ML20087L593
| ML20087L593 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/03/1974 |
| From: | Burstein S WISCONSIN ELECTRIC POWER CO. |
| To: | Oleary J US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20087L573 | List: |
| References | |
| NUDOCS 8403270288 | |
| Download: ML20087L593 (2) | |
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q 231 WEST MICillGAN,MlLWAUKEf, WISCONSIN 53201
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May 3, 1974 Mr., John F. O' Leary, Director Directorate of Licensing U. S. Atomic Energy Commissioit i
Washington, D. C.
20545
Dear Mr. O' Leary:
DOCKET NO. 50-266 POINT EEACH NUCLPAR PLANT LEAKAGE TESTS OF ISOLATION VALVES 1
This letter is to report the details of an abnormal occurrence at Point Beach Nuclear Plant, Facility Operating License' No. DPR-24, as defined by Section 15.1.a.F of the
, Technical Specifications.
This written report is submitted
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in accordance with Section 15.6.6.A.2 of the Technical Speci-fications and follows a telephone report on the subject made to Mr. K. R. Baker'of Region III, Directorate of Regulatory
'oporneinne april ??, -10'; a, m e,anniega.37.cncti7n 15,g,g,3,1 nn of the Technical Specifications.
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l On April 6, 1974, Unit 1 at Point Beach Nuclear Plant was removed from service to conduct the second refueling of the 7
unit.
During the period of the shutdown, presently estimated at seven weeks, leak tests of containment isolation valves are being conducted in accordance with Section 15.4.4.III of the Point Beach Technical-Specifications.
To date, two valves, in both cases second-off valves from the containment, have been found to~ leak in excess of 2000 cc/ min.
We consider containment, isolation valves which exhibit leakage beyond this figure to be reportable items.
At this date approximately 70% of the containment isolation valves have been leak tested an~d testing of the re-mainder is'in progress.
Should other valves be found to have leakage in excess of 2000 cc/ min we will inform the Region III DRO inspector by telephone within the required twenty-four hour time period.
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44 2-May 3, 1974 Mr. John F. O' Leary' 3
It is our intention to repair the valves in ques-tion and retest following repair.
Following the completion of all surveillance testing and repair.(where required) of the Unit 1 containment isolation. valves, we will submit a
' followup report describing the initial leakage, repair and retest of any containment isolation. valve which does not meet the~ initial tecc critaria, as described above.
f Very-truly yours, D
I Sol Burstein Exect ive Vice President 4
Mr. James G. Keppler, Regional' Director i
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Directorate of Regulatory Operations,' Region III i
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