ML20128F472

Forwards Public Notice Re Staff Consideration of License Amend Request for Facility & Advertising Order for Publication in Cecil Whig on 930209

ML20128F472
Person / Time
Site:	Peach Bottom
Issue date:	02/08/1993
From:	Chris Miller Office of Nuclear Reactor Regulation
To:	Doyle V CECIL WHIG, ELKTON, MD
References
NUDOCS 9302110403
Download: ML20128F472 (7)

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- February 8,1993 Docket flo. 50-277 Ceci! Whig ATTN: Vicki Doyle P.O. Box 429 Elkton, Maryland 21922

Dear Ms. Doyle:

Enclosed is a Public Notice for the Peach Bottom Atomic Power Station, Unit 2, that we would like to have published on Tuesday, february 9, 1993, in the Cecil Whig. After publication, please send a copy of the proof of run to my attention. Please note that the enclosed Public Notice and Advertising Order were faxed to you on February 8, 1993, and these hard copies are for confirmation only. If you have any questions, please call me at (301) 504-1430.

Sincerely, ChIrSesL. Miller, Director Project Directorate 1-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Enclosures:

1. Public Notice

2. Advertising Order DISTRJEUT10ti Docket file NRC and Locai PDRs PDI-2 Reading CMiller M0'Brien JShea OGC ' '

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Docket No. 50-271$1 Cecil Whig ATTN: Vicki Doyle P.O. Box 429 Elkton, Maryland 21922 Caar Ms. Doyle:

Enclosed is a Public Notice for the Peach Bottom Atomic Power Station, Unit 2, that we would like to have published on Tuesday, February 9, 1993, in the Cecil Whig. After publication, please send a copy of the proof of run to my attention. Please note that the enclosed Public Notica and Advertising-OrderwerefaxedtoyouonFebruary8,1993,andthesehardcopiesare-for'-l-confirmation only, ifyouhaveanyquestions,pleasecallmeat(301)504-1430.

Sincerely, da s Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projects - 1/l!

Office of Nuclear Reactor Regulation

Enclosures:

1. Public Notice.

2. Advertising;0r' der E

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PUBLIC NOTICE NRC STAFF CONSIDERING LICENSE AMENDMENT REQUEST FOR PEACH BOTTOM, UNIT 2 The Nuclear Regulatory Comission (NRC) has received an application dated February 2,1993 from Philadelphia Electric Company (the licensee) for an exigent amendment to Appendix A of the operating license for Peach Bottom Atomic Power Station, Unit 2, located in York County, Pennsylvania.

If approved, the amendment would add a footnote to Technical Specification (TS) Section 3.6,0.2, allowing continued operation with one ,

safety / relief valve (SRV) inoperable until the next outage of sufficient i duration which requires a drywell entry to allow entry into the drywell to fix l the valve without undue risk to plant personnel. The valve is considered inoperable due to a bellows failure which affects the mechanical pressure setpoint of the valve; the automatic and manual depressurization function of l the valve, patt of the Automatic Depressurization System (ADS), will remain I operable. The licensee has performed bounding analyses that conclude that operation in this configuration is acceptable. The plant has 11 safety / relief valves, 5 of which have the ADS function, and 2 safety valves to provide overpressure protection for the reactor coolant piping. This amendment would  !

be in effect on a one-time only basis until the valve is repaired.

The NRC has determined that the licensee Ysed its best efforts to make a timely application for the proposed change and that exigent circumstances do exist and were not the result of any fault of the licensee. The exigent  !

circumstances result from the fact that the current operating license contains a limitirg condition for operation (LCO) of 30 days following the determ', nation of inoperability of a safety / relief valve. The licensee entered this 1.C0 on January 18, 1993, when the bellow; failure alarm originally came in, the need for this TS change was not determined until ap)roximately January 26, 1993, after assessment of the circumstances of tie alarm.

Consequently, the NRC has determined that these exigent circumstances justify reducing the public notice period normally provided for licensing amendments and proposes to issue the amendment at the close of business February 12, 1993.

The licensee has evaluated the requested amendment against the standards in 10 CFR 50.92 and the NRC staff has made a proposed (preliminary) determination that the requested amendment involves no significant hazards considerattense Under NRC regulations, this means that the proposed amendment does not inyelve a significant increase in the probability or consequences of

, an accidentiwould not create the possibility of a new or different kind of accident, or involve a significant reduction in a safety margin. The licensee's' analysis is presented below:

i l 1. The proposed change does not involve a significant increase in the l probability or consequences of an accident previously evaluated.

The proposed TS change involves a change in the allowable out of service time of an SRV. SRV's are not an initiator for any of the over pressurization transients that the SRVs are designed to help l

3, 2-y l mitigate. A stuck open relief valve is an accident initiatort i however, the condition which has caused the SRV to be inoperable does I not increase the probability of a stuck open relief valve. The l design of the valve is such that a failed bellows will equalize the pressure across the first stage pilot piston and thus prevent the piston from moving and the valve from opening.

The analysis provided in the safety discussion clearly shows that the consequences of any of the overpressurization transients do not j increase with the SRV inoperable. Further, while the probability of  ;

a stuck open relief valve remains unchanged by this condition, the  !

stuck open relief valve transient was analyzed and the station can I fully handle this event.

2. The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

The proposed TS change involves a change in the allowable out of service time for an SRV. The proposed change does not introduce any new accident initiators since there are no physical changes being made to the facility.

3. The proposed change does not involve a significant reduction in a margin of safety.

The Technical Specification Bases define two design bases for the pressure relief system; first, to m et ASME overpressurization criteria, and second, to prevent opening of the unpiped spring safoty valves during normal plant isolation and load rejections. First, analysis has shown that ASME overpressurizatio1 criteria will be met.

Second, this same analysis has shown that an unpiped spring safety valve may potentially lift if two SRVs are inoperable. However, the analysis assumptions associated with the ASME overpNssurization criteria are much more conservative than the analysis assumptions required for demonstration that unpiped spring safety valves are not opened during normal plant isolations or load rejections. Analysis of the MSIV closure overpressure event with a functional MSIV position switch scram signal and two inoperable SRVs yields a peak stees line pressure below the unpiped spring safety valve setpoint.

If th's proposed determination that the requested license amendment involves no significant hazards consideration becomes final, the NRC will issue the amendment without first offering an opportunity for a public hearing. An opportunity for a hearing will be published in the Federal Reaister at a later date and any hearing request will not delay the effective date of the amendment.

If the NRC staff decides in its final determination that,the amendment

does involve a significant hazards consideration, a notice of opportunity for a prior hearing will be published in the Federal Reoister and, if a hearing is granted, it will be held before the amendment is issued.

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Comments on the proposed determination of no significant hazards consideration may be telephoned to Charles Miller Director, Project Directorate I-2, by collect call to 1-(301) 504-1430, or submitted in writing ,

to the Rules and Directives Review Branch, Division of Freedom of Information '

and Publication Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555. All consents received by close of business on February 12, 1993, will be considered in reaching a final determination. A copy of the application may be examined at the NRC's local Public Document Room located at the Government Publications Section, State Library of Pennsylvania, (REGIONAL DEPOSITORY) Education Butiding, Walnut Street and Commonwealth Avenue, Box 1601, Harrisburg, Pennsylvania 17105, and at the Commission's Public Document Room, th0 Gelman Building, 2120 L Street, N.W., Washington, DC 20555.

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