ML20235N817

Application for Amend to Licenses NPF-37,NPF-66 & NPF-72, Extending Allowable Outage Time for Listed Sys & Subsystems

ML20235N817
Person / Time
Site:	Byron, Braidwood, 05000000
Issue date:	09/29/1987
From:	Ainger K COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20235N819	List: ML20235N817 ML20235N879
References
3641K, NUDOCS 8710070084
Download: ML20235N817 (3)

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V Commonwealth Edison

. One First National Plaza. Chic"go, Illinois

_ ~ ' Address Riply to: Post Office Box 767 Chicago, Illinois 60690 0767 '

September 29, 1987 U.S. Nuclear Regulatory Commission  !

Attn: Document Control Desk Washington, DC 20555 j l

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Subject:

Byron Station Units 1 and 2 ]

1 Braidwood Station Units 1 and 2 Application for Amendment to Facility Operating Licenses NPF-37, NPF-66, and NPF-72, Appendix A, Technical Specifications j NRC Docket Nos. 50-454/455 and 50-456/457 References (a): May 2, 1984 letter from L.O. De1 George to H.R. Denton (b): June 24, 1986 NRC meeting Summary Gentlemen:

pursuant to 10 CFR 50.90, commonwealth Edison is hereby applying for an amendment to Facility Operating Licenses NPF-37, 66 and 72, Appendix A, Technical Specifications. The purpose of this amendment is to extend the allowable outage time (AOT) for the following systems and subsystems:

emergency core cooling system (ECCS) subsystems, containment spray system, spray additive system, containment cooling system, and component cooling water system. We believe the extended AOT's will reduce the frequency of requests for emergency relief from Technical Specification Limiting conditions for Operation. Additionally, the increased AOT's will provide a greater degree of flexibility for performing maintenance activities.

Attachment A contains the proposed changes to Technical Specifications 3.5.2; 3.6.2.1; 3.6.2.2; 3.6.2.3; and 3.7.3. Attachment B provides background information regarding the proposed Technical Specification changes.

A probabilistic risk assessment report titled " Byron Generating Station Limiting Conditions for Operation Relaxation program" (WCAP-10526, April, 1984) was submitted with reference (a) to support these proposed Technical Specification changes. The differences between the Byron and Braidwood plant designs have been reviewed and it has been determined these differences are insignificant in their contribution to the core melt frequency modeling. Thus, the conclusions of this Byron study apply to the Braidwood Units.

The proposed Technical Specification changes have been reviewed and approved by both On-site and Off-site review in accordance with Commonwealth Edison Company procedures. We have reviewed this amendment in accordance with 10 CFR 50.92(c) and determined that no significant hazards consideration exists. Our evaluation is documented in Attachment C, 8710070084 870929 O(

PDR ADOCK 05000454- hO t P PDR-JO

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• U.S. NRC September 29, 1987 Commonwealth Edison is notifying the State of Illinois of our application for this amendment by transmitting a copy of this letter and its attachments to the designated State Official.

In accordance with 10 CFR 170, a fee remittance in the amount of

$150.00 is enclosed.

Please direct any questions regarding this matter to this office.

Very truly yours,

/ d K. A. Ainger Nuclear Licensing Administrator Enclosure Attachments (A): Proposed Technical Specification changes (B): Background Information (C): Evaluation of Significant Hazards Consideration cc: Byron Resident Inspector Braidwood Resident Inspector L. N. Olshan - NRR S. P. Sands - NRR M. C. Parker - State of Illinois NRC Region III Office l

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ATTACHMENT A PROPOSED CHANGES TO APPENDIX A, '

TECHNICAL SPECIFICATIONS, FACILITY OPERATING LICENSES NPF-37, NPF-66 and NPF-72 l

Revised Pages:

Byron Braidwood 3/4 5-3 3/4 5-3 3/4 6-13 3/4 6-13 3/4 6-14 3/4 6-14 3/4 6-15 3/4 6-15 3/4 7-11 3/4 7-11 I

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