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-

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IC7, Downers Grove, I!!inois 60515 J

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 Supplement to-the'_ Application for t

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.

{0 9009190125 900906 ADOCK0500g4 DR 3

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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 j

S. C. Hunsader.

Nuclear Licensing-Administrator i

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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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