ML20070P369

Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & & NPF-77,permitting Use of Continuous Pressure Testing of Containment Airlock Door Seal Gaskets in Lieu of Manual Testing

ML20070P369
Person / Time
Site:	Byron, Braidwood
Issue date:	03/20/1991
From:	Checca A COMMONWEALTH EDISON CO.
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20070P374	List: ML20070P369 ML20070P396
References
NUDOCS 9103270271
Download: ML20070P369 (2)

Text

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[ D Ctmmenwealth Edison

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) 1400 opus Place

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) Downers Grove,Illinoin 60516 March 20,1991 Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulatiori

- U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Document Control Desk

Subject:

Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 Amendment of Facility Operating Licenses

- NPF 37, NPF 66, NPP 72, and NPF 77 NRG RocketNo.L5A45AL45.5_and.50 A55L455

Reference:

(a) - October 4,1988 letter from R.A. Chrzanowski to T.E. Murley.

(b) August 14,1989 letter from R.A Chrzanowski to i.E. Murley.

Dear Dr. Murley _

Reference a) provided the request for amendment to the Byron and Braldwood Station Te(chnical Specifications to nermit the use of continuous press testing of the containment airlock door seal gaskets In lieu of manual testing.

Reference (b) provided information about the radiation exposure reduction that would occur _with this amendment. After discussions with the staff it has been determined that additional surveillance testing of the cutainment airlock seals would increase the assurance that the limiting condition for operation would be met. Consequently, a revised technical specification page is being submitted to incorporate the additlonal requirement.

The revised Technical Specification page is contained in the enclosure. The 3roposed change has been reviewed and approved by both on site and off site review n accordance with Commonwealth Edison procedures. Commonwealth Edison has reviewed this proposed amendment in accordance with 10 CFR 50.59 determined that no significant hazards consideration exists. This evalu(c) and has ation was previously submitted n reference (a).

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Dr. T.E. Murley 2-March 20,1991 Commonwealth Edison is notifying the State of Illinois of this su3plement to our application for this amendment by transmitting a copy of this letter to I,s enclosure to the designated State Official.

To the best of my knowledge and belief the statements contained herein are true and correct in some respects, these statements are not based on my personal -

knowledge but upon information realved from other Commonwealth Edison and contractor em yees. Such information has been reviewed in accordance with Company prac ce and I believe it to be reliable.

Please direct any questions you may have concerning this matter to this Very truly ycurs, Allen R. Checca -

Nuclear Licensing Administrator l

l Enclosure

{

cc: ' S. DuPont Resident inspector, Draidwood W. Kropp Resident inspector, Byron L

R. Pulsifer-Pr ect Manager, NRR Braldwood A. Hela Projec Manger, NRR Byron-

- A. Davis Re lonal Administrator, Rlll i

IDNS Office o Nuclear Facility Safety i

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