ML20072E505

Forwards Reactor Containment ILRT Comm Ed Braidwood Nuclear Power Station Unit 1 Conducted from 940304-0422.Rept Describes Second Unit 1 Type a Containment Leakage Rate Test Performed Using Technical Surveillance 1BwVS 6.1.2.a-1

ML20072E505
Person / Time
Site:	Braidwood
Issue date:	08/12/1994
From:	Kofron K COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20072E508	List: ML20072E505 ML20072E511
References
BW-94-0131, BW-94-131, NUDOCS 9408220273
Download: ML20072E505 (1)

Text

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l August 12, 1994 BW/94-0131 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk

Subject:

Braidwood Station's Unit 1 Reactor Containment Type A Integrated Leakage Rate Test .

NRC Docket Nos. 50-456 and 50-457 Enclosed is Com Ed's report for the " Reactor Containment Building Integrated Leak Rate Test," conducted from March 4 through April 22, 1994, for Braidwood Unit 1. This report is to be submitted to the

) NRC approximately three months after conducting the test in accordance with 10 CFR 50, Appendix J, Section V.

The report describes the second Unit 1 Type A containment leakage rate test performed using Braidwood Technical Surveillance 1BwVS 6.1.2.a-1, " Unit 1 Primary Containment Type A Integrated Leakage Rate Test (ILRT)," in accordance with the requirements of

) 10 CFR 50, Appendix J, Section III.A.

Should you have any questions, contact Allen Checca, Braidwood Systems Engineering Supervisor, at (815) 458-2801, extension 2243.

.b c K. L. Ko r'n Station Manager Braidwood Nuclear Power Station KLK/JML/dla Attachment cc: J. B. Martin, NRC Regional Administrator, RIII R. R. Assa, Project Manager, NRR j S. G. DuPont, Senior Resident Inspector

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