Federal Register noum. Wnttan Petitim withmt requesting leave of the for hvo tointervene must be Eisd with comments may also k dalivered to B *rd UP to 15 days prior to the ftret the Secretary of the Commw% U.S. Room P-223. Phillips Building,7920 Pmbearirrg confecs odedided in the Nuc!sar Regulatory enmmission, Norfolk Avenue.Bethesda. Maryland Pmceeding. but rud an amended Washington. DC 20555. Atlantion: from 7.30 a.m. to 4:15 p.m. Federal Petitica must satisfy the spad'Ldty Docketing and Services Branch, or may workdads. Copies of wittten commentsrequiramants described above-be dahvered to the Commiscon's Pubbc receive may be eramined et th NRC Public Document Room, the Gahnan Not later than 15 days tn the thrst Document Room.the Gelman Building. Building. 2120 L Street. NW., Prehearing ccaferencs in the 2120 L Street. NW., Washim DC Washington. DC 20555. N Ehng of Proceeding. a petitioner shall Sie a 20555, by the above date. W requests for a hearing and petitiona for supplernent to the pedtion to intervene petitions are Eled during the last 10 leave to intervens is dW=d below. which must include a hst of the days of the notics penod. it is requested contentions which are sou ht to be that the petitioner promptly so inform By June 11.1993, the hcensee may file a request for a hearing with respect htigated in the matter. contantion the Commission by a toll. free telephone to issuance of the amendment to the must consist of a speciSc sf meamant of call to Western Union at 148001248-subject facilf operating beanse and the issue oflaw or faa to k ramd or 5100 (in Missourf 148001342-6700). any person w interest may be controverted. In addition.the petitioner no Western Union operator should be affected by this proceeding and who shaU prodde a brief expMn of tbs given Datagram IdentiEcation Number wishes to participate as a party in the bases of the cxmtention and a concise N1023 and the following message proceeding must file a written request staternent of the alleged facts or expert addressed to (Project Director): for a hearing and a petition for Isave to opinion which support the contention petitioner's name and telephone intervene. Requests for a hearing and a and a which the petitimer intends to number, date petition was mailed plant pet 2 tion for hve to intervene shall be rely in proving the contention at the name, and publication date and page filed in ocx:ordance with the heart =g. b petitioner must also number of this Federal Reguner nodce Commierion's ** Rules of Practice for provide refersnma to those A copy of the petitice should also be Domestic Uconsing Pw Lgs"in to sourms and h=n-ma of w the sent to the OfEco of the General CFR Part 2. Interested persons should petitioner is aware and on which the Counsel, U.S. Nuclear Regulatory consult a currect copy of to CFR 2.714 peutioner intends to rely to marahhah Commission. Washington, DC 20555, which is evailable at the Commission's those facts cr arpart opinion. Petitioner and to the attorney for the Ucansee. Public Document Room, the Gelman must provide sufEcient information to Nantimely fLlings of petitions for Building, 2120 L Stmet. NW., show that a germine disputs exists wfth leave tn intervene, amended peutions. Washington. DC 20555 and at the local the appucant on a materialissue oflaw supptarm antal petitions and/or requests pubhc document rootn for the peticular or fact. Contantions shall be limited to for a hearing will not be entertained facihty involved. If a request for a anatters within the scope of the absent a determination by the hearing or petition for leave to intervene amendment urAar consideration. The Comm wen.the presiding ofBeer or the is Elod by the above dete.the contention must be one whicii. if Atomic Safety and Licensing Bosid that Commisaico or an Atom 6c Ssfecy and proven, would entitle the petidooer to the petition and/or est should be Ucer. sing Board, designated by the rebef. A pedtioner who s,ans to Ele such granted bened upon a _ tanH of enrn=1osion or by the Chairman of the a supplement which entisfies these factors spee!Eed in to CFR Atomic Safety and i Wng Board reqd wis with respect to at least one 2.714(aX1)(i)-(v) and 2?14(d).

28052 Federal Register / Vol. 58. No. 90 / Wednesday. May 12, 1993 / Notices For huther details with respect to this egniacant increase in the probability of an function for all analysed deatgn basis action see the appucation for accident previously erotusted. acudents except for those involving a ne consequences of having a IDOP while concurrent LDOP. amendment which is available for a 120 VAC vital bus is energized by the Dunna a LDOP.h vital bus powed by public inspecum at the Commission's inverter backup bus are the same for the the backup bus will expemnce an Pubhc Document Room the Celman existing s-hour Action sisteinent and the interruption of power until h EDG restorn Building. 2120 L Street.NW.. proposed u-hour Acuan Statement.In either power.nu cauen aH sensore for tM RPS Washington. DC 20555, and at the local case. if thm is a I.OOP while a vital bus is and ESFAS ch anals on this vital bus to trip public cocument room for the particular on the inverter backup bus, the vital bus will In addition, an actuation channel may be de. facihty involved. experience an interruption of power until the energiaod resulting in an EDG not receiving 3 d esel tortores power to the inverter backup an undervoltage signal. The rwult of having Baltimore Gas and Electric Company. bua his causes the Raector Protocun a d- &==d actueuon channel a Docket Nos. 50 317 and 50-31g.Calvert Systeun (KPS) and Engineered Safety Features equivalenEo having an inoperable I'DG. one j Clifts Nuclear Power Plaat. Unit Nos.1 Marew Syeese (ESFAS) een oro on the train of ESFAS equipment would not be cad 2. Calvert County, Maryland chanat powered by this vital bus to trip and operable. Current increase the possibility of en inadvertent Terhawl Spect5 cations allow an EDG to Date of amendments request: April 1. actunuon. k inopmble for 72 houn ne proposed This interruption of power may also cause change snow, a vital bus to be on the backup 1993 an actuation rA=nn=1 to be deenergized bus for og hours and is therefore more j Description of amendments request: rwulung in an einegency dinal gewatm restricuvo than the ACT be an inopmble b proposed amendments would (EDG) not receivieg en undervoltage signal. EDG i mvise Technical Specification (TS) 3/ m reedt d hems a d =petuauon 6OThS Mm 4.8.2. Onatte Power Distribution rh=nnai is equivalent to having an inoperable haw an ACT of eight hour, a de. f Systems AC Power Distribunon - EDG: one train of ESFAS equipment would energised vital bus. Using the inverter Operating." in mlation to the actions to not be operabis. As current T=rhnW1 backup bus to energias a 120 VAC vttal bus I i be taken if any of the 120 volt AC vital Sp=e* ~ ens snow an EDGto be inopmble when as inverter is out-of-service unprova l buseos are not operable. b existing TS for 72 hours, anowing a vital bus to be h rWimbaty M the safety prot cuan system f 3.8.2.1 action statement requires that an by the inverter backu bus for 4s when ev=npami with operating with a de-is see rwtncuvaJa oder energimd vital bus. Threfore, th proposed l inoperable vital bus be notored to analynd initiating events. the vital bus change would not involve a significant operable status within 8 hours or be in energind by the inverter hadup bus wiu reduction in the margin of safety. f 4 at least hot standby within the next 6 NRC staff has myiewed the hours and cold shutdown within the of the two anowed hcanwe a analysis and, based on this following 30 hours. b proposed action outage them (ADTs) for the vital bus mmain sview,it appears that the thtee statement change would add an the emme, the probabWty of the interruption standards of 50.92(c) am satisSed_ odditional option. An inoperable vital of power increases because the A(yf for the bmfore,tia NRC staff propoem to bus would be womd from its vttal bus has increened. However, as the associated p bus within the first 8 Pmbebility of a loss of offsite power is unan, determine that the amendments requ hours and the vital bus restored to this increees to pmbebility is not sign 15 cant. involves no significant hazards nordme.eh change wiu not invoin a consideration. operable status by reenergizing the vital signmmat imreese in se pmbabihty M localPuMic Documenf floom bus from its associated inverter, which is the normal source of power.within 48 ~d" '""' d ""

• C' *** P"'I "" Y location: Calvert County Ubrary. Prince FmdericWaryland 20678.

hours or be in at least hot standby

2. Would not create the possibihty of a new Attorneyforbeensee: Jay E. Silbert.

within the next 6 hours and cold or different type of =rridaat froar any ahutdown within the following 30 accident previously evaluend. Esquire.Shaw Pittman.Potts and ne proposed change to add an Action Trowbridge. 2300 N Street. NW., hours. Statement to the AC Electrical Distribution Washington. DC 20037. j Basis forpro sed no sigrtificant Syeesm Technical h i" ="= to allow a NRC Project Director: Robert A. Capra hazards consi ration determination: tro VAC vital bus to be emersiend by the ~ l As required by to CFR 50.91(a), the invwer backup bus la 44 hours does not Baldanore Gas and E3ec tric Company. lican oo has provided its analysis of the represset a change in the - ". - -wonofthe rnartr=8 Non. 30417 and 30 315. Calvert y issue of no significant hazards plant. Wa~ny, no new hardware is being Cliffs Nuclear Power Plant. Unit Non.1 s consideration, which is presented added to the plant es part of the proposed and 2.Calvert County, Maryland below-change nor are there engammatly diflerent Date of amendments request: April 1.

1. Would not involve a signL8 cant increase of 1,. "" being intrad==d.

) in the probebility or na===t-of an a vital bus to be powered by the 1993 accident previously evalueend. Inverter p bus for et hours does not Description of amendments request: l The 120 Volt Vital Aleeraetlag Oarrant creses the pose 6binty of a new or dHerent b propoemd amendments request (AC) system is designed to supply type of anddoet.Themdore.41s change =Amial="stive, editorial, and format l cxetinuous power to plant vital would not create bunty of a now or 2 F@ ung Ucense j i instrumentet6aa and control systems, no d15erest type of t tem any anddest

• % DPR*H d F IIOpwednI J

only event evaluated in the Updated Final evduened. Ucanae No. DPR4g for the Calvett Cufis Safety Analysis ILeport (UFSAlt) potentially

3. W motlevolve a sigMacant Nuclear Power Plant. Unit Non.1 and 2.

i aflected by the 130 Vett Alternetlag Current reducales la the mergia of seisty. (VAC) wital bus being by the D e proposed to add en Astaan respectively.'!he respacet is to delete, or 1 D6stributtaa incorporees as appropriate, all inverter backup bus is the d of.eite. Steisseest to the AC ^^ "- to anow ahandwritten or " pasted-up" changes power (LDOP). Allowing the viel bus to be SysteenT=ehairst ", energiend by the laverter harkupbus does 120 VAC vtaal bus to be powered by the and the resnoval of all previous hcense not aflect the probability of having a LOOP. taverme backup bus fur 48 heure does ut conditions that have been completed to j since this unsup is not sa initiator to the represent a aq= tar =at reductica in the b s-dsincdon of b f'amamlastaa. b event. No procursors to any of the arv4Amata mergia si endory. By unlag the inverter Props changes and mlormatung wiH in the UFSAll are aN=rwt when the plant is haciaap bus to supply powse to a 130 VAC reedtin the operaung ha=a 4 in this haeup Thereders, having a 120 VAC vital bus, the Kr5 and ESFAS channel, whAch vtal bus energland by tbs tavaster backup wodd be in the artpped position if the vdel coctaining esuy those licanes conditions bus for 48 hours does not ineolve a bus was de enerlised. is able to perform its that are currently.tpplicable. y y' w-= %,7-.-r-1 g-m

l i Federal Register / Vol. 58. No. 90 / Wednesday May 12. 1993 / Notices 28053 The proposed deletions to acility portions of the snubber inspection As the proposed changes are editorial Operaung Ucense No. DPR-53 are: propam. and administrauve and do not Paragraph 2.C(3) nlating to fire Parapaph 2.C4 pertaining to constitute a substantive change to the protection with the exception of the specified additional reactivity acd operating licenses. 6 marpn of sa.fety sentence which states:"The licensee is power distnbution surveillanms. is not affected. reqmred to implement and maintain the Parapaph 2.C6 relating to fire Based on this review.it appears that administrative controls identified in protection requinments with the the three standards of 10 CFR 50.92(c) Section 6 of the NRC's Fire Protection exception of the sentence which states: are satisSed. Therefom. the NRC staff Safety Evaluation on the facility dated "The licensee is uired to implement proposes to determine that the September 14.1979." and maintain the a.ministrative amendment request involves no ~ Paragraph 2.D relating to controls identified in Section 6 of the ificant hazards considation. consideration of an optimum cooling NRC's Fire Pmtecdon Safety Evaluathun. PnMic Document Room tower system. on the facihty dated September 14 location: Calvert County Ubrary. Prince The following items relating to 1979 " Frederick. Maryland 20878. construction and pmoperational testmg Paragraph 2.E relating to a reference Attorneyforlicensee: Jay E. Silbert, which have been completed are also to paragraph 2.D.2 which is no longer Esquire. Shaw. Pittman. Potts and valid. Trowbridge. 2300 N Street. NW., requested to be deleted: PreoperationalTestingItems A.1.a Paragraph 2.G relating to leBal action Wuhington, DC 20037. Reactor Protection System. A.1.b making any license granted between NRC Project Director: Robert A. Capra Control Element Drive Module Cooling July 21.1976, and such time as a P Ce mDdd System. A.I.c Reactor Component mandate is issued on the proceedings No. 50155. Big Rock Point Plant, Ucen to the Handling, and A.1.d Main Steam Charlevoix County, Mir.higan isolation Valves. Construction Items A.2.a admmistrative controls to prevent completed wit no conditions Date of amendment request: March 4 licable to Calvert Chffs. 1993, as revised March 14.1993 overpressurization. A.2.b replacement aFjasisforproposed no significant iksmption of amendment request: and spacers added to the expansion hazards considemtion determination: h proposed chege willavise the omts in the sah water system and A.2.c As required by to CFR 50.91(a), the Todinical S 'Scations (TS) to n MPply Ene3o 6e volume licensee has provided its analysis of the mnform to wording of the avised issue of no significant hazards 10 CFR Part 20 and to reflect a Items.to be completed prior to post-consideration.N NRC staff has separation of Chemistry.andRadiation core loading hot f=% testing. ,yg,,g g 3,,.s st Proach respMbWues. Items B.I.a Uquid Waste System the standards of to CFR 50.92(c). ne Basis for proposed no significant Eveporators tests. B.1.b Radiation NRC staffs review is prwented below. hazards considemtion determination: Monitoring and Process Radiation

1. Would notinvolve a significant As required by to CFR 50.91(a),the Systems tests. B.1.c variable Or wer bmm b b probabWty a heenm 1.as providd its analysis of b Tri System tuts, and B.2.s Ins

• tion consequences of an accident previously issue of no signiScant hazards an design documentation of safety evaluated; consideration. which is prwented related pipe hangers, restraints, and The heensee is requeeung huse bekw-mpports.

amendments which will result in

1. Will the proposed change involve a items to be completed prim to amending the Unit 1 and Unit 2 Facility signtacant ine:3ese in the probabihty or prWho beyond low power physics Opmung Ucene in a clean, c usequences of an accident prwiously testing. Items C1.s Solid Waste System consistent format. All past handwritten "I"*t*U tests. C1.b Hydrogen Purge System and " pasted-up" chan willbe N PNPosed change does not a5 ct de deleted or incorporste as abpropriate.

'I Q[ d RADIOLOGICA tests. C2.a Evaluatian of b adequacy of the dien) generator air start system and alllicznse conditions t t have TI a modi $ cations.C2.b mm letion of been mmpleted to the satisfaction of the Errt.tJENT REI. EASES emetions of h bcon instmmutation. 2.c NRC will be removed. Incthty Technical Spec 1Bcations, and are Completion of reactw internals De proposed changes are editmial M*trative in ne'ure: vibration monitoring capability, and - and gainiserstive and do not - - Change *" Chemistry and It>Hata= C2.d Modification of the primar7 Preuction Supervisar" 4 "Redlauan const$tute a substantive change tob. - Protection Supervisor." Control Element Assembly indication ~ o dng beensea, brefors, the system. do not infolie a Mr=t

• Ch'*8' I""

Opating Ucense No.DPR49 are: consequences of an amant previously. $*M$M*', he proposed deletions to Fadlity locruse in h prdbabWty k-denne h mentyen es a unit d redieuon. Paragraph 2.C2.a exempting the evsluated. .The ESussesr -

• enen license fmm comphance with technical

2. Would not create the p==44 of seence the associated beams han been fication requirements appl to a new or di5ersat type of accident.

novised to cocions with the wrised 10 TR s testing until the first refae any accident previously evaluated; or Part 30. Maximum PermissiWe -mretion e outage or reptar= ment of the existing the proposed changes do not modify iMPCI terminology has beets espesood with charmal pnar to the first outage. b plants tion or operation as Emuset Concentration". Parsgraph 2.C3 pertaining to they are edit and d=hw tire. As .m actual instantaneous does row lwts e d ** G*'em Emussa Dess Ram escuon inmmplete construction itans tests and a rwuh.no new acrident initistas en other itema.nees items included introduced.Rafore,h changea do hu b 0 dR 30 eses determining a.s.ing of salsty not create the possib0ity of a new or reus arrwpond roughly to the maximum related systems due to inoperable different type of m:cident kom any perminiMe concentration and snee(s) snubbers, conduct an inspection or test acxidant outly evaluated. - s reestved by the maximum expos ed member program rslating to inoperable snubbers

3. W d not involve a =w'ht of the pubuc if anowed to contin a for an durmg operatica, and completion of reduction in a margin of safety.

attre year.mee IWts are used inere as

i } 28054 Fedcal Register / Vol. 58. No. 90 / Wednesday. May 12. 1993 I Notices instantaneous linuts (dose rows above which Description of amendinent roguest s gniacant incesse in b conseguences of an are not a!! owed to contmus for seam than b proposed amendment would accident pmiously evaluewd. one hour at a smas) so se to provide esama'* change the Pahsedes Technical

2. Osoes

• Possbery of a new or S *UScot20n Table 4.2.1 as fouows.

d#emme W ofoceedent /msri any not to exceed to CTR 50. Appendix !!hnits. E pimouslyevoluomd.

2. W111 the proposed change (s) create the poutbih of a new or different bad o

1. Change the surveiUance inwrval br ne proposed change to Technical acendent anypreviously evolushedt item 2. Partial Movement of All Rods Specincetion alters only b frequency of a n1s pmposed dange to toquered try the (Minimum of 6 Inches)" from once survet!!ance test. It does not aher the manner impisamentauos of the new to GR Part 30 "Every Two Weeks" to once "Every 92 of testing or the meaner in which any plant j

requtrements temoept for the title chsage) and Days." systems are operated. r are adminietmme a natuse. Nether es

2. Delete the footnote to that table.

D'mfom.OPemoon d the ladlity in l accordanr= with the Technical meterial condition of b lecility nor the wkh Mdn br redd W of E sp-ma, men.=. not asete the i accident analyses are afbcted by this OtD 20 and CRD 31 during the possibility of a new or diffent had of pent==d damen. Themitre, tbs proposed change dass not asets the poestbt!!ty of a remamder of Cycle 10. accident froen any previously evaluated. i diftennt type of scetdent than ph ti

3. Correct the FSAR references in that

3. Javofve o sign @ cant reduction an o l

r evalueend. table to resect the tofthe muerpin ef sofety.

3. Wi!! the change taselve a Palisades IJp6sted he 4 mage to the Techdr=1 I

significant in the omrgut of saisty? Basisforpro med no ificant Specifica does not e IScantly ofbet Each haut that was esmetod increased the the prohahnhoy et a sed inlitag to y, 3 g. saargin of safety by==Hng the Immat mese insert (b anly QtDM esisty W conservative; or remained the same. As required by 10 CFR 50.916a),the g g, g,g 3,,,, - The changs of d'==nre to "so lim== bas provided its analysis of the under question 1.abom changek k I centimeters"(18 haches)is amore issue of no signi$ cant hasards agreement with the control rod exercising conservative, providmg a higher degree of consideration which is presented frequenet requiredby the Standard Protection tor occupattonally exposed below: Technion:Specificettoes Comtmstion i , plante.NUREG 1432. Revtston 0. Most af the se.aant coneestreones have

1. Itsvolve o signFamr:t sacrease In the,,,g,gg g, g

i ,f a,,,,g,, charged to seGect new sciennac tabrunetton p,g,g,7g,, g - 3 p,,,,,4 .'Improouassmo e Tachaw We<= ens== and a changs la the pubhc dose limat from N proposed dany a he Threiaard sceulamos Aegessemusam.!") NUREG 13es. 500 mran a 90 mmm. Spar 4mr=tions seduces the tagesney of Theroams, opssation of the lucihty in - The halt for dissolved and entsatand canard adanscasmgswouemmeekeeng accordance with the propoed dangee es noble guess was dansed tross 2 x 10' to 1A tmm tri-weekly as .The psusumed Technical

• par *r=na== would not involes a

[",1' ~,, "g - d d '"8 d"C'**d ang=**=NHC staf has reviewed the=* :=harmar= ini intent of shie isegesende d $ "" 8,'""' *gr" d --+ ' m =n-bound es as to passent their licensee's enelysis and, based on this } The esmaemos that the esseet seds use est p inser+ tag into the onre a rescaer trip. review,it spears that the three l - sahant dess e erese verne sed e determlas any mar====y desgos and wese N emensstag of rods le sely anpsble standards os 10 O'R 50.92(c) are 'I'01 satisSed.Therefore,the NRC staf found to be est appropnanely. No cainage will proposes to determine that the be neceenery move the rods a sumu dnsaamm ak I aThe instantaneous release row limits for amendment request involves no etrborne sensase utli not be charged because rod motion does proeide ammme est he I et iarissir basards cona6dmWien. they are imposed on ucensees as e contrat a centres ud is met armly ---h==a= ny head IbcalPublse Docunwnt Room I j en,ure that hasasses most AppendixI at a fully withdrews passe 6== seg ha=shm9 re,quW

• Alerna empelste let tese has asper eocured. Whos the suenour is location: Van Wylen IJbrary. Hope l

dose rate hantes ansy changs shghtly due to OPeeting at .this unen sange of smeet Couage. Houand. Mich 40423. changes in scientifnc data and will be leerkseethe cimasensas ase he Aaseraryforlicenses: add L Ram. rmswed and changed as appsprisme prier to prestest so the test has little damos of Esquise. n=====s Power Osas y, j y-detecting==eh=W=3 laterference if it were - 211 West Michigan Avenue. Nrefore, the propamed change dans not to accer. he sure=aumme= cannat. and was Mi 49301 involve e seducahns la the margin of enday. not th ta, #I=====' hihases ts es pyepset ihrecsor:L B.ndoseh h NRC staf has rettswed the electrical ciutub whid seismens the emetrol licensee's smalysis and, based as this rod. Opsettag hisaary has shears ena sener Detroit Edissa Company,Dockst No. i 50-341. Fared.1,Mearse County, review,it appean that the three esehes,wheah to pneumed ' M38EdBRE ~ i standards of 19 O'R 90.33 c) are F "'"""""" "8'885 d Does ofeinendment reguest: March setiened.Therefore,the NBC staff ha bass di m esmen Proposes to determine that the p 41mes whid dhc @ ammael and tip 23.1992 amendanset request involves no and lasertion empedy. Pellendes Descriptaon of amendment sequest. 4 signincant hasards maald-stlen-hisaary abows u es subtest sure=i n==<= N amendment would IocalPublic Document Jloomt has never desseted such a nosehenical - modify Condition 1.C.(10) to location: North Central problem. eliminals the Einergency Diesel a Collage.1815 Howard Street. Stano the suhteet eweethemos, amenal red GeneratorIEDG) main engine bearing i Michlgan egyys sensstag, hee beste gnhabliny of dameeng - spedalinspection requirements. Waas==yfor ha-:Jedd L Becem, the hales wkteh at was h====a=st in esset. Basisfer no sgngicoat l ed stem eheagudad mammeum,andhm, hasards motion determination: Esquire.Censumere Power y, 212 West Michigna Avemos, muabir sud w ad As required by to Q'R 50.91(a), the H-a o has provided its analysis of the MI 988 esercielag is seducing the frequency ofmewd md wthve lasue of no signiScant hasards j PF8)'Cf g-n.=-

==e Power y,Dedet nosqplSeant etha ento et considerstica,which is presented 4 i No. 36 358.Pausades P Van Bures reactar operetten wsth a sammet ved widch - below:

• j i

County SGebigen will not taaset upon a seecnar algenL ne change to eliminate the j Nredare.cparetles of the ha S Bumseguacy Dbasel Generator (EDG) Date a(aneadawat roguest: March occaremens wee the psopened Tudhateel beertug taspeedos program onetsined in 29.1993 Specifications woeld met vendt ta e-1.acenar Omudinsa 2.QtD) does not: l a f i e l

1 Fed;ral Register / Vol. 58. No. 90 / Wednesday, May 12,1993 / Notio2s 28055 (1) Involve a sipificant increase in the survetflaws be performed dunng shutdown. (1) The proposed changes do not involve probabiltry or consequences of an socident The rhme does not: e sign.ficant increase in the probability or previously evabated. N *-t= (1) Involve e signtficant incruse in the consequences of an accident previously program proposed for elimination has not probability or con onces of an acddent evaluated because b proposed changes an detected any degradation in any EDG engme previously evalue N Q removes a ahwetrouve in nature. None of the l beanngs. The Fermi 2 EDG's have been requirement that certain surnf1-== be Proposed changes involn a physical shown to be reliable and will be maintained pam d during shutdown.The modif! cation to the plant, a new mode of reliable through effective W= surveillances will sull be required to be oPerstion or a change to the LTSAR 1ransient monitonng and preventative maintenance. armed under the provisaans of the TS analyses. No 1.imitmg Condition for Therefore, the change does not adversely - ting Condition for Operanon (140) sad Operadon. ACTION statement ce affect EDG rehabihty. N change increases Acuon Raquirements. Neo prortsaan Survoittav Requirement is affected by any the EDG evallability by shm! noting EDG out-assure that to equipsnant is evellable of the proposed champs. of-service time wluch is requiryd to perform to mitigats N poned chose. 12)The proposed cnanges do not crinate b thwe inspecuent nerefore, the change does does not ehmtnata, but re retalarma, heS PD"IM1uy of a new or different kind of not involve a significant increase in the guadance that surveillance salvities must be accident from any accident previously probabt11ty or consequenas of a previously scheduled wtth re$ard to their impect on evaluated because b proposed changes do ' evaluated acudent. plant safety.Therefore the change does not not introduce a new mode of plant operation (2) Create the possibility of a new or involn a sign 1 Scant lacrosse la the w inmin a physical uddcatson to the P ant. The propond changes are l different kind of saident from any ecodent probability or conesquenas of an acddent. administraun in nata previously evaluated.This proposal does not (2) Create the possibuity of a new or I31b Proposed changes do not inalve affect the manner of EDG operation or. the dtfferent kind or acddent from any acddent e signt$ cant reduction in a margin of safety design of the plant and does not involve a previously evaluated.N proposed % because they an admmistraun a nata special test. No riew or different accidents are does not affect the plant design. Equipment N De f Proposed changes involve a created. removed from servicz and any plant physical modi $ cation to the plant. a new (3) Involve e signi5 cant reduction in a surnillance activides an still restricted by mde of opamuan w a change to the MAR margin of atfety. Sincs EDG reliability is the TS LIIYs and Adion Raquirements and transW ana ung Condmon fw maintained and EDG evailability is all Surveillances must still be scheduled with Operation. AGON statement or teproved, safety margins are not reduced. regard to bir impact on safety. The NRC staff has reviewed the (3)Invotn a signiacant reduction in a Se C as r e hcensee s analysis and, based on this margin of safety. By giving Sexibility to licensee.a analysis and, based on this review,it appears that the three schedule surnillances during operation standards of 10 CFR 50.92(c) ar, when consistent with safe p1 sot opesecon the review,it appears that the three satisfied. Therefore, the NRC staff margin of eatsty is not seany affected. standards of 10 CFR 5032(c) am The NRC staff has reviewed thal, satisfied.Therefore, the NRCstaff proposes to determine that the amendment request involves no license's analysis and, based on this Proposes to determine that the sfgnificant hazards consideration. review,it appears that the three amendment request involves no IocalPublic Document Room standards of 10 CFR 50.92(c) are sigalficant hazards consideration. location: Monroe County Lib satis 5ed. Therefore, the NRC staff localPubhe Document Room System,3700 South Custar Roa, proposes to determine that the kescon: Mons County Library Monroe.Michisan 48161 amendment request involves no System,3700 South Custer Road, Attorneyfor heensee:]ohn Flynn, significant hazards consideration. Monroe. Michigan 48161 2000 Local Public Document Room Attorneyforlicensee: John Flynn. Esq., Detroit Edison Companb*, gan Second Avenue. Detroit,Mic location: Monroe County Library Esq, Detroit Edison Company. 2000 48228 System,3700 South Custer Road. Second Avenue. Detroit. Michigan 48226 NRC Project Director: L B. Marsh Monroe Michigan 48181 Attorneyforlicensee: John F1ynn, NRCPmject Director: L B. Marsh Detroit Edison Company, Docket No. Esq., Detroit Edison Company,2000 Entergy Operations, tac., et al., Docket 5 1, Ferme2, Monroe County, Second Avenue, Detroit, Michigan No. 50 416 Grand Gulf Nuclear igan 48226 Station Unit 1, Claiborne County, Date of amendment request: March NBC Pmject Director:L B. Marsh ys.,;,,;PP; 23 1993 Detroit Edieon Company, Dochet No. Date of amendment request: April 21, Descrsption of omendment request: SW1, M2, Mona County, 1993 N proposed amendment would Michigan Description of amendment request: ehmtnate the qualification on some 18-. b roposed amendment revises the P month surveillance requirements that Date of amendment request: March requirert ent for control rod testmg to the surveillance is to be performed 23,1993 "during shutdown."The pmposal Description of amendment requestr increase the " notch testing" surveillance interval for ' ally follows the guidaoce of Generic Letter The proposed amendment would withdiewn control rods oncs every 91-04, which gives guidance for change the submittal frequencly of the Technical Specification (TS) chan to Radioactive EfDuent Release Report 7 days,to oncs every 31 days. l Bas:s for se:t no significant eccommodste a 24 month fusi c from semi. annually to annually in hazards cogerotion determination: The licensee is not planning to extend accordance with a recent change to 10 the fuel cycle at this time. CFR 50.36a, and changes the pmvisions As required by to CFR 50.91(a), the Basis for pro sed no sigruficont for delegation of approval of changes in beanse,e has provided its analysis of the i harneds conti erotion determination: plant procedures. Issue of no significant hazards As required by 10 CFR 50 91(a), the Basis for proposed no significant consideration, which is presented licensee has provided its analysis of the ~ hazards consideration determination: b*1W 88 issue of no significant hanrds As required by 10 CFR 50.91(a), the "ge b w consideration, which is presented licensee has provided its analysis of the consequences of an occident previously below: issue of no significant hazards evaluated. The proposed change eliminates the consideration.which is presented h current and proposed survainance quahficanon that certam t8-month below: requirements for the control rod dnves 1

2,8056 Federd Register / Vol. 50. No. 90 / Wednesday. May 12,1993 / Notices inc!ude verttying each withdr:wn contml rod inenlees no signifkant hazards reactor strutdown for a wide range of events. ts capable of waving et least one notch once considersuons-including Anticipated Tnnsien*z Wtrhout per seven days wben operating above the The NRC staff has reviewed the Scrant Bened epon the BWR (botDng witer lower power set int of the Rod Pettern licensee's analysis and, based on this reactor! Owims' Group submittals. the NRC Control Systuca 1.This survalliance review. It appears that the three has de'erudned that Category i neutmn Snx '" ~~""" 18 S" *"d*d for (4.1.3.12.a) provides a means o identfring standards cT10 CFR 50.92fc) an ~""'"3"fRs to enpo with Ims existing R f Coolant coctral rods that are immovable as a resun med* hh h NRC nan of excessive friction or mechamcal Acr.idents. Ant 2ctpeted Transients Without interfersnca and provides e meau of Proposes to detarmine that the Seem. or other stodents that do not result identifytag problems with the rod posttien amendment request lavalves no in severe core damage condinons. indicating system (Survetilance Requtrement significant hazarda cnasiderttion. Bened on the above. the removal of 11rwr me 41.3 5.bl. Iocal Public D s3 Boom Condition tcX4) of Attadment 1 to the CGNS No safety-ralated eq[uipment nr ft.nenon Jocodon: Judge George W. AA.4 ucunse will not signihrty will be attered as a reruit of this c'magah Library. Post OfBcs Box 1405. S. incense pmtabihty or consequences of a Proposed amendment only bcreases the Commen at Washbgtog h prvvtously anal aod strident. T surveillance interval for partially withdrawn h The change would not create the rods frocn once per erven days to once per MississiPP!39120 31 days Based on the demonstraksd hrneyMcansee %M possibility of a new or different kind of accident freen any previously analyzed. reliability of the control rod drt S (CRD) Reyneida, Esquire. Wineton and Strewn. Thh t Sep pmpose d M ucense systeca et Grand Gulf Nuclear Stotion IGCNS) 1400 L Street. N.W.,12rja Floor. Condtm - (cX4) of Attachment i to the CCNS cod simner fac!!iues.the abDityof the GD Wmahineton, DC 20005-3302 Operating Ucense. No physical changue to scram function to reliably contml reactMty NMC frofect Director John L. PeGet the plant would resuh if this changes durir:3 abnorrmal opertuonal (Actmg) Ucan e Condition is . nor wocid any transients is not compromised.This chanP changes in plant operation occur. has no influence or i:nnect on the gd inuty Entergy Operations. Inc., et mL Docket The conclusion of the NEDO-31558 repert of a=y =,H A-at or analfuncnon evamete No. 30 418, Gread Gstf Nacieur was thst 6 faitum of the neutron Bux the GGNS Updated Fual Salsey Analye&s Station. Una 1,na herne Ceesty, monito sng instrumentation wiu um prevent Report (USFARI No accident or Mississippi the operstar fraca determining reecsor power melfunctaans evaluated are a5ected. levels. Stif5cient infrmation is available therefore, & consequences of these have a:n Date of amendment request April 21 ,p,,,gg.h h opmucoal h signincantly traeased. 1993 and to conclude that reactivity cxurtml has Based on the above, the proposed r+= nee Desa2pdon of covendmerat been amenplished. The tEDMisse also does not sigmacantly increase the probability This emendment would delete provided an alternes eteerte hr neuroe niin or consequences of any meddent prev 6ous!Y requirement for Bux monitoring as instrumentation to sneet, wh6ch is a:ompiaMe evaluated. outlined in Regulatory Guide 1.97 to lieu of the Genegory 1 criteria of Reguletory

2. The proposed change would not asete

" Instrumentation For -Water. Guide 1.97. Bened upon the BWR Owners' the poss1Mitty of a new or diffwent kkid of Cooled Nuclear Power P ts to Accmas Group subminals. 2e NRN dhed accident ham any preymme0yt ametreed. Plant and Environs Conditions During est ceagwy t rieuwen Dux % Extending the surveulanos to at days has bstrumematbn is not needed for existbg no mfluence on nor does it contnbute ta any and Following an Accident,. for the BWRs to cope with tres of Coolant wey to the possibility of a new or different Grand Gulf Nuclear Station (CCNS) Accidents. Anucipated Trenssents Without Lmd of amdant or analfuncuan from those since analysis shows that these Scam or other sa:idents that do not result previously analysed. The method of requirements are being met by in severe core darnage conditions. performing the surveinance is not changed alternative methods. Based on the tabrmah provided above. No new acr$ dent enodes an anated by Basis for proposed no sfgnfficerr! & removal of Ucanse Condition (cX4) of extending the surveinanca interval frors 7 hazards considertrden detertrtinotfon Attachmect 1 to the OGNS Operettng ucanse days to 31 days. As etsted above, no sedery-As uired by 10 CFR 50 91(a).the wul om enew the possibuity M e new w $ N Z M jgg, licanese has provided its malysis of the h I'"" **T d mrefers. the proposed change does not issue of so significant hazards

c. This change would not involve a create the poestbihty of a new or dtSerent consideration, which is preestated spFrant reducuan in the margin of safety.

Lind of accident imm any accident below: No changes to plant operation, testing, or prweiouaJy analysed-

a. No =W A~a' 6acrease in the probabuitF physical contgureuon of the plant will be or

- of an ocx*iset prwetounty necessary with the removal of this ucense 3 The proposed change does not tavolve e sig:uncant reduction in a mar 5 n of safety. eval results froen this change. Condition. 1 The proposed change does not alter the Removal of this ucense t'=dturm does not As stated in the NEDO-31554 kuuro of the requirement that aD contml rods be a5ect the physical opengurettom or operation existing neutron Dux monitoring i OPERABLE in OPERATIONALCONDmONS of the plant, so the probability of an arredant instrumentsuco will not prevout the operator 1 and 2. m proposed change does not previously evahnsted to met incrossed-from desennining reactor power levels. change those required actions tf a cuatrol rod The NEDO 31554 esport emetyeed event Suf5ctent inbrmation ws11 be availeMe upon j ts !=-; " The revised sure=hr= la scenartoe to decennias the - ~ of which to base opereuomal da^ha and so i confunedom week other control sod neutmo flux rrmunning uw-Ney and conclude that reactivtty control has been surveillanoes r=arinase m==tme=4= the concludes that the fanure of thle ,mm. pushed. relhetmhey and eveilaMhty of the saem instrumentation wiD not preeent the operator Thus, the margin of safety will not be funcuos as wou as the required *Waawn froan determiningt=arere power leveh-reduced by de4rting ucanse Condition (cX41 margia. Tarh= tral $g s will Ahernate stette wE be stellalde of M=chaat 1 to the GCNS Operating continue to regnire the mayority of the free reactor power suey be naturned-Ucanse. control mde to be tested once per seven days-Suf5cient Infonnation wiu be usediable spon na NRC staff has reviewed the The mergin of selety provided by the ce.J which to been operothonal d=r**== end to licansee's scalysis and, based on this TS is not affected by tnotesing the conclude that sweettvtry control has been rwiew it appears that the three survamance toterist tri 31 deye. arenmpushed, thereby not *-

the standards of 10 CFR 50.92(c) are Therefore, the proposed chanp does not q= ~= of an arradane AddittomaDr.

satis he NRC staff rwult in e sigaticant reduction in a energin criteria contained in NEDO 3tS58 regarding the neutron Sun taanitoririg instrumentation Proposes to determine that the of ea .ce the above vraluedan eparettoa provtde oef5ctenti:enSdencethat the amendsneet rtquest involves De i is eccnrcescs with the psoposed areendrment instrumentation will to avn R=W to cuaSre signiacs.nt hasards masideration.

Federal Register / Vol. 58. No. 90 / Wednesday. May 12. 1993 / Notices 28057 IocalPublic Document Room modifies neither the qualihtions otun .m proposed changes do not location: Judge George W. Armstrong required by, nor the cornpetence of, any inn n a :gniacant hazards mnsideret on Library. Post Of5ce Box 1406. S. PORC member. Adding the Manager of because the char.ges would not; Commera at Washington Natchez. Planning and Scheduling, and the I' I"* I" ' '28 inC'8'*C"" i' * , 7'**** "I '" "'C'd'"' I Mississippi 39120 Manager of Plant Engineering to PORC p ,3 Attornryfor heensee: Nicholas S. membership expands the capability of The proposed chacges simply remove the 1 Reynolds. Esquire. Winston and Strewn, management to more mmpletely cover provisions of 6 N Protocuan Program ha 1400 L Street. N.W.,12th Floor, appropriate aspects of station cperation. are mntained in & Technical Specahcations Washington, DC 20005-3502 Increasing the number of PORC and placa them in b TRM [ Technical NRC Project Darector: John L Pellet members required for a will.. Requimnents Manual). No curant (Acting) ensure that a quorum continue to requirements are teng added or deleted Maine Yankee Atomic Power Company, be majority of PORC members N aside from removal of the special reports e Renew M h Fw h n Dockst No. 50-309. Maine Yankee espability of PORC to meet its Program and its revisions will be the Atomic Power Station.11acoln Concty, msponsibuities is not diminished-rwponsibility of the PORC IPlant Operetions Make The proposed addition of three Rmew r-mitteel and SORC (Site snelytial methods to the list approved Operations Rmew Committeel, just as it has Date of amendment request. Apnl 7 by b S'RC (Techdeal SpectScation alwsys been the responsibility of these 1993 5.14.2) for determining Maine Yankse's pe to nww chanEes to are protect.on core operating limits does not rhange ting Condition for Operation and Description ofcmendment request; the whent that m operathg Surv=itlaw= Requirements when they wem P part a the Technical spectacauonsan N roposed amendment would limits meet e.il conditions of the safety add 10m. m daign basis omdents are increase the membenhip and quorum analysis, and thus does not represent s affected by this cAange, nor are afety requirements og the P t Operation reduction in a margin of safety. De ,ystems edwrsely affected by the cnanges. Review Committee (PORC).to reflect propoed changes are admidstnh b hbe. Mrles a spea a 6 cunent plant management positions, natum and do not involve a =ioni81e=nt probability of occurnace or the and would add three analytiesi tr.wthods reduction in a margin of safety. mmqunas of any design basis accsdents. to the list of those approved by the NRC

2. Creete & possibility of a new or for determining core o

• limits.

Based on this review. It that di8' rent kind of accident from any Basis fwpro sed no spu scont the three standards of to 92(c) N r Posed changa simply renEn & mlusted. hazards cons retson determinadon: are satisSM brdore* b NRC staN P provtsions of the Fire Protection Program that As required by 10 CFR 50.81(a), the Proposes to determine that the ere contained in the Torinrat specacations licensa has provided its analysis of the amendma t request involves no and places them in the TRM No marrent isme of no signiScant hd signi$ cant hazards consideration. aqunments are being added or deleted consideration.The NRC staff has localPublic Document Roorn aside from removal of the specsal reports reviewed the licensee's andysis aEndn=t location: Wiscosset Public Library. High esct2an.There are no new failure medes the standards of 10 CFR 50.92(c). The Street. P.O. Bax 367 Wlacasset. Maine w=u with the propmd chansa. Since NRC staff's review is presented below. 04578 the plant w111 conunne to operste u

1. The proposed amendment does not m f

. Mary An d "188'd th' PP **d Ch""8 " II* ' Lynch. h g involve a signiacant increase in the l m dify the P ant twp m t Point where Maine Yankee Atomic probability or consequances of an it can be considered a new accident. mnPany. 83 Edism &lve.

3. Invoin a signincant reduction in a accident previously evaluated.

Augusta. Maine 04336 margin of micy. Because the proposed changa do not NRC Profed Dfractor-Walter R. Butler No cheny is being proposed for b N involve any alterations to the plant. changgs to setpoints, or operating Northoset Nuclear Energy Company, $N, Q"3g1, **[""' conditsons or parameters, the response Docket No. 50 245, Mill =ana Nh being deleted and the requirements of the plant to previously evaluated Power Station, Unit 1, New London contained therein en being incorporeted into accidents is not affected. Nrefore, the County, r o-tat b TRM. Plant promdurw will continw to proposed Technical SpeciScations Date of amendmentrequest: April 16. d' th' 'P'"8C 1882 Ct'*** **CY 7Ge impimentenon a'"h requinants, changes will not increase the probs,bility g993 Just es when the requimnents resided in the or cona ences of an occident ' CW 888 87 88. Technical SpeciScottons. Fire Protection previous evaluated. PmPosed ameh remcrne Proym chanen will be ammed by the

2. The proposed =W-t does not requireme ts fran the Te5 =le=1 provisions of10CFR50.59 and the current fire create the bilitI of a new or SpeciScotion to the Fire protecstaa license condition. As such, h different d of accident from any Protacion Program, places these changes do not directly affect any pmtective accident previously evaluated.

same requirements in a Technical boundanes nor does it impact the safety The proposed amendment constitutes hatts br b boundary. Thus, there are no administrative changes that do not aHect Requimmants Manual (TRM)hcant Sosisfor no sigru ednrw tinpacts on b penettw the design, operation, maintensnea or g . dh b undenes, safety limits, or ofseisty. m b NR the testing of the plant. Thus, no new As mquired by to Nuita) ee 33,,,,,,. C staff has revie modw of failure are created. Therefore. s calysis and,bened on this thew changw do not create the U] D

view.it appears that the three 8

lw t possibili of a new or different kind of

• netards of to CFR 50.92(c) are mnsiderahn, which le pmeented estis$ed.Thenfore.the NRCstaff accident any accident pmviously evaluated.

Proposes to determine that the ee wie 1 N t2. m 3.The proposed amendment does not has reeeased me attached pmposed % amendment requwt involves no involve a sfgniacant reducion in 8 and has crmchaded that doeatinedvo M b=at hazards consideration. magin of safety. e 816ntScant hazards cons can. m best Public Document floosn Tne proposed char.go to PORC besse h this condustom is that the three - locadon:Leaming Raourtze Center, znembership and qucrum sequirements crateria of1OCFR$0.92(c) are not Nmes Valley State Technical College.

28058 Federal Register / Vol. 58. No. 90 / Wednesday. May 12. 1993 / Notices 574 New London ' urnpiks. Norwich. 3.4 9 3. it is not necessary to beve another timelinees of detecting any RCS leakage and T Connecticut 06360.

• • chnial 8 Pee!5 cation mquin the vent. Only to allow for any required action to ocrur Attorneyforlicensee: Gerald GarSeld. the PORVs require electrical power (bettery) earber. Limiting the apphcabihty of this t function. By procedun, the PORV must be leakage rate along with incnumg the ume E89uire* Day
• Be#U & Howard*

declared inoperable when its assocsated allowed for determimnr its source is Counselors at Law City Place. Hartford. bettery is inoperable. Thus. Technical intended to prevent any "-~y plant Connecticut 06103 3499 Spect$ cation 3.4 9.3 adequately ensures that shutdowns and subsequent eqtupment NRC Profect Director: John F. Stolz the RCS prowun boundary is protected. As transients. Additionally, changes to the Nutheast Nuclear Energy Company, a4 e result, the proposed change does not monitoring of this leakage level an proposed el" Docket No. 50-423. Millstone impact the margin of safety. to reduce operetor burden and further Nuclear Power Station. Unit No. 3. New The NRC staff has reviewed the en h-= overst! plant operet'.on, thus landon County, Connecticut hansee's analysis and, based on this decreasing the probabihty of previously ,, justed evens ne consequences of those arts e e anged by his reposalme Dete of amendment request: January standards of 10 CFR 50.92(c) are m strettw wncuon 2 de ete the ^6 * ' 93 ' Nhnprion ofomendment it quest; satisf ed. Thefore, the NRC staff ' outdated footnote has no safety impact. Proposes to determtne that the

2. Crnte h pouibihty of a new or Thz proposed amendment modifies amendment request involves no different kind of accident frun any accident requirements when certain electrical significant hazards consideration.

previously evaluated. power sources are not operable to Local Public Document Room As stated above thne proposed changes an prohibit certain operations, and to location: Learning Resourtes Center, intended to impmn the early detection of remove a current requirement to vent Thames.VaUey Smte TechMcal Colle. RCS leakage while enhancina operator tha reactor coolant system, based on 574 New landon hrrnpike. Norwich, availability br detwmintnr tlzis sourts of adequate overpressure protection Connecticut 06380 """#I requirements e istmg elsewhere in the Attorneyforlicensee: Gerald Garfield.' Op Y [ Con ^ tec ni,ca spec: cations. 1w Esquire. Day, Berry at Howard, City steed state canditkes have been Basis forpro sed no significant Place. Hartford. Connecticut 06103-wtabfished. while incnasing the time to hazards consi erotion determinotion. 3499. conduct thorough investigations. Therefore As required by 10 CFR 50.91(a) the NRC Project Director: John F. Stolz them changes will not create the poulbinty licensee has provided its analysis of the of a new or dLfferent kind of event. issue of no significant hazards Pennsylvania Power and Light

3. Invoin a significant reduction in a consideration, which is presented Company, Docket Nos. 50-387 and 50-margin of salsey.

ne motsvetion br pmposing these below: 388 Susquehanna Steam Electric Ch."8's is to improve the detection The proposed changes do not involve a Statioc, Units 1 and 2. Laserne County, significant hazards consideration beatuse the Pennsylvania capabthties of the operstar by incorporating stricsse limits and elunmating some cher.ges would not;

1. Involve e oignificant increase m the Date of amendment request; April 16.

unnecessary burdens. thus mcmasing. not domessing the marp'n of safety, d the pmbebthty or consequences of an occident 1993 The NRC staff has reviewe previously analysed Three of the proposed Description of amendment request: chtnaes add additional restnctions to the The amendments would revise the heensee's analysis and, based on this t+ct.nical specifications while one rherme Technical SN$ cations (TS) as review,it appears that the three ren. oves an unnecewary restnetton which is requested by NRC Generic Letter standards of to CFR 50.92(c) are adequately covered by Technical (GU88-01. NRC Position on IGSCC in satisSed. Herefore, the NRC staff Prot . he p do not BWR Austenitic Stainless Steel Piping." proposes to determine that the affect any of the design baars accidents nor GL 88-01' requested licensees to submit amendment request involves no are there any malfunctions associated with TS changes to include a statument in the sign 16 cant hazards consideration. thew changu. section on Inservice Inspection (ISI) that localPublic Document Room

2. Create the possibility of a new or the ISI program for piping covered by location:Osterhout Free Library, different hindof mocident imm any the scope of GL 88-01 would be Reference Department.71 Souta previously analyzed so:idant. The proposed performed in acxxirdanna with the staff Fr=nkHn Street. Wilkes-Barre.

1 change to ehminate the requirement to -positions on ocbedule. tasthods. Pennsylvania 18701 d:pressurtse and went the free: tor coolant personnel, and sample e ion as Attomeyforlicensee: Jay Silberg. I system! RCS does not create the ibihty. Esquim. Shaw. Pittman, Potts and l rhl'e0;=*ea' "'#""_%a*t. outhned in the GL Also, nama wem requested to maif the so- = da22=" - "w-i being fulfilled by Technical SpectScotton unidenti$ed leakage within W

n. D 003 3.4 0.3. Thus, as long as this overpreneurs containt-t to limit any increase to 2

1. CI g*f m within any 24-hour period. The protection is in place there is no possibthty

-e of an socidem of a diflerect type nhan 's submittalis their response to Tasmeemos Valley Authority, Docket pmvlously evaluated. GL g8-01. Nos. 56 327 and 50 328, Sequoyah

3. Involve a signifkant reduction in the hasards con [r 'no significant Basisforp Nuclear Plant, Units 1 and 2 Hamutan runrgin of safety.no baan & be tation detertnination:

• Tamanesee requirement to depressurtze and vent the RCS upon a loss of AC or DC power or the As required by 10 CFR 50.91(a), the Date of amendment request: March asso: ated buses while shutdown was to heensee has provided its analysis of the 10.1993 (TS 02 08)

(nsure that the reactor vessel cannot be issue of no signi$ cant hasards Description of amendment request: overpreuunzod. Technical Specification consideration, which is presented he proposed amendment would revise 3 4 9 3 requires one of three rystems be belom various technical speciBcation Jo ierable to provide ure protection. The proposed change does not: ents to allow a reduction in the inis can be two tresid heet removall RHR

1. Involve a signiScant increase in the l

boric acid concentration in the boric suction relief valves two (power-operated probabihty or :xmeequences of any accident reh f valves) PORVs.or a vont arms of 5.4 previously evaluated. acid tanks (BATS) from 12 percent to square inehas Stace one of these eyeesms t-WA of the more restricthe aPproximately 3.5 to 4.0 percent by must be opemble by Technical Specincation leakage hmit is intended to improve the weight. lo accomplish this, the

~_- Federal Register / Vol. 58. No. 90 / Wednesday, May 12. 1993 / Notices 28059 l following changes were proposed: (1) that it does not represent a signi&mnt kind of soddent fmm any pnviously l Limiting Condition for Operation (IDO) hazards consideration based on enterte analysed. 3.1.1.1 and 3.1'1 estal lished in to CPR 50 e2(d Operation of As prwnounty stated. Mode 4 has been would be revised'2 Action Statements Nuclear Plant (SQN)la accordance deleted htun TS 3.1.2.s and added to TS to increase the flow wi the easedmont wn! not: 3.1.2.s to provide consistency beween thm I rate from 10 to 35 gpm (gallons per

1. Invo e algniamnt increase in the two TSs and TSs 3.1.2.1 and 3.1.2.2. The I

minute) and to decrosse the baron prnhah111ty or.-- _ r= of an occident analysis prcnodes the basis that sufBdent i concentration from 20.000 ppm (parts paviously evduend.' shutdown margin still remains to meet the I per million) to greater than or equal to ne reduccon of the bcric add TS requirement for Mode 4 when it is added 6120 ppm;(2) Surveillanca concentration in the boric acid tanks (BAT) to TS 3.1.2.5. Thesefore, this oes not Requirements (SRs) 4.1.2.1 and 4.1.2.2 and diminsuom,of. ts brthe coste the possibinty of a new or florent would be revised to better describe the

• • • • '"ad best trem circuits wul not kind of acddent imm any previously heat traced flow path,to change the

- angnia==tly saaem se pebehan(er analysed. j minimum heat trace solution C"*"9"** d ** 'CCId**'.g are

3. Invdw a signmcant mductbo in a i

evaluated. Only minor margin of safety. I temperatum limit from 145,F to an planned; and while operating pmcmeses m merlin of safety mquirements is not ambient temperature limit of 63 F.and wulchange to seeeet the new boretion enacted by the smoval of the best trece to establish requirements should the method, the capsbuity to enfely shut down circuits and the reduction of the banc acid i area temperature drop below the limit; has not been changed or modiSed.TS concentretaon in the BATS.The required flow (3) SR 4.1.2.2 would be changed to raise controls have bem pieced on the barte add paths and boreted water sourons are still the required flow rate;(4) LOO 3.1.2.5 storegs system to emeurs that the lack of heat evenabis as before.The required quanuty of would be changed by deleting the heet tracing does est tasalt in the barca borated water le still evadable based upon i trace requirement,i the teeng out of solutism. .SQN the new eenluodea, and the abdity to deliver minimum boron volume an decreasing abihty 2 baree et to pw this horsed watw mmains the same. As te wi e m Mon stated pwvbusly. 6e mducdon d the boric l the minimum solutiontorn ture 20.000 parts per million (, ). Wtth the oc d ena==tretaos in the BATS will ensure red Cd proposed changs.Q lNovide the that the boric sod==aina in solution et the f increasing the minimum containment ability to borete et 3s gun with a solut6am of nom.at rooms tempereture in the auxiliary I borsted water volume in the refueling between 4,130. to 5,teo-ppm baron.This wul - buindias To ensure this, ambient water storage tank, and expand the ense that the boroa addittom tem Waa _ m wn! be penodicaDy vw1 Sed. l applicability to include mode 4 (5) SRs essentially the same. In addition. as horan with the above chances. there will be a not i 4.1.2.5 and 4.1.2.6 would be changed to additico trass the BATS is not taken medit for improvunent in system reliabinty and - i add a requirement to verify that the in any accident analysis, the probabu or ecoordingly, the proposed changes do not boric acid tank solutloc tem is onnamtuanme d esry saddent p aSecs the anergin of animy. paluated wulam be assend Mwing Mode 4 e licebnity fran TS greater than 63*F every 7 de s by ^8 part of this .for =, - i 3.1.1.s to TS 3.1.2.5 not lovolve a i verifyin &et the area tempersture ia Mode 4 was T53.2.2.8and reducsion la the margin of safety. This is i greater an 63*F. indicating the action placed in u 3.1.2.5.no endysh 4 f - J by the analyens.which setabusbw that must be taken if the tem reture is supports &e relocanos and d==aastrates Annaimum home requirements to ensure below 63'F. and chan g th format of that there is sufficient boreted water volume that there still emains edequate shutdown the SR by separating requirements and mecentredan to prw6de the required margin for cooldown below 350 degrees F for the boric acid storego system from shutdown mergia. Resed upon this analysts. (Mode 4). i thoes for the refueling water storage this changs does not insotw e alg-an==t The NRC has myiewed the licensee's tank (RWST) uirements;(6) LCO inavnes in the pMty or comesquences analysis and, based on this aview. it 3.1.2.6 would changed by deleting dan omdent pw6mly mlused-appears that the thme standards of to the heat trece requirement, replacing the ~ M m2(c) m satisRed.nemim.de d a minimum contained borated water NRC staff proposes to determine that the poviously adyend. volume s 5 cation with a ngure that Us crisinal SQN desism required beet amendment request involves no relates m imum conantretion to trace circuits to ensure the baron, which was ' al Scant hasards consideration. minimum volume stored for various et t: percent by weapht. would remain in Public Document Room RWST concentrations, reducing the solution and be evaineble for reactor coolant location: Chattanooga. Hamilton County i minimum solution temperature, rysism reactivity control throughout core his. Library.1101 Brood Stroot. Chettanooga. p lowerlag the bemn conosatatine m Tann==maa367402 f removing Mode 4 from licabili of y the LCO, and changing n 2 3.s e 44 peut by weight. Attorneyforficensee: General can has shown thm is ao Counsel.Tasmesome Valley Authority. Action statement to require that the ou ef plant be placed in the Hot shutdown g$dberon 400 West Summit Hill Dnve.ET 11H. l condition rather than the Cold g Knoxville, Tennessee 37902 l runnins above se Fahrenhott(F). The miopcr Necte Frederich j shutdown condition if stated conditions euxillery huudies, this equipment is Hebdon cannot be setla8ed;(7)1XX)e 3.9.1 and located essamuy.remales well ahose SS 3.10.1 would be changed to increase the degrees F. Comunuous monitoring of the Teemessee Va'lley Aetherity, Docket i required boration Sow rete and decrease required see tem tuves, in==>=r*5a= Nea. 90-327 and Mat Segeoyah the required baron concentration; and with en alarm la main coetml rooms, will Nuclear Plaat Unies 1 and 2.Heseiltoa (8) other adminierestive and applicable allow la opuneer settons aseem es Basis chen acdudas empmem sentes show heTS-M eT " " [ Basisfor no signifkant '*R*I"** ~ l~ * ~ etom a n h a er Done of amndantmuestMarch a 43 degrees F Dy chantasslag the esed 10,1993 CTS 93-02) hazards consi strtion determination, Deschption of amndment must: e me-m 8 e8 C"" I

• is "9utred to CFR S0.91(a)* the evetlabihty of the beric acid asoregs sysumL - %e proposed messedmont would add a licenses has provided its anal ofthe la addition, the baron -essues reestas referwoos to the test ts of to I

issues of no signi5 cent well abow =apare=d RCS commonsrution. m Part 50 J.. Primary i i consideration, whicl} is presented Therefore, the removal of requiresmanes lor.. below: heet nece adecules and the reducena of the u.=, m===sn===Gmakage Testing i TVA has evalueted the technical barna rinar-tratica in the BATS do not for Weter Cooled Power Reactors"1o the sparimah (TS) cameegs hasdecennimed asum the poseartisfy of e new or dieneent technical spec 15 cations, and remove the i

i l 4 28060 Federal Register / Vol. 58. No. 90 / Wednesday May 12. 1993 / Notices { current detailed test requirements and maintain these contonnwnt test taken for the associated normally-shut reqmmems under 10 m 50. Appedix 1 vacuum rehef valve to satisfy the accqptance criteria. Other related N pmPosed change dow w sher any containment isolation function in the i containment system spec 15 cations T put a vacuurn rehehoolatie valve is { would also be removed. In addition, a 'g'**I ' ly ta p;oposed change to Table 3.6-2 would h matamment leakage usumpoons usM e inoperable. In addition, a proposed clarify the additional testing determne affaite den umits for comphance Bases change would explain the requirements for the purge valves. with to UR 100 are not s5ected. All other functional relatimship between the i Basisforproposed no sgmficant proposed chaag== are cleriScations, vacuum rehal valves (swing-disk valves hazerde corisiderotion determination: including the revised wordmg for the that operate on containment low imtwte m TS Tabh 3.64 Na pmesure only) and the vacuum reDef As required by 10 CFR 50.91(a). the hc nnee has provided its analysis of the clanSescas do um impact the imet of the isolation valves (air operated valves in 'U*C**d s tesues of no atsnificant hazards series with the vacuum rolletvalves and considmtion, which is presented new or different kind of accident from any fail oP.en m loss of air pressure). hs for propoW no sWest below' previously analyzed. bC8dfd8C0885d8'UI808d8f8ffMAUf30A? TVA has evaluated b proposed technical

3. Involve a signi$ cant reductaan in a l

speciScotion ITS) chansp and has determmed marsin of safety. As required by 20 CFR 50.91(a), the that at does not represent a signt5 cant The margin of safety provided by SQN's licensee has provided its analysis of the F.azards consideration based on entena anowablie contatmnent leakage rate test limits issues of no significant hazards estabhshed in to CFR sn tr(c). Operation of 10.75 La for penodic Type A tesung and 0.60 consideration, which is presented Squoyah Nuclear Plant (SQN)in accadance La for Types B and C testing) roma*na below-with the amandmant wiu not: .,,*ad TVA*e proposed change recnoves WA has waluate b propoed wchnical

1. lavo ve a sagatScant inaones in the detailed requimmen.s such as containment speciScotion [TS) change and has deearmmed Probability or caneequences of an accident test requirements. test schedules. and test that at does not represent a signihnt Prwtously waluated.

accuracies fraca TSs.These detailed hazards consideration based on criteria SQN s Primary mawnmant design mquirmaenu am governd by 10 CFR 50. estabhshed in to CFR $0.02(c). Operation of include me proviekos and loetures mqu Appendix 1. and have not been a5ected by Sequoyah Nuclear Plant (SQN) in accordance m settsfy the towing mgaimments of 10 M TVA's proposed change. Individual leakage with h proposed amendment will not:

50. Appendix 1. TVA a proposed TS change hinats associated with SQN's containment air

1. Invotre a signibnt increase in the t

be.a in b ry are ous! val a 10 CFR so. Appa=M N evaluation for c W Wy b 's NWh2N~ determining rmainment nsakegs ret cmuu of 10(7R 50. Appamdh any eyeessa luactices er desegn functions and offaite cose hesita buswtag en p aM m med b Q TSt. M e6er m pg % m m 6. N proPoeod changes ses cleriScations and do acceptability of SQN's vectzum rehof valves ,.g smrtins ,,g not aSoct the intent of the afheted be containment isolation on,and hmits 10L7514 br periodicType A testing p*r.m r 3 maatly.TVA's mairtn these normal); valves for TS. ( ,"O prapnaad change wiu'not a5ect the margin of isolenst t. the event the namented g g a g ;; S g, v,,-g,= "h has revie.ed me umn.ee s 1:;:'bia'f=P.;c"fs" =" a ,s e reference under 10 CFR 50. Appendix J. analysis and, based ott 61s aview. It appmech pnaina masisunt wts b TVA's pioposed = =M==^ does not affect appears that the three standards of 10 vocaram rebef valve's containment isolation tha individual TS taakmen rotas associaied CFR 50.92(c) are satisfied. Thetsfore. the des mcsion. svacuwnmbef valva (spnng4onded. wth SQN's containment air lock. purge NRC staff proposes to determine that the sw2ng. disk check vaW m daign to vdves. or secondary bypnes Mekage to the amendment request involves no auxihary bunding since these leakage rate sgrnMcant hazards consideration. [ [prMucts hmits m not spectScab ofthe localPuhhc Document Room from the contelament atmosphere during hrnais^ focation: Chattanooge-Hamilton County normal opermion and durtog an analysed The d vi ual un4.n.edau e,orstam d m SQN TS m ubmrr. n01 aroad stmet.Chatan=sa. evmi aede m >===e=t. ohr cha en clanfications* Tennessee 3y402 valve is leak tested in accordance with mda wording for h AttorneyforJocensee;Gemaral to TR 50. Appendix J (Type C test).to footnote to TS Table 3.6 2.These Counsel.Tennesase Valley Authority. enom that the row froen thevalvo l88n combined wt me ladare ate fran clanScataons do not impact the intacit of the 400 West Surnmit Hill Detvs. ET 11H. 1"n ohr Types B and C matamme a i dieeted spar *=nons. Knorville. Tennessee 37902 la modusica.1VA's proposed TS change NRC Profeet Director-Frederick J. peserstmas e um win wt asset -wamant test criteria. Hebdon m.a w M e m W m 6e e system conditions or plant conSgurations, tad will not afiset SQN e aeruaat analysis. Tammessee Vaney Authortry Docket case design beats accident analysis Gomef-coolant aa Want ROCAD bounds 6e too l, .The proposed change ic en==ula ed by TVA Nos. 50 327 and 50428, Segmeyah to be a T3 Leprovernent that is enesistent Nuclear Plant. Units 1 and 3 Hasallton lenkesehash-The vacuum schof valves m normah with the idancs contained in the recently 'y cloemd vatves and m held ebend by a spring a NUREG 1431.Conesquently.this force norsaal plant tion. Tbs h wiu not tacrease the probabutty ar Dirts of amendment roguest: March cenwequences of an accident previously 19.1993 (TS S3 06) valves experience tionalebsing evaluated. Descrrpdon of amendmentisquest; brcs durtag a pressurisation event inside

2. Creets the posalbihty of a new or The propoemd emendment would clarify metainmentle.g 10 CAL A mytow of the

' dafterent kind of accident fmm any the cr-:,tainment teoletion requiretnet2ta design basta nuts tambing contaht depmmartahindicans metem m m previously manlyzed-the cxyntainment vacuum Postulsed scenerks that would open the No ystoel mod *w6aa is beingmade to ndef an voeuumrehefisolation vocousa sonst vetves seuowd by a 10CA or any p.p.nt he,dwm, pim op.cmg i slves. His wquid be armmphsbed by other acc$ dent randma requiring owpotnts. hmits, or opersing Ww as T"'urnitingM*n for motatnineet teolanna This conwnmant e mesh of this shooga. TVAD geopmeed TS anwedsnamt is essegned no vaesprdeenGod - Jperation 3.E.3.b. and adding a note to isolation fanwaa r==ina consistent with mnamment test requinsments imm Tss and Table 3.s-2 that would aDow cndit to be the SQN ramal Salwy Aaalysts Report (PSAR) l l

4 Federal Register / Vol. 58. No. 90 / Wednesday. May 12, 1993 / Notices 28061 Section 6 2 6. and the exemption to 10 CTR be opersble in accordance with TS 3/4 6 81 1b. Not involee a s1 mi6 cant increase m the

50. General Design Cntena 56, pmvided in Considenng SQN's vacuum felief salvesas 6

deactiveted automatic valves, will ensure consequences of an escident prevnously NUFKr1232. evalusted becsues the changes do not alter A seven. day t!meframe for returning an that the TS acuan mquinments nmain the Updated Safety Analysis Report (USAR) moperable vacuum rehef isolation valve to constatent with thedesign funcuens. Both LOCA evaluation and ensure that the plant cperable status is provided and is consirtent vacuum rehef and aantainment elation can be safaly shutdown for an 10 CFR Part with other TS action requirements that are requinments will continue to be pnWtded.

50. Appendix R fire. There is sufBclent nme apphcable upon unavailabthty of SQN's Accordingly, the proposed change does not -

available under the LOCA sequence of events control air system 11 e.. reference TS 3/4.7.8 tnvolve a reduction m the maqpn of safety. to close the breakers before the operstor is "Aunliary Bu11d2ng Gas Treatment Systerre The NRC has reviewed the bcensee's mquired to tranaler pump suctions to 6 TS 3 6.1.8. " Emergency Gas Treatment analysis and, based on this mnew,it containment emergency sump. Procedures System 2; and TS 3/4 7.7. " Control Room Emergency Vantalanon System").The seven-appears that the three standards of 10 win s, quin that the breakers are closed by d'Y ""*fr*** "'"'" **' "d"*d"*' CFR 5492M am endsned. h.h th'*F8'atoes. N cumuletive red 6stion dose-isolauon capabihty is restored in a NRC staff proposes to determine that the acerved by the operstor while performing reasonable amount of time such that rehance amendment request invoyvos no these manual acnons would be below the h,adehnes of to CTR Part 20 an upon a smgle vacuum relief valve does not significant hazards consideration. So, Appendix A. General Design Cnteria e ust for an indefinite penod of ttme. LocalPublic Document Room 1_ Accordingly, the proposed TS change does location: Chattanoogs. Hamilton County za. Not create the possibility of a new kmd not mvolve an incman in the probaothry or Library.1101 Broad Street. Chattanooga. of accident from any accident previously consequences of an accident previously Tennessee 37402 evaluated. evaluated because adequats time is available Attorneyforlicensee: General under the LOCA sequence of events to the

2. Create the possibihty of a new or d;fferent kmd of accident from any Counsel. Tennessee Valley Authonty, operators to restore power to the Boreted Previously analysed.

400 West Summit Hill Dnve. ET 11H. Water Storage Tank (BWST) outlet valves and No bysical modi $ cation is being made t Knoxville. Tennessee 37902 the containment emergency su=p valves any p ant hardwsm, plant operstag MC Pro Dirt *ctor FredeckJ. when needed. b breakers needed to restore setpoints. hmits. or opersting procedures as Hebdon the power to these valvw am located in a twult of this change. TVA's proposed radiologicaDy accessible areas poet.LOCA. change orovides a TS improvement that Toledo Edison Carnpany.Centerior 2b. Not creats the possibility of a different clarifies the co tion and function of Serdce Cosupany, and & Cleveland kind of accident from any accident SQN's recuum to reivalves se designed. The Electric Illuminating Cosmpany Decket provlously evaluated because adequate thne is remnable to the operstors to restore power proposed change removes the posential for creating a confbet between Specifkadon 3/ Station, Unit No. s. Ottawa County, - to the BWST outlet valves and the 4 6.3. "Conwn==nt looietion valves." and Ohlo containment emergency sump valms when Specifkation 3/4.6.6."Vocuum Rehef needed. h breakers needed toimetare the Valves." SQN's vacuum rehof valves provide Date of amendment request: Power to these valves are located in quahSed containment isolation protection November 9.1992 mdiologically accessible areas post-LOCA. that meets the intent of the TS action Descrrption of amendment request;

3. Not involve a signifkant reduction in o -

mquirement for containment penetrati he proposed amendment would revies' ma of safety because eau am not "1 8 AC*** *A**8" '"

• I"**I '"*d* "'

Technical S ociScation (TS) TS 3/4.5.2 isolation. 8 P The proposed change does not alter any TS Bases 3/4.5.2 and 3/4.5,3.and TS. contributing to accident seversty or e ens. hre is suf5cies ume occident analysis or any assumptions used to Bases 3/4.8.2.1 to allow the de. available to close the breakers before the support the accident analyses. N energization of the Borsted Water contamment leakage assusaptions used to Storage Tank outlet isolation valves DH-operator is required to tran=6-pump sucuans from the BWST to the Conwa= ant determine offstte dose limits far compliance 7A and DH-7B in the open position. Emergency Sump. with to crR 200 am not affected. A *No-d*7 tim *freme for meuming an during operstional Modes 1. 2. 3. and 4. %e NRC staff has reviewed the m effect of these changes win allow licensee's analysis and, beeed on this I tYi[p istInt the licensee to perform control room review,it appears that the three d.d a wnh other TS neuen trements that an evocastion actions in the event of a fire standards of to CFR 50.92(c) are s appucable upon unov htyof SQN's with one less person on each shih. In satianed. Denfore, the MC M. control air rystem (i s., reference TS 3/4.7.a. addition, as a related change. TS proposes to determine that the TS 3.6.18. and TS 3/4.7.7). The seven. day Surveillanca Requirement 4.5.2.d.2. bis amendment request involves no. timef:une ensures that redundant tooletion proposed to be resteed to reGect the-alam*=nt heurds consideretios.- capabihty is restored in a tenoomebbe amount of time such that m%nna upon a sin 6 8 testing of the aralves' interlocks only%&'Lacal Public Document Acoert. - 3 neuutn rehef vales does act exnet lot an during timee of O.* 4x:ction: University of Toledo Mbrary, on. Sosasfer ao s4alficasf. U Documeszts Department,2801 BeaczeA indennite period of tienef - 7 mydhe faczards cong erstion derarmlaadoni. ' Ayemans. Toledo. Ohio 43606 - ~ M,0* ",* "g*,,",g' N,g. As requsred try 3D CFR.50 &1(a).the..,,.. forlicensee: Jay E. Stibesg. F* ,,, g dent freen any prerknaty snalysed. licensee has provided itsanalysis of the Esquers, w.Pittman Potts and

3. Involve a vtgMfirent reductina in a issue of no significant hazards Trowbridge.2300 N Street. N.W.,

i margm of misry. rnneideration, which.is pr===aad Weehington, DC 20037 The margin of safety previded by the belowr MCrroject Director: John N. Hannen dwign of SQN's containment wecussa rehef Toledo W-wi has reviewed the propdoed i s penetretion r=mata= *- i TVA's - changes and den = net = mat hats algatfkomt EleMc Coe It. U' Dockd No. proposed chance doa not adeet the hasards caosideration does not emnet bearnee so.ess.Callaway [n t l nn 's, containment neolatton hmeton or the operation of the Devis-Desso Nuc$est Power Callaway County. Missouri anowable contamment leakage rete veaun Station. Unit Number 1. in aczardance with. - epocssed in the T5s. m proposed change the proposed chasses would.,

• Dese of amendment regnest:

l eneures that h proper action la taken in the 1a. Not invotw t indnese in p November 11,1992 mot h automatic closum capetdlity of b probabthey of en previously ..... Description of amendment suposte benterey saanaeuia vuln ne lost tar any reason evalueend becausetsbessovej cd_ power'icr - & annendsnent wouId reviseTecimical (improper action would be h ischruon of a these vains does set a5sca be nuessrbreet 'S - Specifkation 3.9.7 and===nr4=ted Bases vacuurn saSef penetretion that to required to loss of coolant arrwat itDCAI ' ' M. - to allow the fuel pool transaur potes to r

28062 Federal Regneter / Vol 58. No. 90 / Wednesday. May 12, 1993 / Notices I ~ travel ovw bl assemblies in the spat Technical Specifications (TS) for the demonsonwd that primary-to secondary fuzi for rebling actintnes, fuel North Anna Power Station Unit No. 2 leakage as not expeasd during all plant h g system maintenanos, and (NA-21.The proposed changes would conditions. includmg the case where the seal 'ld 18 not Produced in the krww pint of the allow steam genormat ($G) tube sleeving *Y '"[* transfer to esal replocanent. in accordants with the Westinghouse e lak.WW Arsis r proposed no signi# cent horords considerufica detenmnotfort laear welding process described in evalus h e b W M f e As required by to CFR $0.91(a), the WCAP 13088 Rev.1," Westinghouse sleeved tube mesembly, using tmunding licensee has provided its analysis of the Series 44 and 51 Staam Genwator valum br operating retumes of Senes a4 and issue of no signtScant hazards Generic Sleevmg Report-14eer Welded 51 eteam generators. The evaluation le consideration, which is p 'ad Sleeves," Novoseber 1982, and WCAP. considered ceaserveelve in that no condit hr the t tube is emund in daarsmiaing below: 13619,'pedfic Applicathon oflaser the possuse of the sleeved tube The proposed change does not derselve a w.[ded sao,,es ger North Amma Unk I aseembly. ne neek habre-break criserte n sign $oant basard considerstaos

r==

Steam Geoormora." >"*ff 1993 Th counpares the p-eu t.e-e throughwell crack os of the Calleway Pient with thas NA-2 SGs b W mame tiabe length which will leek et a specified value et would not:

1. Involve a signinennt incmase la the degradation salated to correnton nonaal operadog condtuons thereby l

probabihty or conesquences of an acxsdent phenomena sudt es wastage, pittles, penm adequate leakege deseties and prevaously eveJusted. intergranular attack, and stress sale shu of the plant prior to the crack The Callaway Safety Analysis Aaport has carrosion crecbag. Tubes that a &ength equal to the anticalanck been reviewed and been lound to be experience excoastve degradstlan leng& ' emld be postulewd to herst et l steem line break conditions. The North Aane un= had by this proposed chmega The rduce the teengrey of the % 40-Unit 2 T=rh=ir=t Spectfkatacas henkt l design of the plant assumed gate movement g g A di%, to support plant rebel and fuel handhas tubes are considered dadective and orth Anna Power Station maintains an system mamtenance. Allowing gate movement over the opent f9el pool wiD not currently must be removed hona earv6ce adenanstrative==ad=n= aHowable leek new increase the anoes of any -cum-t or by pluging.De testaMotion of in unit tot 50 geuans per day (GPD) per aseen malfuncilon of pment since the fuel SG tubes removes the heat gemenetarl l racks have been to be able to surface of the cluged tube from e a e = i withstand a transfer gate drop trona 151ochee ,,,,4,. s',,.-.1vetube needs to The a key IedM' -- hek um knits q { a e the rocks with no damage to etered a redumion in the primary Bow ava e innare ng and may es heding modem Wes l $. Cres*e the possibility of a new or ultimately seduce the genweden W- . ~ r Serta 44 and 31 mum j -MCAktes, he.1. different kind of accident from any previously evaluated. capability of the unit. laser weMed h* * ** - - -- pante j Technical Specifications and sleevin process described in WCAP C' * ** II'7 " admimetrative controls wiD soeurs that the 13088. .1 andWCAP13819 is en trusfer Sass will not be nethe SG tube repair method that secures a the tact thatleek4ehre4 reek is rects in a menner which can bel length of smeDer % tubing cons; t be appbcobisOdetaricallyno i Therefare there is no new type of eacidset (elorve) on the beide dthe SG W Primary-to.seonedury tenhage or degradetson r or ms! function created. spanning the degraded bb ans been evidenced in W _ ^= sleeves)

3. Involve a signtScent todar=6a= ta a welded sleeve restores inkgrkT to the sleeved tehe==-hay, b _

i missin of esfoty. and installation of elseves does not hypotheecala===r-of huure of the The margin of esfery remains neefbened smce the Techn6cel 5 ficeuces and signi$tantly a9ect the best transfer sleeve would be bounded by the cunent administrettee con wiB esswo that the capsbuity or the zeector coolant fleer steem generseur tube ruptus analyste included in the North Asme Power Station gates will not be dropped on the recho la e rate through the elsewed tuba.%erefore, manner whitti can damage fuel. a signifkant nuanbar of sleeves una be tM IUpdened Plaal Sebty AnalyWs A* Port! De NRC staff has rewtowed the instaDod witberat decdag the opweden licensee's analysis and, bened on eht' d the reactor coolesit system. review,it appears that the three Dosisfarpro ao nWiessit The propoemd Technical e -r4Ar=rians r standards of to CFR $0.92(c) are hasardscon ' erodon detusedmodon, checer es se the h of Alley

• • 8 3*"'

83*"" d*" **' *d*""*II I satisfied. Thereders, the NBC staf As required by10 GR SO.91(a).Gus Pecs dulga 1 Proposee to datorudne that the Hmm=== bem provided th analyeds of time g amendmant request involese ne leeue dno algalammet besords h W & as m m significant W considerat6en. consklaration, which is presented below emelyses ser the cuneatTechanal 4 i localpuhhc Docarmient Room in condense form: Sp=ria=*'a= -inhaum reecear coolant I . lococon:Callaway County Ptidic

1. Opuseuen d me Nort Asse Ptsmer eyseen Sow ano resuhe des 1.ibrary,710 Court Street. Fulton, stattaa usat a la enneedeems wth the qualiScution tentleg, emelysen, and plant Mineouri 65251.

proposed scenes a-==d===r does est demoneerene that the yle en escapeshie means of Attorneyfer Noenses;Gesaid rh-anM tavolve a eipenest tecreams ta she a Esq. Shaw,Pittman,Potts & prahahinty er - etas encidmet maintalaims tabe loneytty. Phasing 11mit Trowbridge,2300 N Street.N.W Previously e==W atterta ese _ -. " ' usingthe padanos of ne tubsebest and/or tube support plass Regulesary Golds mt. Festhernesse, per i I Washlastan. DC 20037 lainersectina immt welded e6eese Calde m es NRC Project Dhector: John N. H=anaa ,.=ap ela= basbeen and sleeved canbe eneehemed periodic==ren=== with geneous y n Virginia Elssaric and Power Company, ennlysedla asesudeems ibe Docket No. 38438, North Amma Pseuer requhumisets of the ASME Code sad cunent^. , --- These menemen ~ Station. Unit No. 2. Immisa County, Reguletary Guide 1.121. Fetiges and stress denenesesse that tw=Hei= ef sleeves

• • • ly"e of the sleeved tube ensembuse muse of the tube wul Virl aia pseduced eczepsekle sueults. ha.ch==i,=1 suenere to e candities needisesat i

l Date of aswadnuar reguat: April 4. tuting has abown that he struchsel eneagth wie is original deden ham 6e. 1983 ofthe est alseves under asemel, r%=Enn== man of the sleeve with the Descripdon e amendmenf sogasset: fruhad upset omeditlose le ernthis apphcable== rela =a of the ASME and he proposed c[hanges would revise the =~=y==Ma hedts. l.enk testing hee resuhs of the 1sakse sad==rh=Mr=1 tests, i I

Federal Register / Vol. 58, No. 90 / Wednesday, May 12, 1993 / Notices 28063 support the conclusion that installation of incurred by &nfore, for greater Collections Npartment. Unfversity of laser welded tube slems will not increase primary t aree is matotained the probabdity cr consequences of an through sleeving. Use of Regulatory Guide Virginia, Charlottesville, Virginia 22903-acodent nreviously mluated. Depending 1.121 a1teria assures that the margin of Q'Tgg g- '*498 upon thebreak knean kr a posttdered safety wittr rwpect to structural intagney i. steam generator tube ruptmo event, the same kr the sleeves as kr thewtgmal Wupin. . Hunton and W1111ama, tation of tube sneertag could act to sesem ponersta tubes. Riverfront P East Tower, est E. uce h radiobgical m-to h h portions of the installed slem Byrd Street, Richmond, Vi 21219 pubbe due to reducmd Bow rate through a usembty which re; resent the reactor coolent MIC Project Director-N. sleeved tube compared to a non-eleeved tube sure boundary can be mor.dtored kr the Berkow based on h rwtriction a5arded by the tson and prugressen of sleevertabe wall i sleeve wall Mr+na-, inn thus - the requirements V a h and Pwer Cosepany,

1. h proposed b=mma amend =-ar does of Gu6de 1.63.

of the tube Nos. 50-338 and 50-339, North not cresta the possibinty of a new'ar'dffferent tridged by slem )otats ero adocttvely Amma Power Station, Unita No.1 and kind of accident previously evahnsend. removed from the pressure boundary, and the No. 2. IAedse County, Vlayimia !=piementauon oflaser welded sleeving sleeve then forms the pressure boundary in will not introduce ar rent or advwree then armes. h areas of the slamd tube Date ofamendmenfl'9utst: APtil 8 m chanps to the plant design bests. Stress and assembly which require inspection are 1993 fatigue acalyms of the repair has shown the defined in the Bases to the North Anna Unit Description o amendmenf request: he proposed c[hanges would revise b ASME Cods and Regulatory Guide 1.121 2 Technical Syew, allowable values are met. Implementation of Technical Specincetions (TS) for b laser welded sleevin6 maintains overall tube h e5ect of sleeving on the design North Anna Power Station, Units No.1 bundle struaural and leakage integrity et a transsents and accident analyses 1.m been and No. 2 (NA-1&21. The changes would level consistent to that of the crismally reviewed based on the installation of sleeves separate the contaf nment recirculation supphed tubing during all plant condluons. u to tbs level of steem generator tube sprey subsystems into two containmerrt leal and mechanical testing of sleeves p ' coincident with the mintmum recirculation spray trains. TS 3.6.2.2 rupport the conclusnons of the releations reactor ow rate. Currently the Nath Anna that the sleeve retains both structural and Technical Specifications limit mtatmum descibes the various subsystems that leakage integrtry during all conditions. reactor coolant flow rete at 2H.00 gpn total. are included in the GMainment Sleeving of tubes does not primde a Virgmia Electric and Poww Comneny has Recirculation Spray System (CRSS) and mechanism reruitmg in an acodent outside iseparately! submitted a prcrposed barnes the actions required if these stems of the arse s5ected by the siervos. Any amendment to lower tt.s mW=um sneesured harnme inoperable. CRSS is to ' bypothoucal acddent as a result of potential flow rate to 275.300 gpti.. h reduce and maim =M containment tube or sleeve degradstion in the repelred installation of sleeves is... ershanted as the pressure below stmospheric portion of the tube is bounded by the existing equivalent of some level of steam generster 1011% a high energy line and tube tu o accident analpis. Sines the tuos plug h slem esign does not effect an other provide for long-term post-ecddent = the unmediate aree repaired. in addition to Evaluation of the installation of sleeves is cooling. The curtsnt description of the component or location of the tu outside of , the fact that b installetme of sleeves and based on h determinstmo that IDCA CKSS 6 h TS describes the system as evaluat.cas for the licunned minimum reactw consisting of six separate and the impact on current plu6 sing level analyses coolant flow bound the effect of a independant subsystems and a casing is accxAnted for, the possitnhty that laser welded sleeving creates a new or different comtunation of tube alugging and sleering cooling tank. If snore than one of the six up to an equivalent 1the eaual sesem subsystems becomes inoperable, then type of accident is not suppor ed-generator tube plugging limit.1rJormation within one hour the inoperable provided in WCAP.13068. Rev.1 describes

3. The proposed license amendment does the method to determine the flow subsystems are required to be restored not involve a significant reduction in a equivalency for all combinations of tubesheet or the effected unit must be shut down.

margin of safety and tube support plate sleeves in order that his could result in unnecossary plant The laser welded sleeving repair of the minimum flow requirements are snet. 0 des;raded steam generstar tubes as identified sti within e d. esign param the m WCAP.13088. Rev.1 has been Based on the preceding analysis it is accident analysis bases. demonstreted to restore the integrity of the concluded that operation of North Anr.a he current TS do not occurately tube bundle under normal and postulated Power Station Unit 2 btlowing the reDect the terminology used in the accdont conditions. The safety factors used installation of Alloy 690 laser welded sleevw U dated Final Safety Analysis Report P in the design of sleeves for the repair of at the tube su elevations and within the (UFSAR) or the CRSS design basis degreded tubes are consistent with the sakrty tubesheet en of the steam tors,in document. De TS changes would factcro in the ASME Boiler and Pressure accordance with the --+ et - Wesel Code used in steem ponerator design. does not resuh in the creation of an - esperate the CRS subsystems into two N ptugging limit crtteria sur the siseve have unreviewed safer.y' question. an incrosse in T, captainment recirculation sprzy trains. been established using the methodology of the bility cf an accident previously Each train would consist of one inside Reguistory Guide 1.121. N design of b crute the fbility of a sew or recirculation spray subsystem and one sleeve )oints has been verified by testing to different kind of ocd t fratn any accident outside recirculation spray subsystem preclude leakage during normal and previously evaluated nor reduce any margins and its associated casing cooling pump. i postulated ecodent conditions, to plant safety. His change would more accurately !=plementation of lame welded sleeving will describe the CRSS as it is addressed in reduca the poesntial for primary-to+econdary The NRC sta!!has reviewed the the UPSAR and the CRSS design basis leakage dunna e postulated steem hoe break while maintaming evallable primary coolent Econsee's analysis and, bened on this document.He TS chanps er, also arm in the mot of a IDCA. By review,it appears that the three consistent with the accoent analysis standards of 50.92(c) are satisSed. bases. Yp,,$,, nerefore. the NRC stnff to .Bosisforproposed no sigraficant "I break W is reduced. These Wed determine that the amen ont request hazards cons >deration determinotion; intersecuen now are returned to a condition involves no signiScant hazards As required by 10 CFR 50.91(a) the consistent with the Design Basis. While the consideration. heenese has provided its analysis of the installation of a slem causes e reduction in IocclPublic Document Room ~ issue of no signiscant hazards flow, the reduction is for below the reduction locotion:he Alderman 1.ibrary. Special consideration which is presented bekrw: i

28064 Federal Regpater / Vol. 58. No. 90 / Wednesday, May 12. 2993 / Notices harme=Hy. operation of North Anna Description amendment aquest; of ecddents related to or dependent on Power Statkn la acardance with & De proposed would revise mntrol rod asseatbly operation will remain Ta:hnical Specification changes will not Technical Sa-dh=== (TS) L12.A. """**d b duPomed e will resch i

t. Lavolve a significant increass in the CentM Bad h Umstr 11LB.

In a smallincrease in the hty that. et any given thma, a mntrol or shutdown barA Probabihty or consequenase of an acddent Power Distribution Ilmitr. 3.12.C* will be inserted " 'tly blow fia up to 18 prevmsly realuated le the IFSAR. The inoperable Control Rods; 3.12.D. Core stepa) ns insanon ' L Nwyn. by W d divide ik four @ d cthe Containment Recirculation Spray Syswm Quadrant Power Balance:3.12.E. Rod the control and shutdown banks will mto twoinmependent rams and odd new Position Indicator fhn nals; and Table contine to mes & esfety analysis mterion ACTION statements for each Unit that 4.1-2A. Minimum Fnquency for for staady state and ANS Condition II addresses the inoperabahry of one or more EquipmentTests karSunyPower imoderens frequency) trana-ts. no allowed rectreulation sprry subrystems while the Station Units 1 and 2. These proposed

• '**""==t is not a mah-wn of cursema ACDON etmement only adesess' chanps addrons opticet with a sod important to seisty in this can es y d a malfunch is the teoperabthty of one siabeystem.Nw urgsnt failure concition (control rod A ~ ion chaa e are not increened.

Technical'w'sth the way the UTSAR anamblies immoveblo due to a failun he proposed chups add acdon cons'. stent w external to the individual control rod sutets ud um hmha to aHW addresses the Containment Rectreuletaan Sprey System. The changes do not involve e assembly dnva machamem Le., g, g g, raod:Scation to plant equtnment nor do they programming cirt:ui.but acnaining vsly, whik ahutdown or catml as eftsca the manner by whnc5 % toduty le tnppable), including o stion am M e Mthb h r operstad. Therefore, there k so Ang= to the with one control er shutdown g, g g gg gog g p P d y ah operation with shutdown or txmtrol rod th possib of new or assembhas below their insertion limits dt5srent klad of accident fraon eay acr=4aat . Addid naI % bedvtag expudt would have no e5ect on accident previously evaluated. N changes do not definition of addons and tim limits for offect the ramanse by which the 2ec1bry is pMh d a k eHect u operated or involve a charge to equipseert or certain 1.imiting Conditions for acx:ldent coneognarnas. He proposed features which affect the operational Operation where ame am cunently editorial rhauges have no o!! ct charer*ada*a of the facihty.N proposed daSned an atso added. Cartain whatsoever en plant operation. Use of a changes merely add addttiacal restricoons administrative champe are egg,ggggg with reystd to the time the inditty can be which provide constatency en cennus to Pmide a to operstod with enore than one recircaledom readability,through ca fraff= Hon of verdreHon of the trip hty of the sprey subrystem inoperabla. Nee Th defined terms, standar ization of tr 1en shutdown bub,as c Spaah chaeges ero coastehmet erstk the operat"aI mode nomenclature, and industry arparianm with the Standard arru.ns enelysis bases. deletion of obsolete tipina. rsanging of Techairal SpectScations has shown. 3 tavolve a aiyrmr.nt,eduerma la w marpa of seisty, N nroposed changes do the control rod assembly partial 2.He proposed chups MH not not a5sct tk==enarby which the luc!!aty movement surveillance teel frequency emetsthe WH y of a new or t is operated or involve a change to eqapnt from biweekly to monthlyis also different of an4 dent from any proposed-or features which affect the opers*ina. hreviously evalueted.There are no new cherecseristice of the facihry.These Basis for proposed sto sigarficarat un modes a snachsmia'na assodated Technical specia:=t6== chaga ero basards mnaimersoon decerminer="" wth phat c#oerenon for an axanda constsesot wuh the (F5AR use are As required by 10 CFR 5031(al the $ar h enes' has Provided its analysis of the (trol ve i beeis tem M no signiScanGawds perioda of operation with immovable da==n,, canaideration, which is presented but trippable control rod assemblies bebw: does not involve any modiftration in the W NRC staff ba reviewed the t parational hmus or ph design of hoensee's analysis and, based on this ,,ignmcan ineone th &p bthey review,it eppears that the thres d occurrence or potendal casequences d an the involved eyetema. re are no new standards of 50.92(c) are saus5ed. ecedent evaketed in the

• ccident procurocra aoswA due to the Therefore, the NRC staff to

[U ted Final Analysk Report!. aUowed mainte'.ance period. The determine that the request tag up to 72 hours for diaraa* and proposed thanges involve no physical involves no sign 1 Scant hasards repair maanrwad weh eledrosuc or electrical alterations to the plant or new modes of considerstion.

==haaa of the ControlRod Drin oposation.Thus, a new failure mode or LocalPuhhc Document Rooset System is accsytebla, since the priseery accident is not made possible by these %%.De Alderman Ubury.Special safety funrMan of the control rod=====Maa "*C* *dP M '*"""E W 3. results of the current soddent Collections Department. Univeseity of Virginia Garlottarvius Vhginia 22903-,,,.= [h analyses are not impacted by dtis ad naa=== period, b m. co.,,,,o, eneeuw, ch.nc. n-of=. the -rsa asawy un,yforhemmDrul w. -. tam,ne, hans leecept ser a eman is not im usupta. ,Hunton and wmiam swed d,visuae sor one beau-d N staff hee revie**d th' Riverfront East Tower.951 R. shutdown margin will be maintained.no licensee's analysis and, based on this Byrd Street. Richmond. Virginia 2321g, email dev6etion fuous the amatrol red review 11apposts that the thne NRC Picpect Dtinctor-liercert N. insertion limits anowed ter one bank dortng standards of 50.92(c) ars =a" *-A Bertow the typetr pertad we how only a udear herslore, the PSC staff to

• 5=ct a normat een pewer dharthethees.

determine that the ont request . Doctric and Power t'_ _ g, N proposed sedes socsthe bvdves nW n'-* hazards de not a V 2 'No a.d m n.s y o asimyof@ es se mn,ae,e,, Power Station Unit Not.1 and 2.5arry Perform ther ha-adad seisty a.ana'a== when localP Document Roorn ,,,,,7,"r"'T,7, ( locatfon:Swem ",y'"w'aT.Colkgo of 8 l County, nglala wmm a u. s -.hm,. l oots of_d,nent m,estu mmwe the pr-sY=andomson - Virginia 231ss. mrod _ d ma an.taes

,1 J ~ Federal Register / Vol. 58, No. 90 I Wednesday. May 12, tees I Nations 28065 Araanseyfor beenees-Marh==t W. de seven days of DC opesenan pose. h pecquesed demens de notlawoda any Maupin. . Hunton and Willissoa, ese amtmusemed. he the proposed new sende et operation or requin ary Riverfront . East Tourer 951 E. amodzaset menemas adams assegies et piryslini to the plant. Byrd Street. Richmond. 23219.

• • I8ty.

J. Deershe mesmdusser henfos e NRCPropod aractor: N. Based on the NRC staN sevisar of the sgrurxarre seducesos in a snesin arsofyrst Berkow linan==='s analysia, it thetene kmismesatamos ena emquen to amisty three atendards of 30.02 ass==mim due to these chamens because the addiuone! Washlageon Public Power Supply brefore,theNBCstaf repsonsto in8Pections have boom dh as assum System.Decket No. 56 397. Nuclear determine that the amen ont request

1. 4PauRinedesdee dpahissas j

't* Project No. 2. Beaton Consty, involves no '5 ' athazards NPalt w, of Wa=hi" Neon consideration, Piping that may be meespqRes a telhas dus 1 goicscn i Date of osmosedraent seguest: April 1 lacol Asildne J'W-==* Asami h NBCstaf has reviewed the I 1993 location: Richland Public ,355 licaname's analysis end. bened en this i Description of assandrneut sugasst: Northgate Street kN revaew it that the three i ne pmposed amentimanr would 99352 standards 50.92(c) are satis 5ed. require increased minimum levels of Attorneyforscenese:Nicholes S. diesel g====w (DG) knol storage Reynolds. Esq., Winston & Strans. DEBS g,,gase, the NRC staN reposes to determtnelhet the aman ent request I capacity. These chan are bened on L Street. N.W., Washingtan. D.C. Esse 6-involves no signi8 cant hazards j testing and sev6 sed latisms that 3sn2 comendmune. demonstrated the existing levels of DG AutCProjectDrector needereR. fuel sensege gesties were imedequate Quay ' gg%% to meet the -loss of coolant arddene Jocesion:maru aPublicLi

• 955 Washlapton Public Power Northgate Street. *WM W MCA) '"*

"****PLA** 8"P"'""""t8 system, pocket No. so.as7, oessa I '7"fo p,d'F' #M7,,,p,,,,, Pro)ect No. 2.Bestem County, Attorneyforhcessue:Nidnolm S. 3 hazards a watson determisessen Washington Reynolds,Esq.;Winesan & Seewn 1400 i As required by to CFR 50.91(a), the Dirte ofsmemhnentregnest: April 1 tmt.E WM M 200@ lir=n== bas psovided its analysis of b 1993 i issue of no signiScant hammeds Descrapese af annendesentreguest. NEProped Dmcsacneede Re l consideration.no NRC staff has ne proposed===ad==8 would agg Quay i reviewed the lioeness's analysis assinet inservice inspection segelsessames se abe 7...L 4 Pidshshed N=sen== d I the sr=ad=de d to CFR sos 2(c).no Techniemi Speci6catsens frs)su Consideretten ofImmanece of staff presents its evolustion of the accorrimans wish Gameric 1mener as 01, am sepacenyc licensee's analysis below: "NRC Position on Intergranular Stsees r 3===== Proposed No ht"

1. Dass the amusadstentinwohe e Corrosion Craddag (IGMX3 h BWR llamerds Osmaidersaan Deemrudaation, sigmfxmar hiereasein rAep. ' ' ter Auseanitic Statnises Staat Pt

• la and Opportunity' Sir a Ilsering consepanoes c(as aczadmorp - 7 addition, due proposed s'mfumed i

m ammune of DG hl stored as sne is sat would ceaset en unreisted The following amin== wue 'ously ad=w=smtise error in the TS seisand to Published as separate indivi 1 1 E Y,aI mmh"7 a reference to a table listing highAew notices.N notice content wu the j awumpuoins requin DG operouse ter aseen Pressure interinos valos leakage sanne es abom by wm published as days - m m

• asms,es pressee anonitors.

Individual notices either because tiene i 1 se d ips pe.aremenemed Basis for me p did not allow the Commission to wait ),mseds con @ sideration desarmednament for this biweekly notice c,r because the based on aczuel test results and sovesed calculetnans so lacarparete the asst As required by le(FR 50.st(al,the action ineeleed endgant cirr==d-r== information and other TS h=h="" i licosase has provided its amelysis d the by are repseted here h=ra-the Maintaining the original design - -da~ issue af me sigalScent haamde biweek}y metice lists all a=en A= mats M volvin hasards ~g w. ~,e.h.a., ar - .ae.,

t. ~.t.e - -.

accadents puestensly sgn#ismet emuness de she praestasyar For details, see the individual notics

2. Dess sin amendeset asume,n.

- r --stem eondespsevesesfy - in the FederalBagister on the day and ' "7-of a meerer abfjbrunt khed of evalueendF giend.His notice does not extend acewhatAem any pseessmay h chosess a the1st psegrunde met sans parlod of the original notice. evalueese involve a dyntae==t lacsusse la the h proposedTS cheapse the slaimum probability er - - -- ofanantident Daquemme , et al.Dechst amount er DG Sael required to be stored prior Previously evalumedbecause ta=paat-are No. 36 412 Poirer to==4a-t tantsstion. nis changs does not not assumme as the tuttissa of any analysed Statism. Unit No. 2. Shippingport, represset a change la saades of operades af soumL 7ts immeessieuresEmes peampytuomia equipament er the plant lamelf, sequhe regehamanes kr mer tumisme physetal hto One , er early dateselosof a emmessend useen DetMfesusndmentioquest: April 14, introdmas meer er element modes of IGECC and seres to the 1983 existlag sysesses. struensea, med causepsacos ofsuch a thereby Deerfption of assondment regnest-

p==

%, proposed -h does -h-ceng ashey. b amendment would nat. shoueure.aeses the passchtlay of a asw

2. Does the===d==# asses th'

' ~ 4 31 M the T=r4=4rmi or d1 Surges hand of antadset ham emy possGdbyefe asererd$nuut Adadof provteunir esehnmand. =~ ad==tpesi sayammalmstpsM ---_ _% ('TS) g, ggg, g,,g,cge m i Dese en esmedsmergee.he e insamtr stanse:** Complete vertScotton of sign #Insat seductsaar Ja e massia sfanglesyf he thanges donot essets the puestett .WgEAMJtY of the naammalisector line TS esmeos that the erwaal of a asaruriEBurnet kled of actedsat temi trip switd cbcuitry aba!! be perteined dustyt "T='=--*= imr SG esst to say --ed-d pre,tensty evuemaned hommer'C-prior to startup fress the Aret shutdown

1 28066 Federal Register / Vol. 58 No. 90 / Wzdnesday, May 12, 1993 / Notices e to MODE 3 occurring after April 6 Date ofpublication ofindividual Bnefdescnption of amendments: 1993.a notice in the EEDERALREGISTER: These amendments revise b largest Date of publicofion ofindividual Apnl 1,1993 (58 FR 17296) load to be mjected in the 18-month test notice in Federal Register: April 27 Expimoon date ofindmdualnotice: for each of the emergency dieaal 1993 (58 FR 25676) May 3,1993 generators: change the loading sequence Expimtibn date ofindividual notice: McalPublic Document Room for the 110 percent load test within the \\ May 27.1993 location: Athens Public Library, South 24-hour full load test; and add a LocalPublic Document Room Staet, Athens, Alabama 35611 mquirement to conduct a full-load location B. F. Jones Memorial Library, Nodu oflum of hnts to - rejection test once every 18 months. 663 Franklin Avenue. Aliquippa. Facihty Operadng Uceassa Date ofsssuance: April 30.1993 Ptnnsylvanla 15001. Effectne date: April 30,1993 Dunng the period since publication of C

• of Nos.r 70,56,and 43 Florida Power and Light Caespany, the last btweekly notice, the Focility Opemting License Nos.NPF-Docket Nos. 50-250 and 50-251 Turkey Communion has issued the followmg 41 NPF 51 and NPF-74:Re P: int Plant Units 3 and 4,Dede County, amendments.no Commission has amendments revised the Technical Florida determined for each of these SpeciScations.

Date of amendment mquest: April 13 amendments that the appliation Date of frutial notice in Federal 1993 complies with the standards and Regisser: November 13,1991 (56 FR Desenprion of amendment request: requirements of the Atomic Energy Ad 57689) and March 25,1993 (58 FR The proposed amendment would revise of 1954, as amended (the Act), and the 18217). ths Technical Specifications (TS) 3.3.3.2 Comminaion's rules and agulations. The Commission's related evaluation nlating to the Moveable Incore Detector The Commission has made appropriate of 6 amendments is contained in a System to reduce the minimum number findings as required by the Act and the Safety Evaluation dated April 30,1993. i of operable detector thimbles from 38 to Commission's rules and regulations in No signiScant hazards consideration i 25 and to incmue the minimum 10 CFR Chapter 1, which are set forth in comments received: No. number of detector thimbles per the lianse amendment. healPublic Document Room quadrant from two to thne whenever Notice of Consideration oflasuance of location: Pnoenix Public Library.12 the number of operable thimbles is less Amendment to Facility Operating East McDowell Road, Phoenix, Arizona i then 38.To compensate for this License, Proposed No Sigmficant 85004 reduction in b number of detector Hazards Consideration Determination. t ~ thimbles.TS 3/4.2.2, Heat Flux Hot and Opportunity for A Hearing in Carolina Power at Light Company, Docket No. Stat. H. B. M== Channel Factor - F, (z) and TS 3/4.2.3, connection with these ani== was Steam Electric Plant. Unit No. 2, Nuclear Enthal y Rise Hot Channel published in the Federal Register as Factor - F(delta H. and their associated indicated. Darnagton County, Sath Carouna i bcses would also be revised to increase Unless otherwise indicated,the Date of applicationfor amendment: thzir measurement uncertainty factors. Commission has determined that these November 27,1991, The proposed amendment would be amendments satisfy the criteria for Brief desenprion of amendment:The applicable to Turkey Point Unit 3 only categorical exclusion in acx:ordenm amendment avises the TS to allow one for the remaining period of its Cycle 13, with to CFR 51.22. Therefore, pursuant safety injection accumulator to be Date of publication ofindividual to 10 CFR 51.22(b), no environmental inoperable due to improper pressure, notice in Federal Register: Apnl 27, impact statement or environmental borated water volume, or boron 1993 (58 FR 25678) assessment need be prepared for these concentration for the same amount of Expimdon date ofindividualnotice: amendments. If the Comminaion has time curantly allowed for inoperability May 27, m 3 pnpared an environmental assesament due to isolation. Local Puolic Document Room under the special circumstances Date ofissucnce: April 19,1993 location: Florida International provision in 10 CFR 51.12(b) and has Effective date: April 19,1993 j University, University Park, Miami, made a determination based on that Amendment No.146 Florida 33199 assessment,it is so indicated. Focility Operating license No. DPR-For further details with respect to the

23. Amendment revises the Technical l

Tennessee Valley Authority, Docket li P cations Specin tim " 8ee e Nos. 50-259,50 200 and 50-394, Browns ndm Fern Nuclear Plant Units 1,2, and 3, the Commission's related letter Safety Register: September 30,1992_(57 FR Lirwtone County, Maha Evaluation and/or Environmental 45078) Date of amendment squest: March Assessment as indicated. All of these The Commission's related evaluation 18.1993 (TS 331) items are available for public inspection of the amendment is contained in a Enef description of amendments:The at the Commission's Public Document Safety Evaluation dated April 19,1993. Proposed changes conest of Room, the Gelman Building,2120 L No significant hazards consideration administrative changes to the Technical Street, NW., Washington, DC 20555, and commanta received:No i Specifications for & Browns Ferry at the local public document rooms for LocalPublic Document Room i Nuclear Plant (BFN), Units 1,2 and 3. b particular facilities involved. location:Hartsville Memorial Library, Home and Fifth Avenues, Hartsville, The changps include deletion of Arizona Puhuc Service y, et al Unit 2 Cycle 6 tien various Docket Nos. STN 50-52a. 2 529, ' South Carolina 29525 requirements apphcable only to BFN administretive Mons, conect and STN 50 s30,Palo Verde Nuclear Duka Power Casapany, Docket Noa. 50-di andes between the Technical Generating Station Units 1,2, and 3, 3ss and 50-370 McGuire Nuclear Speci cation Bases and the BFN Final MaricoPa County, Arisman Station Units 1 and 2, Mecklenburg 7 Safety Analysis Report, and clariScation Date of applicationfor amendments: County, Nonh CaroHas of certain requirements to ensure August 21,1991, as supplemented Dore of application foramendments: consistency in application. February 19,1992 and January 25,1993. October 23,1990, as supplemented July r e 4 i

j Federal Regreter / Vol. 58. No. 90 / Wednesday. May 12, 1993 / Notices 28067 18.1931. March 3.1992. and January The Commisseon's related evaluation The December 31.3ss2. sad February 21.1993 of the amendment is contained in a 17,1993, letters pseraded additional i Brief description of amendments:b Safety Evaluation dated April 16.1993. information in rt of the amendments revise Technical No significant hazards consideration amendments. & did not ch= nee i SpeciS :ation 3/4.7.5. *' Standby Nuclaar comments received: No. the NRC staffs proposed one significant Service Water Pond." to require an localPabffe Document 11oom hazards considendon d=ama== nation. average water temperature of less than locatieTomlinsonLt. . Arkansas b Commtarion's related evaluation or equal to 62 degrees F at an elevation Tech University. Russell Arkansas of the amendments is ruiandnad in a of 722 feet. 72801 5 3 _ ' Seisty Evaluation dated Apen 30,1993. Da sg Entergy Onae=H=. Inc.,n.r1..e gnaM ; No si Mnennt hasards n===Lamentian f endment Nos.:136 and 118 54313 aM364,h Nadeer msnmets mcMwd: No Facdtry operuang ueensesos.NPF-Oms, Unit Nos. I and 2. Pope County. LeoelPubheDocumentAeosi 9 and NPF-17: Am=~h s revised the Arkansas lomDN APPung County Pubhc t Technical Specifications. Date ofcmendment mquest. 301 Qty hah Dnw. My. Date ofburial soccein Federal November 10.1992 D UU3 Regssser: Decembar as.1990 (55 FR Bn'efdesenption of amendraents.% Nebraska Public Power Dietract. Docket 53069) The July 18.1991. March 3 amendments revised the description of No. 50 238. Cooper Nudear 54ation. 1992, and January 21.1993, suhmirrals the Plant Safety Committee (PSC) Nesnaka Commty, Nebraska provided corrections and clarifying compos!! ion. revised the PSC infonnation which were within the re sikdit== and established a Date of amendment request: scope of the initialnotim and did not tec cal review and control process for S*Ptember 9.1992 cha ne the initial no ='-n%t hazards the review af most pA Bnefdescripbon of amendment:b consideration de'armi=h Date ofissuance: April 21,1993 PTCPosed changes modify the Cooper b Commission's related ermhtarina Efectrw date:30 days from the date Nuclear Station Technical of the amendzoents is erme=+nad in a ofissuance Specifications making a number of Safety Evaluation dated April 5.1983. Areeadmont Nos.:165 and ig7 administrative to clarify and No significant hazards consideration Facility Op--"=g License Nos. DPR-improve consistency, and correct a comments im,M No 51 andNPF4. Amen mmat= rarised the variety of minor ermrs. o LocalPn6 des Documsset Roose Technical SpeciSations. Date of1sseence: April 23,1993 locanon: Atkins IJbrary, University of Date afleetsaf moensein Federal Effecetw thier April 23.1993 North Corokaa. Charlotte (UNCC Register:Masch 3.19S3 (se FR SA330) A._ '.r J No.:182 Station). North Camhna 2a223 h ra===ta*='s usieted evahmetkun of Facuity Operottag Efernse No. DPR-the amaad - - 4 is contasood in a Safety 46. Ameodment revised the Technical Entergy Opwadons, A W No. 50-348. Ark.ansas Nude,ar One. Unit Evaluation dated April 21.1983. SpectScatioca. No. 2. Pope County, Arkenama No MMr an' h*==Ma ~Wrm Dde yWde e FM comments recalved: No. Registen December 23,1992 (37 FR Date ofopplication for amendment: LocalPublic Document floom su1s} June 27.1991, as supplemented by letter locxrtion:Tomlinson Library. A 4=n=== b r a=='== ton's related evaluation dated April 29,1992. Tech University. Russellvme; Arb"" of the amendrnent is contained in a Bnef desenption of amendment:b 72801 amendment revised the Technical Safety Evaluation dated April 23.1993. Specifications (TSs) for eneuminment 7.. No sirdMeant hazards consideration .,__, m Q o g e g g f**'* 8C""$ Ausborsty elGeor5 a.Cky e"(Deken. IocalPublic Document Rum i fo d ices t ab=e 3.8-1 adding Gwgia. Decist Nos. 84321 mai so. Madh M Wary. H8 new surveillance uarement secuan Sea,Edwin L Hatch NedearPlant. 15th Street. Auburn. Nebraska 68305. numbered 4.8.2.5.a. or the 480V etr Units 1 and 2. Appites Ceesty. Geesgla NarGn A6asticEmergyServios frame breakers, ren"=ba-ing sxisting Date ofappffootion for ennendensner C n. . Decket No. 56 443. Surveillance Requirement 4 a.2.5.a.2 as February 30.1991, as suppheested Seabrook Station. Unk No. l. 4.B.2.5.a.3. and rewording SugM1.n= February 4 and Doomsbur71.1982.and * -aw -M County, New Hasupshire Requirement 4.s.2.5.h to darify its February 17.1983 ~- intent Brie descriptamof Date qfamendmentieguest: November 3 1992 as tu plemented by Date ofissuance: April 16.1993 Effecrae date:30 days fann the date. amen ents incorper,1aseellosenble eedt. of-service times far ear,.manmand letter dated h*ebruary 26,1993~ ofissuance repair with extended f"ar+1==1 est M.< * " * " 9# t Amendment No.:146 Tacility Operatify Licanse Na NPF4. intervals for Emergency Coes Combeg, amedmont 6WM 3 C*UO I* Amendment nvised the Tarbr=1 Isolation AmustionInstrena"tation. Emmetar Protectina System, control rod. eenior necto parahh A j Speci$ cations. Date o/initialmotics in Federal blocks. Reactor Core Isolation Cooling, ' "9*I""*"1g N and selected instrumentation. - - I' Register: August 21.1991(56 TR Date Jssecace AprG 30.1993 ' '- removes th'ee-t that the 415631.b additionalinformation' Eg dete Noletetthen60'dep, - Oper=Haas e an E contained in the supplammatalletter frotn ths date of' amu==n= hcense, houww. dated April 29.1992. withdmw a Aenendammar Nos.:145 and125 : Manager must either or have held portion of the original request and thus. Facility OpemttagMcumse Nes2PR. an SRO Ikanseh ahe Seabrook Statima i is within the scope of the initial notice 57 and NPF-5. A===4=aaaa seelsed the prior to -7 --t to the position. and did not affect the staff's Technical 4=rmentkma., Date s[seenaca: April 26.1993 no striM=* h-ds ma Dets a(Jmcafstatice is Federal Effectin4 fate: April 26,1993 ..o determination. Register: April 15.1992 (57 FIL13131) AmendsiestNo.:20 l 1:

28068 Federal Register / Vol. 58, No. 90 / Wednesday, May 12, 1993 / Notices facility Operating Ucense No. NPF-Effective date: April 20,1993 Power Authority of The State of New B6. Amendment rmsed the Technical Amendment Nos. 60 and'25 York. Docket No. 50-286, Indian Point SpeciScations. Facility Operating Ucense Nos. NPF. Nuclear Generating Unit No. 3 Date ofinitial notice in Federal 39 and NPF-85. N amendments Westches*::r County, New York Re5 sMn December 23,1992 (57 FR revised the Technical Specifications. Date of application for omendment: i 61119). The licensee,s letter dated Date ofinitial notice in Federal Jan 19,1993 February 26,1993, provides additional Registen February 17,1993 (58 FR Bnr desenption of amendment:b supporting information; the informstion 8777) amen ont revised the Technical does not change the initial proposed n b Cohn's related evaluation S eciScations (TS) to extend the P signi6 cant hazards consideration of the amendments is contained in a containment hydrogen recombiner l$ ion's related evaluation Safety Evaluation dated April 20,1993. refueling surveillance test interval of the amendment is contained in a No significant hazards consideration (8Peded in TS Section 4.5.7.a.2) to m comments received: No acx:ommodate operation on a 24-month Safety Evaluation dated Apnl 26,1993 cycle. This change followed the No significant hazards consideration localPublic Document Room comments meeived: No. location: Pottstown Public Ubrary,500 guidance provided in Generic letter 9 t-Local Public Document Room High Street. Pottstown, Pennsylvania 04,

• Changes in Technical Specification l

e to Acanmodate S Q co location:Exeter Public Ubrary,47 Front 19464. y Street, Exeter, New Hampshiro 03833. Power Authority of N State of New Date ofissuance: Ap'ril 16,1993 Philadelphia Electric Company, Docket York Docket No. 50-286, Indian Point Effective date:Apnl 16,1993 Nos. 50-352 and 50-353, Umerick Nuclear Generating Unit No. 3, Amendment No.:130 Generating Station Unita 1 and 2 Westchester County, New York FaciLfy Operating Ucense No. DPR-g,g, of,pp ;,,g3,, jo,,,,,g,,,g; $t ona Mntgomery Canty, Pennsylvania y Date of application for amendments: October 9.1992 Date ofinitial nouce in Federnl April 3,1992, as supplemented January Bnef description of amendment:The Registen February 17,1993 (58 FR

12. 21 and 22,1993 amendment revised the Technical 8779)

Bnefdescnption amendments:The SpectScations (TSs) to incorporate the N Commission's related evaluation amenciments revios e Technical following changes: of the amendment is contained in a Speci$ cations (TS) Surveillance (1) The containment fan cooler unit Safety Evaluation dated April 16,1993. Requirements of the Stand-by Uquid filtrution system testing frequency, ' No signi8 cant hazards consideration Control System to substitute the (speci$ed in TS Section 4.5.A.4) was comments received: No Pertinent requirements from the draft changed to acx:ommodate operation on a localPublic Document Room improved NRC Stsndard TS provided in 24-month cycle. location: White Plains Public Ubrary, 100 Martine Avenue, White Plains. New NUREG1433. (2) b central control room filtration York 10610. system testing frequency (specified in Eff do e ri 1 93 Amer iment Nos. 61 an'd 26 TS Section 4.5.A.5) was changed to Public Service Electric si Gas Company, facinry Operating Ucense Nos. NPF, accommodate operation on a 24-month Docket No. 50-311. Salem Nuclear Generating Station, Unit No. 2, Salem CYCI'- 39 and NPF-85. b amendments (3) m containment vent isolat2on County, New Jereey revised the Technical SpeciScations. vain mechanical stop wiScadon Date of application for amendment: Date ofinitial notice sn Federng Registen February 12.1993 (58 FR frequency (specified in TS Section April 24.1992, and supplemented by 4.13.A) was changed to accommodate letter dated February 2.1993 12265) The Commission's related evaluation Operation on a 24 tnanth cycle. Brief desenption of amendment:The of the amendments is contained in a These changes followed the guidance amendment reduces the reguired provided in :.n ric Letter 91-04, minimum safety injection now rates, r Safety Evaluation dated April 20,1993. No afgniScant hazards consideration "Chan in Technical SpeciScation increases the maximum allowed comments received: No Surv Intervals to Acx:ommodate emeqpency core cooling system (ECCS) local Public Document Room a 24-Month Puel Cycle," as apphcable-poucp runout flow rates modifies the location: Pottstown Public Ubrary,500 Date ofissuance: April 21,1993 acceptance criteria for ECCS pump High Street, Pottstown, Penneylvania Effectin date-April 21.1993 performance, and updates the Baees 19464. Amendment No.:131 section. Phileds!pkla Electric Cosapeny, Docket facil!!y Operudng Ucense No. DPR. Date ofissuance: April 21.1993 64: Amendment revised the Technical Effectrve date: Apnl 21,1993 Nos. 50 352 and 56 353, I NO UmerickGenerating Station. Units 1 Speci$ cations. Ucense No. DPR-and 2. Montgesnery County, Date efinitial notice in FM 75:his amendment revised the Pennsylvania Register December 23,1992 (57 FR MM S Scahs. 01120I Date of dalnouce in Tederal Date of application for amendments: De CommMon's related evaluation Register: September 2,1992 (57 FR Janu 8,1998 Bd descripdon ofsmendments:De of the amendment is contained in a 40219) cmen ont reduces the frequency of Safety Evaluation dated April 21,1993-he Commission's related evalustion Testing of cartain fire detection No significant hazards consideration of the amendment is contained in a instrumentation as per the requirements comments received: No Safety Evaluation dated April 21.1993. recommended in the 1990 Edition of the local Public Document Room No signiacant hazards consideration N:tional Fire Protection Asmodation location: White Plains Public U comments received: No Standards. 100 Martino Avenue, White Plains, ' loenf Public Document Roorn Date ofissuance: April 20.1993 York 10610. location: Salem Free Public Library,112

[. Federal Register / Vol. 58. No. 90 / Wednesday, May 12, 1993 / Notices 28069 West Broadway. Salem. New Jersey Amendment Nos.:211 - Unit 2; 168 - Bnef description of amendment:The DB079 Unit 3 amendment revised Technical Rochester Gas and Electric Facslity Opemting Ucense Nos. DPR-Specification 6.3.1 for tem rary relief 52 and DPR-68; Amendments revise the to permit a speciSc indivi ual to Corporation, Docket No. 50-244. R. E. TS. assume the active duties of Manager, Ginna Nuclear Power Plant, Wayne Defe ofinitialnotice in Federal Perry Operations Section, within the County, New York Register: October 28.1992 (57 FR Perry Nuclear Power Plant Department, Date of application for amendment: 48828) without currently holding a Senior October 15,1990, as supplemented he Commission's related evaluation Raactor Operator (SRO) license for the March 8.1991. November 30.1992 and of the amendment is contained in a Perry Nuclear Power Plant. Unit 1. The Apnl 5,1993. (Partiall Safety Evaluation dated April 22,1993, temporary relief has been approved for Bnef desenptson of amendment: No ahm' Ban' haurds consideration..alnnttedperiod of time during which Revised Technical SpeciScation (TS) for comments received: None . the SRO ucense qualification leahge rate testing requirements on LocalPublic Document Room ' requirement will be met. The individual certam contatament isolation valves location: Athens Public Ubrary. South wiu be included in the next scheduled (CIVs) found in TS Table 3.6-1. These Street. Athens. Alabama 35611 changes am conststent with an a proved Senior Reactor Operator / Reactor InserviceTestmg(IST) Program or Tennessee Valley Authority, Docket Operator Training and examination Pumps and Valves,1990-1999 Dird 10- Nos. 50-327 and 50-328, Sequoyah Pmgram currently scheduled to begin in Year interval. He remainder of the Nuclear Plant Units 1 and 2, Hamilton June 1994 and will sit for the next SRO amendment request will be issued as a hy, Tesw license evamination scheduled for Date of application or amendments: August 1995. separate document at a latet date. March 27,1992; supp(emented May 11 Date ofissuance: April 16,1993 Date ofissuance: A ril 20,1993 Effective date: Apn 20,1993 May 28. September 8. and October 8. Effective date: April 16,1993 Amendment No.:52 1992; February 18 and April 1,1993 (TS A83endment No. 47 Facilsty Opemting Ucense No. DPR-92-01). Facility Operating Ucense No. NPF. 18: Amendment revised the Technical Brief description of amendments:ne

58. This amendment revised the Specifications of facility Operating amendmentsincorporate the technical Technical Specificationa.

Umnae DPR 18. speciScation changes that are naassary Date ofinitialnoticein Federal ~ Date ofinitialnoticein Federal for erpamion of the spent fuel pool Register: March 31,1993 (,58 FR 13511) Register: Demmber 12,1990 (55 FR storege capacity to 2091 fuel assemblies' he Com=Mn's related evaluation 51186) and addition of a fuel rack storage of the amendment is contained in a The March 8,1991, November 30, module to be located in the cask loading Safety Evaluation dated April 16,1993. 1992, and April 5,1993, letters provided area of the cask pit to accommodate no No significant hazards consideration clarifying information that did not more than 225 additional fuel commets remive No change the initial proposed no assemblies. The new racks incmase the localPublic Document Room significant hazards consideration total spent fuel storage capacity to 2316 determination. fuel bundles and evtand the projected location: Perry Public Ubrary 3753 The Commission's related evaluation storage capacity into the year 2005 or Main Street, Peny* Ohio 44081. of the amendment is contained in a 2006. Union Electric Company Docket No. Safety Evaluation dated April 20,1993. Date ofissuance: April 28,1993 ~ 50 483, Callaway Plant Unit 1 No significant hazards consideration Effectwe date: April 28,1993 Callaway County, Missouri comments received: No Amendment Nos.: Unit 1 - 167: Unit localPublic Document Boom 2 - 157 Da hfonli h fwanw h e location: Rochestat Public Ubrary,115 Tacilsty Operating Ucense Nos.DPR-Masch 5,1%3 South Avenue, Rochester, New York 77 and DPR-79: Amendments avise the BriefdescriPtion of amendment:ne 14610. technical specl$ cations.. amendment revised Technical Tennessee Vaucy Ahty,W &fe ofirutialnohcein Fedem! Specification Surveillan= Requirement Nos. 50-280 and 50-296, Browns Ferry Engister: June 24,1992 (57 FR 28217) 4.7.8.d to allow a one time schedule Nuclear Plant, Units 2 and 3 Limestme no Commissin's mlated walunde extension of b awhher transient event Canty, Alabazna of the amendments is contained in a inspection. Safety Evaluation dated April 26.1993. Ikste ofissuanos: April 27,1993 Date of application foramendmentsr No =f anMmnt harmada consideration dyfactim dote: April 27,1993 August 25.1992, as supplemented comments rec =fvod: None A_m.nd=*=t No.r 79 Dommber 23,1992 (TS 327), localPublic Document Ram Brief desenprion of amendments:The location: Chattanooga-Hamilton Cbunty f ejfj,7op,,,efagye,,,, yo, ppy. 30: Amendment revised the Technical proposed changes are administrative Ubrary,1101 Broad Street. Chattanooga. revisions of the Browns Ferry Nuclear Tennessee 37402 3p,c.gge gm, Dde ofirddalnoM Federal fc ""k3[ %e Cleveland Elodric Disminating Regisesr: March 25,1993 (58 FR 16247) modify the indication for the low mnp==y, Catedoe W Company, h Comm6=Im's mleted waluade range dryweH presum cator and U, . Ught Casapany, Obie Man = of the amendment is contained in a recorder, and correct labeline of various Campany, M,. mala Power Safety Eraluation dated April 27,1993. recorders. bee changesMass some Company. Toisde Maa= Company. No significant hasards consideration issues identified by the control room Nuc *** comments rocaind: No. design review at the Browns Ferry Power Mant, Unh No.1,Laks County, localPublicDocument Ram Nuclear Plant. N location:Callaway County Public Date ofiesuance:dpsil 32.,1993 Dats ofepphcotsonforamendmerrt Ubrary,710 CouM Strost.Pulton, Effective date: April 22,.1993 February 26.199.3 . Miseend 65251c - -, - - - ~ - - -

i 28070 Federal Register / Vol. 58 No. 90 / Wednesday, May 12, 1993 / Notices Virginia Electric and Power Cornpany. 1991, and in part an application dated For exigent circumstances, the Docket Nos. 50 280 and 50 281, Surry }une 28,1991. Commission has either issued a Federal Power Station, Unit Nos. I and 2, Surry Enef description of amendment:The Register notice providing opportunity County, Virginia. amendment revised Technical for public comment or has used local S eci5 cation (TS) Section 6.13. "High media to provide notice to the public in P Date of application for amendments: Radiation Area," so that the the area surroundmg a licensn's fadhty October 26,1992 Bnef desenption of amendments: 8Pecification more closely resembles the of the licensee's application and of the These amendments, which are in partial Westinghouse Standard Technical Commission's proposed determmation response to your a phcation, wilj Specifications (NUREG-0452). In of no significant hazards consideration. Increase the limit or the intermediata - addition. TS 6.4 ** Training " and TS The Commission has provided a ti.5," Review and Audit." wers revised rea.sonable opportunity for the public to range high flux reactor trip setpoint and establish an allowed outage time for the to acx:ount for tscent organization comment, using its best efforts to make source range mstruments when the changes at Kewaunee. Finally TS 8. available to the public means of " Administrative Controls." was revised communication for the public to reactor power is below a specif;ed level. due to administrative and format respond quickly, and in the case of Dcte ofissuance:A ril 21,1993 Effective date: Apn 21, changes. telepbme comments, the comments have been recorded or transenbed as 1993 Araendment Nos. 176,175 Date ofissuance: Apnl 21,1993 ropnate and the licensee has been focshty Operating License Nos. DPR. Effecon date: Apul 21,1993

• Pfarmed of the public comments.

in 32 and DPR.37: Atnendments revised Amendment No.: 99 In drcumstanen where failure to act the Techmcal Specifications. TOC'hty Operoting Lseense No. DPR-Dofe ofinitial notice in Federal

43. Amendment revised the Technical in a timely way would have resulted, for S ecifications.

example,in derating or shutdown of a RegisterE December 23,1992 (57 FR P 61122) Date of mitial notice in Federal nuclear Power plant or in prevention of either resumption of operation or of The Commission's related evaluation Registen October 28,1992 (57 FR IL u8 Po e the h[m,m, ission may of the amendment is contained in a 48832) d Safety Evaluation dated Apn! 21.1993. The Commission's related evaluation have h'ad an No significant hazards consideration of the amendment is contained in a opportunity to provide for public comments received: No Safety Evaluation dated April 21.1993. commant on its no significant hazards local Pubhc Document Room No significant hazards consideration consideration determination in such locorson: Swem Library, College of mmmentassoalved: No. case,the license amendment has been William and Mary Williamsburg, LocalPublic Document Room issued without opportunity for Virginia 23185 location: University of Wiamnein comment. If there has been some time mmen leu an 0 Virginia Electric and Power Company, G Bay, W na n 54 1-days, the Commission may provide an Docket Nos. 50 280 and 50-281, Surry Power Station. Unit Nos.1 and 2. Surry Notice ofIsenanes of Amendments to Opportunity for public comment. If County, Virginia. Facility Operating Ucenses and Flaal comments have been requested,it is so Determination of No SigniScant stated. In either event, the State has Dore of applicors.on for amendments: Haaards Consideration and been consuhed by telephone whenever December 11,1993 Opportunity for a Hearing (Exigent, ' Pouible. Bnef desenption of amendments: Pub M m m w g Under its regulations, the Commission These amendments eliminste the reactor Circumstances) may laeue and make an amendment coolant system loop stop valves immediately effective, notwithstanding interlocks operabihty requirement. . Dunng the 'od since publication of the pendency before it of a request for Date ofissuance: April 72.1993 the last bi y notics, th* a hearing from any person,in edwarece Effective date: Apnl 22. Commission has issued the following of the holding and completion of any 1993 Amendment Nos.177,176 amendments.The Commission has required hearing, where it has Focility Operottng Ucense Nos. DPR. determined for sech of these determined that no sigmficant hazards 32 and DPR-37: Amendments revised amendments that the application for the consideration is involved. the Technical Specifications, amendmant complies with the no Commission has applied the Date ofinitJat notice in Federal standards and requirements of the standards of 10 CFR 50.92 and has made Register: January 21.1993 (58 FR 5436). Atomic Energy Act of 1954, as amended a final determination that the The Commission's related evaluatico (the Act), and the Commisman's rules amendsnect involves no significant of the amendment is contained in a and regulations.Re Commission has hazards consideration.The basis for this Safety Evaluation dated April 22.1993. made appropriate findings as required determination is contained in the No significant hazards consideratice by the Act and the Panmission's rules d===ats related to this action. comments received: No and regulations in to CFR Chapter 1. Accordingly. the amendments have LocalPubhc Document Room which are set forth in the hmnme been issood and made eflective as location: Swem Ubrary. College of amendment. William and Mary. Willismaburg. Because of exigent or m -,wf indicated. Unless otherwise indicated, the Virginia 23185 cir-*=== associated with the dets Co==wtan has determined that these the amendment was needed, there was amendmaats satisfy the critaris for Wisconsin Corporah not time for the Commission to publish, categorical exclusion in accordance Dockst No. 50-306. Kewassee for public comment before knanm.Its with 10 CFR 51.22.Therefce, prouent NuclearPower Plant.Kewsmos Couady, usual 3Nisy Notice of Ennaf doration of to 10 CFR 51.22(b), no swironmental Wisconsin issuanos of Amendment. Proposed No imped statement or environmeetal Date of oppbcocon for amendment. Significant Hazards Consideration aueesment need be prepared for these August 31.19t2.which su in Determination, and Opportunity for a amendments.lf the Commission has toto an application dated Mr 20 Hearing. prepared en environmental meessment

1 l I'ederal Register / Vol. 58. No. 90 / Wednesday. May M.1993 / Notices 28071 under the special cir"**"= petitioner's interest. W petition should be da!!vered to the Commt== ion's Public provis.on in 10 CFR 51.12(b) and has also identify the spectSc aspect (s) of the Document Room, the Gelman Building. mode e determination beood on that sub)ed mattar of the proceeding as to 2120 L Street. NW.. WasMn on.DC assessment. it is so indkated. which petitioner wishes to intervene. 20555. by the above date. For further details with respect to the Any person who has Od a petition for tions are Ed d the last 10 action see (1) the appHr=Han br leave to intervene or who has been ys of the notice it is requested smendment. (2) the===mAmet to admitted as a party may amend the that the petitioner pmenytly so inform Facility Operating ham. and (3) the tion without isquesting leave of the the Commission by a tou. free telephone enm+w's related htier. Safety up to 15 days prior to the Brst call to Westem Union at 1-(800) 246-Evaluation and/or Environmental prehearing confursoce scheduled in the 5100 (in Missouri 1-(800) 342-4700). Assessment, as !adMad All of these proceeding, but sucfi an am= dad h Western Union operator should be items are available tw pub!!c inspection petition must the =padMty gfvon Da Ident1Bcation Number et h e-mta= ion'amnnraimane s . _,ts abe m - -f N1923 the following message Room, the Gelman mum., 2130 L Not letar than 15 days to the first addressed to (Profoct Director)- Street. NW., Wa=Ma==n. DC 20555, and preheezing mniersnoe uled in the petitioner's name and telephone at the local public d-m-t room for picaeding, a petitioner shall h a. number, date tion was mailed. plant theparticular facility involved. suppl =mant to the on to intervene name, and on date and page The emission is alsa oSering an which must inc! a list of the number of is Federal Register notics. r oppottunity for a hearing with respect to motections which are ttobe A copy of the tion abould ciso be the issuance of the amendment. By June litigated in the matter. contention sent to the ce of the General 11.1993, the limnsee may b a request must consist of a specinc statement of Counsel U.S. Nuclear Regulatory for a hearing with respect to issuance of the issue oflaw or fed to be rained or Commteaton. Washington DC 20555, the amendment to the sub)mct facility controverted. In addition, the petitioner and to the attomey for the licensee. operating license and any person whoes shall provide a brief explanation of the Nautimely Elings of petitions for interest may be affeded by this bases of the contention and a concies leave to intervene, amended petitions. proceeding and who wishes to o'a'ammt of the aMayd facts or expert scpplemental petitions and/or requests participate as a party in the proceeding opinion whidi support the mnr=ntion for a hearing will not be entertained must ale a written request for a hnering and on which the petitionar intends to absent a determination by the and a petition for leave to intervene. rely in proving the contention esi e . r==i-ion. the presiding ofBose or tb th Requests for a hearing and a petition for hearing. N petitioner must also "Mamic Safetfand Li Board that lesve to intervene shall be nJed in provide refersoces to those the podtion and/or d be accordance with the -mladon's sources and d~'rmants of w the granted based u a _ hane of the e ~ fadors =(a=i_M _ _ in to CFR " Rules of Predics for D unanHe petitioner is aware and on which the 2.714(a) 1)(1}-{v) and 2.714(d). Licensing Promedings"* in 10 CHL Part petitioner intends to rely to estahEsh

2. Interested persons should consult a those lects or opinion. PeriH=ar Deted at Racivine. Maryland, this es day current copy of 10 CPR 2.714 which is must provide t information to of May 1993.

Fw es Nuclear Regulatory Pa==

• avellahlast the --ww's Public show that a genuine disputs axists with e

l Doc===e Room. the Gelman Building, the applicant on a materialissue ofleer McM E**. l 2120 L Street.NW Washington,DC or fact. Contentions shall be limMed to menor,msJon asactorProNs.W 20555 and et tb local public d===t matters within tb scope of the WN C#3c* of %.ar macrerRep1*a room for the particular facility involved. amendmant undar consideration. b (Dac. 93-11061 FUed 5-1183: 8 45 em] If s request for a hearing or petation for contantion must be one which,if ea4essoaosruneew leave to intervene is Ed by the above proven,would entitle the tiener to date, the -m*w or an Atomic relief. A petitioner who to Eis such e Safety and i_hdag Board, designated a suppiamant which saHanan these by the -mwian or by the Chairman requirements with respect to et leastone e con -ntian will not be paral'+=d W., of the Atomic Safety and ik=adag e I Board Panel, will rule on the request participate as a party. and/or petition; and the Secretary or the Those permitted tointervene becocne designated Atomic Safety and f handag parties to the praraa d* subled to ey Board will issue a notics of a hearing or hitaHons in the order granting larve to an appropriste order. interveen, and have the opportunity to As required by 10 CFR 1.714.a p=6= fully in the condud of the tion for leave tointervene aball set wAJw the a===*=6tw to with particularity the laternet of present evidenos'and crSe awamina the petitioner in the prar==Aw and witnesses. Since the nemiasion has e how that internet beametad the mada a fLnal dotar=w+h that the results of the ian b Peti amand==nt involves no =hiar=

• ___ny expfain the reasons hasards consideration,if s' hosting is should =.a f

why inkarv= nth should be permitted it will notetsy the, with particular rederemos to the vecess of the==.=d- =t. Any following lectors: (11the nature of the bid would take place while the a . mant is in e5ect. Pedtioner's right under the Act to be unade a party to the prar-adw- (2) the A request for a hearing or a petition nature and extent of the lar neeve to intervene must be Elod with property, MaMal er interest in the Secretary of the -=la-h U.S. e the pean==% and (3) the possible Nuriaar Regulatory em-ww___ e&c of any order which may be WaA N*aa DC 20555. Ansatican entered in the proceeding on the ru=r1;g sad Services Branch, or sney i

CONGRZSSIONAL CORRZ8PONDENCE SYSTEX DOCUM.ENT PREPARATION CHECKLIST This checklist is be submitted with each document (or group.of Gs/As) sent for. ing into the CCS. q e 1. BRIEF DESCRIPTION OF DOCUMENT (S) U //d '- ~ x s 2. TYPE OF-DOCUMENT" [ Correspondenser , Rearingse (Qar/As) 3. DOCUXENT CONTROL 8ensitive (NRC Only) Non-sensitive / 4. CCNGRZSSIONAL COMMITTEE and SUBCCXXITTEE8 (if applicabis) Congressional Committee Subcommittaa i 5. SUBJECT CODES (a) (b) (c) 6. SOURCE OF DOCUMENTS (a) 5520 (document name (b) Scan. (c) At'Eachments (d) Rakey (a) Other 7. SYSTEM LOG DATER (a) /, ~ llI t' A Data CCA sent document to CCS (b) Data CCS receivessdocumsat (c) Dats returned to CCA for additional information (d) Data resubmitted by-OCA to CC* ~ (a) Data entered into CC8 by ~ (f) Date OCA notified that document is in CCS 8. COMMENTE 140050}}