ML20086L497
| ML20086L497 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 03/26/1974 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20086L507 | List: |
| References | |
| AO-74-13, NUDOCS 8402080269 | |
| Download: ML20086L497 (2) | |
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PHILADELPHIA ELECTRIC COMPANY
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2301 MARKET STREET lb !L
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MAR 2 81974 " _
PHILADELPHI A. PA.19101
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4 March 26,1974 Mr. A. Ciambusso Deputy Director of Reactor Projects United States Atomic Energy Commission Directorate of Licensing Washington, DC 20545
Dear Mr. Giambusso:
Subject:
Abnormal Occurrence The following occurrence was reported to Mr. R. A. Feil, A.E.C.
Region I Regulatory Operations Office on March 20, 1974. Written noti-fication was made to Mr. James P. O'Reilly, Region I Regulatory Operations Office on March 21, 1974.
In accordance with Section 6.7.2.A of the Technical SpecificoLions, Appendix A of DPR-44 for Unit 2 Peach Bottom Atomic Power Station, the following report is being submitted to the Directorate of Licensing as an Abnormal Occurrence.
Reference:
License Number DPR-44, Amendment Number i Technical Specification Table 3 5.B.1 Report No.:
50-277-74-13 Report Dato:
3/21/74 Occurrence Date:
3/19/74
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Facility:
Peach Bottom Atomic Power Station - Unit 2 R. D. 1, Delta, Pennsylvania 17314 Identification of Occurrence:
Open circuit in the motor control wiring of M0-98A (RHR heat exchanger HPSW outlet valve).
Conditions Prior to Occurrence:
Plant shutdown. RHR inservice in torus cooling mode.
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Description of Occurrence:
M0-2-10-89A HPSW outlet valve from RHR heat exchanger closed suddenly while in throttling service. The valve would not reopen when given an open signal from the control room manual controller. An alter-nate heat exchanger was subsequently placed in service.
Designation of Apparent Cause of Occurrence:
Investigation disclosed a broken wire in the opening circuit that supplies power to the coil for opening the valve. The broken wire soccurred at the point where it was connected to a crimped lug. The failure is believed to have caused by poor craf tsmanship coupled with vibration of the valve during operation.
Analysis of Occurrence:
This f ailure essentially inhibits the use of this heat exchanger for cooling purposes.
It does not ef fect the RHR's ability to deliver water to the reactor vessel. Only one of the four RHR heat exchangers is required to cool the primary system under any postulated accident conditions. No safecy significance is associated with this problem.
Corrective Action:
Proper repairs were made to the broken wire and the valve was stroked for operability.
Inspections on electrical connections on similar valves were performed. No additional improper connections were located as a result of this inspection.
Very truly yours, i.', s '; i i j'~
M. J. Cooney Ass't Gen't Superintendent Generation Division cc:
Mr. J. P. O'Reilly Director, Region i United States Atomic Energy Commission 631 Park Avenue King of Prussia, PA 19406 6
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