ML20100F932

Forwards Reactor Containment Bldg Integrated Leak Rate Test for Braidwood Nuclear Power Generating Station, from 951101-16

ML20100F932
Person / Time
Site:	Braidwood
Issue date:	02/15/1996
From:	Tulon T COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20100F935	List: ML20100F932 ML20100F937
References
BW-96-0018, BW-96-18, NUDOCS 9602220249
Download: ML20100F932 (1)

Text

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Commonwealth Illnon Company j

, liraidwtxid Generating Station

!/ Route al, llox 8 4 I

liramille, IL M 607-9619 Tel H15-158 2801

)

February 15,1996 i BW/96-0018 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk l

l

Subject:

Braidwood Station's Unit 1 Reactor Containment Type A Integrated l

Leakage Rate Test '

NRC Docket Nos. 50-456 and 50-457 Enclosed is Comed's report for the " Reactor Containment Building Integrated Leak Rate Test," conducted from November ist through November 16,1995, 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.

i The report describes the third Unit 1 Type A containment leakage rate test perfoimed using Braidwood Technical Surveillance IBwVS 6.1.2.a-1, " Unit 1 Primary l

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 Harvey Cybul, Braidwood Systems Engineering Supervisor, at (815) 458-2801, extension 2243.

J. Tulon Station Manager Braidwood Nuclear Station 0:CORRESivCSTECifBW96-0018 Attachment cc: 11. J. Miller, NRC regional Administrator, Rill R. R. Assa, Project Manager, NRR C. Phillips, Senior Resident inspector I

9602220249 960215

! PDR ADOCK 05000456 P PDR -

220054 m m C_sm, ,y1 1 i

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