ML20086H814
| ML20086H814 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 05/28/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20086H817 | List: |
| References | |
| AO-75-38, NUDOCS 8401200250 | |
| Download: ML20086H814 (2) | |
Text
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r PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET PHILADELPHIA. PA.19101 12:518414000
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May 28, 1975
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Mr. A. Giambusso Director
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Division of Reactor Licensing N,'[
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Washington, DC 20555 l
Dear Mr. Giambusso:
Subject:
Abnormal Occurrence The following occurrence was reported to Mr. Walt Baunack, Region 1, Office of Inspection and Enforcement, United States Nuclear Regulatory Commission on May 18, 1975 Written notification was made to Mr. James P. O'Reilly, Office of Inspection and Enforcement, Region 1, United States Nuclear Regulatory Commission on May 19, 1975 In accordance with Section 6.7.2.A of the Technical Specificatio.ns, Appendix A of DPR-44 for Unit 2 Peach Bottom Atomic Power Station, the following occurrence is being submitted to the Directorate of Reactor Licensing as an Abnormal Occurrence.
Reference:
License Number DPR-44 6
Technical Specification
Reference:
4.7.A.2.f Report No.:
50-277-75-38 Report Date:
May 28,1975 Occurrence Date: May 18, 1975 Facility:
Peach Bottom Atomic Power Station R.D. 1, Delta, Pennsylvania 17314 Identification of Occurrence:
Excessive leakage through the "A" loop RHR outboard injection valvs (M0-2-10-154A).
l Conditions Prior to Occurrence:
Unit 2 shutdown.
1 Description of Occurrence-l During a routine local leak test of the RHR "A" loop injection valves, valve M0-2-10-154A was found to leak. The preliminary test per-formed, which identified the leak, was with water; later testing with air confirmed the leakage rate to be in excess of 6000 cc/ min.
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Mr. A. Gi ambusso 50-277-75-38 May 28, 1975 Page 2 Designation of Apparent Cause of Occurrence:
Under investigation.
Analysis of Occurrence:
The safety implications of the occurrence are minimal since the inboard RHR injection valve (M0-2e10-25A) was found to be leak tight.
Corrective Action:
4 The valve was disassembled and minor surface indications were noted en the seating surfaces. Following repairs, the valve will be reassembled and retested.
Failure Data:
None.
Very truly yours, O 'i [6 c' p^' d C 7
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v<"C M. J. Cooney
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Ass't Gen't Superintendent Generation Division cc: Mr. J. P. O'Rei l l y Director, Region 1 Office of Inspection and Enforcement d
finited States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 l
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