ML20248F985

Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising Tech Spec Tables 3.3-1 & 4.3-1,per Generic Ltr 85-09 for Reactor Trip Sys Automatic Actuation Using Shunt Coil Trip Attachments

ML20248F985
Person / Time
Site:	Byron, Braidwood, 05000000
Issue date:	04/03/1989
From:	Hunsader S COMMONWEALTH EDISON CO.
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML20248F989	List: ML20248F985 ML20248G005
References
0064T:2, 64T:2, GL-85-09, GL-85-9, NUDOCS 8904130281
Download: ML20248F985 (2)

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Comm nwealth Edison i ' 72 West Adams Street Chicago, Illinois ' a

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[\ Address Reply to: Post Othce Box 767 ~ -)

( Chicago, Illinois 60690 0767 i l

April 3., 1989 l

Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 l Attn: Document Control Desk j i

Subjects Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 Application for Amendment to Facility Operating Licenses NPF-37, NPF-66, and NPF-72 and NPF-77 Appendix A, Technical Specifications NRC Docket Nos. 50-454; 50-455. 50-456 and 50-457 Reference (a): December 23, 1987, S.C. Hunsader letter to T.E. Murley

Dear Dr. Murley:

In reference (a), Pursuant to 10 CFR 50.90, Commonwealth Edison (Edison) proposed to amend Appendix A, Technical Specifications, of Facility Operating Licenses NPF-37, NPF-66, NPF-72, and NPF-75 (Now NPF-77). The proposed amendment requested changes to Technical Specification Tables 3.3-1 and 4.3-1, as requested in Generic Letter 85-09 for Reactor Trip System Automatic actuation using shunt coil trip attachments. Based on recent discussions with the.NRC staff, Edison is supplementing that submittal with additional information. Specifically, Edison'is adding how testing will be performed on the by-pass breaker. As a means to facilitate the NRC review,-

a complete package of the amendment request is being provided with this I letter.

i The revised Technical Specification pages are contained in Attachment A. The description and summary of the proposed changes is presented in Attachment B. Attachment C provides the Safety Evaluation and j Environmental Assessment.

The proposed changes have been reviewed and approved by both on-site and off-site review in accordance with Commonwealth Edison procedures. Commonwealth Edison has reviewed this proposed amendment in accordance with 10 CFR 50.92(c) and has determined that no significant hazards consideration exists. This evaluation is documented in Attachment D.

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.

8904130281 DR 890403 3 ADOCK 05000454 f I l

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'Please. direct any questions you may have concerning'this matter to Lthis office.

Very truly yours, llb D gr#

d e' S. C. H nsader Nuclear Licensing Administrator

/scl Attachments (A): Proposed Technical Specification Changes (B): Description and Summary (C): Safety Evaluation and Environmental Assessment (D): Evaluation of.Significant Hazards Consideration

.cc Resident' Inspector -Byron Resident Inspector - Braidwood L. N. Olshan - NRR S. Sands - NRR Region III Office M. C. Parker - State of Ill.

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