ML20070U073

Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,reducing RHR Min Flow Rate & Removing RHR Autoclosure Interlock on RHR Sys Suction Isolation Valves,Per Recommended Action Portion of Generic Ltr 88-17

ML20070U073
Person / Time
Site:	Byron, Braidwood
Issue date:	01/31/1991
From:	Schuster T COMMONWEALTH EDISON CO.
To:	Murley T Office of Nuclear Reactor Regulation
Shared Package
ML20070U075	List: ML20070U073 ML20070U080
References
GL-88-17, NUDOCS 9104080104
Download: ML20070U073 (2)

Text

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l January 31, 1990

// /p Dr. Thomas E. Murley Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington DC 20555

Subject:

Byron Station Units 1 & 2 Braidwood Station Units 1 & 2 Application for Amendment to Facility Operating Licenses NPF-37/66 & NPF-72/77 Implementation of Generic Letter 88-17 NRC DochgLRom. 50-414J655 and_iO-456/457

Dear Dr. Murley:

Commonwealth Edison proposes to amend Appendix A. Technical Specifications of Facility Operating Licenses NFF-37 & 66/NPF-72 & 77 for Byron /Braidwood Stations, pursuant to 10 CFR 50.90. The proposed amendment is the result of an engineering review to identify any Technical Specification changes which might prevent or mitigate the consequences of a loss of decay heat removal event. Amending Technical Specifications was one of the programmed enhancements specified in the " Recommended Actions" portion of Generic Letter 88-17. Three major requirement changes were identified. A detailed description of the changes can be found in Attachment 2 but may be summarized as follows:

1) Reduction of the residual heat removal (RHR) minimum flowrate during refueling operations.

2) Removal of the RRR auto closure interlock on the RER system suction isolation valves.

3) Allow one safety injection pump to be available for injection purposes if normal heat removal capability were lost.

Attachment 1 contains the marked up Technical Specifications and Bases Pages indicating the proposed changes. Attachments 3 and 4 contain the Significant Hazards Consideration Evaluation and Environmental Assessment respectively.

The proposed Amendment has been reviewed and approved by both on-site and off-site review in accordance with 10 CFR 50.92(c). We request the review and approval of this proposed Amendment be completed by August 1, 1990. This will allow an appropriate amount of time for planning and scheduling the j i removal of the autoclosure interlock feature in the next Unit 2 Byron .

refueling outage currently scheduled for September, 1990. '

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, , C , T.E.'Murley - 2 -

January 31, 1990 Commonwealth Edison'is notifying the State of Illinois of this application for amendment by transmitting a copy of this letter and it's attachments to the designated State Official.

Please direct any questions regarding this submittal to this office.

Very truly yours, M

T.K. Schuster Nuclear Licensing Administrator Attachment 1) Marked.up Technical Specification & Bases Pages

2) Detailed description of changes

3) Evaluation of Significant Hazards Considerations

4) Environmental Assessment ec: Resident' Inspector-Byron Resident Inspector-Braidwood

@ . Shemanski-NRR S.P. Sands-NRR 4 Region III Office pficeofNuclearFacility-IDNS 1

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