ML20211H040

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Supplemental Application for Amend to License NPF-37, Changing Tech Specs to Assure That One Essential Svc Water Pump Will Not Be Intentionally Taken Out of Svc from Each Unit at Same Time for Maint
ML20211H040
Person / Time
Site: Byron Constellation icon.png
Issue date: 10/29/1986
From: Ainger K
COMMONWEALTH EDISON CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML20211H046 List:
References
2322K, NUDOCS 8611040381
Download: ML20211H040 (2)


Text

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CONMn0RWeelth h iV One First Nabonel Plaza, Chicago, IEnois

% Address Reply to: Poet Omco Box 767 Ctuca00, IEnois 60890 - 0767 October 29, 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 Appendix A, Technical Specifications NRC Docket Nos. 50-454 and 50-455 Reference (a): August 15, 1986 letter frce K. A. Ainger to H. R. Denton

Dear Mr. Denton:

Reference (a) requested a license amendment to create an additional technical specification for the essential service water system. The proposed technical specification required an essential service water pump and associated valves of a shutdown unit to be available to support an operating unit.

This letter supplements reference (a) and contains two additional measures to assure the availability of the essential water system. First, Byron Station will not intentionally take one essential service water pump out of service from each unit at the same time for maintenance. Secondly, an additional technical specification is hereby proposed to require the availability.of the essential service water crosstie between Units 1 and 2 whenever either or both units are in Modes 1, 2, 3, or 4.

The additional technical specification is contained in Attachment

1. This' additional technical specification is being proposed for the same reason as the amendment in reference (a) was requested; that is, to address the probability and consequences of a loss of all essential service water.

As a result, our evaluation of significant hazards considerations discussed in reference (a) is applicable to this additional technical specification concerning the crosstie between units.

8611040381 861029 PDR ADOCK 05000454 P PDR

s Mr. H. R. Denton October 29, 1986 Please direct any questions regarding this matter to this office, one signed original and fifteen copies of this letter and attachment are provided for NRC review.

Very truly yours, e

K. A. Ainger Nuclear Licensing Administrator in

. Attachment cc: . Byron Resident Inspector L. N. Olshan - NRR M. C. Parker - State of Ill.

2322K

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