ML20086H673
| ML20086H673 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 08/04/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20086H676 | List: |
| References | |
| AO-75-46, NUDOCS 8401190546 | |
| Download: ML20086H673 (2) | |
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PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET
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PHILADELPHIA. PA.19101 4
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- v August 4, 1975 Mr. A. Giambusso "d.'
Director Division of Reactor Licensing Office of Nuclear Reactor Regulations i
i United States Nuclear Regulatory Comission g
Washington, DC 20555
Dear Mr. Giambusso:
Subject:
Abnormal Occurrence The following occurrence was reported to Mr. Don Caphton, Region 1, Office of Inspection and Enforcement, United States Nuclear Regulatory Comission on July 25, 1975 Written notification was made to Mr. James P. O'Reilly, Region 1, Office of Inspection and Enforcement, United States Nucicar Regulatory Conrnission on July 25, 1975.
In accord-ance with Section 6 7 2.A of the Technical Specifications, Appendix A of DPR-56 for Unit 3 Peach Bottom Atomic Power Station, the f ollowing
. report is being submitted to the Directorate of Reactor ' Licensing as an Abnormal Occurrence.
Reference:
License Number DPR-56 c
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Technical Specification
Reference:
3 11.0 e
Report No.:
50.278-75-46 I,I l
Report Date:
August 4, 1975 l
Occurrence Date:
Ju ly 25, 1975 r
l Facility:
Peach Bottom Atomic Power Station I
R. D.1, Delta, Pennsylvania 17314 la Identification of Occurrencer hi' Inoperable hydraulic snubber on the 'C' RHR pump discharge line.
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Conditions Prior to Occurrence:
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Unit 3 operating at approximately 50% power.
t He Description of Occurrence:
h inspection of Unit 3 snubbers outside the drywell y
A routine identified snubber 3-10-H8-S-12 as failed.
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PDR 1
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,Mr. A. Giambusso August 4,1975 Pcgu 2
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1 Designation of Apparent Cause of Occurrence:
f It appears-that during the placement of scaffolding or accidental contact during subsequent construction activity, an elbow connecting snubber to snubber reservoir was damaged. Additionally, the reservoir retaining bolts appear to have lourened because of vi-bration resulting in reservoir separation from its mounting.
Analysis of. Occurrence:
No damage to piping or supports was.noted during the inspection.
Safety implications are, therefore, minimal.
Corrective Action:
1 The snubber was repaired. The inspection procedure was re-vised to call attention to the reservoir retaining bolts and the eluow on the reservoir. Snubber surveys are continuin.g on a routine basis.
Unit 2 snubber survey was completed satisf actorily in June 1975 No other snubbers were found inoperable in Unit 3 i
Failure Data:
g-l A0-50-277-74-45, 50-277-74-34, 50-278-74-16 and 50-278-74-8.
t Very truly yours, l.
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M.
. Cooney Ass't Gen' t Superintendent Generation Division
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Mr. J. P. O'Reilly Director, Region 1 j
Office of Inspection and Enforcement j
United States Nuclear Regulat' ry Conmission o
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631 Park Avenue l
King of Prussia, PA 19406 k
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