ML20086K324
| ML20086K324 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/05/1974 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| AO-74-46, NUDOCS 8401270028 | |
| Download: ML20086K324 (2) | |
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,g November 5, 1974 Mr. A. Giambusso Deputy Director of Reactor Projects United States Atomic Energy Commission Directorate of Licensing Washington, DC 20545
Dear Mr. Giambusso:
Subject:
Abnormal Occurrence The following occurrence was reported to Mr. Burt Davis, A.E.C.
Region 1 Regulatory Operations Office on October 26, 1974. Written notification was made to Mr. James P. O'Reilly, Region 1 Regulatory Operations Office on October 28, 1974.
In accordance with Section 6.7.2.A of the Technical Specifications, Appendix A of DPR-44 for Unit 2 Peach Bottom Atomic Power Station, the following report is being submitted to the Directorate of Licensing as an Abnormal Occurrence.
Reference:
License Number DPR-44, Amendment Number i Technical Specification Paragraph 3 6.D.2(a)
Report No.:
50-277-74-46 Report Date:
November 5,1974 Occurrence Date: October 26, 1974 Facility:
Peach Bottom Atomic Power Statien R.D. 1, Delta, Pennsylvania 17314 Identif 4 cation of Occurrence:
Bellows leak indication on relief valve 71J.
Conditions Prior to Occurrence:
Unit 2 operating at approximately 90% power.
~
Description of Occurrence:
With the plant in steady state operation, the light which moni-tors the 71J relief valve bellows integrity indicated a bellows leak.
This occurred at approximately 1:02 p.m. on October 26, 1974.
Designation of Appcrent Cause of Occurrence:
Unknown at this time. The indication reset at 9:55 p.m., on 33'd U M f' i
the same day. Power level had been reduced to approximately 87% during A
8401270028 741105 PDR ADOCK 05000277 S
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.Mr. A. Gitmbusso
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s November 5,1974 Page 2 this interval for other reasons.
The bellows leak indication light came on again at 11:37 a.m.,
October 30, 1974 and remains lit at this writing. The reactor was operating at normal pressure and approximately 81% power at that time.
Analysis of Occurrence:
Failure of a bellows assembly on a relief valve makes the safety valve function of the relief valve inoperable. The Technical Specifications permit operation for a period of 30 days with one relief valve inoperable. This occurrence has minimal safety significance.
Corrective Action:
The electrical indication actuation circuitry for valve 71J was checked to the extent possible without entering the drywell. The tests performed indicated no cable grounds existed and that the circuit was working properly. Additional investigations will be performed when accessibility to the drywell is possible.
Failure Data:
The following abnormal occurrences were previously reported to the A.E.C. which deal with difficulties experienced with relief valve bellows or bellows instrumentation:
Abnormal Occurrence dated October 31, 1973 Abnormal Occurrence dated November 9, 1973 Abnormal Occurrence dated November 16, 1973 Very truly yours,
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f M. J..Cooney y
Ass'y Gen't Superintendent Generation Division cc:
Mr. J. P. O'Reilly Director, Region i United States Atomic Energy Commission 631 Park Avenue King of Prussia, PA 19406
.