ML20086K408
| ML20086K408 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 02/15/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20086K411 | List: |
| References | |
| AO-75-14, NUDOCS 8401270075 | |
| Download: ML20086K408 (2) | |
Text
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,a PHILADELPHIA ELECTRIC COMPANY 4 *t" f A\\
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2301 M ARKET STREET
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PHILADELPHIA PA.19101 (i 5 'fg tr Q
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D Febmary 15,1975 Mr. A. Giambusso Director Division of Reactor Licensing Office of Nuc1 car Reactor Regulations United States Nuclear Regulatory Ccrsnission Washington, D.C.
20555
Dear Mr. Gismbusso:
Subject:
Abnomal Occurrence The following occurrence was reported to Mr. Walt Baunack, Office of Inspection and Enforcement, Region 1, United States Nuclear Regulatory Commission on February 6,1975 Written notification was made to Mr. James P. O'Reilly, Office of Inspection and Inforecuent, Region 1, United States Nuclear Regulatory Ccrmnission on Febmary 6, 1975. In accc. dance with Section 6 7 2.A of the Technical Specifications, Appendix A of DPR-hh for Unit 2 Peach Bottom Atomic Power Station, the following report is being submitted to the Directorate of Reactor Licensing as an Abnomal Occurrence:
Reference:
License Number DPR-hh Technical Specification
Reference:
371 Report No.:
50-277-75-lh Report Date:
Febmary 15, 1975 Occurrence Date:
February 5,1975 Facility:
Peach Bottcm Attnic Power Station R.D.1, Delta, Pennsylvania 1731h Identification of Occurrence:
Unit 2 Recirculation Systcm Sample valve, A0-2-39, failure to fully close.
Conditions Prior to occurrence:
fD' Plant at 99.5% power.
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Paga 2 Description of Occurrence:
Following completion of sampling, the switches for the Recimulation Systcri sample valves, A0-2-39 and A0-2-h0, were placed in the closed position. It was observed that the ind'.cating 1snps showed the valve A0-2-39 had not fully closed. Cycling of the velve while observing the flow at the sampling station confimed that the valve was not fully closing.
Designation of Apparent Cause of Occurrence:
Unknown, at this time, due to inaccessability of the valve.
Analysis of Occurrence:
The safety implication of this failure is minimal because the other redundant valve in series with A0-2-39 did fully close and would have isolated if necessary.
Corrective Action:
Further opening and closing of A0-2-39 resulted in stopping flow completely, but the indicating lamps were still incorrect. Valve operrbility will be checked during the next outage.
Failure Data:
A0-278-7h-23.
Very tmly yours, l
l M.
. Cooney j
As 't Gen'1 Superintendent l
Generation Division i
cc: Mr. J. P. O'Reilly l
Director l
Office of Inspection and Enfomement l
Region 1 United States Nuclear Regulatory Ccrnmission 631 Park Avenue l
King of Pmssia, PA 19h06 i
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