ML20086J065
| ML20086J065 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 01/31/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20086J066 | List: |
| References | |
| AO-75-6, NUDOCS 8401230087 | |
| Download: ML20086J065 (2) | |
Text
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. PHILADELPHIA ELECTRIC COMPANY S ~-
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MY January 31, 1975 Mr. A. Giambusso Director, Division of Reactor Licensing Office of Nuclear Reactor Regulations U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Dear Mr. Giambusso
Subject:
Abnormal Occurrence The following occurrence was reported to Mr. Tom Shedlowsky, N'.R.C. Region 1 Office of Inspection and Enforcement on January 22, 1975 Written notification was made to Mr. James P. O'Reilly, Region 1 Of fice nf Inenact na aad Eaforca eat en J=ne=ry 22, 8975 In eccerdenca with i
Section 6.7.2.A of the Technical Specifications, Appendix A of DPR-56 for Unit 3 Peach Bottom Atomic Power Station, the following report is being subm.tted to the Directorate of Reactor Licensing as an Abnormal l
Occurrence:
Reference:
License Number DPR-56 Technical Specification
Reference:
3 3 8 3.a Report No.:
50-278-75-6 Report Date:
January 31, 1975 Occurrence Date: January 21, 1975 Facility:
Peach Bottom Atomic Power Station R.D. 1, Delta, Pennsylvania 17314 j
Identification of Occurrence:
Failure of PS-3-3-250A, RSCS 3DX rated power interlock.
Conditions Prior to Occurrence:
Unit 3 shutdwn.
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8401230087 750131 PDR ADOCK 05000278 S
.1180, COPY SElff REGION a
V Mr. A. Giambusso e
January 31~,1975 Page 2 Description of-Occurrence:
During a routine instrunent surveillance test, PS-3-3-250A was found to have suffered corrosion damage which rendered it inoper ab le.
The corrosion resulted from a buildup of mois ture in the switch housing.
Designation of Apparent Cause of Occurrence:
Minor leakage from the bourdon tube resulting in a building of mois ture in the switch case.
Analysis of Occurrence:
Because either the PS-250A or PS-250B switch serves independently to arm the RSCS below 30% rated power, the failure of only one of these switches has minimal safety implications.
Corrective Action:
The entire switch assembly was replaced in kind, calibrated, and checked in accordance with the applicabic surveillance test.
Failure Data:
None previous.
Very truly yours,
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M. J. C oon e~y l'
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Ass' t Gen' t Superintendent j
Generation Division cc:
Mr. J. P. O'Reilly Director Office of Inspection and Enforcement l
Region 1 United States Nuclear Regulatory Coanission 631 Park Avenue King of Prussia, PA 19406 l
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