ML20059H996

Suppls 900420 Application for Amends to Licenses NPF-37, NPF-66,NPF-72 & NPF-77,revising Tech Spec 3/4.6.3.Since Relief Request VR-1 Will No Longer Apply After Issuance of Amends,New Relief Request Will Be Submitted in 1991

ML20059H996
Person / Time
Site:	Byron, Braidwood
Issue date:	09/06/1990
From:	Hunsader S COMMONWEALTH EDISON CO.
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9009190125
Download: ML20059H996 (2)

Text

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=,,_ /; Commonwealth Edison-J

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- i IC7, 1400 Opus Plica >

Downers Grove, I!!inois 60515 y

September 6,:1990' Dr. Thomas E. Murley Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Hashington, DC 20555-ATTH: DOCUMENT C0!! TROL DESK

Subject:

Byron Station Units 1 and.2L Braidwood Station Units 1 and 2 t

Supplement to-the'_ Application for Amendment to Facility Operating Licenses NPF-37/66 & NPF-72/77 HRC Docket Nos. 50-454/455 & 456/457 Reference (a): April 20, 1990 T.K. Schuster letter to T.E. Morley.

Dear Dr. Murley:

In reference (a), pursuant to 10'CFR 50.59, Commonwealth-Edison proposed to amend Appendix A, Technical Specifications of: Facility Operating Licenses NPF-37 & 66/NPF-72 & 77 for Byron /Braidwood. Station. The proposed amendment revises. Specification 3/4.6.3, Containment Isolation Valves, to delete the requirement for type C leakage testing for specified Steam Generator blowdown isolation valves and to insert a requirement:for-the type C leakage testing for the 1/2 SI8968-safety injection valves.

Though the type C testing requirement for the Steam Generator blowdown isolation, valves (1/2 SD002A through 1/2 50002H and 1/2 S0005A through 1/2 50005D) are to-be deleted from the Byron and Braidwood. Technical Specifications, with the issuance of the Amendment, the valves will still~be tested per the requirements of the Byron and Braidwood Pump and Valve-Inservice Testing (IST) program. A water leakage test or a more conservative air leakage test will be performed consistent with"ASME Section XI 1983 Edition, up to and including the Summer 1983 Adenda, Sub Article.IHV-3420.

Since Relief Request VR-1 to both the Byror, and Braidwood IST programs will no longer be applicable and will require revision upon issuance 1 of the Amendment, a new note or relief request will be provided to the NRC  :

staff in the next revisions to the Byron and Braidwood IST Programs that will describe the details of the leakage testing to be performed. This will De

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provided to the NRC staff prior to the Spring, 1991 outage.for Braidwood and ,

the Fall, 1991 outage for Byron.

9009190125 900906 {03 .

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-U.S.. Nuclear Regulatory Commissionj - September 6 1990.

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.i Commonwealth Edison is notifying.the State of Illinois of this supplement to the application for.this amendment.by transmitting a copy of

-this letter to the' designated State Official.

.P1' ease direct any questions you may have concerning this matter to

~this office.

Very truly:yours, ,.

.( H1:!15 S. C. Hunsader .

j Nuclear Licensing-Administrator  ;

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/ tim:ZNLD/ID241 -f cc: Resident Inspector - Byron. _

Resident Inspector - Braldwood T. Boyce - NRR S.P. Sands - NRR Regional Administrator - Region.III-Office Of-Nuclear Facility - IDNS t.

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