ML20206J786

Revised Application for Amend to License NPF-37,revising Tech Specs to Allow Temporary Closure of Certain Valves in Safety Injection Sys During Leak Testing of RCS Pressure Isolation Check Valves

ML20206J786
Person / Time
Site:	Byron
Issue date:	06/16/1986
From:	Ainger K COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20206J790	List: ML20206J786 ML20206J796
References
1772K, NUDOCS 8606270273
Download: ML20206J786 (2)

Text

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- Commonwealth Edison i- 72 West Adams Street, Chic"go, Illinois

, b' Addrtss RIply to: Po11 Offica Box 7'67 Chicago, Illinois 60690-0767 June 16, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Byron Station Units 1 and 2 Application for Amendment to Facility Operating License NPF-37, i Appendix A, Technical Specifications NRC Docket Nos. 50-454 and 50-455 Reference (a): November 26, 1985 letter from K. A. Ainger to H. R. Denton

Dear Mr. Denton:

Reference (a) applied for an amendment to Appendix A, Technical Specifications, of Facility Operating License NPF-37 for Byron Station. The requested amendment involved Technical Specification 3.5.2, Emergency Core Cooling Systems. The proposed change would allow certain valves in the safety injection system to be temporarily closed during leak testing of some reactor coolant system pressure isolation check valves.

This letter provides information to modify the originally requested amendment. The amendment has been modified to allow closure of an additional I

valve during check valve leak testing. The amendment has also been revised to specify certain operational limitations when the valves are temporarily closed. Attachment A of this letter contains the proposed change to the Technical Specifications.

This revised amendment request has received both On-Site and Off-Site review and approval. It has also been reviewed again in accordance i with 10 CFR 50.92(c). We have concluded that no significant hazards considerations exist. Mis is documented in Attachment B.

Since this proposed change involves systems within the duplicate design of Byron and Braidwood stations, we request that it be included in the draft of the Braidwood Technical Specifications if it is approved for Byron.

l 8606270273 860616 4 '} \

DR ADOCK 0500 I

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. s Mr.'H. R. Denton June 16, 1986 Commonwealth Edison is notifying the State of Illinois of this revision to the proposed amendment by transmitting a copy of this letter and its attachments to the designated State Official.

Please direct any questions regarding this matter to this office.

One signed original and fifteen copies of this letter and attachments are provided for NRC review.

t Very truly yours,

. l .

K. A. Ainger Nuclear Licensing Administrator 1m Attachments A: Proposed Technical Specification Change B: Evaluation of No Significant Hazards Considerations cc: Byron Resident Inspector L. N. Olshan - NRR M. C. Parker - IDNS 1772K

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