ML20086L517
| ML20086L517 | |
| 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) |
| References | |
| AO-74-11, NUDOCS 8402080281 | |
| Download: ML20086L517 (2) | |
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U PHILADELPHIA ELECTRIC COMPANY
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~WW Mr. A. Giambusso Deputy Director of Reactor Projects United Sta tes Atomic Energy Conrnission Directorate of Licensing Washington, D.C.
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Dear Mr. Giambusso:
Subject:
Abnormal Occurrence The following occurrence was reported to Mr. D. Caphton, A.E.C. Region I Regulatory Opera tions Office on March 19, 1974 Written notification was made to Mr. James P. O'Reilly, Region I Regulatory Operations Office on March 19, 1974.
In accordance with Section 6.7.2.A of the Technical Specifications, 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 No.1 Technical Specification Table 3.7.4 Report No.:
50-277-74-11 Report Date:
Ma rch 19, 1974 Occurrence Date: March 18, 1974 Faci li ty:
Peach Bottom Atomic Power Station - Unit 2 R.D. 1, Delta, Pennsylvania 17314 Identi fication of Occurrence:
Following a Group I isolation caused by instrument sur-veillance testing, it was determined that the main steam line drain valve M0-2-77 failed to close.
Conditions Prior to Occurrence:
Plant stable at approximately 48% power.
P Description of Occurrence:
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q /ch 644 During instrument surveillance testing a Group I isolation I J '\\
was initiated due to valving an inscrument into service. Main steam s402080281 740326
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PDR ADOCK 05000277 COPY SENT REGION M
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l Mr. A. Gitmbusso March 26, 1974 Page 2 line drain valve M0-2-77 failed to close as required by Group I
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isolation.
The valve was manually closed by the operator immediately following the occurrence.
Designation of Apparent Cause of Occurrence:
Since the valve was manually operable immediately af ter this occurrence, the Group I isolation circuitry apparently malfunctioned and did not request a valve closure.
Analysis of Occurrence:
This valve, MO-2-77, is in series with another isolation valve M0-2-74, which did close correctly as a result of the isolation.
Because the line was isolated, there was no safety implicatio.,.
Corrective Action:
The valve was operated numerous times following this occur-rence from the test pushbutton in the automatic isolation circuitry.
The valve also operated correctly during the Group I logic system functional surveillance test which was performed to ensure proper relay and valve operation.
No specific cause for the failure of this valve to close on the Group I isolation was identified as a result of this i nves ti ga ti on.
Very truly yours, i 1, i
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M.,J. Cooney Asst. Gent. Supt.
Generation Division cc:
Mr. J. P. O' Rei l ly Director, Region I United States Atomic Energy Commiasion 631 Park Avenue King of Prussia, PA 19406 l
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