ML19316A311

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Responds to Util Rept Integrated Leak Rate Tests of Reactor Containment Bldg,711029. Test Procedure Deficiencies Do Not Warrant Rejection & Containment Exhibited Acceptable Characteristics
ML19316A311
Person / Time
Site: Oconee 
Issue date: 01/12/1972
From: Deyoung R
US ATOMIC ENERGY COMMISSION (AEC)
To: Thies A
DUKE POWER CO.
References
NUDOCS 7912050880
Download: ML19316A311 (2)


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Docket No. 50-269 JAN 12 W2 Duke Fower Company ATTG: tir. Austin C. Thies DT DI j]M7 Senior Vice President Production and Transmission

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422 South Church Street P. O. Box 2178 Charlotte, North Carolina 28201 Centlepen:

Based upon our review of the Oconee 1 report, Integrated Leak Rate Tests of the Reactor Contain ent building, October 29, 1971," and subsequent inforration provided by you, we have reached the following conclusions:

1.

The test procedure deficiencies are minor and do not warrant rejection of the initini Oconee 1 Containment Leak Rate Tests.

2.

The Oconee 1 containnent exhibited acceptable leakare characteristics based on the data presented in the report und cubacqncat infort,ation on lenetration 38 and the enertency lock tests.

It is reco=nended that the leakane rate for Fenetration 38 and the encrrency lock be included in the report and added to the results of the integrated Icak rate test. This increaerd integrated leak rate sheuld then be used to calculate the allowable leakace rate (L--) for future reduced prennure tents.

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in the " Reactor Buildinr Inter.rned Leak Late Test Procedure and Measure ent System" Section (Section 2) of the report. Iter. 7 " required Plant Stetus" states that certain isolation valves are to be closed, but not that closurn runt be accotplished by the nornni rode of actuation.

Uc request that this tcat procedure be clarified to rinhe it vandatory that the rode of closure be by normal trode of actuation.

Sincerely, Original signed by

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R. C. DeYoung R. C. DeYount, Assistant Director for Pressurized L'ater Reactors Division of Reactorfhicensint aDRL:PWR-4 DRL:PWR-4 DRL:

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