ML20236D092

Forwards Response to Fire Protection Open Items,Per Request During 870730 Meeting W/Nrc Re Fire Protection Program, Including Safety Evaluations for Mods 2085 & 2079

ML20236D092
Person / Time
Site:	Peach Bottom
Issue date:	10/16/1987
From:	Gallagher J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Butler W NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation
Shared Package
ML20236D095	List: ML20236D092 ML20236D127 ML20236D153
References
NUDOCS 8710280017
Download: ML20236D092 (3)

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PHILADELPHIA ELECTRIC COMPANY g 2301 MARKET STREET g P.O. BOX 8699

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O PHILADELPHIA A. PA.19101 I

(215) 841 5001 )

JOSEPH W. G ALLAGHER p

.o!E."..".'/.'."I"l... October 16, 1987 u; G9 Docket No. 50-277 50-278 Mr. W. R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555

SUBJECT:

Peach Bottom Atomic Power Station Responses to Fire Protection Open Items

References:

(1) Letter to W. M. Alden (PECo) from R. E. Martin (NRC) dated July 27, 1987 (2) Letter to Philadelphia Electric Company from R. E. Martin (NRC), dated September 14, 1987 (3) Letter to W. F. Kane (NRC) from S. J. Kowalski (PECo) dated November 28, 1986

Dear Mr. Butler:

The purpose of this letter is to forward information requested by the staff at a July 30, 1987 meeting held at the Peach Bottom site to discuss the fire protection program and other issues. The following information included in this submittal is identified by agenda numbers from the agenda transmitted to Philadelphia Electric Company (PECo) in Reference 1:

Agenda Items A.1-A.ll Safety evaluations to resolve agenda items A.1 through A.11 were given to the Nuclear Regulatory Commission during the July 30, 1987 meeting for modifications 1029E, 1351D, 1352A, 8710280017 871016 h PDR ADOCK 05000277 gh p PDR l ,1

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,- r.'W. R. Butler October 16, 1987 l Page 2 l

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a 1353A,'1950, 1950A, 2079,.2079, 2080, 2082, 2084, and '2091. '

"@ Attachment-I is the safety evaluation for' modification 2085 which was-not available at the July 30, 1987 meeting,.and the  !

safety evaluation for modification 2079 which was not-included as a'part of Enclosure 4 to Reference 2. As discussed in the July.30, 1987 meeting,' modification 2084 is an-interim means to resolve noncompliance'II.A.2 identified in our Justification:for Continued Operation (JCO)rsubmittal ,

(Reference 3). This modification has been implemented on )

Unit 2. Modification 2285 is the permanent resolution'for j this noncompliance which will be implemented on Unit 3-during

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+ the current pipe replacement outage. The same modification a will be implemented on Unit 2 during-the next-refueling

. outage. The only outstanding safety evaluation is for modification 2285. The design of this modification is in progress, and the safety evaluation will be completed'and i forwarded to the Nuclear Regulatory Commission by January 1,  !

1988.-

Agenda Item C

Attachment II provides additional information in response to the agenda item C discussion on high/ low pressure interfaces.  ;

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-Agenda Item D.a Attachment III provides additional information in response to the agenda item D.a discussion of compliance with'NUREG-0783. j Agenda Item E.c  !

Attachment IV provides additional information in response to the agenda item E.c discussion of cold shutdown repairs for Peach Bottom.  :

Agenda Item E.d Attachment V provides additional information in response to the agenda item E.d discussion of manpower requirements for each fire area at Peach Bottom.

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, r. W. R. Butler October 16, 1987 Page 3

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If you have any questions or require additional information, please do not hesitate to contact us.

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Very truly yours, i

I Attachments j cc: Addressee W. T. Russell, Administrator, Region I, USNRC T. P. Johnson, Resident Site Inspector 1

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