ML20086F855
| ML20086F855 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/26/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Boyd R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20086F860 | List: |
| References | |
| AO-75-76, NUDOCS 8401090596 | |
| Download: ML20086F855 (2) | |
Text
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PHILADELPHIA ELECTRIC ' COMPANY 2301 M ARKET STREET t'
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1F PHILADELPHI A. PA.19101 RL ~
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a sann c) ut Mr. Roger S. Boyd Acting Director Division of Reactor Licensing Office of Nucicar Reactor Regulations United States Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Boyd:
Subject:
Abnormal Occurrence The following occurrence was reported to Mr. Walt Baunack, Region 1, Office of Inspection and Enforcement, United States Nuclear Regulatory Commission on November 18, 1975 Written notification was made to Mr. James P. O'Reilly, Region 1, Of fice of Inspection and Enforcement, United States Nuclear Regulatory Comissiun on November 18, 1975 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 Reactor Licensing as an Abnormal Occurrence.
Reference:
License Number DPR-44 Technical Specification
Reference:
1.0.D.4 Report No.:
50-277-75-76 Report Date:
November 26, 1975 Occurrence Date: November 17, 1975 Facility:
Peach Bottom Atomic Power Station R.D. 1, Delta, Pennsylvania 17314 Identification of Occurrence:
Broken pipc support.
Conditions Prior to Occurrence:
Reactor shutdown and depressurized.
Description of Occurrence:
During a routine inspection of plant piping, a rigid pipe support was found to be broken on the RIIR shutdown cooling suction line downstream of the outer isolation valve, MO-10-17 I
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Mr. Roger S. Boyd 50-277-75-76 November 26, 1975 -
Page 2 1
Designation of Apparent Cause of Occurrence:
-a Component failure.
Analysis of Occurrence:
The safety implications of this occurrence are minimal due to the location of the pipe support on the RHR system piping (external to the outer isolation valve and upstream of the shutdown cooling line 1
valves to the RHR loops).
Corrective Action:
The pipe support was replaced in kind, as recommended by the' Philadelphia Electric Company Engineering Department.
The investigation j
of this occurrence is continuing through the Philadelphia Electric Company Engineering Department.
Failure Data:
None previous.
Very truly yours, i
4 M. J. Cooney Supe intendent Generation Division - Nucicar cc:
Mr. J. P. O'Reilly Director, Region 1 Office of Inspec, tion and Enforcement U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 i
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