ML19323G123

Advises That Containment Isolation Valves Leak Tested W/Air Per 10CFR50 App J in Response to 800421 Request.Revised Tech Specs Reflecting Test Results Forthcoming.Notifies That Exemption Request Withdrawn

ML19323G123
Person / Time
Site:	Browns Ferry
Issue date:	05/27/1980
From:	Mills L TENNESSEE VALLEY AUTHORITY
To:	Ippolito T Office of Nuclear Reactor Regulation
References
NUDOCS 8005300421
Download: ML19323G123 (1)

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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374o1 400 Chestnut Street Tower II May 27, 1980 Director of Nuclear Reactor Regulation Attention:

Mr. Thomas A. Ippolito, Chief Branch No. 3 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Ippolito:

In the Matter of the

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Docket Nos. 50-259 Tennessee Valley Authority

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50-260 50-296 Please refer to your letter to H. G. Parris dated April 21, 1980, with the enclosed request for additional information regarding implementation of 10 CFR Part 50 Appendix J containment leakage testing at Browns Ferry Nuclear Plant. The containment isolation valves listed in the referenced letter are now tested with air in compliance with 10 CFR Part 50 Appendix J.

Local leak rate tests performed at each Browns Ferry unit during the last refueling outage have demonstrated compliance with Appendix J requirements.

We will submit revised technical specifications to reflect testing with air.

Since TVA now conforms to the requirements of 10 CFR Part 50 Appendix J for the isolation valves referenced in your April 21, 1980, letter, an exemption is no longer needed and the request is hereby withdrawn.

i Very truly yours, TENNESSEE VALLEY AUTHORITY

.% %~tA L. M. Mills, Mantger Nuclear Regulation and Safety Y

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An Ecual Opportunity Emoloyer

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