ML19324C184
| ML19324C184 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 11/06/1989 |
| From: | Weiss E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19324C183 | List: |
| References | |
| 50-440-89-12, NUDOCS 8911150146 | |
| Download: ML19324C184 (2) | |
Text
The Cleveland Electric Illuminating Company Docket No. 50-440 Perry Nuclear Power Plant License No. NPF-58 As a result of the inspection conducted on June 27 through October 23, 1989, and in accordance with 10 CFR Part 2, Appendix C - General Statement of Policy and Procedure for NRC Enforcement Actions (1989), the following violations were identified:
A.
10 CFR Part 50, Appendix J. Paragraph II.G. requires that Type B tests be performed to dettct local leaks and to measure leakage across each pressure-contain?ng or leakage-limiting boundary for containment aenetrations whose design incorporates gaskets, among others.
l Jaragraph III.D.2 requires that Type B tests on penetrations incorporating gaskets be performed during reactor shutdowns for refueling, i
but in no case at intervals greater than two years.
If opened following a Type A or Tyne B testing, containment penetrations subject to Type B i
testing shall se Type B tested prior to returning the reactor to an operating mode requiring containment integrity.
Contrary to the above, no Type B tests were conducted on the gasketed flange of the residual heat removal relief valve E12-F055A seal leak off
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line since it was tested as part of the preo>erational Type A test performed in 1983.
In addition, the flange lad been disassembled at least twice, in 1986 per Work Order 86-1673 and in 1987 per Work Order 87-6296, j
and each time no Type B test was conducted prior to returning the reactor to )ower operation.
During the 1989 refueling outage the flange was also wor (ed on and during the Type A test was found to be leaking at least l
1.62 scfm or 45% of the maximum containment allowable leakage rate.
This is a Severity Level IV violation (Supplement I).
B.
10 CFR Part 50, Appendix B, Criterion VI requires that procedures including changes thereto, which prescribe activities affecting quality be reviewed for adequacy.
i Contrary to the above on July 6, 1989, during the performance of the containment integrated leak rate test the licensee revised its containment leak rate testing procedure without a review for adequacy to permit the flooding of the main steam lines. The inadequacy of the revision allowed water to leak out of the main steam lines thru an open drain line flooding the drywell lower level which required realignment of valves to drain the drywell before continuing the test.
This is Severity Level IV violation (Supplement I).
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'8911150146 891107 PDR ADOCK 05000440 0
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l Pursuant to the provisions of 10 CFR 2.201, you are required to submit to this office within thirty days of the date of this Notice a written statement or L
explanation in reply, including for each violation:
(1) the currective steps that have been taken and the results achieved; (2) the corrective steps that will be taken to avoid further violations; and (3) the date when full compliance will be achieved.
Consideration may be given to extending your h
response time for good cause shown.
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Dated Eric W. Weiss, Acting Chief L
Operations Branch
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