ML20036C474

Forwards Biweekly Notice of Applications & Amends to OLs Involving Nshcs,Published in Fr on 930428.Correction to Biweekly Notice Published in Fr on 930506 Also Encl

ML20036C474
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, HOUSE OF REP., ENVIRONMENT & PUBLIC WORKS
References
CCS, NUDOCS 9306180122
Download: ML20036C474 (30)

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UNITED STATES f,.J.. '"

j NUCLEAR REGULATORY. COMMISSION-t WASHINGTON. D C. 20666-0001 i

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May 20, 1993 The Honorable Joseph Lieberman, Chairman Subcommittee on Clean Air and Nuclear Regulation Committee on Environment and Public Works United States Senate Washington, D. C.

20510

Dear Mr. Chairman:

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

hazards consideration, notwithstanding the pendency before the Commission of a request for a hearing.

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

Enclosed for your information is a copy of the Commission's Biweekly Notice of Applications and Amendments to Operating Licenses. involving no significant hazards considerations, which was published in the Federal Reaister on April 28,1993 (57 FR 25851).

Also, a correction to the Biweekly Notice was published in the Federal Reaister on May 6, 1993 (57 FR-26987).-

Sincerely, ThomasE.briey, 1 rector I

Office of Nuclear _ Reactor Regulation-

Enclosure:

Federal _R_eaister.

Notice cc: Senator Alan K. Simpson 5.

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION g!

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May 20, 1993 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

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

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

Enclosed for your information is a copy of the Commission's Biweekly Notice of Applications and Amendments to Operating Licenses involving no significant hazard.; considerations, which was published in the Federal Reaister on April 28,1993 (57 FR 25851).

Also, a correction to the Biweekly Notice was published in the Federal Reaister on May 6, 1993 (57 FR 26987).

Sincerely, N

hThomasE

urlek, rector

< Office of Nuclear Reactor Regulation b

Enclosure:

Federal Reoister Notice cc:

Representative Barbara Vucanovich

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UNITED STATES

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j NUCLEAR REGULATORY COMMISSION iN 2

WASHINGTON. D.C. 20666-0001

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May 20, 1993 The Honorable Philip R. Sharp, Chairman Subcommittee on Energy and Power Committee en Energy and Commerce United States House of Representatives Washington, DC 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 Commission to issue and make immediately effective any amendment to an operating license upon a determination by the Commission that such amendment involves no significant hazards consideration, notwithstanding the pendency before the Commission of a request for a hearing.

In addition, the legislation requires the Commission to periodically (but'not less frequently than once every 30 days) publish notice of any amendments issued,.

or proposed to be issued, under the new authority above.

Enclosed for your information is a copy of the Commission's Biweekly Notice-of Applications and Amendments to Operating Licenses involving no significant hazards considerations, which was published in the Federal Reaister on April 28,1993 (57 FR 25851).

Also, a correction to the Biweekly Notice was published in the Federal Reaister on May 6, 1993.(57 FR 26987).

Sincerely, L.

P Thomas E. karley, Nector Office of Nuclear Reactor Regulation

Enclosure:

Federal Reaister Notice cc:

Representative Michael Bilirakis t

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,8 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 cc:

Representative Barbara Vucanovich The Honorable Philip R. Sharp, Chairman Subcommittee on Energy and Power Committee on Energy and Commerce United States House of Representatives Washington, D. C.

20515 cc:

Representative Michael Bilirakis e

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b 6-Federal Register / Vol. 58 No. 86 / Thursday, May 6,1993 / Notices 26987 P

J Correction to Shooeldy Notice Applications and Ammhts to Operating Uconessinvolving No Significant Hazards Consideration On April 28,1993 (58 FR 25851), the Federal Register published the Biweekly Notice of Applications and Amendments to Operating Licenses i

Involving No Signi6mnt Hazards Considerations. On page 25872, bottom of column 3, the notice entitled "Duquesne Usht Company, et al.,

Docket Nos. 50-334 and 50-412 Beever.

Valley Power Station, Unit Nos.1 and 2, Shippingport. Pennsylvania," and ~

ending in the middle of column 2, page 25873 "at the local public document rooms for the particular facilities 1

i involved" should be moved to the bottom of column 2 of page 25867.

Deted et Rockville, Maryland, this 29th day of April 1993.

Far the Nuclear Reguletary Commision.

Steven A. Verga, j

Dstector. Urision of Neoctor Projects-4M, Office ofNucieer Nom 1ar Aegulation.

1 IFR Doc. 93-10841 Filed 5-5-93; 8:45 aml j

eusse coes teeMus j

. l

e 26968 Feder1d Register / Vol.18. No. 66 / Thursday. May 6.1993 f Notices (Docket No. SM981 controlitems pad.1 mpnrod to be The proposed changes do set involve e tested by June 13.1993, or later, untij change in the ufety limita, se'poinu. or Cooper Nuclear Stetion, Coealderation the next refueling outage, but no trter d"*'f" "'* ** ^1**** f""P ""d changes of issuance of Amendment to Facmet than Septruber 30,19m.

d" " ' "8 fiC""d '""" 'b ' *"""*9"' *c"'

7 Cpersting Licanee, Proposed Na -

Before issuance of the proposed

• N" Significant Hazards Consideration license amendment, the Commission No D:t:rmination, and Opportunity for a will have made findings required by the margin of safety.

n in e Hearq:Correccon Atomic Energy Act of1954 (the Act) and tb Commissr as emended The NRC staff has seriewd th acacy: Nuclear Regulatory on a Commission.

regulations.

hom's an@ d bd u Ws acnoN: General notica; correcdon.

De Comnoission hs inede a review it appears that the these standards of 10 CFR 50.n2(c) are proposed determmetion that th seisSd. Therefore, the NRC staff suvum: This document corrects a r_,c.ia.: mprest r,avolves no gen < tral nonce oppearing in the Federal significant hazards consideration. Under proposes to de6 ermine that th Register on April 30,1993 (58 FR the Commission's esgulations m 10 CFR amendment request involves no

. iEMMs coandergion.

261741 which considers issuance of en 50.92, this means that operation of the

,khe Cornmission is seeking public smandment to facihty Operating facility in accordanca with the proposed 1.icense No. DPR-48, lesued to the amendment would not Illinvolve a comments on this proposed determination. Any comments wesived Nebraska Public Power District, for significant increasein the probability or w thin 30 days aPs tb due af operauon of the Cooper Nuciaar Station. consequences of an accident previously publicgion mms notice wiu be located in Nemah Courdy Nebreska.

evaluated: or (2) create the possibility of This action is necessary to cornct an a new or different kind of accident from considered in makag arty f.nal determination.

erroneous date.

any accident previously evaluated; or Normally, the Comm eon will not ron FunrHER MD804ATION CONTACT:

(3) involve e @fmt reduction in a issue the amendment until the Michael T. Lesar. Chief. Rules Review margin of safety. As Jequired by 10 CFR Sachon. Rules Review and Direaloes 50.91(a), the liconees has provided its expiration d th 30-day notice period.

However should cummstances change Branch. Division of Fseedasa of analysis of the issue of no significant during the notice period such that Information and Publicatjons Services, hazards ennsiderstaan, which is failure to act in a timely way would Office of Administration.U.S. Nuclear pmeented helew.

result, for example,in derating or Regulatory Commission. Washington.

The proposed thenscu de not irrvoke a shutdown of the facility, the DC 20555, telephone (301) 492-7758.

SHCbeceese(bechanges would not:

Commission may issue the license On page 26178,in the firstsentence

1. Isreke a segrun-e increase is tha amendment before the expiration of the of the third full paragraph in the frret probatuttry or consequences of an stridsr.:

30-dey notics period. provided that Its columa. the date **)ane 1.1993" abound previously analysed.

final determination is that the be changed to road May 17, 1993'*.

The isurveillanca test intervall STI amendment involves no significant Cated at sea =ada Mryland, this 3rd day

• i$

he ty ift herards consideration. The final of M2y 1993.

tengmeered seMy femense actuation rystemi determination will cxmsider all pubh,c For the Macteur Angshnery Otvrmnistnon.

ESFAS. irsecter tr+p systemi RTS. or other and State comments received. Should MichnetT.imeer, systems -maweh vbe insenenente and the Commission take this action. it will Chief. Rufes Merunt Secten, Males Persew thereby a resuanet wane &acrease in the care publish is tb Federal Eagaesar a notice and Dweetenus Snesect. Desse en ofProeders damage frequency (CDFl. Where of issuanos and pro 6(de for opportually of InfarrnatJon and Pubhcxrtson Servsces.

quantskuesens sien made, the mamma for a hearing afierissuance. The ogeea(Agou=ar am, incnese se CDP was fused to be of the order Commission expects that the need to IFR Doc. 93-30642 PEsd 5-5-43; 8 45 eral 8

o th D

take thia action w 11 occur very I

8'u8'e cosa sue e**

is e one-time chargeand not a permensat infrequenriy.

Increase. Whefs qualttstive assessments were WZztten comments iney be suhrtitted

[DocWo.M made, e enunknamon of one or more factors, by mail to the Rules Redw and such as: (a) Diverse signals; (b) redundant Directives Aranch Divialon of Freedom Northeast helear Enoryy Co~.

paths: (ct peemen new Mure rates based on ofInformatvm and Publications l

P ant.specsAc dese:le enhapely low risk Services. Office of Adaninistration. U.S.

Condderatlos oflaaesenoe of

%,gg g, W Oposeeng signir-of abe derzahme sa care demar Nuclear Reguietary Cesaraission, p--'miagetase:and del other n" Washington. DC 20355, and should cite License, Propoemd No Sagednesat frequent tests. mese used to justdy de Hazardo con Deserealeetterb ndnimus kyw ziskincreensa. In addition, the Publication date and pa8e number of I

and Opf-, _ 4 for e Haedng dany channel cheris and analog channel this Federal Register notica. Written

^

i oposatloc s! tests will coaticue to be comments may also be delivered to The U.S. Nuclear Regulatory performed et the trageencsee required by room P-223.Phitfipe Building 7920 Commission fthe Commission)is technical spectAcaesses. These surveillences Norfolk Avenue. Bethesda, Maryland, considering tsausnce of en amendment walesentsee to messes erst ene hosereteent from 7:30 a.en. to 4:15 p.cn.1ederal to Facility Operating License No. NPF-rellahasar enemmed 4 she hesis of tarhnal workdeys. Cop +'es of written comments

49. loosed to Nesh=2 N=r4a=r Energy 8P*ctF

• leesde M received may be examined at the NRC Company (the licensee), for ap==rian of

2. Caste the pommy of a rww or Public Document Rosm the Gelman ths Mint <ma & clear Power Station, diflosentModof socidest Imsa any Building. 2120 L Street NW.,

Unit No. 3 located in New London.

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Washin ton, DC 20535.

, m, g Connecticut.

N ficenses has requested that plant operenng proandarea.Therefare, there The fa ing of requests forheering and can be noimpact on plant response to the Petitions for leave to intervene to technical specifications be changed to point where a tHeerent scodent is created, discussed below.

estend the interval for survelilance

1. leedve e eigencent weection in a By June 7,1993,the ficansee may tim

)

1

'esting of 42 instrumeertaden end margin et seasy.

a request for a hearing with respect to j

Federal Registre / Vol 58. No. 80 / Wednesday. April 28, 1993 / Notices 25851 Sc Standard Review Flan for the Deted: April 22.1993.

determination. Any comments received lleview of Femedial Action ofinactive lohn C. neyne, within 30 days after the date of Mill Tallings Siter-Review and A.*uory Coaumerne Management ofpcw.

publication of this notice will be comment on Revision 1 cf the Standard grg poc. g3 9907 Filed 4-27-03; a45 ami canafdered in making any final determination.

Review Plan for use in reviewing the sa m ocoes m a Normally, the Commission wiu not Remedial Action ofinactive Mill issue tha amanAmant until the Tailings Sites Under Title 1 of the expiraum of the 3Nay notice period.

Uranium Mill Tallings Radiation UNTTED STATES NUCLEAR However. should circumstances change Control Act. Representatives of b NRC REGULATORY COMMISS60N during the notice period such that staff wtU participata.

C. DOE Site Characterization Progress 8Jweeldy Notice failure to act in a timely way we.dd result. for example in derating or R

its-Hear bnefin b and hold App 4 cations and Amendments to shutdown of the facility, the beons with repr tatives of b Facility Operating Licenses invoMng Commission may issue the limese NRC staff on NRC's tw and No Significant Hazards Considerations amendment before the expiration of b fouow-up to the DOE S

.P ed that its L Back round h

Characterization Progreu Reports for 6

the Proposad Yucca Mountain Pursuant to Public Law 97-415.the amendment involves no significant repository. Also discun the revised U.S. Nuclear Regulatory rhmmMion hazards consideration. The Enal promdura for evaluati 6 DOE study (the Commiadon or NRC staH)is determination will consider all public plans. Representatives o DOE will publishing this regular biweekly notica. and State comments received before Participate, as appropriate.

Public Law 97-415 revised section 189 action is takan. Should the Comminion D. Syrtematic Regulatory Analpis--

of the Atomic Energy Act of1954.as take this action, it will publish in the Hear briefings by and hold discuulons amended (the Act), to require the Federal Register a notice of issuance with reprwentatives of the NRC staff Commission to publish notice of any and provide for opportunity for a and the Center for Nuclear Waste amendments luued. or proposed to be hearing aAer issuance. He Commission Regulatory Analyses (CNWRA) on the issued under a new provision of section expeds that the neert to take this action current status of the Systematic 189 of the Act.Ris provision grants the will occur very infrequently.

Regulatory Analysis, conducted by Commission the authority to issue and Written comments may be submitted CNWRA, and products resulting from maka immediately effedlve any by mail to the Rules Review and this Inidative, including technical amendment to an operating h==e Directives Branch. Division of Freedom assistance efforts and the development upon a determination by the ofInformation and Nblications of the Uwnse Application Review Plan. Commission that such amendment Services. Of5ce of Administration. U.S.

E. Standanf Review Phn-Hear a involyw no significant hazards Nuclear Regulatory Commission; briefing by and hold discussions with consideration. notwithstanding the Washington DC 20555, and should cite representatives of the NRC regarding a pendency before the Comniission of a the publicadon date and page number of proposed NRC staH Standard Review request for a hearing from any person.

this Federal Register notim. Written Plan for use in reviewing the DOE Study This biweekly notice includes all comments may also be delivered to notices of amendments issued, or room P-223. Phillips Building. 7920

Plans, Proposed to be issued from April 5 Norfolk Avenue.Bethesda Maryland F. Committee Activitice-Discuss 1993, through Apnl 16,1993. The last

,from 7:30 a.m. to 4:15 p.m. Federal anticipstod and proposed Committee biweekly notice was published on April workdays. Copies of wn,tten comments activitsee, future meeting agenda, and received may be examined at the NRC 14.1993.

organizational matters, as appropriata.

G. Miscellaneous-Discuss Notice of Consideration o(Isenance of d

0 S N

miscellaneous mattere related to b Amendments to Facility Operating Washington, DC 20555. neliling of condud of Committee activities and Licenses. Proposed No SigniScant requests for a hearin and petitions for complete discussion of topics that were Hazards Consideration Determination, leave to intervene is discussed below.

not completed during previous moeungs and Opportunity for a Heartng By May 28.1993, the licensee may Ele as time and availability ofinformation no Commission has made a a request for a hearing with respect to Pennit.

proposed determination that the issuance of the amendment to the 54th ACNWMeeting July 21-22,1993 following amendment requests involve rubject facility operating license and Bethesda, MD. Agenda to be announced. no signi5 cant hazards consideration.

any person whose interest may be 55th ACNWMeeting August 25-28.

Under the Commission's regulations in affected by this proceeding and who 1993. Betheeda. MD. Agenda to be 10 CFR 50.92, this means that operation wisbos to participate as a party in the announced.

of the facility in acrordanca witn the prMN must Ble a written request 56th ACNWMeeting September 22-Proposed amendment would not (1) for a hearing and a petition for leave to involve a signi5 cant increase in the intervene. Requests for a hearing and a 23,1993. Boshands MD. Agenda to be announced probability or consequences of an petition for leave to intervene shall be accident previously evaluated; or (2) nied in accordance with the Commission's " Rules of Practice for ng O& 27-28' create h possibility of a new or Domestic Licsasing Proceedings" in to

~^3*"d*

different kind of accident from any )

CFR part 2. Interested persons should

)

acddent previously evaluated; or (3 consult a current copy of to CFR 2.714 58th ACNW Meeting November 22-involve a signi6 cant reduction in a which is available at the Commission's 23.1993. Bethesda. MD. Agenda to be margin of safety.The basis for this Public Document Room, the Gelman announced.

proposed detarmination for each 59th ACNWMeeting December 15-16. amendment roquat is shown below.

Building. 2120 L Street. NW.,

1993.Bethesda.MD. Agenda tobe

%e C= hon is seeking public Washington. DC 20555 and at the local announced.

comments on this proposed public document room for the particular l

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i 25852 Federal Registir / Vol. 58, No. 80 / Wednesday. April 28, 1993 / Notices facility involved. If a request fo,'s amendment under consideration. The Commission, the presid!ng officer or the hearing or petition for leave to r2ervena contention must be one which,if Atomic Safety and Licenseg Board that is filed by the above date, the proven, would entitle the petitioner to the peution and/or request should be Commission er an Atomic Safety and relief. A petitioner who fails to file such granted based upon a balancing of l_icensing Board, designated by the a supplement which satisfies these factors specified in 10 CFR Commission or by the Chairman of the requirements with respect to at least one 2.714(a)(1)(i).(v) and 2.714(d).

Atomic Safety and Licensing Board contention will not be permitted to For further details with respect to this action. see the application for panel, will rule on the request and/or participate as a party.

Those permitted to intervene become amendment which is available for petition: and the Secretary or the parties to the proceeding subject to any public inspection at the Commission's designated Atomic Safety and Licensing limitations in the order granting leave to Public Document Room. the Celman Board will issue a notice of a hearing or Intervene, and have the opportunity to Building. 2120 L Street, NW.,

an appropriate order.

participate fully in the conduct of the Washington, DC 20555, and at the local As required by 10 CFR 2.714. a petition for leave to intervene shall set hearing, including the opportunity to public document room for the particular forth with particularity the interest of present evidence and cross-examine facility involved.

I the petitioner in the proceeding, and witnesses.

Baltimore Gas and Electric Company how that interest may be affected by the if a hearing is requested, the g

., g y

results of the proceeding.The petition Commission will make a final Cliffs Nuclear Power Plant, Unit Nos.1 should specifically explain the reasons determination on the issue of no and 2. Calvert County, Maryland why intervention should be permitted significant hazards consideration. The Date of amendments request: April 1.

i final determination will serve to decide with particular reference to the following factors:(1) The nature of the when the hearing is held.

1993 if the final determination is that the Description of omendments request:

petitioner's right under the Act to be amendment request involves no The proposed amendments would made a party to the proceeding:(2) the signiacant hazards consideration, the revise Technical Specification (TS) 3/

nature and extent of the petitioner's Commission mav issue the amendment 4.1.2 "Boration Systems." The proposed property, financial. or other interest in and make l' imrkdlately effective, changes will separate the requirements t

the proceeding: and (3) the possible notwithstar. ding the request for a for mitigating small break loss-of-effect of any order which may be hearing. Any hearing held would take coolant accidents (SBLOCA) from the entered in the proceeding on the place after issuance of the amendment.

requirements for providing emergency petiticner's interest. The petition should if the final determination la that the boration. The requested changes are also identify the specific aspect (s) of the amendment request involves a administrative in nature in that they do subject mrar of the proceeding as to significant hazards consideration, any not odd, revise, or delete any of the which peut mer wishes to intervene, hearing held would take place before existing TS requirements. The changes Any person who has filed a petition for the issuance of any amendment.

provide needed clarification to ensure leave to intervene or who has been A requast for a hearing or a petition that the appropriate boration lineups are admitted as a party may amend the for leave to intervene must be filed with operable during the applicable mode of peution without requesting leave of the the Secretary of the Commission U.S.

operation. The TS Bases Section. 3/4.1 Board up to 15 days prior to the first Nuclear Regulatory Commisalon,

" Reactivity Control Systems," will also preheanng conference scheduled in the Washington DC 20$55, Attention:

be revised to support the proposed proceeding, but such an amended Docketing and Services Branch, or may amendments.

petition must satisfy the specificity be delivered to the Commission's Public The specific changes and clarification l

requirements described above.

Document Room, the Gelman B tilding.

proposed to separate the requirements Not later than 15 days prior to the first 2120 L Street NW., Washington DC for mitigating a SBIDCA from the prebearing conference scheduled in the 20555,by the above date. Where requirements for providing emergency proceeding. a petitioner shall file a peutions are filed du ing the last to boration are:

supplement to the petitica to latervene which must include a list of the days of the notice period,it is requested TS 3.1.2.6 Boric Acid Pumps -

contentions which are sought to be that the petitioner promptly so inform Operating, Limiting Condition for litigated in the matter. Each contention the Commission by a toll-free telephone Operation (LCO), will be changed to must consist of a specific statement of call to Western Union at 1-(800) 248-include a reference to TS 3.1.2.8 the issue of law or fact to be raised or 5100 (in Missouri t.(800) 342-6700).

Charging Pump Emergency Core Cooling controverted. In addition, the peutioner The Western Union operator should be (ECCS) Subeystema:

1 shall provide a brief explanation of the given Datagram IdentiScation Number TS 3.1.2.8 Charging Pump ECCS

{

bases of the contention and a concise N1023 and the following message Subsystems will be changed to only statement of the alleged facts or expert addressed to (Project Directnr):

contain the requirements which need to j

petitioner's name and telephone be met to mitigt.te a SBLOCA. This LCO opinion which support the contention licable to Mode and on which the petitioner intends to number, date petition was mailed, plant will continue to be app % of rated rely in proving the contention at the name, and publication date and page 1 when greater than 80 hearing.The petitioner must also number of this Federal Register notice.

thermal power. The previous provide references to those speciSc A copy of the petition should also be requirements for providing emergency sources and documents of which the sent to the Office of the General boration capability are moved to TS peutioner is aware and on which the Counsel. U.S. Nuclear Regulatory 3.1.2.9 Borsted Water Sources -

petitioner intends to rely to establish Commission, Washington DC 20555, Operating.

The footnote on TS 3.1.2.9. Borsted those facts or expert opinion. Petitioner and to the attorney for the licensee.

Water Sources Operating, which makes naust provide sufficient information to Nontimely filings of petitions for show that a genuine dispute exists with leave to intervene, amended petitions, the LCO applicable to Mode 1 when the applicant on a material issue of law supplemental petitions and/or requests greater than or equal to 80% of rated or fact. Contentions shall be limited to for a hearing will not be entertained thermal poweris removed. The 140, as i

matters within the scope of tha absent a determination by the changed, will be applicable in Modes 1 l

i

Federal Register / Vol. 58, No. 80 / Wednesday, April 28, 1993 / Notices 25853 through 4 to assure the requirements Therefore. the proposed change would not affect the probability or connquences of a needed for emergency boration are involve a signiacant reducuon in the margin previously evaluated accident.

available, of safety.

2. The procedural requirenaents of the The NRC staff has reviewed the RETS wul be maintained in the ODCM and Basis for proposed no significant hazards consideration determination:

li'ensee's analysis and, based on this the PCP.

tion of hylant will not be As required by 10 CFR 50.91(a), the review,it appears that the three ajtwed ech g g dt b standards of 50.92(c) are satisBod.

not place the plant in any new cond e

licenses has provided its analysis of the Therefore, the NRC staff proposes t introduce any mode of operation not issue of no signincaat hazards determine that the amendments request previously analyzed. Therefore, this change consideration, which is presented tavolves no signi6 cant hazards wul not create b oulbuity of a new or below:

1. Would not involve a significant increase consideration.

different kind of accident from any accident in the probabdity or consequences of an LocalPublic Documerit Room previously evaluated.

accident previously evaluated, location: Calvert County Library, Prince

3. The proposed changes relocate the The Boration System provides borated Frederick, Maryland 20678.

procedural details and bases of RETS from water to the Reactor Coolant System to Attorneyforlicensee: Jay E. Silbert, the Technical SpeciScations to 6 ODCM or PCP. N RETS procedural detai;s and bases ensure that negative reactivity control is Esquire. Shaw, Pittman. Potts and will be maintained by thm programs.

evaliable dunng each Mode of Operation and Trowbridge,2300 N Street NW.

Changes to these programs will require en during transient mnditions, The curnnt WashinEton. DC 20037.

onsite nyiew. In addition, new Technical Specifications combine the NHC Project Director: Robert A. Capts gminatrative controls have been added to requirements for providing emerBency the Technical Speci$ cations which essure boration and for mitigating a small break Commonwasalth Edison Cosnpany, de pmper mntrol and maWenance d &ne lossf<oolant(SBLOCAl The proposed Docket Nos. 50-295 and 50 304, Zion documents and provide an equivalent level changs will separate the requirements for Nuclear Power Station, Units 1 and 2 of anuruce ht activities involving etaergency boration from those for a 1.aka County, Ilhnots radioactive ef0uents, solid radioec ave waste, SDIDCA. The change does not add, revise. or delete any of the existing requirements, nor Date of application for amendment:

and radiological envuonmental monitonng are conducted in full complisnce with does it afSct the ufety function of the March 11,1993 segulawry nquitunnts. kmfore, then is Boration System.

Description of amendments requess.

a reducts a in 6e marpn d safety.

Separating the Benson System Technical Th* Proposed amendments wo, ld u

as reviewed the The N,RC staff h,s and, based on this Specifications to dist nguish between the revise e Technical SpeciBcations by g;

,,n,gg requinments for emergency boration relocating the rocedural details of the review,it appears that the thne purposes and h requirements to mitmate a SBLOCA will have no effect on the radiological a uant/ radiological standards of to CFR 50.92(c) are probability of an accident previously environmental monitoring program and satisfied.Therefore, the NRC staff evaluated. Nee changes are administrative solid waste program to the Offsite Dose Proposes to determine thatthe in nature and only clarify the axisting Calculation Manual (ODCM) and the amendment request involve-s no Process Control m (PCP).

cant hazards consideradon.

requirements.

si The proposed changes to the Baration Basis for Pro no sigru'[icant al Public Document Room System Technical Speci$ cations will have no hazards conss erution determination:

location: Waukegan Public 1.ibrary,128 effect on the consequences of an accidect As requhd by 10 CFR 50.91(a),the N. County Street, Waukegan, Illinois previously evaluated. They will clarify the hcensee has provided its analysis of the 60085 alignment of rystems currently required to be issue of no significant hazards Attorneyforlicensee: Michael L operable. Therefore, this change will not considoation, which is prnented Miller, Esquire: Sidley and Austin, One involve e sisaiscant incnan in 6 probabihty or consequences of an accident

. below:

First National Plaza, Chicago, Illinois previously evaluated.

1. The proposed changes only alter the 60690

2. Would not create the possibility of a new forrwt and location of procedural details and M

1. ct Grecton James E. Dyer or different type of accident frocn any en u strative controls of the radioactive er% mdialogical environmental Detroit Edloon Company, Docket No, accident previously evaluated.

4 solid radioactive wasta 50-341, Fermi-2, Monroe County, h proposed changes to the Baration n-

%,1 chanys are Mministrative in 4

Michigan System Technical Specifications are pr v, e administrative in nature and, therefore, do nature m 4, not involve any chaya to the not represent a signiScant chany in the configuration or oper.tlon of plant Date of amendment request: January configurotion or operation of the plant.

equipment. The Radiological EfDuent 29,1992 Specifically, no new hartiware is being added Technical SpecdScations (RETS) procedural Desen'ption of amendment request:

to the plant er part of the proposed change.

details are being moved to the Offsite Ibse The posed amendment would no existing equipment le being modined, nor Calculation Manual (ODCM), and the Procnes m the Fermi 2 Technical are any different types of operations be Control Program (PCP). However, the Speci cations for surveillance testing of introduced. The proposed change will pn y contents of the RETS ere not being changed.

ectivated charcoal samples from the clattfy existing T=rk nie=1 S facetions.

De purpose of the RETS is to aseurs that the Contml Rm Emergency Filtradon Therefare, this chany not create the proper controls br the radiological efDuont System (CREFS) and the Standby Gas possibility of a new or diffurent type of system are in place.no containing accidsnt from any accident previously the procedural details of - will continue Treatment System (SGTS). Specificallv, evaluated.

to perform the same ibactions. Any future laboratory analysis of a representativt

3. Would not involve a signiScaat changes to the programs osataining the RETS charcoal sample from the CREFS and reduction in the margin of safety, procedural details would requise an onsite SGTS are required at least every is The proposed changes to the Boretion review and approval. Therebre, the RETS months, after 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of operation, System Technical Spec 15cetions are will continue to receive a hi h level of following structural maintenance on 6

administrative in nature and, as such. will considerstion even they will no filter or chart. cal adsorber housings, and maintain the existing of sairty.

longer be part of the T ical followinI painting

• fire or chemical Carifying these Techn Specincettems will Specifications. All the cunent provisions of release in any ventilation zone distinguish between what borated water the RETS are being retained, so noos of b commurticating with the CREFS or sources and Bowpaths are required be assumptions used in the accident er q SGTS. The licensee proposes to update emergency boretton purposes and which will be affected. Based on this eva.+.4 It ones are required to mitigate a SB1DCA.

has been determined that b chanps 4, not the standards need to evaluate the

25854 Federal Register / Vol 58. No. 80 / Wednesday. April 28. 1993 / Noticas surveillances in accordanr= with adhtirm. for Unit 2 anly, the pressurizer review requind (engineering evejna,mni and pr:vious commitments to the NRC.

spray water differential tmperatum to ensun the correct subject u evaluated Basis forproposed no significant limit would be reduced to 320*F (from (stmetural integrity). Reformatting b oction herords consideration determlaction:

625'F). and an auxillary spray water statements was done to more clearly sent As required by to CFR 50.91(a), the differential temperature limit of 380*F h'[3 wh 6

licensee has provided its analysis of the would be rped$ed.

evaluation rince none is spened in the srS' issue of no signancant hazards Basisforproposed no significant m y2 hours is beoed os typical technical consideration, which is presented hazards considemtion determination:

spmScation an-uma h perhming below:

As required by to CFR 50.91(a), the certain orttana prie to beinnner a plant

(!)lnyntw a supn/icantinoense m the licensee has provided its ana}ysis of the shutdown. These are administrauve changes probabery or enraseynescas of an "*a' issue of no signincant hazards that are reneonabhe, sais and do not affect the Previously evaluated.

consideration, yrhich is presented LJFSAR therefore, these changes do not By providing en improved precedure br below.

inv Ivo a significant increase in the charcoal analyets the proposal

1. Does the kn=olve a signincaat ProbeWity or conseq-aa of an acddent greater assurance that the charcon3 Prmmaly evaluated.

can perform na deeren fnmainn end, thus. the og[.

b W dSundance nment cc,cacquencma of evaluered arrMants ero

,, p,,,googty 44A2.2 has Wa nyased Im units mm The pmposed amendosat modASee valid. The mer, hod of laboretwy analysas hee no sffect upon how the plant is operated, Speciacetions 3 4.9.1 and 3A9.2 by sepenu ance.

an 4.4A2.2 incorporating the STS (Standard Tarknnral to pm e the sundana in a h hmat including the motbod of semple resnoval.

and add surw taar= 4.4A2.2 for murdary a

Thusfwe the pmbebibty of any evakasted Specifications) action requirements in additicam to clar*stiac of the limtting

Prey water differential taanperature. Normal sccident is unchanged.

Muon tar operm and mannh pressuriser spray is surpplied from the RCS (4 Civete the poesabahry of e arw or and la not to seceed the mavimum Wnmems. 'Ihs % won Bret imW difmnt kind of ecodestfrene any occident PrmousJy awfueted.

to revise the BV 2 pressutaar spay

Prey *,ater

'ai temperature limit differential tesnperature limit by replacing durird p war operation, but dwing hastup As described in 1) ebove, the proposal hee the 625 F flanM with the 320*F neut. h '

am swa opera the &Bmatial no effect on h manner of pies opero6co-pressurizer sprey differential temperatur, MmPmmre niey approach the limit at low ne proposal does nce hrvolve say chemge to limit was identined as e er=r=rn during RCS tempetums. Thefme. SurmHance tbs plant design. Thebro, & change inverrigation into the BV-2 pressurtser twge Requirement 4.4.9.2.2 is opphed tv.xrmal crsstes no new accident modes' line tharmal stratiScation issue and the leak.

sprey and requires verifying the dJaurential (UInvoJw a sagmficantiedeccan le a befre. break analysis =nanciated with the temperature is withis the um6t at least once margin of sofrfy.

large bore snubber removal. Additional per 30 seisahe dwing beatop and rmWwn By providing as improved procedure for changes were alas included bllowing review oPeretions. This frequency is consistent with charcoal analysts the proposal acts to of the STS br cleriScotfon of the acnon 4.4.9.2.1 for vertne=rsa= of the pressuriser ceintain existing safety mar 5tas, reseements fbr Specince6cns 3.4.9.1 and tsemperature also regadred dartag heetup and The NRC staH has reviewed the 349.2.

co idown operations. T.arw t=nem a

lic:nsee's analysis and, based on this m cumet EV.2 eseculary sprey R*quirement 4.4.9.2.3 is appued to auxibery review. It appears that the three differestini temperorure Ibant was sprey opeatian wie wr+h of 6.

standards of 10 CFR 50.92(c) are ino-g./. in SpeciScation 3.4A2 to dismar.el umperahn se least once per 30 satisEed. Thersfore. MRC staN pr vide the===imuss vehas consistent with minutes when =whry sprey is used. Since the pressuriser equi omrihary sprey suey be used at times other u ue awysis br 5">speciEcstica.The he dwingh.mm and cooldown Proposes to determine tha: the s

sures Ik amindment request involves no migiufirsat hazarda consideration provides far a Itmited smaber of cycles above opemtions,it has separeced frcan normal local Public boeunaent Room 320'F. however, the design anatyris has been spray bor cheapse resect the etelytis vert 5ed to account for auritlary sprey M and are re==lan=at with b

=

Jccotion: Monroe County Library opereelou with e difhrential tumrpereture OPeretion of the pressurtser spreys, thenfore, Systarn. 3700 South Custer Road, lintM of 3erF. Therebro, to ensure the these ch=ag== do eat inve&w e an=*=as Monroe. Michi an 48161 the %r mesu de eaeptance criterie h Mee8e la &e psobap w masegosacos

=W y

use of the plant the ammal s of an accident evaluated.

Attoirreyfrir iemseerJohn Flynn, 65mmesi eneysmaam unnM has M l rey

2. h es mes &e pmaMuty d Esq. Detroit Edison Co.

.7000 reduced to 330"F and en eux111ery r' F {es a new or difhreat khed of =rr6tn=rr* Aum any Second Avenue. Detroit, gaa esseemael hmpworms umir d y,0*

accidmet greviody evalueted?

48228 been added. The BV 2 pip 0mg edecent to the h requireensets of BV.2 'y-d Ae=etaa NRC Project Director:L. B. Marah pressuriser sprey nocale is equip with a 3.4 0.2 will contimme to severs the alerw

• aHows es nanit.

PeaW d ee, : A and Duquesne Light Cornpany. et al. Docket BV-1 dosse't have this desiga, there bee. the inczrpcretes more casservative spray weeer Nos. 50 334 and 50-412. Beaver VaBei Power Station. Unit Noa,2 and 2 3eo'F diarrumtial temperature doesn't apply differential teerparature limalas thee ers for BV-2.The proposed r h estahh=h== a co=="a==* wah tas ena}yssa. The proposed Shippingport. Fennsylvmala more oneservative Beast and not ass =t change dame not tatroduce any new mode of Dets of amendaient Muest: February tbs Npdated Flael 3sasty Anatyals Report) plant operados or soy phryrica!

3g,3993 UFsAa.thereen this change does not

==,uar=,== is the ther.bre, this tavalve a sigutar=* increase in the rh anLua will not cruees the possibihty of a Descriptaort ofa==+ tingeset.

p.a.wi,,, = -

=_m og,,,,,4,g,,

new or d&5erese kind of accident troon soy i

The proposed amencl==nt would prov6musly evah==*=d accident previously evaluated.

modify Sp=rifie=ricas 2.4.e.1.3.4.e.2 The sensa=======*= sar these m revned action stemmerne kr i

and 4.4.9.2. The changes wculd specify i.

--ma== have beso revised to speciScations 3.4.a.1 and 3.4.9.2 to a 72-hour tune 11 asst for an -

N t-Inarpersas the STS esquir===ra= la tarent.

consistent with the naa==a of the STS and win cvaluation if en out-of-lfrait tr'=sitine'is but the br==# has been changed to separate ensun an ang+a== ring evalaatta= le r==rhad 2 to no tisme ben each of the indivtdual =*== end to performed when segutred to maoise the i

currently MThe% also LDC rPorste a y2 heer action time e pedarm structusel latogrtry of the RCS and th toformat the acties pens==neng jate a Et P"*"I"" I' *"

l

=<*= steessesses are e==6an=* with the operetnam. Changing the brast amparates the of cetions. Waur difissential spuey ori6iss=4 STS.

individa.1 =rv6a= requiremmate late 1

temperausre wrondd be seenitored every laser sevisions b the STS =<^ A=d he individual er*6a== Addtag the y2 hour t

30 minutes i==*==<4 of every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. In wording to more cleedy drEne the type of action tsme to perform the em6 neering t

I

Federal Register / Vol. 58, No. 80 / Wednesday, April 28. 1993 / Notic:s 25855 evaluation is consistent with other action limiting conditions for the use of these toduction in a margin of safety. Each requirements which provide a typical action tystems, therefore, the changes to standard is discumed as follows:

time to perform an action function prior to Surveillanem Requipment 4.4.9.2 emphasize (1) Operation of the facility in accordance plant shutdown. none changes do not veriBcation of 6 differential temperatun with b proposed amendment would not reduce the limiting condition br operation or when these conditions spply. Reducing the involve a signifbat incroue in b action requirements, therefore, these changes frequency to once per 30 minutes provides probabuity or of an accident will not create the possibuity of a new or edditional amurance that the di5erential prwiously evalue d15erent kind of accident from any accident temperature is adequately monitored and The ;noposed amendment would pr:mit previously evaluated in the UPSAR.

maintained within the speciSed limits. Rose full power operation of St. Lucie Unit 1 with Surveillanca Requirement 4 4 9.2 for both changes or sure the required parameters are a decoued value of design rsector coolant units has been sepented into individual veriSed during the applicable conditions and Sow. It is postulated that this steady state surveillancee 4.4 9.2.1 and 4.4.9.2.2.

on a conshtent frequency, therefore. bee RCS flow decrease would occur as a result of Survat!!ance Requirement 4.4.9.2.1 requires changes wul not reduce the margin of enjety. an incrossed level of steam generator tube venfication of the pressurizar temperatures at The NRC staff has reviewed the plugping. No increase in the probability of lea t oncs per 30 minutes during rystem licensee's analysis and, based on this any accident prwimsly analyzed is likely to ccur because no changes are being made to bestup and cooldown operatiors This is review,it aPPean that the thru the plant's required mode of operation or to consistent with the current surveulanca standards of 10 CFR 50.92fc) are any active plant component. By their nature, requirement. Surveillanea Requirement satinfled. Therefore, the NRC staff steam generator tube plugs an passive 4.4 9 2.2 requires venScation of the normal spray water temperature d15erential at least Proposes to determine that the components and this amendment does not oncs per 30 minutes during rystem heatup amendment request involves no change the nature or type of plugs which may and cooldown operations. This includes significant hazards consideration.

be used.

changing the surveillance requinment to localPublic Document Room Florida Power and Light Company (FPL) rpply to normal spray, aplaces the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> location: B. F. Jones Memorial Library, has submitted the results of a safety frequency with 3,0 minutes and changes the 663 Franklin Avenue Aliquippa, evaluation which concludes that potential radiological consequences of previously appilcation of this survetilanca regstrement Pennsylvania 15001*

to rystem bestup or cooldown operations.

gOIUfF C8888" Gerald Charn0ff* analynod accidats mmain wieln their Survelliance Requinment 4.4.9.2.3 has been established os criteria when added for verification of the auxiliary rpray Esquire, Jay E. Silberg. Esquire, Shaw, including the of increased steam water temperature differential at least once Pittman. Potts & Trowbridge,2300 N generator tube plugging or mduced RCS Bow per 30 minutes during surillary sprey Street. NW., Washington. DC 20037.

consistent with this proposed a-d-aat.

operation. neee changes specify frenuancy NRC Project Director: Walter R. Butler his conchasion is rupported by reanalysis of relevant 11mitin6 > vents in sental accident cnd application requirements similar to Florida Power and Light

, et -

Specification 4.4 9.2.1 where a parameter is cateprhe, as appropriata.

veriSed under the cnnditions when that at, Docket No. 50-335 St.

P t,

Therolore, operation of the facility in parameter may approach the limit nose Unit No.1, St. Lucie County, Florida accordancs with this amendment would not rhanges provide for reasonable verification of DQte o[ amendment request: March involve a signficant incean in the i

the required parameters at a consistent probability w consequences of any accident l

gg*ggg3 frequency and are applied when required to Description of amendment requestr (2)Opeh of th inciW b ha previously evaluated.

venfy system operability, therefare. these changes will not create the poutb111ty of a Mio proposed amendment allows a with the proposed =aadmant would not i

new or different kind of accident from any reduction in Reactor Coolant System croots the possibility of a new or different accident previously evaluated (RDS) design flowrate from the current kind of accident from any accident

3. Does the change involve a value of 370,000 gpm to 355,000 gpm in previously evaluated.

significant reduction in a margin of Technical Specifications (TS) Figure nas amendment does not result in a safety?

2.1 1, and Tables 2.21 and 3.2-1.

change to any active plant component or in 1

no BV 2 625*F aurillary spray differential The purpose of the proposed change the mode of operation of the plant. The

)

temperature limit was incorporated in is to accommodate future steam design function of the Reactor Coolant System. Steam Generet rs. Emergency Core Specsfication 3.4.9.2 to provide the 8'nerator tube g (SGTP) uP to cooling Systen and other eyrtems will not manimum value consistent with b 15% (average),

not expected. it rhanen. De designed - c=== capacity of the kressuriser equipment sprelScation.owever, this only provided for a limited is possible that SGTP performed during steam genarstors can are-date the number of cycles. By f.ocorpwsting a the upcoming refueling outages may potential reduction in primary to secondary conservative reduction in the limit to 320*F eliminate any remalning margin hat transfer area caused by increased tube i

I for normal spray and 380*F br anMitary between the actual number of pl plugging without significantly *We the sprey the analysis assumptions are satisfied tubes and that used in existing plant's dynamic behavior. The presencz of i

1

** 8'"*" tubes is not changed and the equipment meets the acosptance analyses assumptions.

P gProposed amadent.Thmbre, criteria for the design life of the plant-Scsisforproposed no tignificant opmuon oI the facility in accordance with Dy

• 1I l*****I1 **"h* " 0 hazards consideration determination'.

P

\\

h*I"'a*rg"in of safety is not reduced.

the proposed amendment will not ccante the cod the m As required by to CFR 50.91(a), the possibility of a new or different kind of Changing the action statements to specify licenses has provided its analysis of the acc6 dent imm any accident previously an engineering evaluation in lieu of an analysis is acceptable since the engineering issue of no signiScant hazards evaluated.

evaluation can be performed in a r===nable consideration, which is presented (3} Opetion of the facility in accordance period of time to ensure those parameters below.

with the proposed amendment would not that may be affected are consistent with the Pursuant to 10 CFR 50.92, a determination irvolve a sign 1 Scant reduction in a margin of analysis assumptions. Tbs engineering may be made that a proposed license

safety, evaluation provideo c.dequate naturance that amendment involves no algniacant hasrids The impact of the proposed change on the structuralintegrity of the RCS and consideration if opmtion of the facility in evallable margin to the acceptance criteria for prwsudaer are acceptable for continued accordanca with the proposed amendment SpeciSed Acesptable Fuel Design 1.tmits operation and is consistent with the STS.

would not: (1) lavolve a significant increase (SAFDL). primary and escondary therefore, these changes will not reduce the in the probability or consequences of an m arisation transients to UR margin af safety.

accident previously evaluated; or (2) creets 50.46(b) criteria, peak coatainment pressure, j

Normal pressuriner sprey during bestup the possib!!!ty of a new or different kind of potential radioactive does releases and to j

and cooldown oporttions and auxiliary sprey accident from any accident previo.r.aly existing 1.imitirsg Conditions for Operation operation when using auxiliary sprey are the evaluated. or (3) involve a signiScant has been =rambed as part of the safety

.m m

25856 Federal Register / Vol. 58 No. 80 / Wednesday, April 28, 1963 / Notices evaluation =h=in=d by FPt.la support of P A), credit for the full aussber of

3. N marsta of salsey associated wkh the this amendment. Aher masidering the containment coolers required to be change in the pressure for can*=in==nt leak Proposed seem sneerstar tube pluging Iml av=itahl= by TSs (4 of 8), and en initial tesung hu bem d==a==*=ted by the suuhe and twultant ItCS Bow, a ra parinos of containment pressure of 3.0 psig of the accident analyses.The emelyses limit events to the arr-gamara criteria

'*9"I"d by TSe rather than 0 3 sig. -

r=h was a result ofIDCA and steem ilne (8nArw Me Peak comm===* presum listed ve abows that a enn==rvative safety The restdts showed that the h'f est Pa beek does not rhaliange the cneani====t

- in to the acceptable limits remains ava le. Fm this pn FPL has concluded would occur for a IDCA rather than a design pressure of 52 pels, m relata== hip that there is no sigalacant :=d*= la a MSIJi and reach a mart =um value of of the test pressum to the peak calenimma marpa of safety as a result of this proposed 36.5 paig. Da NRC sta5 found the presswo nmains the same: therehme. the 11ccuse amand===t.

revised analyses acceptable in the Safety required margia of sehry agulated er sech Based on the diam==Mn= presented abow Evaluation acrosepenying Amarwim.,. afheted sehry analysis is==Imanised. Slaca and on the supporting technical 60 and 30.

the revised Tarhairal Sp=r+ar-rin-,alue just:5 cations. FPL has cnocluded that thi*

The calculated peak conomin==nt cxmtimuse to be less them the cime=6====+

proposed license amendment involves no sigm5 cant hasards ranalA-ration.

Premuro is used for Isak teettag th design and penser than or equal to the calculated a====+====* premure.

The NRC sta5 has reviewed the mntainmet, cantinment isolation the change does not brvoiw a =lgniaar.t valves, and c n atamare penetrations, reduction la e ofsehry.

e licmaes's Mysis and,bued on this revizw. It appears that the three including the containment altiock,in The NRC sta5 reviewed the standards of 50.92(c) are satis 6ed.

acmrdance with 10 CFR 50 Appedi4 limnsee's analysis and, based on this i

• Proposed====wl-nts would review,it appsers that the three Berefore, th NRC Wa5 to mmgnias es mised, acmpted value of standards of 10 CF1t 50.92(c) are deurmine that the amen request involves no signi5 cant hazarda 36.5 peig, rounded up to 37 peig, as the satisSed.nerefore, th NRC Wa#

basis for these tuts-proposes to determine that the d 'd*ti As resguired by to CFR S0.91(a). th*

amendment request involves no p,c.umns Roorn 11 en8" he8 Provided its analysis of tbs i min,=at hazards <===ideration.

h location: Indian River Junior College issue d no sign 18mit hasards localPublic Dricumerat Rooms na daratica, whid is psesented locacorr: Burke County Public Library, pg

'F de 34964 Fourth Street, Waynesboro Georgia Attorneyfor beertsee: Harold F. Reis.

1 sirvisica d der comminmens w kt nag de

m.,an,eaeig.6a,==.

Esquin Newman and Ho

.1615 i

L Street. NW., Washington, 20036 incnese in the probability or consequences Aft 7tneyjbr5censee:Mr. Arthur H.

NRCProfect Dimefor: Herbert N.

of as acddest a

• eselustesL Domby Troutman Sanders, Berkow Utillassion af ab revisedleasses will notNationaBank Plaza. Suite 5200,600 cause say deslys er emanysk scespiance Peachtree Street. NE., Atlanta, Georgia Georgf a PowerCourpany Oglethorpe criterie to be exceeded harmi== the 30308 Pcwor Corporation Maaicipal Electric cone =ta===t wt!! santinue to be tested at a NRCProjectDirector: David B. '

Authority ofGeorgia, City of Dahon, pressure greater than or equal to the highest Matthews Georgia.Dockst Nes.so 434 and so.

pressure====r4aand withkhmettomaldesige bests Vogels Electris F--

 ; Plant, accident.Tns senscessel N Power Campany and Soyland i

425[ta 1 and 1.Barbe County, Georgia intsp of pleut systuns is smalhessd.

PowerF --M Inc Dechst No. So.

Un N-

. this chmage does not eSect the 441 Clisson Power h. theit No.1, Date of amendmerrt squest: April 8 Inalan== der any transieme.Thesuhre the DeWitt County, Illinois

=

1993 probability of eczusraecs is sat aSucted.

Description ofamendment h chmey to the pressus Imr -a u-ant Dose ofamendmentrequest: April 16 The proposed amendments w d leek testing does not esset the tatsgrity of the 1992,

- revise the Tarhairal cations Bestan pueduct barriers utilland kr Description of anaudment squest.

"l'i 'enom et dass caussgossess %e pro

===ad====4 would (TS ) to change the us of the peak 8

as a result af as=='t h addiales, the change tem Power Station Tarknical contain===*bressure (P.) calculated for othets ammar solamens used e imput to the dose Spec 18catlan F1gese 3.1.51," W design basis dents. De vehse would

=h-l=e8=== am hag =d tan theme Percent Sodhna Pentaborate Solution as be changed from 45 psig to 37 in puertamely asummed. 'thmetus, the aedes aggggg,g TSs 4.6.1.1.c. 3.6.1.2.a. 3.6.1.2.,

dass pe=dina6=== somata withis the h h Mon k W d he 4.6.1.2.a. 4.6.1.2.d. 3.6.1.3.b. 4.8.1.3.a.

accupeamos criterna hr each ed the tsanaismes and 4.6.1.3.b.

afheted. Since it has been dan==i==d that eat ruults hem raising se Standby Sosisforproposed no adga$ cess the mensiset results me naami ca-d by the Liquid Control System storegs tank level hazards consideration change in pressum der containment leak instrument aero to prevent potential air detersiination.On Mard 22,1993, the testing it is macinded that the an==g=nau entralammtla the pausp mrMan piping a

NRC fund Amendassam 80 (Unit 1) 8' " """' *--4 8'*l88888 8' mot due to vert **in5. A ~ M the incnesed.

d and 39 (Unit 2) which modiSed the Tarhaical Specs 8caelas Bases whida 2.The assage in pauseum kr""

describe this cures weald be revised to

.Vogt1s Licenses and TSe by increestag hk todas dass em crosse the passegmy d Mled se %

maximum core power level hem 3411 e new or desmuse kind of assidset boun any gg a

g A M - ----

---

g&hr'm/rsodu*

roegawatts thermal to 3568 magswetts accidset,.. : :'y seelumesd.The changs la i

thm' mal To su putesse peevious premme dem um aSua medse h amindments, liconose As W by1M M(a) so

,evisodanaiyeesados trevided

. sequences. No msw apar.edag comapsetion is u - n-P-ided=-ai*aa.

that fcsoses,a ne,st hilum samaria, in imM das algnh M

.,s.

he s m m i.

1

.si. m coolant are'd==*= UACAs) and mala swam Hasbseek W)muidesk. De

=ldam== asaswhihise modesesebeing rannid===*A== which is psesented below:

1

,yp,",,g,,MM M

Y,,,,h M

mised anal beneA n d t u s m ure!

,i,,,,,,,

g

changes, a som accmate Sehty Analysis IFSARIconsieme ts - seeliable solene of sodiusi paneshauses accounting of best staks laside reprasmet the sysserum af esames to solutten ahose the sortsed lastrumsat asse, conut--* as improved mass and be analyasd which dan==a== sede pine Hoesseur, the low level and high-levet alarm energy evaluation model (WCAP.1032% operation.

seapoints wee miss iostand to aansunt for the -

-- - ~

e Federal Register / Vol. 58, No. 80 / Wodnesday, April 28, 1993 / Notices 25857 rwind instrument zero ruch that the not Descript/on of amendment request:

The change to TS 4.5.A revises the volume of sodium pentabante solutia The proposed amendment would 1) monthly surveillancs requirement for corrnponding to each of thee, seepotets does increase the minimum fuel storage the emergency diesel generators by 1,("M,' ",%g3 jg"*

requirements for the emergency d.iesel pecifying the loading range and power 8"

generators. 2} revise altamate train anor to be used during the tast. (Aa avaliable to shut down the roector in the mot of an ATWS mat. In addition, testing requitetnants for ths omergency editorie} change makes it clear that twiuons hm been made to the rg.us to diesel generators. 3) revise the monthly during the test. operation of the bl oil provide additional understanding and less emergency diesel generator load testing transfer pump for the running mofusion in the use of the f!gure. Since these requirement,4) add a requirement to emerpacy diesel generator must be changes do not impact the obthty of the perform a semi-annual demonstration of veriSed). In addition, a new, sem].

rystem to perform its funaim, this request the emergency load capability test of the knnual test of the etnergency diesel does not result in a signinrent incense in the emergency diesel generators,5) revise generetots will demonstrate their ability consequences of any accident prwtously the Remedial Actions to be taken if to start and deliver power at the

'P*"

more than one of the required electrica.! mavimum expected emergency loading.

ggde vi sattes becanes unavadable when the Technical Speci8 cation 4.5.B. Station evaluated, the (sandby 11guld controll 514 rystem is designed to miti ate h reactor is critical. 6) remove a mstriction Batteries, is revised by dividing it into 6

consequences of transients / accidents in the placed on 115 kV power to theitation three separate requirements based on event of a failure to scram. Operstion of the by a previous Amendment. 7) revise or fregtency of performance. He change is SIC ryttem and 6 impact of the proposed add the Basis associated with aach item, editorial.There is no change to changes on the SIL rystem have no imped 1 through e, above, and 8) maka minor technical

• uirements.

on the probabihty of occurrence of those U

2. De proposed amendment does not edit N chan8'8 transients /ealdents 032s / r Pm osed no u.gm can hazords connfemtmn deternunotw!

create the possibility of a new or (21 This request does not result in any n

change to 6 plant design or operation different kind of acrident from any beyond the change to the inscument zero for As required by to CFR 50.91(a), the previously evaluated.

the SIL storage tank level instrumentation.

Licensee has provided its analysis of the The proposed amendment makes no The proposed changa does not involve any issue of no signi8 cant hazards hardware modifcatbus mies u channes to the plant design other than that consideration. The NRC staff has un U8 Pershg cmdihs. T&d specthcally desenbed and impacts no other reviewed the licensee's analysis against ca@n 3a2 wnhcmase the systems or components. In fact, the proposed the standards of 10 CFR 50.92(c). The ese ue d a wege mqu mut. -

changes ensure the design requirements of staff's review is presented below:

am n a now unnecessary asMon the system are achieved. As a result, no new

1. The proposed amendment does not on use of the 115 kV Surowiec supply failure modee are introduced, and the request involve a significant increase in the hne, pavent the loss of both emergency wtll not crate h possibthey of a new or babili y uences f an different kin of accident from any accident diesel generators through unnecessary P

ea a

am e ed y

be i

of tha SIC Scat (T

an e er system as the reliabihty of h Sir rystem plant systems or components, nor mquimd g

inoperable emergency diesel generator--

operation is in fact inansed by pmenting directly affect system or com nant including the emergency buses and de potential e!r entrainment in b pump maintenance.Tne reposed e

distribution cabinets associated with the suctin piping due to vortexing. Since this would improve sa operation of a

l emergency diesel generator.

request does not involve an adverse impact P ant.

to ryttem operation or reliabinty, and since increasing minimum dksel fuel Technical SpeciEcstion 4.5.A would wa ed by the p posed ch

, this sig mquirets usurn specify the load range and power factor Sir systern factivity contml cepability is compliance with American National to be used during the monthly

)uebnin sbNk Standards Instituta (ANSI) N195-1976, emergen diesel generator surveillance no NRC s reviewed the which specifies that stored fuel oil be test; estab sh a now, semi annual licensee's analysis and, based on this sufHcient to supply the emergency emergency diesel generator surveillance review,it appears that the thme diesel generstors for 7 continuous days test; and make two clarifying editorial standards of 10 CFR 50.92(c) an of Operation.

changes. De change to TS 4.5.B satisfied. Therefore, the NRC staff Removing the operational restriction marganiaes battery testing requirements; proposes to determine that the on the 115 kV Surowiec line mDects the no technical changes are made, amendment request involns no inceased reliability cf this source dus

3. The proposed change does not si Scant hazards consideration.

to the operability of the naaMated involve a significant reduction in a al Public Document Room especitor bank.

margin of safety.

Joection:Vespasian Warner Public namedial Action 2 to TS 3.12.B is The pro change to TS 3.12 1.ibrary,120 West Johnson Street, avised to prevent loss of the second would this specification Clinton, Illinois 6172y (altamate train) emergency diesel consistent with curant administrative Attorneyforlicensee:Sheldon Zabel, generator during testing. when one train controls, which are more restrictive than Esq.. Schiff. Hardin and Waite, 7200 becomes inoperable and the cause of the the present requirements of TS 3.12.

Sears Tower,233 Wacker Ddve, inoperabililty is not due to a common The proposed monthly surveillance l

Chicago. Illinois 60606 mode failure.

requimment of TS 4.5.A.1 would clearly NRC Pmfect Dimetor: James F., Dyer Ramedial Action 3 to TS 3.12.B specify the load to which the emergency provides a reasonable time to restore the dimel generators are to be tasted (90 to Maine Yankee Atomic Power Company, required 115 kV incoming line and an 100% of their continuous rating), while Docket No. 50-309, Maine Yankee inoperable emergency diesel generator - TS 4.5.A.3 adds a semi-annualload test Atomic Fewer Statim Ilocoln Canty, including the emergency buses and de at the maximum expected emergency M*A**

distribution cabinets sesociated with the loading values. The change to TS 4.5.B Date of amendment request: February emergency diesel generator--should is editorial only; no technical changes 17,1993 these sources becxime inoperable.

are made.

i I

25858 Federal Register / Vol. 58, No. 80 / Wed.seday, April 22, 1993 / Notices Based on thlis review,it appears that leak test areMad by SR [Survedlance operesor ao mhrusse to artart at least one the three standards of 10 CFR 50.91(c)

Requiremant) 4.1.3.5.h2 does not a5ect the CRD [Contml Rod Drin) pump tf there is m utisSed. Detsfen, h NRC sta5 rehabWty of the check valves because mm. then one toeperstas scrasa menmrulen:v pmbWty of es semn oa umulata check and reactor pressure is equal to a greater PNPo*es to determine that the valves is assured by 13 Section (0.5 which than 900 pstg. Contml rod scram am:ndment roquat involves no uiree that inseretco testing of the check occumulators and eaunst!stor check valm signi$ cant hazards conalderation.

,es comply with ASME Code, Section E are requimd to support the scram function Local Pubhc Document Rooat ta eddition, the proposed rhang== will not only at roector pressures less than 600 psig.

locofion: Wiscasset Public Library, High asect am chane= any plant hardware, plant To prevent approaching the 600 psig umit, Street, P.O. Box 367. Wlar==-d Maine design or pnest syssent operation frein that the ;roposed TS requine plant operators to 04578.

already descibed La the USAR [ Updated immediately scam the roector if there is Attorneyforlicensee: Mary Ann S*lety Analyets R*postl. msofore, the more than one hoperable scrum =~a--A=w Lynch, Esquire, Maine Yanka. Atomic proposed chan8ss do not modir or add any and these is not a CRD pump opersdng when Pow:r Comp *ny. 83 FAlann Drive, inidadng Pamneten est woul signiScantly meete;rma is ine than wo ps no incnese the probability or consequences of proposed reunoval of SR 4.1.3.5.h2 not Amsta. Make 04336 any socident prvrionsty analyend.

affect the rehab@ty of the sanm occumulator NRC Project Duector: Waltar R. Builer ne operatma of Nine Mile Putne Unit 2.

check vains because operehdzty of these Nta ara Mohawk Power Corporation, 6 aumdance mth the propond valves is assund by TS 4.03 which requirse

.'* mew m d '. rent and,88 68 MW d WM8dn6 Per h E CM* AM "Mm*"

wW n88 CM*

No.54-418. Nine Mus Padus a-sd.nt - any Cod..

N"'t.,r Station Unit 2. Osmgo arrua=a ev= baad The comtml rod systesn is da agaad to bring County, New Yark b

funenan of the scram the suector subcritical at a ree fast enough to Dots of amendmerrf agoest: April 7, accumuistor is to assist in conted rod prevent fuel thermal parameture inun 1993 insertion when reactor pressure alone is exceeding their respective saisty limite Descriptfort of amendrnent mquestr insufScient. Prompt operats action is stin during limiting plant events. The safety Ths Preposed Technical SpeciSestion mquimd a pannt cir~a=+== where function of the a ross occumunesars is to more than one scram accumulator is assist in anstvol rod haeroom when reecer (TS) changes would revise TS Sectf on 3/ inoperable and roector pressum might be pressure alcme is insufficient. The proposed 4.1.3.5, Control Rod Scram insufncient to screm the m cepebsty changes do not asset the capabihty of the Accumuletors." Action a.2.s for of the control rods to their sessey control rode to perform their safety functics Limiting Condition for Operation 3.1.3.5 funcima and provide proper reecuvny and petrride proper reactmey insertion would be revised to allow the reactor insertion within the required time wtil not b e within the requimd time. Therebre, the fuel operator 20 minutes to restart at leest affected by the

changse, cladding tneagrtry safety limit wW not be ons control rod drive pump if more than N ro additions to the lid 3.1.33 a5scted as the MCPR [Wntm== mucal P

action sin *=mant wW anse the scan h Radol Hrnit wm continee 2 be mot, ons accumulator is inoperable, the cxntrol rod anoociated with anI c8PabWty of au control rods and mduce the For the e stoned above,the proposed ini le eaumulator is withdrawn' probabihty of unnecessary fonted shutdowns ch=ng== do act involve a si inrant and the associated demands on seArty reduction in a i of c raector pressun is greater than or syseisms. N addmonal Im Actbn The NRC staff mnewed the equal to 900 psig. If reactor pressure is proposed (Les. thutdown if reactor pressure liranama's analysas and, beood on this less than 900 psig, the operator would is ness thes too psig) provides ir pensept review,it appears that the three be to place the reactor mode operesor arena to prenst nector operarse standards of 50.92(c) are satis $ed.

s la the shutdown position. The in a condithou where the arm==l= tors are Therefore, the NRC staff proposes to proposed changes would also delete the requimd to support the scram anrMan, determine that the amendment request a

survcinance requirement of n Removal of SR 4.1.3.5.b.2 does not eliminah hvolves no Me an' hazards 4.1.3.S.b.2, which requires scram teedng and maintenance of he scan consideration.'

accumulator che::k valve testing at least e%and LocalPubire Document Rooss val check once per is months. Testir,g of the valvw wm courttaus o be damr==treted by location: Ralerence and Doruma=ts a

scram occumnistor check valvw would the Ts requimd 157 !!nse rice Tating)

Department, Penneld Library State contmue to be demonstreted during Prograsa.

University of New York.Orwego,New each refueling outage in accordanca In addition, the proposed changse do not York 13128.

with TS 4.0.5. which requirse inservice represent a ch==r= to the plant or.the design Attorneyforfresnase: Mark J.

testing of ASME Code Class 1,2, and 3 bases as ducibed in the NMP2 INine Mins Wetterhahn, Esquire. Winston & Strewn, crsmponents.

Point Nuclase St=Hr a Unit 2] USAR. N 1400 L Stmet. NW., WaaMagton. DC Bosisforproposed no signif5cani Pr*Pa**d chanese de act modify ury 20005-3502.

hazards consideration determinotion.

equipment am do esy cmate any rw==mt NRC Profect Dareefor Robert A. Copre i

Initiating events that would cnete any new As required by 10 CFR 50.91(a), the w different kind of accident. As such,the Ni are Mohewk Fewer Corporation, liccnsee has provided its analysis of the last kidal rnrhns unused tr the dodgn No. M0, Nbe Ma Foht issus of no signi5 cant hazards is accident analyses am stin vand. The Nuclear Station, Unit 2. Oswego i

consid: ration, which is presented currest USAR wtB reenmin azuress with

' New York below:

mspect toits discuer60s of the licansing baste The operstice of Ntne MLie Fedet Umat 2.

evumes and les analyuls of plant responsa and Date ofnrnenament reguest. March l

in accordance with the proposed causeq-Therehre.the 22,1993 l

am:ndment. will not tavolve e =Lg=6Ar==+

do not crease the pass of a new Descriptiott of cumendment Mquest:

l incesse in the probability or r===rpa==r==

or t kind of accident frams any

'Ihs proposed amendment would revise cf en areMant provicualy ev=6.=A accident prertously evaluaasd-Section 6.9.1.9," Core Operating Linutts The proposed changes to Action a.2.a of he operation of Nine Mile Point Unit 2.

Report." of the Technical Specifications 12 (1.imi Condition im Opesetloal in accordance with the proposed (TS) to permit use of the SAFER /

l 3.1.3.5 pruri additional operuttag amendment, will not involve s =innieran, GESTR~LOCA methodo!UEI which has Sexibility where pient seisty is not as reductico in a margin of saisty.

immediate crecers and psevent pient At noneni reactor pressure (te.. greater been apprtrnd by the NRC Mor operation to a reeh-whom the then sao psis), reecear presem alone is occident analyses.TS Bases Section 3/

acemanlaar-e are regehod to arppset the ruf5cient m across the connot rods. The 4.2 would also be revised to refied the scram function. Removal of tl a la month proposed TS changes allow the plena addition of the SAFEPJGESTR-IDCA l

Federal Register / Vol 58, No. 80 / Wednesday, April 25. 1993 / Notices 25859 methodology as well as several editorial posalbuity of a new er different kind of are consistact with the requiretnents of changes.

• c:id*nt-NUREG 1434, Standard Technical Basis forproposed no s!gnifaatnf Thembn, opersuon r4 he W Point SpeciBcatians General Electric Plants, hamrds consideration defarmination Unit 2. in somedance with the pro d

BWR/6."

As required by 10 CFR 50.91(a), the

[,]*

Q %[8 Basisfor no s/gnl$ cant hazards cc erutfon detarmination:

licenree has provided its analysis of the prevbusly assessed.

)

issue of no signmeant har.ards ne operation of Nine MDe Point Unit 2.

As required by 10 CFR 50.91(a), the consideration which is presanted in scmrdance with the proposed lloonsee has provided 11s analysis of the below:

smendment, will not involve a s!gslScant issue of no dgnmeant hazards i

ne operation of Nine Mile Point Unit 2, reduction in a margin of safety.

consideration, which is presentsd s

in accordance with the proposed SAFElVCEST1t.LDCA is an tmproved below:

I amendment, wiD not involve e signi5 cant BTS lamargency core system!

ne operation of Nine MUs Point Unit 2, incesse in the probability or consequeocae evaluation methodology usse e in acx:ordance with the proposed of an accident previously evaluated.

realistic approech to calculate peak claddine amendment, w111 not involve a sign 15 cant SAFER /GESTR-IDCA uses a roahrtic temperaturea. IDCA events are analyzed increase in the probeMuty or conuquencme approach to caloilate peak c.! adding with naninal values k inputs and of an arrM= 4 Mudy evaluated, ternperstures wsth margin "L+=*=ted by corWarisma The Staff has periously ne purpose of the SIE IStandby Liquid statistical considerations. He use of SAFIR/ determined that SAFER GESTR-LDCA Controll Systani is to bring the reactor to and GESTR-LOCA methodology was approved by tastbodology conbr ne to 10CFR 50.44 med maintain it in a cold shutdown mndition the St 5 in their Safety Evaluation on Appendia K and may be used ta beu of the from normal power operaSons fonowing Amendment 12 to GESTAR D. In the Safety currendy reisrooced SAFE /REPIDOD failure to scram with the control rods event.

Evaluation, the Staff concluded that SAFER / methodology. Therefore, the peak clam 1"E inittstion of the 514 System is oct a CESTR.1DCA satisfies the requiremaats of

• tam r=tmtd d with SAFER /CEST11 procunor to any accidsut. Therefore.

10CFR 50.48 and Appendix K. N Staff are appibhla. N Sta5 etated that inoperability of the SIC System cannot stated that SAFIR/CESTR-LOCA is SAFER /CESTR-LDCA is noceptable so long incnese the prnhahitity of an accident acceptable as a basis br and referonos in as the material contained in SAFER /CESTR-previously evaluated. The SLC System wu hcenas opphcations so long as the matenal LOCA is applicable to the speciSc plant not da to provide shutdown capability i

contained in SAFER /GESTR.IDCA is involved.

during T10NAL CONDIT10N 5. Since applicable to the specific plant involved.

Niagara Mohewk has reviewed CESTAR H the Sir Syseen's purpces is ao shut the Niagara Mohawk has cxmSrmed the and confirmed the ficabilhy of SAFER /

reactor down following a fedure to saam appilcebility of SAFER /GESTR.LDCA to GEST 1t.LOCA to

. Thus, the proposed during power operation the USAR [ Updated NMP2 [Nine Mile Point Nuclear Stetion Unit changes do not affect the beets ite any Sahty Analysis Re I tvise no crsdtt br

21. The SAFER /CESTR-LOCA mathadalogy Technical Saaan=H<= and prerbuely the operability of SIC System la conservettvely cxiculates peak et.Mt established seJety limits remais vahd.

OPERATIONAL CDNDITION 8. Therebre, temperaturw such that USAR IU Rereks% the operation of Nine Mile Point the SIE Syveem not being operable in Sehty Analysis Report] accident analysee Unit 2,in accordents with the proposed OPERATIONAL CDNDIT10N 5 will not remain bcunding for the new methodology.

rh'afas, will not tardvs a sigm15 cant involve a of ret Amet incrosse in the Therebre, operstion of Nine Mlle Point Unit reduction in any margin of sahty.

consequencas of an en:1 dent previoudy

2. in ocxx rdance with this proposed change, The NRC staff has reviewed the evaluated.

will not involve a signiScant increase in the licensee's analysis and, based on this The operation of Nine Mile Point Unit 2, probability or consequencme of any ecz:ident review,it appuers that the three in amordance with the proposed previously evaluated.

standards of 50.92(c) are entisSed.

ameodent, will not omw the poss!bluty of The operation of Nine Mile Point Unit 2, Therefors, the NRC staff proposes to a new or differiet kind of accident frten any in acx:ordance with the proped determine that the amendment request ecddent pmeanly N c

amendment will not ceste the possibility of involves no aI RIficant hazards

• "9"*#

• ' ' "'

• E I S

change in any syveem's enn%uration and no e new or different kind of accident from any consideration-acddset previously evaluated.

new moda of opernuom we introduced, no SAFER / GEST 1t-LOCA uses a reahstic M

"" kom SIC System's only is to mitigate the anpitcation approach to calculate peak location: Reference and Documents mnesquenew of a to scram during c[edding temperaturw with marsta Department, Penfield Library State power operation:it neither causes nor substantiated by stettstical ccmsidersticos.

University of New York Oewego, New prevents an accident eum occurrics.

ne peak cladding tem tures calculated ' York 13126.

Furthermom,in OPERATIONAL with SAFER /GESTR ere in encordene:o Afrorneyforlicensee: Mark J.

CDNDf710N 5 the SIC Syveem has ao

• n*l "d funman nefon this change with Appendix K and rumsin tetrading br Wetterhahn, Esquire, Winston & Strawn.

T all operating conditions and evotations. The 1400 L Street, NW., WaaMa='an - DC win eat crests the possfulity of a new or um of SAFER /GES11L40CA maahadc4agy

~

"" ""7 20005-3502 t

12 CESTARIL P'8 opera Nine Wils Point Unit 2.

tamrporation of SAFER /CESTR4DCA le Mohawk Power Corporation, in acxxirdancs with the proposed only a change to analytical techniques and Doc No. 50 410, Nlme Mlle Point

""""d"""' *ill " "*I ', T "~"'

does not affect plant operating seodos or any Nuclear Cf = Ham Unit 2. Wo reduatoo in a energin of safety ne purp se of the sir System is to bring systern operaticot. nua, the proposed change County, New York the reactor to and maintain it in a mld does not adversely a5ect the response of any mmana-a* or system to prurtously analysed Date of amendznent request. April y, shutdown r=dvlan from nmnal power ocxdents. The moponse to previously 1993 openekma bliowtag a kihns to scum evaluened accidents r==ains within Description of amendment request.,

during poweroper=nana Infume f the o

previously asesesed 1 knits cd tasapersture and The proposed Technical SpacMention SIC System is not to term'a=*= en preneum. Further, all sahty-nlated systems (TS) changes would revise TS Sectico inadvwwnt aMr= Hey 05RADONA1.

nw SDM Sh aTM.

g[f*8 3.1.5, ** Standby Liquid Control System "

ga n and g

to remove the t for the La advwnly 3,,,=h= man wtth T=rh= W1 2

a Standb Liquid 1 System tobe synr=Ha== and brocmdural controta, wul 7

affect a change, assuring that the des 6gn espahibtles of those systems and operabie in Operational Condition 5 assers that as inadvenent cztricultry event

=y - ~ em no,6.n-w in a mannac (Refueling) with any control rod will out ocxzr durie6 re*=Hwg ap=~'* In not pnyvioasty assessed so sis to crease the withdrawn.'nne proposed TS changes

N

the EPS TE==mr Pne=Ma=

258G0 Federal Register / Vol. 58, No. 80 / Wednesday April 28, 1993 / Notices System) and Control Itod System, which are condidons with other than a 24-hour run North Atlantic Energy Service uttemely reliable, will provide protection in provides the necenary initial cnnditions ke Corporation Docket No. 5M43, the unukely event that an inadvertent the IDOP testing. Diesel peerstar design See. brook Station, Unit No.1, cnticality does ocrur. Therefore. this chang

• and function remain as previously analyzed.

Rockingham County, New Hampahin will not involve a signiacant reduction in a Diesel generator response during accident Date of amendment request: February margtn of se ety-cnndluons an not anected by bu changeac s

26,1993 The NRC staff has reviewed the nefore, no sign 15 cant incrase in the licensee's analysis and, based on this probabWty or consequences of a scrident Description of amendment request:

mytow,it appears that the three previously evaluated results fran thne D* Proposed amendment would modify Technical Speciacation (TS) 3/

]

standards of 50.92(c) are satisEed.

chaps, nerefeti, the NRC staff proposes to The operation of Nine Mile Point Unit 2, 4 7.3 applicable to the primary detennin:s that the amendment request in sa:ordance with ths pmpond component cooling water system.

l involves no significant hazards amendment, will not create the possibility of Limiting Condition for Operation (LCO) i a new or disent kind of accident from any 3/4.7.3 would be revised to require one consideration, Loca1Public Documeni11oom accident previously evaluated.

operable pump in each primary This request dou not invoin a physical component cooling water (PCCW) loop location: Reference and Documents chany in any rystem's canaguration and M vics two pumpa.b amendment also D:partment, Penfleid Library, State

• d" of opastion an introduced.

would delete Actions b. and c., and University of New York. Oswego, New new changw win om nduce my requind Surveillance Requirement 4.7.3 b.2 York 13126 which would no longer be applicable

• " 8 Attorneyfcrlicensee: Mark J.

Wty di h

W with the requirement for one operable Wetterhahn,Lsquire.Winston & Strswn, proposed wul estabush b ume lamal PmP Per loop.

1400 L Staet. NW., Washington, DC condmons u thoes requimd by the curnat Basis forproposed no significant 20005-3502.

Technical SpeciScation. Testing of the dieul hazards consideration deternunation:

APC Project Director: Robert A. Capra genenters in accordance with thm chance As required by 10 CFR 50.91(a), the will anure that diesel generator responses Nia6are Mohawk Power Corporation, resin as previously analyzed for au licensee has provided its analysis of the Docked. No. 50-410, Nine Mile Point requimd conditiona. Therefore, thm changes issue of no significant hazards N: clear Station, Unli 2, Oswego do not create the possibility of a new or consideration.N NRC staff has County, New York dinerent kind of accident from any reviewed the licensee's analysis against Date of amendment request: March Previously evaluated.

the standards of 10 CFR 50.92(c). The "

The operation of Nine Mile Point Unit 2 NRC staff's aview is presented below.

I 30,1993 Desaiption of amendment request:

in acmduce with the propond A. He changes do not involve a amedmet, wm wt inmin a signiacant significant increase in the probability or The proposed Technical Specifications reduce a in a margin d safety.

consequences of an accident previously (TS) changes would revise TS Anowing the diseel genenton to reach fuH evaluated (10 CFR 50.92(c)(1)) because 4.8.1.1.2.e.4 and 4.5.1.1.2.e.8,"AC t*mpwatun addons by wher dan de 2& even with the proposed LCO change, Sources - Operatin." The current TS require that a simt ated loss of offsite f"'

• • 'd two operable PCCW loo s would be

'I a.a reguffed and the single allum criterion power (IDOP) test be performed within uusfy b intent dconducung h test still would be met. The PCCW system is 5 minutes of completing a 24. hour full fonowing b 24-hour load tut. These designed to perform its safety functions load emergency dimi generator test chance wul not rwult in any reduction in assuming a single failure of any run.ne proposed TS changes would teeung and wW nm aned diesel pontor separate the requirements for the 24-reliabWty. As propoeod, the chang =s wi!!

component. This is accomplished with hour run from the LOOP test.

edoquetely d=-trete the dimi pnerator's two independent redundant loops. Each Basisfor proposed no significanf fwe=1 capability at full loed temperature of the PCCW loops contains two 100%

hazards considerotion determination:

conditions, thus ensuring the design margin capacity pumps. De required safety As required by 10 CFR 50.91(a), the of safety in the diesel generator's abiHty to functions can he accomplished with one licensee has provided its analysis of the start and accept the required loads in the pump operating in one PCCW loop.The luus of no sign 1 Scant hazards Preschd time. Therelare, the changw second operable loop with at least one wW nm inmin a signiacant nduedonin a operable pump provides the consideration, which is presented margin of safwy.

ndundancy necessary to meet the single below:

The operation of Nine Mile Point Unit 2 The NRC staff has reviewed the failure criterion. De proposed changes in acmdance with the proposed licensee's analysis and, based on this to the action statement and the amendment, will not invoin e O "i"""'

review,it appears that the three surveillance requirements merely reflect f

incram in the probability enomqueo "

standards of 50.92(c) are satlafled.

the proposed change to the LCO.

Therefore, the NRC staff reposes to B.De changes do not ::nate the of an accident previously evaluated.

c," ggt N [gh M determine that the amenbent request possibility of a new or different kind of i "*

Specificauon 4.8.1.1.2.e.4.a) and.b) involves no significant hazards accicent from any accident previously immediately following the 24-hour lead eset consideration.

evahated (10 CFR 50.92(c)(2)) because demonstrates that the diesel paarstar can focolPubBc Document flo$m the PCCW system would continue to meet the single failure criterion. De start and accept the required loads in tbs loca&n Reimnce and Documents preseibed time when the diemi peerstar is Department, Per.Seld Library, State Proposed chan do not affect the orby e

ty o ed fN Pen an a

niv ty of New York Oswego,New g

pn M

18 (8 pew drupondag to a W&e affect the operational characteristics of Power as assumed in the wr4d-at analysis-AttorneyforScanses: Mark J.

the facill Bec== the purpm of periming the WOP Wetterhahn, Esquire. Winston & Strawn, C. The chan do not involve a 1400 L Stnet NW., Washington, DC significant red ction in a margin of e

t d to @

cu ca 20005-3502.

safety (10 CFR 50.92(c)(3)) because the the dieaal generator et full iced temperature conditions establishing fullIced temperatum ABC Project Director: Robert A. Capra proposed changes do not affect the

s Federal Ragletar / Vol S8, No. 80 / Wednesday, April 28, 1993 / Notices 2S861 manner by ~which the facihty is operated The NRC staH has reviewed the

c. m proposed amendn.ent rd not or involve equipment or features which hcanne's analysis and, based on this indw a sgnifmt mduction in Ae amesin affect the operational charactaristics of review,it appears that the three 8/ 8"l7-the facility. Based on this review, it standards of to CFR 50.92(c) are n ed the pmpom o

cg appears that the three standards of satisfled. Herefore, the NRC staff di pump fuel oil quauty as the old to CFR 50.92(c) are satis $ed. brefore, proposes to determine that the ASn( n=rme=M-Dienkare pump the NRC staff proposee to detsrutine that the amendment request involves no rollabilit'y and operability will not be amendment request involves no s6gnincant significant hazards consideration, degreded. Therenze. the proposed hazards masideration.

bcul Pubhc Document Room amendment does not involve any reduction localPublic Document Room in the of utety Centar.

locotton: Exeter Public IJbrary,47 Front The staff has reviewed the y

g

Couage, Street. Exeter, New Hampahlre 03833.

574 New on Turnpike, Norwidi, 33,,,,,,.s analysis and, based on this Attorneyforlicensee:'thmas Dignan.

review,it appears that the three Connecticut 06360.

Esquire. Ropes & Grey, One standards of 10 CFR 50.92(c) are International Place, Boston Attorneyfor licensee: Gerald Garfleid, ud: Bed. Thefon, b NRC staH Massachusetts 02110-2624.

Esquire, Day, Berry & Howard my proposes to datartnine that the NRC Project Director: John P. Stols Place, Hartford, t%nnardcut 06103-amendment mquest involves no ort N

nergy Cmpany, M C Pwject Director: John F. Stols

$'p"$1f$nt Room

• Nuclear Power Station. Unit No. 3 New Northem States Powerrw.pany, locet on Minneapolis Public1.ibrary, Technology and S ience Department, London County, th=-edene Docket No. 50 283. Monticeuo Nuclear c

Dofe of amendmen.t reguest: Aprill, Generating Plant, Wright County, 300 Nicollet Mall. Minneapolis, gjaa oga Minnesota 55401 1993 Attorneyfor licensee: Gerald Charnoff, Description of amendment request:

Dote of amendment request:

Esq., Shaw, Pittman. Potts and The licensee has requested that December 31,1902 Trowbridge,2300 N Street NW, technical specifications be changed to Description of amendment request:

Was

, DC 20037 permit prelubrication and warmup of ne proposed amendment would revin NRC Director:L B. Marsh tmergency diesel generators before Surveillance Requimment 4.13.B.1.e.

Statms Fnnr Co y,

surveillance testing,

" Fire Suppression Water System." by Docket No. 30 283, Montipla Nuclear Basisforproposed no significant changing the American Society for hazards considemtion determination:

Tating and Matarf ala (ASDC Generating Mant Wright County, As required by to CR 50.91(a), the specification which is followed when licansee has provided its analysis of the performing requimd sampling of the Date ofaemandment request:

issue of no sign 1Beant hazards diesel fire pump fuel oil supply, December 31,1992 consideration, which is presented Basisforpm no significant Description of amendment request:

below:

hasards emtion determination:

ne proposed amendment would revise h proposed changes do not invoin a As required by 10 CFR 50.91(a), the Surveillance Requirement 4.13.B.I.e, sign 1 Scant hazards e=M-

"~ based on licsases has pmvided its analysis of b " Fire Suppression Water System," by the following:

1. N miocation of the botnote to Wue of no aIgn hg chan ina the American Society for i

considention, which is presented Testi,n8 tad Materials (ASBC encrenpass oil" Eof diseel surwittanc,

,p,c f} cation which is followed when

, equi,emois.

cr m ihe betow.

probability or nome of an arew t

a. N proposed amendnaant wG act Pericming requind sampli.ng of the n

previously eval famin a signifsomat increase la the diesel fim pump fuel oil supply.

Each diesel's primary function la b probahWry or acne of as wane Basisforproposed no sigruficuni provide power to mitigate the enas prerbusly evul hasards consademtion determination:

of an accident when offsite poweris b diesel fke pump ea As requind by 10 CFR 50.91(a), the nerobre, the probability of an acddent le e-m*= to be used is not a in any lie =name has pmvided its analysis of the not affected Prelubing is p.a-sd to accident analysis and this change to issue of no significant hazards decream engine wear which wiu extend primardy administrattee in aneurs. Use of the consideration, which is presented diesel life. Ultimetsly, prol reduces the proposed ASTM aparmenH=a will provide below**

rumter of mainten-a thereby the same novel of assurance of diesel fire

,,3e proposed amendment wd not imreasing the availabiltry of the diesels, pump bel all lity as the old ASTM invohw a significant increase in the

2. The pmposed changes do not criste the speciScations.

I nas pep reliability possibility of a new or differest kind of and opernbuity will not be degraded.

probo6dfryor7jyences of ca occident acddent from any previously evaluated Denkre, this amanAmmat does not Lavolve P'N di[sel Bro pump samp Den are no new failun mad== associated an increase in the pmbabuity or speciacation to be need is not e or in any with the poposed change. 51oco the plant cxmeegnaarna of any previously analyzed occan, moeiyrne and this change is will continue to operste as da=4n=d, the accident.

primarily administranve in nature. Use of the Proposed changes will not modify the plant

b. N proposed amendment wW act pmposed AFIM opaciScations will provide response and is not conadered a new creces al,e par *fty ofa new or dWwont the same level of assuranca of diesel are acx;ident. -

ifad of a-la=')hus any "*"'

fuel oil as the old AFIM

3. N peoposed rhanran do not involve a previously analysed.

Scottons.

I Ere pump reliability signiacant mduction in the n of safety.

No safety-related equipeneet, and opersbuity will not be degradei ne pmposed changes do not any funr+ inn or plant operations (other the nerefare, thie==aaA=aat does not lavolve adverse impact on the margin of safety methodology for drewing the fuel all semple) an increase in the probabuity or afbrded the diesel gensretore his change will be altered as a resuh of the peoposed cxmeequences of any previously analyzed will prevent sagine weer and attimately emendment. Nreken, the proposed accident..

extend the life of the diesela. h operabt!1ty amendment does not in any way create the 6 Nproposedamendment wGnot of the diesels is not dependent uprus the poseihility of a new or diflerent kind of create the poemdhdhry of a new or different palube system and therebre, tbs maryta of r+ dant froca any eMdane previously ifad of =*4==* frees any ocddent safety is not aSected, evahased.

pmviously analysed.

25882 Federal Register / Vol. 58, No. 80 / Wednesday, April 28, 1993 / Notices No safety-related equlpment, se his condusion is based on the ocepynents in b pool ne use of the i

function, or plant operations (otha

_.no consideration that 6 isolation signal change deanup line serves to lower h pool water methodology for drawing the fuel oil semple) from level 3 to 2 does not degrade the level which deceases the loading during a will be altend as a ruult of the proposed operation of any equipment or tyrtem.

IDCA or safety /rellaf volve operation.

amendment. Therefore, the proposed Purthermore, the Agastat relays and level

3. Involve e reduction in the margin of amssdment does not in any way crests the switches to be used for the level 2 isolation safety.

)

pc'sibility of a new or dderent kind of signals are identical in design. material, and The NRC provided their review of accident fmm any accident previously construction to those curnntly used for level containment isolation signals in Section 6.2.a svaluated.

3.

of the Safety Evaluation Report (NUREG-

c. ne proposed amendment wi# not m modiacation does not alter or decode 0776). Reactor vezel water level 2 wu found 1

involve o sigruficant reduction in the margin the abihty of the two cleanup line valves to to be acceptable and therefore deSnes the i

of sofer7 isolate the cleanup line following those basis far the margin of safety.

Use of the proposed ASTM rpeciScations LOCAs inside mutainant that require it is therebre conduded that since the j

will provide the same level of assurance of isolation. The isolation rystem design wiu proposed modiScation changes a dinal fire pump fuel oil quality as the old always result in its actuation at level 2. The containment teolation setpoint to a ASTM speciScations. Dieul fire pump design requirement for isolation at level 2 previously accepted value, a reduction in the rallability and operebility will not be remams sati Sed and in compliance with margin of safety will not occur.

dtgreded. Therefore, the proposed NUREG4800 (Standard Review Plan) and The NRC staff has reviewed the amindment does not involve any reduction NUREG 0776 (Safety Evaluation Report.

hcenam's analysis and, based on this in the margin of ufety.

SSEE The NRC staff has reviewed the During transients that twult in reectcr review,it appears that the three standards of 10 CFR 50 92(c) are ws mls 2

liccusee's analysis and, based on this g

d pb2 satiaBed. &nfore, the NRC staff I

review, it appears that the three be used, if necmuery, to lower h proposes to determine that the standards of to CFR 50.92(c) are suppression pool water level Manual contml amendment request involves no satisfied. Therefore, the NRC staff s gjter pump has not been changed.

sf gnificant hazards consideration.

proposes to determine that the operation of the cleanup line following thes*

LocalPublic Docurnent Room amendment request involves no transients is penninible becauw a LDCA location:Osterhout Free Library, significant hazards consideration.

Inside contai==nt has not occuned.

Reference Department,71 South IocalPublic Document Room since the cleanup line isolation signal Franklin Street, Wilkes-Barre

'g""a in compliance with the design location: Minneapolis Public Library.

Peu Iv i 1870 bed El e,

{u Att rneyf tlicensee: Jay Silberg, Technol and Science Department, 300 Nicol et Mall, Minneapolis, accident have not been increase,1.

Esquire, Shaw, Pittman, Potts and Minnesota 55401 The probability of a malfamction of Trowbridge,2300 N Street NW.,

Attorneyfor beensee: Gerald Charnoff equipment important to safety has not been - Washington, D.C. 20037 Esq., Shaw, Pittman Potts and inmued by b modificatim.ne relay NRCriefect Dinctor: Charles L Trowbridge,2300 N Street, NW, room panels, where both the level 2 & 2 Miller Washington DC20037 relays a located. will hm minor changes NRC Profect Director: L B. Marsh to the internal wiring. Seismic qualisation Power Authority of The State of New of b equipment will be unaltered. Valve York, Docket No. 50 286 Indian Point Pennsylvania Power and LJaht operation ren ina -ba -d except for the Nuclear Generating Unit No. 3, Company, Docket No. 50-344, level of roectcr vessel water that initiates a we,a e " County, New York Susquehanna Steam Electric Station, cont =Inmant isolstico signal Unit 2 Luzerne County, Pennsylvania The loeding on the suppreselon pool Date of amendment request: March structure, and submer.ged com$ents in the 12,1993 Date of amendment request: April 5, pool, following safseyhollef va operation, Description of amendment request:

1993 has not been increeeed. Since higher weter he licenses commenced operating on a Descrption of amendment request:

1,,els rwult in higher toeda, the loeding 24-month fuel cycle,instead of the The proposed amendment would revise following the modiScation would either be previous 15-month fuel cycle, with fuel tbs Susquehanna Steam Electric Station less than or equal to the existing loading cycle 9 Fuel cycle 9 started in August (SSES), Unit 1. Technical Speci5 cations depending on whether the filter pump is gfgg og in diSestion dow not rmit in an OPmh m a 24 tnonWo. b i

sup ress o pool cle p line valves HV 15766 and HV 15768 fmm reactor I""*" I" C"*'9"*C" ""'*1"8 8

"" N

=*theaa of equipment impcrtant to Specifications (TS) arrsmdment to i

vessel low water level 3 (+13,*) or high safety. ne consequences of falling to teolate incorporate the changea listed below:

drywell pressure to reactor vessellow one,.Inmant following a 1DCA laside (1) he licznsee posed changing wstar level 2 ( 38') or high drywell cone.inm.nt or proven the suppressica the frequency of ressure water fire Pressure. The same change was pan its are e t g (speciBed in hrotection system tSection 4.12.A.1) to accomm appmved for SSES, Unit 2.by try the mah=H=

l Amendment No. 92, issued on October

2. Creete the possibility of a new or op(etion on a 24-month cycle.

29 1992 different kind of accident frcen any 2)ne licensee pmposed changing I

j) asis /o previoudy mlueted.

Th*

• dl8C*'i " '8"' 'P, termin.1. on the frequency of fire pump dimi engine hazards cons on d on'-

existing releys to receive an input frosn a testing (speciBed in TS Section l

As required by 10 CFR 50.91(a), the level 2 switch. These re are identical to 4.12.A.2) to strommodate operation on l

licensee has provided its analysis of the those used to receive the 3 input signal a 24-month cycle.

issue of no significant hazards The actuation logic remains single fall" (3)The licensee proposed changing consideration, which is presentad A new possibility has not been coated the fmqu of electrical tunnel. diesel below:

thoes IDCAs inside containment that ne propowd change does not:

requim isolation to occur without teolatice of 8"erstar and containment fan

1. Involve an increase in the probability of the cleanu line, cooler fLrs protection sprey and/or occurrence or the consequences of an The tion does not create the sprinHar system testing (speciaed in TS cccident or ma th*= of equipment possibility of a malfunction of the Section 4.11.B.1) to accommodate important to safety as previously evalusted, suppession pool structure and submerged operation on a 24-tnanth cycle.

I

e Federe! Registir / Vol. 58. No. 80 / Wednesday, April 28, 1993 / Notices 25863 (4) The licensee proposed changing Fire Protection System and Fire Barrier Training of Nuclear Plant Personnel) the frequency of Ere detection system Penetration Seal inspection! only increa**

except for the SRO license requirement' testing (specified in TS Section the surninance intenal to be consistent with Basis for proposed no sigmficant

• • d 4.12.D.1) to accommodate operation on P*"g"**

hazards consideration determination:

a 24 month cycle.

adversely a5ect ryetem operability, the As mquired by 10 CFR S0.91(a), the (5) The licensee proposed changing proposed chanan do not cnete se licensee has provided its analysis of the the frequency of Sm home station testing poutbiuty of a new or diSerent kind of inue of no signiBeant hazards (specified in TS Section 4.121.1) to accident imm any previously analysed.

consideration, which is presented accommodate operation on a 24-month (3) Does the proposed amendment involve below:

cycle a signiScant reducuan in the mar 51n of Consistent with the criteria of to CPR (6) The licensee osed chanpng safety?

50 92, the enclosed application is Judged to the frequency of protection Reeponm:

involve no signincant hazards based on the sIstem testing (specified in TS Section surveil { Posed Angu Ito extend the following 'information:

test intervals far High Prmsure (1) Does the reposed license amendment 4.12.G.1) to accommodate operation on water Fire Protection System, fin Pump involve a sign cant increase in the a 24 month cycle-Diesel Engine. Electrical Tunnel. Diesel probability or consequences of an accident (7) The licensee proposed chandrig Generator Building and Fan Cooler Fire previously evaluatedt the frequency of are barrier penetration Protection Sprey and/or Sprinkler System.

Response

sealinspection (specified in TS Section Fire Detection System. Fire Hose Station. 00:

ne proposed changes do not involve an 4.12.C.1) to accommodate operation on Fire Protection System and Fire Barrier increase in the probability or consequences a 24 month cycle.

Penetretion Seal ins

- nl only extend the of a previously analyzed accident because These Proposed chan8es follow the sumiUare inten. Evaluation of es past Shift Supervisors and Reactor Operators will performance of the equipment indicates that still be requtrod to maintain a current SRO guidance provided in Generic Letter 91-the effects of extending the surveillance test leenior reactor operator) license. This ensuns

04. " Changes in Technical Specification intervals would not involve a signiScant that shirt activities are directed by persons Surveillance Intervals to Acrommodate reduct2on in the margin of safety. Thenfon, holding SRO licenses. no Shift Supervisors a 24-Month Fuel Cycle.** as applicable.

the proposed changes do not involve a will report directly to an individual with an In addition, the licensee proposed signiScant reduction in the margin of safety.

SRO license and qualiacations of an reformatting TS Ssction 4.12 in its The NRC staff has reviewed the

" Operations Manager" per ANSI N18.1 1971.

entirety and pro osed several licensee's analysis and, based on this The Operations Manage wiu continue to be a

edgenb a ed d

administrative c angee for clarity.

myiew,it appears that the three g.

d at BasJsfor proposed no sJgnificant standards of 50.92(c) are satisfied.

create the possibility of a new or different hazards considemtion determination:

Therefore, the NRC staff proposes to kind of accident from any accident As required by 10 CFR 50.91(a), the determine that the amendment request prwtously evaluated?

licensee has provided its analysis of the involves no signiacant hazards Raponm:

issue of no signincant hazards consideration.

The proposed changes do'not enate the consideration, which is presented Local Public Document Room Possibili e new or different kind of below.'

location: White Plains Public 1.ibrary.

• CCid*nt any occident previously beca d

Consistent with the criteria of to CFR 100 Martine Avenue. White Plains. New,",,

o or l desi n r ter 50 92, the enclosed application is judged to York 10601.

Operators and Shift Supervtson an still involve no signiScant hazards based on the Attorneyfor licensee: Mr. Charles M.

required to maintain a knowledge of curnnt following information:

Pratt.10 Columbus Circle. New York.

plant conSguration and operation through (1) Does the proposed licene amendment New York 10019.

SRO license requahScation training This involve e signiScant increase in the NRC Project Director: Robert A. Capra ensures that shift activities will be directed probability or consequences of any accident by persons holding SRO licenses.

previously evaluated?

Power Authority of The State of New Additionally, the Shift Supervisors will

Response

York Dockst No. 50 284,ladian Point sport dinctly to an individual with an SRO Since the proposed change to extend the -

Nuclear Generating Unit No. 3, licena and queliacetions of an "Oparations surveillance test intervals for High Pnseure Westcheeter County, New York Mana8er" per ANSI N18.1 1s*1 and the Water Fin Protection System. Fire Pump Operations Manager will continue to be a Diesel Engine. Electrical Tunnel. Diesel Date of amendment request: April 5 knowledgeable and qualified individual.

Generator Building and Fan Cooler Fire 1993 (3) Does the proposed amendment involvo Protection Sprey and/or Sprinkler System.

DescriptJon of amendment request:

a signiscant reduction in a margtn of safety?

Fire Detection System. Fire How Station. CDs Ths hcensee has requested an Raponn:

Fire Protection System and Fire Barrier amendment to the Technical ne proposed amendment does not involve Penetretion Seal inspection done not involve SpeciScations (TS) to revise Section 6.0 a signiscant reduction in a margin of safety changes in equipment / system functione and (Administrative Controls). Specifically, beceum Shift Supervisors and Senior Reactor does not adversely affect system operability' the plant staff"9uirement (sped $ed in Openton wiH stiu be nquind to matne the proposed change does not involve a significant increase in the probability or TS 6.2.2.1) would be revised to remove - a current SRO license. This ensures tha activities an dincted by persons holding consequences of any accident previously the condition that the operations SRO licenses. Additionally, the Shift evaluated.

manager must hold a senior reactor Supervisors will report directly to an (2) Does the proposed license amendment operator (SRO) license and nplace it individual with an SRO licena and caete the possibthty of a new or different with the requirements that the assistant qualiScotions of an ** Operations Manager" Lind of accident from any previously operations manager must hold an SRO ANS! Nig.11971 and the Operations evaluated?

license and that tb operations manager will matinue to be a knowledgeable R*8ponn:

must hold or have held an SRO license and quahned individual. Tbeen changes are at the facility. In addition, the P ant staff expected to enhance 6e Open@ns Since the proposed changes Ito extend the l

Managw's abinty to effectively carry out the surveillance test intervals for High Proesure qualincations ulroment (speciBed in primary responsibilities of that position, and Watm Ftre Protection System. Fire Pump Diesel Engine. Electrical Tunnel. Dieml TS 8.3.1) would modined to mflect to have en ovwell positive effect on the safe Generster Building and Fan Cooler Fire that the operations manager shall meet and of5cient operation of Indian Point 3.

Protection Sprey and/or Sprinkler System.

or exceed the quali8 cation mquimments The NRC staff has myiewed the Fire Detection System. Fire Hose Station. CDs of ANSI N18.11971 (Selection and licensee's analysis and, based on this m.

25864 Feders! Regiefer / Vol. 58, No. 80 / Wednesday, April 28, 1993 / Notices review.11 appears that the three 3, Involve a signi8 cant reducdon in a CENE-y7006 2 A nassesed the impact of standards of 50.92(c) are satisSed.

margin of safety.

changbg ECCS and RCX: surveillance test intervals (STis) and allowed out-of-service Therefore, the NRC staff to The circuitry can only create an

""** IAors) on ce w fauun frequency.

determine that the amen ent request inadvertant trip which is bounded by a involvm no sign 1Sunt hazards required trip or failure to trip which is

• $*p po ddjn h have consideration.

acceptable because no credit is taken for an insignent effea on the W7 fanum Iocal Pubhc Document Room the taip in accident evaluation.

frequency, and when all contributing factors location: White Plains Public Library.

Therefore, the proposed amendment an considered. the net impact of the 100 Martine Avenue. White Plains. New will not reduce the inargin of safety, proposed rune== is to improve plant safeey.

York 10601 Based on this review,it appears that Nu generic analysee have been shown to Attorneyfor heensee:Mr. Charles M.

the three standards of 10 CFR 50.92(c) be appucable to the HOGS es indicated in S*ction mlof thelicensee's A 1,1993 Pratt.10 Columbus Circle. Now York.

are satis $ed. Therefore, the NRC staff

'ubmittall. Since the pro changes do New York 10019.

proposes to determine that the nm @

y anect es W7 fanun n

MCProject Director: Robert A. Capre amendment nquat involvm no frequency and han a beneficialimpact on Public Servics Electric & Gas Company, signiDeant hazards consideration, plant safety when all factors are considered.

local Public Document Room the proposed chanses wu! not signif!cantly Docket Nos. 50 272 and 50 311. Salem location: Salem Free Public libruy,112 incrosse the probabuity or consequences of a Nuclear Generating Station, Unit Nos.1 West Broadway, Salem, New Jersey previously analynd exident.

and 2. Salem County, New Jersey

2. Will not create the possibility of a new 08079 ct ditforent kind of natdant trem any Date of amendment request: Vebmary Attorneyfor Mcensee: Mark 1 want pnvimaly evaluered.

Wetterhahn. Esquire, Winston and Incnasing the ACTS and STis for the ETS 5.1993 Description of amendment request:

Strewn 1400 L Street N W

""d # "'*"" d " " ' "h** **

The proposed amendment revises Salem We ehlnhton, D.C.,205053502 n

a mersucy mm Whn8 Nuclear Generating Station. Units 1 and NRC Profsct Dfrector: Charles L.

Wm M NCW com W" 2 Technical Speci6 cations 2.2 Limiting gi,*

mung syste (RCIC) om inmln any type Safety System settings and 3/4.1.1 Raectnr Trip S em Instrumentation.

Public Service Electric & Gas Coenpany, Cd*"',

QDy The proposed eliminates the Docket No. 50 354, H Creek these chanses. The proposed chares Steam /Feedwater ow Mismatch and Generating Stados, County, New thenfore will not cnate the possibility of a Law Steam Generator Water Level Jerse7 new or di5erent kind of accident from any Reactor Trip due to the installation of Date of amendmer.t request: April 1.

eccident previously evaluated.

3. Wul not involve a signiacant nduction the digital feedwater control system ggg3 In a marsin d sah incorporating a median signal selector.

Descript on of amendment request ~.

The licensee's proposed amendment p$*,QcYtasMaadon ed har s

er n d er ation*,

would extend the surveillance test to potentially affect core damage frequency As required by 10 CFR 50.91(a) the intervals and allowed out-of-service through their impact on the WW failun licensoo has provided its analysis of the times for the emergency core cooling frequency. As requested by the BWR Owners' issue of no signincant hazards system (ECCS) and reactor core isolation Group. GE phed analyses to evaluate the e5ect of the proposed chanses on the W7 cnnsideration. "We NRC staff has cooling (RCIC) sydam actuation failum frequency. & NRC staff has mvimed 6e hcensee's analysts against instrumentatien. This change is based reviewed and approved the generic study the standards of 10 CFR 50.92(c). The

,,3 % t*d informadon contained b

3 d

NRC staff's review is presenated below:

in the General Electric Company (GE)

GENE-y406-2-A and has MD **with

1. Involve a sien*=nt increase in the 36P A. Parts do oNignific th

^

1988) and CE LTR CENE 770-06 2 A fanure frequency. Furthermon. the overs!!

RemovbmviE the steam flow / feed Gow (December 1992).

lewl of plant safety wt11 be improved by the us posed changes as indicated in Section U mismatch and low steam generstor level y,,,,g,f,orpr,opose,d no signif,', cant Qthe licensn's Aptti1,1993 submittall. A

\\

Basis s

reactor trip does not incnase the

,,,g,,,,,,g,,,,,

,g;,,,

niant specise evaluedon was conducted for probability of an accident previously As required by to CFR 50.91(a), the indicated in Section m (of the evaluated because the trip does not licensee has prtwided its analysis of the IKES. u,s April 1.1993 submittall wh 33c,,,,,

cause an accident: therefore, the tri can issue d no sign cant hazards demonstrated applicability of the generic not effect the probability of an acci ent. consideration, which is presented conclusions to HCGS. It can therefore be The consequences are not ekted below:

concluded that the propceed changne wiu not because no credit is taken for the trip a

as, punuant 2 te m2, signincandy nduce a mergin d safety.

when the accidents are evaluated.

Therefore, the pro amendment ermine u in vm a licensee's anahsis and, based on 61s will not increase probability or signiacant hasards consideretion. We how review,it appears that the three consequences of any -M-='

determined that operation of the Hope Creek standards d 10 CFR 5&92(c) am

2. Cnate the possibility of a new or Generedag Station la L with th, satisSed. Therefore,the NRC staff different kind of accident frees any Isoposed chanses:

1. wun met tavoin a signhnt increase in proposes to determine that the ecddent previously evaluated.

the prubabinty or consequences d an amendment request involves no Removal of the steam Dow/leed Dow mismatch and low steam generator level saident pnemuely evaluesed.

signiScant hazards consideration.

N propowd chanew e the ECCS and local Pubhc Document Room trip does not create the hty of a M N h T j g"*" y 'd I"*8""**'**IC" M8 location: Pennsville Public Library,190 new or difEersat kind wrMa=8 than S. Broadway. Pennsville New Jersey previously evaluated har=naa the trip 08070 cannot create an accident. Therefore, the faction (WT) satlan tmquency. The generic analyew antained in 1.icanatog T teaf Attorneyforlicensee:M.J.

proposed amendment connot crests the Rsport(1.TR)NEDC00636P.A andTTRWetterbahn. Esquire.Winston and poulbility of any accident.

Federal Register / Vol. 58. No. 80 / Wednesday April 28, 1993 / Notices 25865 Strewn.1400 L Street. NW.,

by performance of T3 3/4.a.2.2 ACDON b.

the standards of to CRt 50.92(c). The Washington. DC 20005 3502 The cosa-tie will remain OPERABLE and NRC staffs review is presented below'-

NRC Prefect Director: Charles L.

able to perform its function of providing *

1. n e reposed change would not to the Miller

[ s une o increase t e ihty or consequences Southern California Edison Company,'

possibility of a new cr different of of 8 Previous y evaluated accident.

et al Docket Noa. 50-361 and 50-382, accident than any previously usted.

The proposed dariges are related to San Onofre Nuclear Generating Station 3 Will DPerstion of the facility according the boron concentration in the RWST Unit Nos. 2 and 3' San Diego County' 2 this pmposed change invuln a sign *=nt and ECCS accumulators. This increased ggga reduction in a margin of safety?

concentration does not constitute a Response: No change expected to increase the Date of amendment requests: April his proposed ch allows e one-time probability of a paviously evaluated 13.1993 NPtion to Techni Specification occident. no means by which the Description of amendment requests:

4.a.1.1.1.s to allow b tie breakers to b proposed changes might result in ne licensee proposes to revise DPPosite unit cross-tie to be OPERABLE increased radiological consequences of Technical Speci6 cation (TS) 3/4.8.1, w[

d e kc Q $ and-varkus accWenu am MaH below.

e cia A. C. Sources. His proposed change aplacement of the esov transformera. whne The higher boron concentrations may will provide a one-time exception to TS 6 replacement is performed, e wiu result in increased probability of 4.8.1.1.1.s to allow replacement of the be attached to 6 associated battery equipment failure due to in.

480V transformers B04X and B06X and will be aanad to the tem non-containtnent or in-process equipment during b Units 2 and 3 Cycle y clan tE power sourosa. m associst being exposed to an environment more refuehng outages, bettery bank will be maintained OPERABLE severs than that to which it is quahfied.

Basis for proposed no significant by perfumance of TS 3/4.8.2.2 ACNN b.

A review of the general chemistry hasards considemtion determination:

b cr as-tie w 11 remain OPERABLE and properties of b shghtly higbr boron

't ding a concentration Duid indicates no As required by 10 CFR 50.91(a), the ad of mechanism that would result in an licensee has provided its analysis of the companion Unit. mrefore, then h no issue of no significant hazards signtScant reduction in a margin of safety.

appreciable increase in the in-line consideration, which is presented no NRC staff has reviewed the compcnent failure rate. While b below:

licensee's analysis and, based on this corrosive nature of the fluid will

1. Will operation of b facility in review,it appears that the three increase, this incmase will be only acmiance wuh this pmped change

. standards of 50.92(c) are satisfied.

minimal. Thus, there is no signiBeant involve a signiacant increme in the Therefore. 6 NRC staff reposes to increase in the consequences of any Probability or consequenas of an acx:ident usted7 determine that the amen ment requests accident due to an increase in the Pp"ously involve no signincant hazards probability of equipment failure.

T op one of maintaining redundant consideration.

The changes in containment spray offsite power source is to prevent a loss of local Public Document floom and sump solution pH may change the ofhite power. This pmposed change allows locotion: Main Library University of radioisotope removal and partition e one-tune exmption to Technical Cahfornia. P.O. Box 19557,Irvine, characteristics. A review indicates that Specification 4.s.t.1.1.a to a!!aw the tie-California 92713 while the relevant characteristics are breakers to 6 opposite unit ause-tie to be Attorneyforlicensee: James A.

affected the resulting limiting OPERABLE while the anociated load centers Booletto. Esquire. Southern California coefEclent values associated with the B04 and B06 are INOPERABLE. His will Edison Company P. O. Box 800 PH changes are bounded by the values i

allow replacement of b 480V trsnsformers Rosemead. California 91770 used in Comanche Peak design 1

'[ [**'*"$Ugg'ud NitCProject Director:%eodore R.

calculations. nus, no adverse impact

,g bettery bank and will be connected to the Quay on the radiological con nces arising fmn this mechanism has a

temporary non.clase 1E power sources. N TU Electric Company, Dockst Nos. 50-ident15ed.

anociated bettery bank will be maintained M5 and 50 48* rb --A Peak h The impact of the containment spray, OPERABLE by performance of 73 3/4.s.2.2 Electric Statloa Unit Nos.1 and 2, with a lower pH. upon the combustible ACTION b. The aose. tie win nme OPERABLE and able to perform its function SanemH County, Texas gas production rate was also evaluated.

of providing a second sourcs of A. C power Date of amendment request: October No mechanism for inceased to the companion Unit. brefore, there is no 19,1992, as supplemented by letter combustible gas production was incnue in probebility or cocooquences of a dated March 17,1993, identified.

loss of offsite power or any other accident Description of amendmentinquest:

The higher boron concentration could pmn usly waluated.

The proposed amendment would revise have an adverse impact on the Technical Specification 3/4.1.2.5. 3/

inadvertent actuation of the ECCS event.

this ch w an w the possibility of a new or difSerent type of 4.1.2.6. 3/4.5.1. and 3/4.5.4 by Although the timing of the sequence of accident imm any previously evaluatedt increaalag the boron concentrations for events may be affected, the departure Ruponse: No the refueling water storage tank (RWST) from nucleate boiling ratio continues to m pmposed chany anown a one-time and the emergency core cooling system increase from its initial value exception to Technical SpeciScation (ECCS) accumulators. Rose changes throughout the event. Based on a review 4.8.1.1.1.a to allow the tie breakers to the enable the use of extended reload of this event, no changes in the event Opposite unit crose-tie to be OPERABM cycles.

probability or consequences are while the sesociated load centers Bot and Basisforpro no significcat anticipated; however, the continued Boe are WOPRABMEs wiH aDow hazards consi erUtfon determinotion:

validity of this conclusion will be

]

4ao,V trans As mquired by 10 CFR 50.91(a), the reconfirmed on a cycle-specific basis.

e be e ed to the labattery bank licenses has provided its analysis of the

2. De proposed chaoge would not Issue of no signiScant hazards coste the posalbility of a new or and wiu be -W to b tem non.

class 1E power ecurca. N associst consideration. he NRC staff has different klnd of accident from any bettery bank wtB be maintained OPERABLE reviewed the licensee's analysis against previously evaluated.

e l

25868 Federal Register / Vol. 58, No. 80 / Wednesday, April 28, 1993 / N:tices

& proposed change is a pa'ssivs

1. no ebags wtil not involve inoperable to allow calibration of b change associated with Duid boron any signi increase in the probabtLity w monitor.

cCncentration No new or di5erent consequencee of an ecckdent because the Basis for proposed no significant change #pdates s tmMn the Technkal hazards consideration determination:

accident sequancee have been d meth da and. the,,",u,, {.

8

'i'"*pm m8Y As required by 10 CFR 50.91(a), the id:ntified. Furthermore, a review of heat p

tracing requirements !~ha'aa that there admimstrative in natum. It also does not licensee has provided its analysis of the ar3 no additional requirements resulting effect plant operation and will not weaken or issue of no signincant hazards from the boron concentration increase.

degrade the facility, consideration. The staff's evaluation of There are no previously unconsidered

2. The propowd change will not the licensee's analysis for the change to failun mechanisms.

create the possibility of a new or the af0uent grab sample and noble gas

3. b ymye.i.d change would not different kind of accident because the monitoring capability is prwented involve a sigmficant reduction in the change is administrative in nature and below:

mtrxin of safety.

no physical alterations of any plant

1. Does the amendment imelve o

& decrease in the containment configuration, changes to setpoints, or significant increase in the probability or spray and sump solution pH could be openting parametars are pro consequences of an occident previously ed to result in higher airborne 3.N proposed change wt not evaluated?

1 - e concentrations. b accident involve a sfgnificant reduction in a N proposed amendment would source terms could be impacted by margin of safety because the change repleos the current grab sample and variations in the lodine sprey removal involves an update to Section 6.0, noble gas radiation monitor with a and partition factors. A comparison of

" Administrative Controls." of the single system capable of continuous the coefBclents for the minimum Technical Specifications and does not monitoring and analysis of all currently cquilibrium containment sump solution aHect any operating practices, limits, air analyzed radioactive lodines and pH to those used in the CPSES design safety related equipment. and, therefore, Particulates in plant gaseous effluents analyses. indicated bt the expected is administrative. N NRC approved following an accident. N intent of the coefficient values would remain (Yankee Atomic Electric Companyl monitoring and analysis functions is to bounded by the values in the previous YAEC methodologies will be used to evaluate the radioactive releases analyses. nus, no signi6 cant reduction rfonn a lloss of Coolant Accident) following an accident to guide

)

in the margin of safety has been analysis for Vermont Yankee in mitigative and emergency response identified as maanMated with this accordance with to CFR [Partl 50, actions b accident is assumed to phenomena.

Appendix K and to demonstrate

, have already occurred before the Based on this review. It appears that compliance with the (Emergency Core samptr,s affected by this TS change ths three standards of 10 CFR 50.92(c)

Cooling Systems) ECCS limits specified mquest are requimd. As such, the monitor is not an accident initiator and are satisSed. hnfore, the NRC staff in 10 CFR 50.48.

proposee to dotarmine that b ne NRC staff has reviewed the is not likely to contribute to the~

arnendment request involva no bcensee's analysis, and based on this Probability of an accident previously significant hazards considention.

review,it appears that the three evaluated. b in.line, continuous local Pubbe Document Room standards of 50.91(c) are satisfied.

monitor provides at least equivalent, location: University of Texas at Wrefore,6 NRC staff proposes to and in the case of the grab sample.

Arlington labrary, Government determine that the amendment request

""h"" cad analysis capability, and will Publications /Meps,701 South Cooper, involves no significant hazards Provide a more immediate indication of P. O. Bax 19497, Arlington, Texas 76019 consideration, the release of affluents fo -

an Attorneyforlicensee. George L Edgar, local Public Document Roose accident thsough the reactor but -

Esq.,Newman and Holtzinger,1815 L locotfoe: Brooks Memorial Uhrery, 224 elevated release. Further it will provide Staet. N.W., Suite 1000, Washington, Main Street, Brattleboro, Vermont 05301 a mom timely indication of a release D.C. 20036 Attorneyforlicensee: John A.Ritshar, impact over a period of time. More

!GC Project Danctor: Suzanne C.

Esquire. Ropes and Grey, One timely input of such data will allow a Black Intemational Plam, Boston, more deliberate and accurate response Vermont Tankee Nuclear Power Maaaachusetts 02110 2624 to plant eventa. Mitigation actions can NRC Project Direc. tor: Waher R. Butler then be based on a better knowledge of Corporation, Docket No. 50 271, the release. A better knowledge base Vermont Yankee Nuclear Power WaaMngtan Public Power Supply from which to direct accident mitigation St tion,Vernon, Vermont Systess, Docist No. 50 397. Nuclear and esnergsacy repone eHorts should Date of amendment request: March Proket Na,2, Benton County, Imd to more effective to 26,1993 Washington accidents, which abould to a Deschpuon of amersdment squest:

Date of amendment request: March decrease in the consequences of an b proposed amendment would 10,1993 accident.

update Technical Specification (TS)

Description of amendment squest:

m one time exception to TS 3.0.4.,

Section 6.0 to add and revise NRC-N amendmantwould which would allow startup with the approved methodologies which will be fy Technical SpaHReatione new efDuent monitoring eystem used to generate the cycle-specific limits (TS) toimplement replamment of the inoperable, provides the meene to align in the Vermont Yankee Core Operating existing grab sampler and noble gas and calibrate the systeen under arrual 1.imits Report (CDLR) Im Cycle 17.

monitor for Reactor Building post-operating conditions.Durin6 this Basis forpro no sigrdficant accident semp with an on-line maximum of a 30 day period during hazards canal deterd***

monitor that d sample stock which the new efBuent monitorin As required by to CFR 50.91(a), the effluents directly, in addition, the system will be canaidered er licensee has provided its analysis of the proposed change would include a one until the calibration la complete, the issue of no a=<neaat hazards time exclusion from TS 3.0.4 that would licensee willuse a pre. planned consideration,which is presented allow startup from the 1993 refooling alternative method of monitoring off site below:

outage with b on-line monitor mineen that uom in eaa'ainmant

o Federal Register / Vol. 58, No. 80 / Wednesday, April 28, 1993 / Notices 25867 monitors and off-site dose assessment involves no signincant hazards Florida Power and Light Company, l

procedures. This alternate method is consideration.

Docket No. 50-335, St. Lucie Plant, Unit currently used during emergency local Public Document Room No.1, St. Lucie County, Florida conditions to determine mitigative and locatign: Richland Public Lib

,955 Date of application for amendment:

emergency response actions, since the Northgate Street Richland,W gton November 30,1992 5 a samp d be 99352 B

description of amendment:Ris gd nt.

s al b

""D Technical intended for use

-aa:ident, and does Attorneyforlicensee: Nicholas S.

'*jes 3.3-3,3.3-4, and j

not affect the pro ility of an Reynolds. Esq., Winston & Strswn,1400 Peci3ca n accidents previously evaluate since L Street, N.W., Washington D.C 20005-cy Bus Unke e Protection the acddent is assumed to have already 3502 Devices and will permit improvements occurred Wfore the umphe are NRCProject Director:neodore R.

to be made in the undervoltage required. There will be no impact on the Quay protective relaying scheme.

a e

om the ynsequence Prev sly PubHahd Nodou d Date ofissuance: April 12,1993 ntly used under emerpacy Eff date pril 12,1993 dm F

t ung Based on this analysis, the staff W-- Proposed No Sig=me==8 concludes that the changes proposed by Hazards Consideration Deter 8--ha y

ruti g cense No. DPR-67: Amendm nt revised the Technical the licensee will not sign 1Santly and Opportunity for a Hearing SpedSmuons, increase the probability or consequences The following noticos were Date ofinitial notice in Federal pubushd as separate individhreviously of an accident previously evaluated.

Register: January 21,1993 (58 FR 5431).

2. Does the amendment create the notices. N notice content was the b Commission's related evaluadon of possibility of a new or different kind of occident from any acadent previously

,,m,,, ayoye, my wm puby,bg,,

the amendment is contained in a Safety individual nodcas eibr because Mme Evaluation dated April 12,1993. No did not allow the Ccmmission to wait significant hazards consideration The monitor rforms a passive comments received: No.

function that fo ows and monitors plant for this bimekly nodce or beause h acdon involved exi 'at dine-IocalPublic Document Room 8

events after an acddent is assumed t location: Indian River Junior College W h* s bcs"**

have occurred. The requested exception to TS 3 0.4. would use the existing pro-I g,,,33,,,9dma sts Library,3209 Virginia Avenue, Fort Pierce, Florida 34954-9003 planned alternate method of issued or proposed to be issued determining effluents, again after an involving no signiScant hazards GFU Nuclear Corporation, et at, accident is assumed to have occurred.

musideration.

Docket No. 50-239, bee Mile Island These proposed changes have no For details, see the individual notice Nuclear Station, Unit 1. Dauphin automatic centrol function, and thus do in the Federal Register on the day and County, Penneylvania not affect accident initiation.b page cited. His notice does not extend Date of applicationfor amendment:

proposed amendment does not.

the notice period of the original notim.

May 19,1992, as supplemented therefore, create the possibility of a new November 30,1992, January 29, and or different kind of acddent from any Duquesne Light Company, et al. Docket F 12,1993.

accident previously evaluated.

No. 50-334, Beaver Valley Pome Brief

' tion of amendment:N

3. Does the amendment involve a Station, Unit No.1 Shippingport, amendment lates portions of the ni!-

significant reduction in a margm of Pennsylvania 1 Radiological Environmental Tachnical S eciScations (RETS) and relocates sow Date of amendment requeet:

P b existing Srab. sample method November 2* 1992 provided Ume-delsyed results that them to controlled programs in accordana with the guidance contained identified specific isotopes off-une b Description of amendment request:

in NRC Generic Letter 89-01, dated current noble gas monitor only provides b preposed amendment would January 31,1989, indication of gross gamma radiation.

modify the Appendix A Tectaical Date ofissuance: April 5,1993 S ecifications (TSs) to allow for Effective date: April 5,1993 De new monitor provides information P

on actual concentretions of spedfic incrossing the number of spent fuel Amendment No.:173 -

isotopes in the reactor building effluent assemblies that may be stored in the Facility Operatinglicense No. DFR.

on a real time basis, which will provide spent. fuel pool. b changes would 50 Amendment revised the Technical more timely information from which to anow for the storage of fuel with U-235 Specifications.

base mitigative and emergency response enrichment up to 5.0% (weight). The Date ofinitialnotice in Federal actions on than that presently provided proposed amer'dment would affect TS Ra$ eter. December 23,1992 (57 FR l

by the grab sample system, brefore, sections 3/4 9.14,5.6.1, and 5.8.3, and 61112) b January 29, and February 12, the magin of safety created by the Table 3.9-1.

1993 letters provided errata pages that existence and use of the grab sample Date of publication ofindividual did not change the initial no significant system is increased by the proposed notice in Federal Ragister: February 2 hazards consideration determination.

replaosment with the in-line system.

1993 (58 m 7161).

b Commission's related evaluation of Therefore, the in line system does not this amendment is contained in a Safety reduce any margins of safety.

Expiration date ofindividualnots.ee:

Evaluation dated April 5,1993, ne NRC staff has determined based March 8 m3 No significant hazards consideration i

on its analysis that it appears that the localPublic Document Room comments received: No.

three standards of 50.92(c) are satisfied. location: B. F. Jane. Memorial Library, localPublic Document Room brefors, the NRC staH proposes to 663 FranWn Avenue, Ahquippa, location: Government Publications determine that the amendment request Pennsylvania 15001.

Section, State Library of Pennsylvania,

e e

25868 Federal Register / Vol. S8, No. 80 / Wednesday, April 28, 1993 / Noticas Walnut Street and C^===wes.lth Effective dote: April 9.1993 3.311(Unit 2) tu r*Dect as built Avenue, Box 1601, Harrisburg, Amendment Nos.:72 conditions.

Facility Operating Ucense No. NPF-Date ofissuonce: April 8,1993 Pennsylvania 17105.

62. The amendment revised the Effective dote:.Apnl 8,1993 Amendment Nos.: 172 and 155 Illinois Power Company and Soyland Technical Specifications.

Power Cooperative, Inc., Docket No. 50-Dore offrutialnoticein Federal Facility Operating Ucense Nos. DPR-r: February 3,1993 (58 FR 6999) 58 and DPR.74. Amendments revised 451, Clinton Power Station Unit No.1,

- a Comminaion's related evaluation the Technical SpeciScations.

DeWitt County,1111nois Date of application for amendment:

of the amendment is contnined in a Date ofinitialnotice in Federal September 20,1991 and supplemented Safety Evaluation dated April 9,1993.

Register-July 8,1992 (57 FR 30250) by letters dated August 17,1992, and No significant hazards consideration na Commi==(on's related evaluation comments received: No of the amendments is contained in a February 17,1993 1Dcol Public Dbcument Room Safety Evaluation dated April 8.1993.

Descnption of amendment request:

The amendment revised both location: The Vespasian Warner Public No significant hazards camsideration surveillance test intervals and allowed Ubrary 120 West Johnson Street.

comments acsived: No.

out-of service times for Reactor Clinton. lllinois 61727.

local Public Document Room 1 cation:Maude Preston Palenake Protection System. Emergency Core lows M M t u d P m Memorial Library,500 Market Street, St.

Cooling System. Control Rod Block Co Pan 1

e Joseph, Michigan 49085.

System. and Containment and Reactor Ar Nebraska PuWe Power M W Iows No. 50-298, Cooper Nuclear Station.

n ntsti n e

Dots of appliection for amendment:

Nemaha County, Nebraska Clinton Power Station Technical December 19.1991 and supplemented S

fications (TS). In addition, several a

alstrative changes to the TS ar, by additionalinformation on August 25.

Date of amendment request: February October 8, and November 24,1992.

1,1993 contained in this TS change.

Bnef descripuan of amendment:%e Brief description of amendment:The Date ofissuance: April 9.1993 amendment revised the Technical amendment revised the Technical Effective date:Immediately, to be implemented within 30 days.

Specifications by incorporating Specifications (TS) to (1) incorporate the extended allowable out-of-service times NRC Staff position on leak detection per Amendment No. 71 Focility Operating Ucense No. NPF-and surveillance test intarvals for the guidance of Generic Letter (GL) 88-

62. The amendment revised the reactor protection system. isolation 01 and its supplement. [2) incorporate Technical SpeciScations.

actuation system, emargency core the NRC Staff position on inservics Date ofirutial notice in Federal cooling system and control rod block inspection schedules, methods.

Register: December 26.1991 (56 FR function instrumentation. Additional personnel, and sample expansion per 66921) Re August 17.1992, and changes for clarity and consistency were the gufdance of GL 68-01 and its February 17.1993. submittals =M also made, supplement, and 13) make of revisions /clariScations which did not Dateofissuance A 114.1993 administrative changes wherein certain change the staffs initial proposed no Effectiwr date: A 14,1993 system names are replaced by system Amendment No.:193 names which are more consistent with signiScant hemords consideradoo Facility Operating Ucense No.DPR-those used in other portions of the TS.

determination.

The Comminion's related evaluation

49. Amendment revised the Techntral Date of tssuance: April 14.1993 of the emendment is contained la a Speci5 cations.

Effectire dater April 14,1993 Safety Evaluation dated April 9,1993.

Date offnitio1noticein Federal Amendment No.:161 No airihnt hazarde cxmsidesation Register: July 22,1992 (57 FR32573) facility Operat/ng Ucense No. DPR-comments received: No The August 25 October 8.and

46. Amendment revised the Technical local Public Document Room November 24,1992 lettere provided SpeciScations.

location:%e Verpasian Warner Public clarifying information only and did not Dore ofinitialnoticein Federal Library,120 West Johnson Street, affect the NRC's origiani determination Register: March 3,1993 (58 FR 12264)

Clinton, Illinois 61727.

of no si Scant hazards consideration.

The Commission's related evaluation i

The ission's related evaluation of the amendment is contained in s Illinois Power Company and Soyland of the amendment is contained in a Safety Evaluation dated April 14,1993.

Power Cooperative, Inc., Docket No. 50 Safety Evaluation dated April 14.1993.

No signi5 cant hazards consideration 461 Clinton Power Station, Unit No.1, No signi5 cant hazards consideration comments received: No.

DeWitt County,Imade comments rocsired: No.

IoeolPublic Document Room Date of application for amendment:

Lacol Public Docament noorn location: Auburn Public Library,118 December 15,1992 location: Cedar Rapids Public Library, 15th Street Auburn, Nebraska 68305.

Brief description of amendment:%e 500 First Street, S. E., Cedar Rapids, M

a Mohawuower Corpora &n, a-ndment modiBee Technical lowe 52401.

daNo.50 220.Mne We Point SpeciScations 3/4.7.1.1." Shutdown.

Indiana Michigan Power Company, Nuclear Station Unit No.1 Oswego Service Water System (Imope A, B,C).

Docket Ncaa. 50 315 and 50 318, Donald County, New York and 3/4.7.2. " Control Room Ventilation C. Cook Nuclose Plent. Unit Nos.1 and

. Date of applicationfor amendment:

System," to add exceptions to T=chnie=1 2.Berrien County, McMgan November 20,1990, as superseded SpeciScation 3.0.4 to permit tematoning and detensioning of the reactor pressum Ibfe of opplicaticut)br amendments:

February 7,1992, as supplemented Jura 22,1992,)anuary 29,1993. February 18 veneet heed with one of the required May 1,1992 divisions of the systema addreened by Brief description of amendments:The 1993, and March 29,1993.

B description of amendownt:The these Tachnicat Specifications am=-. -.ts change the number of

.- _ revir.es Technical containment thermistor fire datectors am_

inoperable,

' listed in Table 3.3 10 (Unit 1) and Table Spuhuons (TSs) 3.2.7.1, 3.3.3, 4.3.3 Date ofinuance: April 9,1993

Federal Register / Vol. 58, b 80 / Wedneedey, April 28,1993 / 1**1=

2S869 and 3.3.4 and =----u-A na=== to update Brief descnpdon of annendment:N Teclinie=1 Speci8 cations with these TSa to conicrm to the amendment rvrised the T= Sale =1 instrument bus 9s 3bility provisions requirements of to CR Part 50 SpeciScations to incorpcrats b by adding cpec15 cations. Action Appendix J. and NRC Salsey foHowing changes:

Statamu, Surveillance Requirements Evaluations, dated May 4,1968, and (1) % cantatament isolation system nd Basis secdons relative to h November 9,1968.

automatic actuation testing frequency Data ofisstemes.

12,3995 (speciSed in TS Table 4.1-3) wenmsed opereden ad h vital instrusasus buses.

DWs ofa===== April 13,19a3 active date: A 12,1983 to accommodate o month fuel cycle. peration or, a 24-Effaceve date: April 13,1993 endment No.:140 Focility Operating Lksase & DPR-Arneestment No.:51 83: Amendment rensee the Tedudcal (2) De containmcot isolation valve facd.ty Operating uc,ns, & DPR-P" h-testing frequency (=paMad in TS 18: *==aA=-nt revised the Appsma A

&te ofinWal nouce in Fodseal Section 4 4 E.1) was revised and the Technical SpecfBcations.

acceptance criteria hr the ccxnhined Date ofinitloinotice in Tederal

}

u Pa FR tainme t leakage rate (speciBadin Register: December 9,1992 (57 FR TS Section 4.4.E.2) was reduced to 0.5 58251) he Commf== ion's related evaluation

. t a c mm data operade on a 24 La hmWs mlated evaluadm d b amendmnnt is crmtained in a month fuel cycle.

of the amendment is mutained in a (3)ne containment s ray system Safety Evaluation dated April 13.1993 b"h,3 g"can tasting fmquency (specifed in TS A

l 99 -

No signiacant hazards consideratim s

d Section 4.5.A.2.a) was revised to comments received: No estlbom accommodate operation on a 24-month LocalPubbe Document floom locat>on:Ralerance and ru,= ants fuel cycle.

location: Rochestar Public uhrary,115 Department, Pen 8 eld ubrarp Stam (4) The sprey additive valves testing - South Avenue, Rochester, New York Wymsny dNew Yost Ogh fr*9u8nC7 (8PeciBed in TS Section 14810.

York 13128.

4.5.B.2.a) was revised to acx:ommodata Notth A11 antic Energy Service operation on a 24-month fuel cycle.

3,g g y.% g,'"P'*I' (5) The sensitive leahge rate tasting et ab Nos. W e1and M 42, Corporation, Docket No. 50-443, frequency (speciBed in TS Secdon San Ondn N& Genersums Station, Seabrook Stahon. Unit No.1.Seabrook, 4.4.C.3) was revised to clarily that the t on. 2 and 3. San Diagn Cosmty, New th=pahlre maximum test intervalis 3 years.

peu of r -- ' d W August (6) ne Basis of TS Secdon 4.1 Date of applicationfor amendments:

17 1992.

(Operational Safety Revinr) was revised October 2,1902 bestripcion of amendment ingoest.

to spect that the phrase "at least,"

Briefdescripdon ofamendments;ne The amendment revises the Appendix A when re g to surveftfance licenses proposes to revies I te=n==

Technical SpeciBcations relating to Periodicity, does not negate the 25%

Condition 2.C. tis)1 for San Onofre Unit Reactor Coolant Systorm heatop and extanalon tizne allowed oy TS Deanition 2 and 13r== Condition 2.CJ17)d be cooldown limitatioca. Speci5caDy 1.12.

San Onofre Unit 3. " Poet-Acx:sdent Figums 3.4-2 and 3.4-3 are imod18ed to nose changes foDowed the guidance Sampling System (NUREG-0737 Item show epplicability of the curves up to Provided in Generic letter 91-04, U.B.3)," to remove conditions absedy 11.1 equevalent full-power years

" Changes in Technical SpeciBcation complied with, and to revise four Post.

(EFPY),to provide revised RTwor alues Surveillance Intervals to Arc ~n m~h Accident Sampling System v

at 11.1 EFFY st 114 end 3/4 thickness, a 24-Month Fuel Cycle."

ts.

and to indicate b co Date ofisavance: A 9,1993 te of ha~'""*: A til 6,1993 contrq nmatwial. pper canket d b Effacche date: A s 1983 A = nd=-nfNos.:103 and 92 Effsettw date 6,1993 Date of tasvance: A 7 1993 Ammendment No.:129 date: A. 7,1bs3 FocWty Operatang innvaNa M FacM Operadag & Nos. WF.

endrnent h.19 64: Amendment revised the TarimienI 10 and NFF-15: %e -d=-ats Focility Operating Lkaner & NPF-S eci8 cations.

P revised the Opasating Licannes.

86. Amendment revised the Tischnical

&te offnMalnodeeits Pederal Ate offnMafnodcela Federal SpeciScadons.

Register: September 2,1992(It PR RegistenFebruary 17.1993 (58 FR Nte ofinidalnodceln Federal 40219) 8752)

Register: December 9,1992 (57 FR Tbv=e'aad-r4 neleted evaheatica n o F -> ':3 adened eesluation 58247).

of the amendment le e>=*=+-! in e of the arneadm- *a is av==#ahad in a b Cosamission's rata #=d evaluannn Sajsty Evaluation dated Apr!! 9,1995.

Selety Evahnatietr detod April 5,1993.

of 6.m.m,+ ment is enn8ainad in a No signiScent hemards consideration No sign 15 cant hazards canalderation Safety Evaluation dated April 7,1902.

mmments im?.4 No enmments received: No.

No sign 1Bcant hazards consideration loce/Pm6he&cannent /been localPublic &cumentRoom commenta ia

1. No.

locatuwe White Plains PubBe uncery, locados: Main Ubrazy, University of Local Pubbe &cument Noem 190 Mardne Aweeue, White Fishes, New California, P. O. Best 19ss7, Irvine, loecoon: Exeter Puh5c Ubrary,47 Prent York 10610.

f'attinenia 92713 Street, Exeter, New Hempshire 03033

• • 1-Gas and Iloctric Tammessee VaBey Aatbority, Docket Power Ausberity of The State esNees Corporatica, Docket No. 50444.L E.

Nos. 36438,30-30s and 30-298, Browne York, Docket No. 56404,ladian Point Gimme Nuclear Power Flast, Weyes FerryNuclear Plent. Unite 1,2 and 3 N=daar &

Unit No. 3 County, Near York Uneestoma County,Alebeene W=neL==aar Coasty New Jerk Date of application}se =-nament.

&te of applicction fL:ramendments:

Date of appecoconfor omnesdment-October 8.1982 tamber 30,1992 (TS 323)

July 17,1,s2,se v w arsef a %de.of u -

am. quae aomendment:

December 23,1992 Updates the awrikary anscwiemi syneses These licanos ernardments revise the

25870 Federal Register / Vol. 58, No. 80 / Wednesday, April 28, 1993 / Notices Browns Ferry Nuclear Plant Technical Toledo Edison Company, Centerior of no signiBeant hazards consideration SpeciBcations by restoring the Service Company, and & Cleveland are contained in a Safety Evaluation cperability requirements of b Control Electric illuminating Company, Docket dated April 9.1993.Public comments on Room Emergency Ventilation System No. 50-344, Davie-Besse Nuclear Power proposed no signiBerat hazards th:t were temporarily modiBed by Station. Unit No.1. Ottawa County, consideration comments received: No.

previous license amendments issued on Ohio Attorneyforlicensee:Nicholu S.

Reynolds. Esq., Winston & Strawn,1400 S*Ptember 18,1989. These license Date of applicotlonfor amendment:

a gton, E 2M-amendments also remove a list of October 29,1992 supplemented vY o hoent Le e 91-08 Rs de r pt on of amendment:%

j Usts From Technical Specifications,"

ame ont revised Technical N

Street Ric d

on and revises associated Bases-Speciacation (TS) 5.3.1," Fuel 99352 NRC Date ofissuance: April 9,1993 Asumblies," to be consistent with the Profect Director:Nodore R. Quay model TS wording included in Effective date: April 9,1993 Supplement 1 to Generic Istter 90-02, Wisconsin Electric Power Company, Amendment Nos.: 193,208, and 165

" Alternative Requirements for Fuel Docket Nos. 50 264 and 50-301, Point Beach Nuclear Plant Unit Nos.1 and Facility Opemting Ucense Nos. DPR.

Assemblies in the Design Featurse 33, DPR.52 and DPR-68:' Amendments Section of Technical Speci$ cations."

2 Town of Two Creeks. Manitowoc revise the Technical SpeciBcations.

Date oflasuance: April 7,1993 County,Wisconala Effectwo date: April 7,1993 Date of applicationfor amendments:

Date ofinitial notice in Federal Amendment No.179 December 7,1989 Register: October 28,1992 (57 FR yng;;;g,p,,,g;,

yo,,,,yo ypy,3, g,;,7 g,,,7;pgg,, og,,,,g,,,g,; yy, 46828I Amendmentrevisef theTechnical amendments eliminated the p

The Commission *a related evaluation SpeciBestions.

requirements for testing components in of the amendment is contained in a Dofe ofinitial notice in Federal the opposite train when certain St.fety Evaluation dated April 9,1993.

Register: November 25,1992 (57 FR components in a train are out of service.

No signiBcant hazards consideration 55594) The supplementalletter of These components are safety injection comments received: No February 17,1993 withdrew the phrase pumps, residual heat removal pumps, _

localPublic Document Room

".drconium alloy," reverting to the term containment spray pumps, and

. dtcaloy" for describing fuel rod containment accident pumps.%o location: Athens Public Ubrary, South cladding.This change did not change also eHminates testing Street. Athens. Alabama 35611 signiBcantly change the request or affect redundant valves in safety in)oction, Tcnnessee Valley Authority, Docket the staff's notice of the request..

residual heat nmoval, and containment Nos. 50 2SE,50 260, and 50 294, b Commlaaion's related evaluation spray ems when a valve is of the amendment is contained in a in le.

Browns Ferry Nuclear Plant Units 1,2 te issuance: A til16,1993 and 3, Ummtone County, Alabama Safety Eraluation dated April 7,1993.

No signiacant hazards consideration date: Apri 16,1993 endment Nos.:138 and 142 Date of opplication for amendments:

comments received:

Fac&ty Opemdng Ucense Nos.DM-October 9,1992, as supplernented LocalPubhc Document Room a

o fd March 31,1993 (TS 324) location: University of Toledo Library, Rj7. An nt Brief description of amendments:%e. Documents Doparment 2801 Bancroft Date oflidd ce in Federal Avwnue. Toledo, Ohio 43606.

amendments provide a revised we Commission't re{$6 FR 31415)

. July 10,1991 ted evaluation dannition of con alterations for Washlagten Public Power Supply refueling operations, revise surveillance System, Dockat No. 50 397, Washingtos of the amendments is contained in a requirements for infrequently used Nuclear Project No. 2. Benton County, Safety Evaluation dated April 16,1993.

refueling equipment, revise refueling Waaklagten No signi8 cant hazards consideration core reactivity monitoring requirements, Date of applicationfor amendment:

E$

nt Room and avise administrative requirements April 1.1993 location: Joseph P. Mann ubrary,1516 for supervision of nfueling operatices.

description of amendment:ne Sixteenth Street,Two Rivers, Date ofissuonce: April 9,1993 am ent adds a footnote to TS 3.7.3, wt.mnain,

Effective date: April 9

" Reactor Con Isolation Cooling Wolf Creek Nuclear ting 1993 Amendment Nos.194,209, and 166 System." that allows plant operation to continue with the Reactor Core Isolation Corporation, Docket 50 4s2, Wolf facility Operating Ucense Nos. DPR-Cooling (RCIC) automatic transfer of the Creek Generating Station, Coffey 33 DPR 52 and DPR-68:

suction path to the suppression pool County, Kannae Date of frdtial notice in Federal disabled until May 17,1993, or the Date of amendment mquest:

Register: November 25,1992 (57 PR beginning of the 1993 reibeling outsgo, December 22,1992 55592) whichever comes first.

Bri description of amendment:The Re Commission's related evaluation DWe ofissuance April 9, M93 amen ont e of a Won to of the amendment is contained in a Effective date: April 9,1993 Technical Speci8 cation Table 4.8-1.

Amendment No.:114 Diesel Ceneretor Test Schedule, which Safety Evaluation dated April 9,1998' Facility Operating Deense No. NPF-eliminates the requirernent to inasese No significant hazards consideration 21: he amendment revised the the testing frequency upon experfeccing comments received: None Technical SpectScations.

Sve or more failurse in the last 100 valid localPublic Document Room no Commt==1on's related evaluation testa. no proviaton for incrossed testing locotion: Athens Public Ubrery, South of the amendment, finding of emergency based upon the last 20 valid tests has Stnet. Athens. Alabama 35611 circumstan-and fLnal determination been retained.

Federal R,cgneter / Vol. 58 No. 80 / Wettneeday. April 28, 1993 / Notices 2M871 Dose ofinunace April 6,1M3 Egective dere; AprJ 6,1993, to be communication for the public to Room, the Celman Building. 2120 L respond qu2cMy, and in the case of Street. NW., Washington, DC 20555, and 1 nplemented within 30 days of telephone comments, the comments at the local public document room for issuance.

Amendment No.:

have been recorded or transcnbed as the__particular facdity involved.

Amendment & E2 appmpnase and b licensee has been The Commissken is aho eBaring an ininma f the public mmm nra.

opportunity for a hearing with reapest to Foedity OperatingIJeanse& NPF-o

42. Amendment revised the Technical In cirotmstanasa where imiluso to act the 'a====a of the amandment. By May Speciacations-in a timely way would have ser.dted, hr 28,1993, the licensee may Sla a request Date offmnal notice in Federal example,in derating or shutdown of a for a hearing with respect to insummee of Reester February 3.1W3 f58 PR 7008). nuclear power plant or in prevention of the amendment to the subjec2 fanlity The Commiarion's reisted evaluation either rerumptico of operation or ei operating licenas and any perses whose of the n-c.mma is correatned in e increase to power anstput up to the interest may be afte=A by this Safety Evaluetion deled April 6,1992.

plant's ucunoed power level, the proceedinB and who wishesin No afgnificant hazards cocaidention rmannissico may not have had an participate as a party in tbs proceeding comments received; h oppostunity to provide for pobuc must file a written request for a hearing localPublic Document Room comment on its no "$ mincant harsrds and a petition for leswe to intervene, t

consuisretion dm6er=mann= la ruch Requests for a hearing and a petition fcr Locations: Emporia State Universit7-William Allen White Library.1200 case, the license anna,dment has been leave to intanene shall be filed in issued wibut o rtunity ser scardance with the Commisdois Commerdal Street, Emporta, Kansas mmment. H bre been some time

" Rules of Practice for Domestic 66801 and Washburn University School of Law Library. Topeka, Kansas 66621 for public comment but noms than 30 Ucensing Proceedings in to CFR Part days, the Comnussion raay provide an

2. Interested persons should conalt a Notice a(1sswar= of Amand==ste to opportunity for public comment. If current copy of 10 CFR 2.714 which is I scility Operasang Ucomees and Finaj comments have been requested, it is so available at the Comsnisalon's Public Determbastion of No Significant stated. In either event, b State has Huards Con =hstion sad been consulted by telephone whenever Docunent Room, the Celman Building, Opportuairy for a Hearing y Possible.

2120 L Street, NW., Washington, DC Puolic Announcement ar Emerpacy Under its regulations, the Commission 20555 and at the local pubhc document Clrr== = -* a---)

may issue and make an amendment roora for the particular facility involved.

During the

' aince publication of immediately eMeetive. notwithstanding If a request for a haanng or petition for leave to intervene is fued by b shove the last bd y notice, the the pendency befon it of a request for data, the Commission or an Atomic a hearing hoes any peson,la advanca Safety and UmnaNg Board, designated Commiazion has isstad the followins of the holdmg and casopieuen ci any by the enmmission or by the Chairman amendments. W Commission has determined for each of bse seguired beanag, where it has of the Atomic Safsty ani! I hing deturmined bt no aknir,~as huards amendmants that the application for the consideration is involved.

Bond Panel, win rule on b requeat amendment complies with the The Comminion has appBad the and/or petition; and the Secretary or the standards and requirements of b standards ci to CFR 50.22 and has made designated Atomic Safety and ucensing Atomic Energy Act of1954, as amended a final datumination that the Board willissue a notics of a baanng or (the Act), and the Commission's rules amendment involves no significant As required by 10 CFR 2.714, e an appropriate order.

and regulations. N Commission has hazards consideration. The basis for this petition for leave to intervene shall set made appropriate findings as required detamination is contained in the forth with particularity the laternst of by the Act and the Commission's rules documents related to this action.

the petitioner in the proceeding, and and regulations in 10 CFR Chapter I, Accordingly, the amendments have how that interest may be affected by the which are set forth in the license been issued and made effective as amendment.

indicated, results of the pr=a% The petition sbould specifically explain the reasocs Because of exigent or ernergency Unless otherwise indicated, the why intervention should be pernutted circumstances associated with b date Commission has determined that bse with particular reference to the the amendment wes needed, there was amaM=anta satisfy the crteerie for following factors:(1) the nature of the.

not tune for the Co=w--u= to publish, categorical exclusion in sa:ntdance petitionw's right under the Act to be for public comment belope lesuaea, its with to CFR $1.22. Therefore, punuant made a party to the pt=M=ar (2) the usual 30-day Notics of Consideration of to 10 CFR 51.22(b). no soviK=-kl nature and scient of the ner's issuance of Amendment. Proposed No impact statement or anytronmanaal property, an*W or intarsst in significant Haaards Consideration assessunent need be prepared lor these the proceeding; and (3) the possible Determination, and Opportunity for a arnendments.lf the e-on has effect of any order which may be r

Hearing.

prepand an environmental assessment entated in the promedmg on the For eegent circumstances, the under the special circumstances petitioner's intarost. The petition should Commission has either issued a Federal provision in to CFR 51.12(b) and has also identify the specific aspectis) of the Register notice providing opportumty made a determina'6a based on that subject matter of the as to for public comment or has used local assessment, it is so indicated.

which petitioner wis to intervene.

media to pnyvide notice to the public in For furtbar detaih with respect to b Any pwoon who has. filed a petition for the ares surrormding a bcznsee's facf!!ty action see (1) the application for neeve to intervene or who has been of the licensee's application and of b amendment (2) b areendemit to admitted as a puty may amend the Commission's proposed determinanon Facility Opeesting Woenee, sand f3) the petition without requesting leave of the of no significant hazards conaderation.

Cosmrdasica's reissed letter, Salory Board up to 15 days pner to the Erst The Commission haa providad a Evaluation and/or Eaviranasental prebearing coniwooce scheduled in the reasonable opportunity for the public to Assessment, as inchceted. All af these prMap but such an amended comment, uniog its best efforts to make items are a$ailable for pehlicinspection petition must satisfy the specificrty available to the public rneans of at the Commission's Public Document requhsments descnbod above.

e e

25872

-Federal Register / Vol. 53, No. 80 / Wednesday, April 28, 1993 / Notices Not later than 15 days prior to the first addreued to (Pm)ect Director):

Virginia Electric and Puwer Company, prehearing conference scheduled in the petitioner's name and telephone et al., Docket No. 50 339, North Anna proceeding. a petitioner shall Ble a number, date petition was mailed, plant Power Station Unit No. 2. Loulaa supplement to the peudon to intervene name, and publication date and page County, Virginia which must include a list of the number of this Federal Register notice.

Date of application for amendment:

contentions which are sought to be A copy of the petition should also be March 31,1993 litigated in the matter. Each contention sent to the Office of the General must consist of a speci8c statement of Counal, U.S. Nuclear Regulatory Bnef description of amendment: The ths issue of law or fact to be raised or Commission, Washington, DC 20555, amendment suspends the manual controverted. In addauon, the petiuoner and to the attamey for the licensee.

engineered safety features functional test of safety inlection input to the shall provide a brief explanation of the Nondmely Elbgs of petiuons for reactor trip breakers for the remainder of b:ses of the contenuon and a concise leave to intervene, amended petitions, the NA-2 operating Cycle 9.

statement of the alleged facts or expert supplemental petitions and/or requests opinion which support the contention for a hearing will not be entertained Date ofluuance: April 12,1993 end on which the petitioner intends to absent a determination by the Effective date: April 12,1993 rsly in proving the contention at the Commission, the presiding officer or the Amendment No.: 150 hearing. The petiuoner must also Atomic Safety and ucensing Board that provide reft,rences to those speciBc the petition and/or reguwt should be Amendment revised the Technical O emting I;. cense No. NPF 7:

facillfY P

sourcu and documents of which the peutioner is aware and on which the granted based upon a balancing gf the S ecifications.

P petitioner intends to rely to utablish factors speci$ed in 10 CFR those facts or expert opinion. Petitioner 2.714(a)(1)(i)-(v) and 2.714(d).

Public comments requested as to Proposed no significant hazards must provide suf5cient information t C M d M Ed h h of Nw consideration: No. On March 26,1993, show that a genuine dispute exists with York. Inc., Docket No. 50-Indian the staff granted an enforcement ths applicant on a material issue of law t

clear Geners t No. 2 discretion to be in effect until the or fact. Contentions shall be limited to g

amendment was issued.

matters within the scope of the amendment under consideration. The Date of application for amendment:

ne Commission's related evaluation contention must be one which,if April 8,1993, as supplemented on April of the amendments, consultation with "

proven, would entitle the titioner to, 12,1993, and April 14,1993.

the State of Virginia and anal no rslisf. A petitioner who to file such signiScant hazards determination are Brief description of amendment:De coed 6 a @ webba W amendmet twises (Technicaj u

nts th resp to at I st one S ecifications (TS) Section 3.3.D (Weld April 12,1993.

P contention will not be permitted Io Channel and Penetration Prusurization Attorneyfor licensee: Michael W.

participate as a party.

Those permitted to intervene become System) to permit disconnecting a Maupin. Esq., Hunton and Williams, parties to the proceeding. subject to any portion of the weld channel system if Riverfront Plaza East Tower,951 E.

limitations in the order granting leave to that portion became inoperable and Byrd Street, Richmond, Virginia 23219.

intervene, and have the opportunity tn repairs tqthat portion of the system Iocal Public Document Room participate fully in the conduct of the were determined to be not practicable, location ne Alderman Ubrary, Special hearing, including the opportunity to no amendment also revises th*

Collections Department, University of present evidence and cross-examine anociated TS Bases-Virginia, Charlottesville, Virginia 22903-witneanes. Since the Commission has Date ofissuance: April 14,1993 2498.

made a final determination that the amendment involves no sf nificant Effective date: April 14,1993 Doquesne Ught Company, et al., Dockst 6

Nos. 50-334 and 50-412. Beaver Valley hazards consideretion,if a hearing is Amendment No.:162 Power Station, Unit Nos.1 and 2, requested,it will not' stay the facility Operating Ucense No. DPR.

Shippingpat Pennsylvania ef!ectivenus of the amendment Any 28: Amendment revised the Technical

'd d

e place while the Specifications.Public comments Date of amenament request:

,t requested as to proposed no algnificant December 30,1992 A requnt for a hearing or a podtion hazards cocaideration: No. He Description of amendment request:

for leave to intervene must be filed with Commission a reisted evaluation of the ne posed amendments would ths Secretary of the Commiselon, U.S.

amendment and final no algnificant mod f the Technical Specifications and Nuclear Regulatory Commissica, hazards consideration detennination are Bm WW duvW st 6e stum Washington. DC 20555, Atteation:

contained in a Safety Evaluation dated generator tube support plate and Docketing and Services Branch, or may b3 delivered to the Comminion's Public April 14,1993.

tubahmt regions in accorduce with Document Room, the Gelman Building, local Public Document Room processes performed by the vendors, 21201. Street, NW., Washington, DC location: White Plains Public Ubrary, Babcock & Wilcox and i

20555, by the above date. Where 100 Martine Avenue, White Plains, New Westinghouse.Dets of publication of petitions are filed during the last to York 10610.

Individual notice in Federal Register:

days of the notice period,it is requested Attorneyforlicensee:Mr. Brent L April 6,1993 (58 FR 17912).

• [,6one proQ, Brandenburg, Assistant General Expiration date ofindividual notice:

orm

{9 p ne Counsel, hMated Edison Company May 6. m3 c211 to Western Union at 1-(800) 248-of New York,Inc.,4 Ireng Plaos 1822 IocalPublic Documeni Room 5100 (ir Missouri 1-(800) 342-8700).

New York, New York 10003, location: B. F. Jones Metnorial Ubrary, The Westem Union operator should be given Datsgram Identification Number NRR Project Director: Robert A. Capra. 663 Franklin Avenue, Aliquippa, N1023 and the following menage Dtrector Pennsylvania 15001

1 o

o Federal Register / Vol. 58, No. 80 / Wednesday April 28, 1993 / Notices 23873 L

Tennessee Valley A nthority, Docket amendments satisfy the criteria for Comraonwealth Edison Company, Nos. 50 327 and 50-328, Sequoyah categorical exclusion in accordance Docket Nos. 50 295 and 50-304, Zion Nuclear Plant, Units 1 and 2. Hamilton with 10 CFR $1.22. Therefore, pursuant Nuclear Power Station Unita 1 and 2, County Tennessee to 10 CFR 51.22(b), no environmental Lake County, Illinois Date of amendment request: March impact statement or environmental l

27,1992, as supplemented May 11. May anessment need be prepared for these Date of applicationfor amendments:

28, September 8 and October 8,1992; amendments. If the Commission has November 5' 1992 February 18 and April 1,1993.

prepared an environmental assessment Brie deScri tion o amendments. The P

Desenprion of amendment request:

under the special circumstances ame ents revise e Technical The proposed amendment would provision in 10 CFR 51.12(b) and has SPeciacations by deleting the increase the storage capacity of the made a determination based on that mqu:.rements to orm additional spent fuel pool from its present 1386 assessment, it is so indicated.

surveillance tes g when the associe'ed storage cells to 2091 storage cells. This nt Pomms andw would be accomplished by replacmg the For further details with respect to the present medium density fuel racks with action see (1) the applications for g"beITa* '"

" f "" g.

12 fme-standing, self-supporting high amendment, (2) the amendment, and (3)

Per e.

density rock modules constructe i of b Commission's related lottar, Safet Date ofissuance: April 7,1993 stainless stal and a neutron absorber Evaluation and/or Environmental y

Effective date:Immediately, to be material (boron carbide and aluminum.

Auesament as indicated. All of these implemented within 30 days.

composite sandwich, product name Items are available for public inspection Amendment Nos.: 144 and 133 "bors!"). In addition, the proposed at b Commission's Public Document Focility Operating Ucense Nos. DPR.

amendments would add controls Room, the Gelman Building,2120 L 39 and DPR-48. The amendments affecting the fuel arrangement and Street, NW., Washington, DC 20555, and revised the Technical Speciacations.

specing of fuelin the spent fuel pool at the local public document rooms for revise related surveillance requueme*nts, the particular facilities involved.

Date ofinitial notice m Federal Register: March 3,1993 (58 FR 12258) address controls for fuel movement over Conunonwealth Edison Company.

The Commission's related evaluation the cask loading area of the spent fuel Docket Nos. STN 50-454 andSTN 50 of the amendments is contained in a pool, revise the operability uirements 453. Byron Station, Unit Nos. I and 2, Safety Evaluation dated April 7,1993.

of the crane interlocks and ysical Ogle County, IllinoisDocket Nos. S'1W No signikant hazards consideration stops, address additional storage 50-458 and STN 50 457 Braidwood comments received: No capacity in the cask loeding area, and Station, Unit Nos.1 and 2 Will County, LocalPublic Document Room incorporate other related information.

Illinois Date of publication ofindivtdual location:Waukegan Public Ubrary,128 notice in federal Register:]une 24,1992 Date ofopplication foramendments:

N. County Street, Waukegan, Illinois (57 TR 28217)

A ril 15,1992, as supplemented 60085.

P Expuution date ofindividual notice:

November 23,1992.

July 24,1992 Duke Power ComPanT, Docket Nos. 50-LocalPublic Document Room Brief description of amendments:The 269,50-270 and 50-2s7. Oconee amendments revise the Technical Nuclear Station, Units 1,2 and 3, location: Chattanooga. Hamilton County SpeciBcations to incorporate the results Oconee County, South Carolina Ubrary,1101 Broad Street, Chattanooga, of the Setpoint Reconcilation Program Date of application 'or amendments:

ennessee 37402 Notice oflasuance of Amendments to Date ofissuance: April 13,1993 Demmber 8,1992 facility Operating Ucenses Effective date: April 13,1993 Briefdescription of an'endments:The amendments (1) exteno he time interval During the riod since publication of beoen Reacter Protectim System the last biwee y notice, the facility O eroting Ucense Nos. NPF.

(RPS) instrument channes tasts from a P

Cornmisalon has issued the following 37, NPF-66. NPF 72 and NPF-77: The month to 45 days on a s a red time amendments. The Commisalon has amendments revised the Technical basis (2)denne"stagge uma basis,"

determined for each of these S eciScations.

P and (3) remove the time limitation on amendments that the application Date offiutialnoticein Federal placing one RPS channelin bypass and complies with the standards and Register: June 10,1992 (57 FR 24666) one channelin the tripped condition.

requirements of the Atomic Energy Act The November 23,1992, submittal Date ofissuance: April 8,1993 of 1954, as amended (the Act), and the provided additional clari Effective date: April 8,1993 Commission's rules and regulations.

Information that did not the Amendment Nos.:199.199, and 196 The Commission has made appropriate initial proposed no significant hazards findings as required by the Act and the consideration determination.

Facility Opemting Ucense Nos. DPR-Commission's rules and regulations in 38.DPR-47 and DPR 55. Amendments 10 CFR Chapter I, which are set forth in The Commisalon's related evaluation the licanas amendment.

of b amendments is contained in a revised the Technical Specifications.

Date ofinitial notice in Federal Safety Evaluation dated April 13,1993.

Register: March 3,1992 (58 FR 12259)

Am c-e No signiBcant hazards consideration The Commission's related evaluation Ucense comments received: No of the amendments is contained in a Hazards $"N$' No Signiacant tion Determination.

IocalPublic Document Room Safety Evaluation dated April 8,1993.

and Opportunity for A Hearing in location:For Byron, the Byron Public No significant hazards consideration connection with bee actions was Ubrary,102 N. Franklin, P.O. Box 434, comments received: No.

published in the Federal Register as Byron. Illinois 61010; for Braidwood.

IocolPublic Document Room indicated.

Unless otherwise indicated, the b Wilmington Township Public location: Oconee County Library, 501 Ubrary,201 S. Kankakee Street, West South Broad Street. Walhalla, Commisalon has determined that these Wilmington. Illinois 60481.

South Carolina 29691

r 25874 Federal Register / Vol. 58, No. 80 / Wednesday. April 28, 1993 / Notices Duquesne Ught Company, et al. Docht monitoring functions to be performed sumatIMENTAAY ap0AMAT1oH:

Nos. 50 334 and 50-412. Beaver Valley with a reduced number of operable Information on the exact agenda for the Pcwor Station Unit Nos.1 and 2 inoare detector locationa.

pubhc meetings can be obtained on Shippingport Pennsylvania The Commission had previously Friday, April 30,1993. Copies of the~

issued a Notice of Consideration of a enda will be mailed at that time.

Date of o plication foramendments:

Issuance of Amandant published in P ease direct all requests for the agenda November 1992 Brief description of amendments:De the Federal W m January 21, to the Commission's receptionist.

1M3 (58 FR SU2h Haent, by louer Paul B. Ginsburs.

Technical SpeciScations bpendix A amendments revise the A dated March 31,1993, the liranama s) relating w,, p%,

to rsector containment building j

g g

• 1

[FR Doc. 93-9659 Ptted 4-27-93; 8.4S *aml penetrations. The amendments permit g,

y g on.use caos esse-me containment penetrations to be closed amendment dapEb--hae 17,1992, using a device that is functionall equivalent to an isolation valve, flindand the licensee's letter dated March 31, flange, or manual valve during core IM3 which withdrew the appucation for heensee amendent. We abon eJtzrations or movement of irradiated fusl within containment.

documents are available for public Date ofissuance: April 6,1993 inspection at the Commiseion's Pubhc Effective date: As of date ofIsmane, Document Room, the Gelman Building.

and to be irnplemented within 60 days 2120 L Stmt. NW., WashingtonK cf issuanos and at the local pubhc document room Amendment Nos.: 170 for Unit 1 50 1 cated at the Indian River Junior for Umt 2 College Grary,3209 Mrginia Annue, F rt Pierce Florida 34954-9003.

fceility Operating Ucense Nos. DPR.

66 and NFF.73. Amendments revised Dated at Rockville. Maryland this 20th day the Twchnical Specifications.

of April,1993.

Date cfinitial notice fin Federal Por the Nudsar Regulatory Commission.

Register: January 21,1993 (58 FR 5429). Jan A. Norris, he Commission's related evaluation Proact Manager, Profeet Directorate D-J.

of the amendments is contained in a Dinsion o/ Reactor Pro /ects-FU, Ofice of Safety Evaluation dated April 6.1993.

Nudsor Reactor Regulation.

No significant hazards consideration

[FR Doc. 93-9906 Filed 4-27-93; 8 45 aml comments received: No.

en,use caos neo o,-w local Public Document Room

~

lxation: B. F. Jones Memortal Ubrary.

663 Franklin Avenue, Aliquippa, Pennsylvania 15001.

Dated at Rockville, Maryland, this 20th day of Apnl1993.

Far the NucJear Regulatory Nm M=

Stresa A. Varga.

Daractor. Drnsson of Aeactor Prefects - LT Office of Nuclear neoctor Regulatson

[FR Doc. 93-9767 Filed 4-27-93; 8 45 aml crue coot nee-e+-e i

NUCLEAR REGULATORY COMMISSION (Docket No. 50-335)

Floride Power and Ught Co.;

Withdrowel of Applicetkm lor Amerwsment to Facility Opereeng ucena.

The United States Nuclear Regulatory Commission (the Commission) haa granted the request of Floride Power &

Ught Company (the boensee) to withdraw its December 17,1992 eppucation for proposed amendmaat to Facihty Operating uaanse No. DPR-47 i

for St. Lucie. Unit 1. located in St. Lade I

County, Flodda.

1 The proposed amandmant would han revised the Techakal 4

Specifications to allcw cartain j

l u

a i

CONGRZ88IONAL CORRESPONDENCE SYSTEX DOCUMENT PRZPARATION CHECKLIST This checklist is be submitted with each document (or group of Q3/As) sent for 4 ing into the CCS. ',

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1.

BRIEF DESCRIPTION OF DOCUXZNT(5

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TYPE Or DOCUMENT", /

Correspondensen Etaringra (Qs/As) 2.

3.

DOCUXENT CONTROL 8ensitive (NRC Only)

Non-Sansitive

[x 4.

CONGRESSIONAL COXXITTEE and SUBCOXXITTEES (if applicable)

Congressional Committee Subcommittaa i

5.

SUBJECT CODES (a)

(b)

(c) 6.

SOURCE OF DOCUMENT 8 (a) 5520 (document name (b)

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Scan.

(c)

Atlachments (d)

Rakey (a)

Other 7.

SYSTEM LOG DATES (a)

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Date OCA sent document to CCS (b)

Date CCS receives 4 document (c)

Date returned to oCA for additional information (d)

Date resubmitted by-CCA to CCS

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(e)

Data entered into CCS by

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(f)

Date OCA notified that document is in CCS 6')

8.

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