ML20086L223
| ML20086L223 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/01/1974 |
| From: | Ullrich W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20086L221 | List: |
| References | |
| AO-74-17, NUDOCS 8402070467 | |
| Download: ML20086L223 (1) | |
Text
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Peach Bottos Atomic Power Station j;
Dalta, Pennsylvania
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h 17314
( >jg..R A M April 1. 1974 Kr. James P. O'Reilly, Director gf f. 3 3 7 - //N Unitcd States Atomic Energy Conmission Directorate of Regulatory Operations bdb-y 631 Park Avenue I
King of Prussia, Pennsylvania 19406 i
Subject:
Abnormal _ _0ccurrence 24-Hour Notifica_ tion Confirming Mr. Frang's conversation with Mr. R.A. Feil A.E.C. Region I Regulatory Operations office on March 30, 1974.
Reference:
1.icense Number DPR-44 Amendment Number 1
.'l Technical Specification 3.6.D.2 (a) t Report No.:
50-277-74-17 Report Date:
April 1, 1974
- . Occurrence Date
March 29, 1974
.l Facility:
Peach Bottom Atomic Power Station R.D. 1, Delta, Pennsylvania 17314 Identification of Occurrence:
Indication of bellows leak on reactor relief valve 71G.
2 Conditions Prior to Occurrence: -
Plant at approximately 24% power during a atart-up.
Description of Occurrence:
During a plant start-up with the reactor pressure stable at approxi-mately 930 psig, the bellows leak indicator for relief valve 71G j
. illuminated.
Designation of Apparent Cause of Occurrence:
f Not known at this time.
Because power level was too high to permit i
a drywell entry to obtain verification of an actual bellows leak, the overpressure relief valve function was assumed to be inoperable
,j for this valve.
Analysis of Occurrence The failure of the pressure relief valve function of one valve has no safety significance because sufficient relief valves are installed to provide a 25'psig margin between peak pressure and the point at' I
vh.ich the first safety valve opens with only 7 operable relief valve.s E
assuming a 3 second main' steam line isolation and a neutron flux scram from full power. Ten relief valves are still operable.
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8402070467 740405 PDR ADOCK 05000277 i
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S PDR
. Corrective Action Corrective actio llbeundertakenfollowingthcpfxt shutdown.
The Technical Spe(dnications permit continued planFoperation for
~
. 30' days with one inoperable safety valve function of one relief valve. Following shutdown, the leaking bellows indication vill be 5
verified and repairs initiated if required.
i Failure Data:
Several bellows assemblies have leaked at the "0" ring joint in the past. Refer to A0 report 50-277-74-16 and Ao report
(
50-277-November 16, 1973.
2 :
fg W.T. Ullrich, Superintendent i
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Piach Bottom Atomic Power Station i
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