ML20235J954

Forwards Safety Evaluation Discussing Duration of Integrated Leak Rate Test for Plant Containment,Per Recipient 860711 Memo.Std for Test Ref in 10CFR50,App J & for Shorter Run in Topical Rept BN-TOP-1.Otherwise Test Needs NRC Review

ML20235J954
Person / Time
Site:	Oconee, 05000000
Issue date:	07/08/1987
From:	Lainas G Office of Nuclear Reactor Regulation
To:	Gibson A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
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References
FOIA-87-714 NUDOCS 8707160074
Download: ML20235J954 (1)

Text

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50-?f9. 50-270 g g,1987 dnd bO-?I7 PJ J 7 6 5/

NLPORANDUM fCF' Albert F. Gibson, Director Division nf Reactor Safety Pegion 11 FP0":

Gus C. laines, Assistant Director for Reactor Projects II Division of Reactor Projects 1/11 51'PJECT:

D!!RA110N OF THE INTEGRATED LEAK RATE TEET FOR CONTAINMENT Peference:

Oconee Nuclear Station, Units 1, F, and 3 In your July II.1986 memorandum to Mr. Gary M. Holahan, you asked for our assistance in answering twc questions:

1.

'an a test on the containment to detemine the integrated leak rate be run for less than ?4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />? and T.

Who reviews and approves exceptions to the duration of the test?

After reviewing these issues, we agree with Pegion !! that the test should be rt.r for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> as required by the ANSI h45-4-1977 standard.

This stancard is referenced by Appendix J to 10 CFR Part 50, if an exception is to be taken in runninr. the test for a shorter period of time, then utilities must rt.n the test according te topical report. BN-TOP-1.

For any other re-1 ductiun to the test duration, utilities rust request that the NRC review and j

approve ar exc.eptions, We have enclnsed our Safety Evaluation which discusses these two issues in more

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detail.

With this memorandur we consider Task Interf ace Agreement 86-33FM to be enrroiete.

[h Gus C. La.as, Assistant Director for Reactor Projects 11 Division of Reactor Projects 1/11 inclosure:

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