ML20086H614
| ML20086H614 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 07/25/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso Office of Nuclear Reactor Regulation |
| References | |
| AO-75-43, NUDOCS 8401180166 | |
| Download: ML20086H614 (2) | |
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pJ PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET s
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PHILADELPHI A. PA.19101
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July 25, 1975 U.d 3ULO J.A n
Mr. A. Giambusso VN M
Director
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Division of Reactor Licensing l
. Office of Nucicar Reactor Regulations I
United States Nuclear Regulatory Commission Washington, DC 20555 i
Dear Mr. Giambusso:
Subject:
_A_bnormal Occurrence The following occurrence was reported to Mr. Walt Baunack, Region 1, Office of Inspection and Enforcement, United States Nuclear Regulatory Commission on July 18, 1975 Written notification was made to Mr. James P. O'Reilly, Region 1, Of fice of Inspection and Enforcement, United States Nuclear Regulatory Commission on Juiy 18, 1975 In accordance with Section 6 7 2.A c,f the Technical Specifications, Appendix A cf DPR-56 for Unit 3 Peach Bottom Atomic Power Station, the following report is being submitted to the Directorate of Reactor Licensing as an Abnormal Occurrence.
Reference:
License Number DPR-56 Technical Specification
Reference:
- 4. 7. A. 2. f Report No:
50-278-75-43 Report Date:
July 25, 1975 Occurrence Date:
July 17, 1975 Facility:
Peach Bottom Atomic Power Station R.D. #1, Delta, Pennsylvania 17314 Identification of Occurrence:
Excessive Icakage through the torus water cleanup pump in-board isolation valve M0-3-14-70.
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Conditions Prior to Occurrence:
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[9 Unit 3 at approximately 50% pcwer.
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Description of Occurrence:
i During a routine local leak rate test of the torus water cican-up pump suction isolation valves, the inboard valve was found to leak in excess of 2000 cc/ min.
8401100166 750725 PDR ADOCK 05000278 COPY SENT REGION p~8L'OO u
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, Mr. A. Gi ambusso /~3
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50-278-75-43 July 25, 1975 (J
Pege 2 Designation of Apparent Cause of Occurrence:
Torque switch on motor operator was not set high enough.
Analysis of Occurrence:
Upon an isolation signal, both the inboard valve (M0-70) and the outboard valve (M0-71) receive isolation signals. The_ outboard isolation valve M0-71 indicated no leakage. Therefore, the safety implications of this occurrence are minimal.
Corrective Action:
The line was immediately isolated by closing the cutboard isolation valve (M0-71). The torque switch setting was increased and the valve packing tightened. The subsequent leak rate was found to be acceptable.
Failure Data:
None.
Very truly yours,
/
M.
. Cooney A
't Gen't Superintendent Generation Division cc:
Mr. J. P. O'Reilly Director, Region 1 Of fice of Inspection and Enforcement United States Nuclear Regulatory Comnission 631 Park Avenue l
King of Prussia, PA 19406 l
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