ML20126E265
| ML20126E265 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 07/14/1965 |
| From: | Doan R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Wall H CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| NUDOCS 8101150781 | |
| Download: ML20126E265 (2) | |
Text
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'g 141965,
Docket No. 50-155 Consumers Power Company 1945 Farnell Road Jackson, Michigan Attentioat Mr. R. R. Wall Vice President Gentlement As you know, the Technical Specifications of License No. DPR-6 for the Big Rock Point Nuclear Plant require that as integrated leakage rate test of the containment building be conducted at least once every two years, pending agreement upon a different testing frequency. Your second semi-saamal report of operations at the plant, dated June 25, 1965, outlines the results of the most recent (April 1964) test. To aid is the estab-lishment of a more naamingful testing schedule, which in part would be based upon actual testing experience, we believe it would be helpful to obtain a more comprehensive report of the April 19M ttst.
Accordingly, we would appreciate it if you would provide us a report on the 19% leakage rate test which weald contata the followiar datas Schematic arressenest of leakage measuring system employed, a.
including descripties of the instrumentaties and their readable accuracy (least division).
b.
The test procedure and any preparatory work er leak repairs necessary prior to coedoet of test.
c.
Summary of test data recorded la graphical form.
d.
Corrections applied to test data and factors employed to predict the leakage rate under conditions associated with the accident analysis.
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EURNAME>
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Pbrm ABC-818 (Rev. 6-53)
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Analysis and interptecation of leakage rate results including error or uncertainty evaluatiocre associated with the measured leakage rate.
f.
A sumanry of the f.eak repairs performed after the test (if any) to ensure that ar;p expected increase in the leakage rate of the containment vessel, from the "as rasasured" or "as repaired" condition before the next scheduled test will not exceed the anziams allowable leakage rate specified la the license.
sincerely yours, Orlin!SignM &
R.LDoan R. L. Dosa, Director Division of Reactor Licensing bec:
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