ML20086G270
| ML20086G270 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 01/08/1976 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| AO-75-79, NUDOCS 8401100500 | |
| Download: ML20086G270 (2) | |
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PHILADELPHIA ELECTRIC COMPANY k
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(2153 8414ooo c-h' January 8, 1976 W
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l Mr. Victor Stello, Jr.
Director Division of Operating Reactors Office of Nucicar Reactor Regulations United States Nuc1 car Regulatory Comission Washington, DC 20555
Dear Mr. Stello:
Subject:
Abnormal Occurrence The followino occurrence was reported to Mr. Tom Shedlowsky, Region 1, Office of Inspection and Enforcement, United States Nuclear Regulatory Comission on December 30, 1975 Wri tten noti fication was made to Mr. James P. O'Reilly, Office of Inspection and Enforcement, Region 1, United States Nuclear Regulatory Commission on December 30, 1975 In accordance wi th Section 6 7 2.A of the Technical Specifications, Appendix A of 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 l
Report No.:
50-278-75-79 l
Report Date:
January 8, 1976 Occurrence Date:
December 29, 1975 Faci li ty:
Peach Bottom Atomic Power Station l
R.D. 1, Delta, Pennsylvania 17314
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l Identification of Occurrence:
I Leakage of "B" Loop RMR Torus Spray Valve (MO-3-10-388) and Torus Cooling Return Valve (M0-3-10-34B).
Conditions Prior to Occurrence:
Unit 3 operating at approximately 83% power.
1 Description of Occurrence:
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In preparation for the scheduled Unit 3 LPRM outage on January 3,1976 a preliminary local leak test identified thru leakage l
on the torus spray valve and the torus cooling return valve. The preliminary test was performed for the purpose of identifying valves which must be maintained during the outage.
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January 8, 1976 50-278-75-79 Page 2 Designation of Apparent Cause of Occurrence:
To be determined. These valves are subject to throttling operation during torus cooling mode.
Analysis of Occurrence:
Normal operating pressure of the RHR pumps during the design basis accident is greater than 49.1 psig, thereby, precluding out Icakage into the RHR system. However, if the containment atmosphere a-Icaked back through these valves, the leakage would enter the RHR system which is a closed system. Safety implications of this occurrence,are therefore minimal.
Failure Data Abnormal Occurrence Report Numbers 50-277-75-39 and'50-278-75-77 Very truly yours, M.
- Cooney Sup rintendent Generation Division - Nuclear cc:
Mr. J. P. O'Reilly Director, Region 1 Office of Inspection and Enforcenent U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 a