ML20086G274
| ML20086G274 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 12/30/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| AO-75-76, NUDOCS 8401100502 | |
| Download: ML20086G274 (2) | |
Text
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PHILADELPHIA E(ECTh?IC COMPANY
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2301 MARKET STREET y mp Ae
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December 30, 1975
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Mr. Victor S,tello, Jr.
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Director
,s Division of Operating Reactors N
Office of Nuclear Reactor Regulations United States Nuclear Regulatory Comission Washington, DC 20555
Dear Mr. Boyd:
OOPy1
Subject:
A_bnormal Occurrence The following occurrence was reported to Mr. Don Caphton, Region 1, Office of Inspection and Enforcement, United States Nuc lear Regulatory Commission on December 21, 1975 Written notification was made to Mr. James P. O'Reilly, Office of Inspection and Enforcement, Region 1, United States Nuclear Regulatory Comission on December 22, 1975 In accordance with Section 6.7.2.A of the Technical Specifications, Appendix A of DPR-56 for Unit 3 Peach Bottom Atomic Power Station, l
the following report is being submitted to the Directorate of Reactor Licensing as an Abnormal Occurrence.
l l
Reference:
License Number DPR-56
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Technical Specification
References:
4.7. A. 2.F
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and 3 7.D.2 l
l Report No.:
50-278-75-76 l
Report Date:
December 30, 1975 Occurrence Date:
December 20/21, 1975 Facility:
Peach Bottom Atomic Power Station R.D. 1, Delta, Pennsylvania 17314 Identification of Occurrence:
Leakage of "A" and "B" loop RHR outboard injection valves (M0-3-10-154A and B).
Conditions Prior to Occurrence:
Unit 3 operating at approximately 56% power.
Description of Occurrence:
In preparation for the scheduled Unit 3 LPRM vibration fix outage on January 3, 1975, preliminary local leak rate tests performed on December 20 and 21 identified thru leakage on both RHR outboard injection valves.
The preliminary test was performed for the purpose 8401100502 751230 N
PDR ADOCK 05000278 7
S PDR
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COPY SENP REGION '
Mr. Victor Stello, Jr.
50-278-75-76 December 30, 1975 Page 2 of identifying valves which must be maintained during the outage. Water was used as the test fluid. No attempt was made to quantify the leak rate.
_0_esignation of Apparent Cause of Occurrence:
To be determined. Valve is subject to throttling operation during shutdown cooling operation.
Analysis of Occurrence:
The safety implications of this occurrence are minimal since the inboard RHR injection valves (M0-3-10-25A and B) were found to be leak tight. These valves are normally closed with the plant operating.
Corrective Action:
The inborad isolation valves were verified as being leak tight and closed. These valves will be checked and logged closed daily until repairs can be made during the forthcoming outage.
Failure Data:
A similar leak was reported on a Unit 2 RHR outboard injection valve (AO-50-277-75-38).
Very truly yours, M
J. Cooney Superintendent Generation Division - Nuclear cc:
Mr. J. P. O'Reilly Director, Region i Of fice of Inspection and Enforcement U.S. Nuclear Regulatory Commis sion 631 Park Avenue King of Prussia, PA 19406