ML20086L219
| ML20086L219 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/05/1974 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20086L221 | List: |
| References | |
| AO-74-17, NUDOCS 8402070465 | |
| Download: ML20086L219 (2) | |
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PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET
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l April 5,1974 e
)f Mr. A. Giambusso Deputy Director of Reactor Projects United States Atomic Energy Commission l
Directorate of Licensing j
Washington, D.C.
20545 1
Dear Mr. Giambusso:
Subject:
Abnormal Occurrence The following occurrence was reported to Mr. R. A. Feil, A.E.C. Region I Regulatory Operations Office on March 30, 1974 Written noti fication was made to Mr. James P. O'Reilly, Region I Regulatory Operations Office on April 1, 1974 In accordance with Section 6.7.2.A of the Technical Specifications, Appendix A of DPR-44 fer Uni t 2 De=ch 9ettem ate-ie D~.ar St=tien, the fe!!ening report is being submitted to the Directorate of Licensing as an Abnormal Occurrence.
Reference:
License Number DPR-44, Amendment No. 1 Technical Speci fication 3.6.D.2. (a)
Report No.:
50-277-74-17 Report Date:
April 1,1974 Occurrence Date: March 29, 1974 Facility:
Peach Bottom Atomic Power Station R.D. #1, Delta, Pennsylvania 17314 Identification of Occurrence:
Indication of bellows leak on reactor relief valve 71G.
Conditions Prior to Occurrence:
Plant at approximately 24% power during a start-up.
Description of Occurrence:
During a plant start-up with the reactor pressure stable at approximately 930 psig, the bellows leak indicator for rel'ef valve 71G illuminated.
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Mr. A. Giambusso April 5,1974 Page 2 Designation of Apparent Cause of Occurrence:
Continued plant operation at signi ficant power levels has prevented investigation of this problem to date.
Because the reactor power level was too high to permit a drywell entry at the time the bellows Icak indication was indicated, verification cf an actual bel-lows leak could not be accomplished. The overpressure relief valve function of this valve is assumed to be inoperabic.
Analysis of Occurrence:
The failure of the pressure relief valve function of one valve has no safety significance because sufficient relief valves are insts11ed to provide a 25 psig margin between peak pressure and the point at which the first safety valve opens with only 7 operable relief valves assuming a 3 second main steam line isolation and a neutron flux scram from full power.
Ten relief valves are still operable.
Corrective Action:
Corrective action will be undertaken following the next shutdown. The Technical Specifications permit continued plant opera-cion for 30 days wi:r. one inoperanie sarety valve tunctior.
,t or.c relief valve.
Fo11cwing shutdown, the leaking bellows indication will be verified and repairs initiated if required.
Failure Data:
Several bellows assemblies have leaked at the "0" ring joint in the past. Refer to A0 report 50-277-74-16 and A0 report 50-277, dated November 16, 1973.
Very truly yours,
/97kw3 M. J. Cooney f/
Asst. Gen 1'. Superinterident Generation Division cc: Mr. J. P. O'Reilly Director, Region I U.S. Atomic Energy Commission 631 Park Avenue King of Prussia, PA 19406 N