ML20086H659
| ML20086H659 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 08/14/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso Office of Nuclear Reactor Regulation |
| References | |
| AO-75-48, NUDOCS 8401190517 | |
| Download: ML20086H659 (2) | |
Text
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oC bm PHILADELPHIA ELECTRIC COMPANY x
2301 MARKET STREET
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PHILADELPHI A. PA.19101 p
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(215)841-4000 August 14, 1975 f
Mr. A. Giambusso, Director Divi sion of Reactor Licensing Office of Nuc1 car Reactor Regulations Uni ted States Nucl ear Regulatory Commission Wb shi ng ton,
D.C.
Dear Mr. Giambusso:
Subject:
Abnormal Occurrence The following occurrence was reported to Mr. W' lt Baunack, a
Region 1, Office of Inspection and Enforcement, United States Nuclear Regulatory Commission on August 5,1975 Written notification was made to Mr. James P. O'Reilly, Office of Inspection and Enforcement, Region 1 Uni ted States Nuclear Regulatory Commission on August 5, 1975 In accordance with Section 6 7 2.A of the Technical Specifica-tions, Appendix A of DPR-56 for Unit 3 Peach Bottom Atomic Power
. Station, the following report i's being submitted to the Directorate of Reactor Licensing as an Abnormal Occurrence.
Reference:
License Number OPR-56 Technical Specification
Reference:
3 5.B.I Report No.:
50-278-75-48 Report Date:
August 14, 1975 Occurrence Date:
August 4, 1975 Facility:
Peach Bottom Atomic Power Station R.D. #1, Delta, Pennsylvania 17314 Identification of Occurrence:
M0-10-89A High Pressure Service W ter outlet valve inoperable.
a ConSi tions Prior to Occurrence:
Unit 3 at 82% power.
Description of Occurrence:
During testing of the High Pressure Service W' ter System, a
H0-10-89A failed to alter loop flow or pressure when it was positioned.
'8401190517 750814 gDRADOCK 05000278 8 ~,7 ] 7 PDR
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50-278-75-48 Mr.,A. Giambusso
. August.14, 1975 Page 2 Designation of Apparent Cause of Occurrence:
The valve seat ring was cracked.
Analys's of Occurrence:
There were minimal safety implications associated with the failure since the valve is used only in the shutdown cooling or torus cooling mode of operation, neither of which is required with the unit at power.
Corrective Action:
The valve was disassembled and the cracked valve seat ring was removed. The valve was reassembled, without the valve seat ring, and locked in the wide open position; the manual 10-11-valve is throttled to provide for the design flow rate.
Installation of a new valve. seat ring will be accomplished as soon as material is received and plant conditions permit.
Failure Data:
Previous failures were reported as: A0-278-75-35, 277-75-24, 278-75-5, 278-74-36, 277-74-13, 278-74-17, and 277-74-53 Very truly yours, s'
_,,y_.
7,.
M.
Cooney y
Ass. Gen 1. Supt.
Generation Divi sion cc:
Mr. James P. O'Reilly, Director, Region 1 Office of Inspection and Enforcement United States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406