ML20086H633
| ML20086H633 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 07/18/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso Office of Nuclear Reactor Regulation |
| References | |
| AO-75-39, NUDOCS 8401190492 | |
| Download: ML20086H633 (2) | |
Text
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( s,. 'y July 18, 1975 ..,y 4 5N ---{ T i' '.3' ~ l Mr. A. Giambusso Director Division of Reactor Licensing Office of Nuclear Reactor Regulations United States Nuclear Regulatory Comission Washington, DC 20555
Dear Mr. Giambusso:
Subject:
Abnormal Occurrence The following occurrence was reported to Mr. Walt Baunack, Region 1, Office of Inspection and Enforcement, United States Nuclear Regulatory Comission on July 8,1975 Written notification was made to Mr. James P. O'Reilly, Region 1, Office of Inspection and Enforcement, United States Nuclear Regulatory Comission on July 9,1975 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 following report is being submitted to the Directorate of Reactor Licensing as an Abnormal Occurrence.
Reference:
License Number DPR-56 Technical Specification
Reference:
4.5.D.I.c Report No.: 50-278-75-39 Report Date: July 18, 1975 Occurrence Date: July 8, 1975 Facility: Peach Bottom Atomic Power Station R.D. 1, Delta, Pennsylvania 17314 Identification of Occurrence: Valve M0-3-13-18 (RCIC pump suction from the Condeasate Storage Tank) was found electrically inoperabic. CSE Ma, Conditions Prior to Occurrence: b .,. 2 a y /> Unit 3 at approximately 49.6% power. E Description of Occurrence: / i 38 o.o During the performance of Surveillance Test ST 6.11, Valve M0-M 3-13-18 (RCIC pump suction from Condensate Storage Tank) f ailed to ffg operate electrically from the main control room switch. The valve was m n.cn in the. opened position. g W O N __
O e 9-278-75-39 a Mr. A. Gitmbusso July 18, 1975 Page 2 Dssignation of Apparent Cause of Occurrence: Investigation determined that the positive d.c. Icad to the control relays was not in contact with the terminal strip hold down screw. Analysis of Occurrence: l In the as found condition, the RCIC System would have supplied water from the condensate storage tank. It would not, however, have made en automatic transfer of its suction to the torus on receipt of low stcrage tank level. This system is backed up by the HPCI, which was oper able. It is concluded that the safety significance of this f ailure is minimal. Corrective Action: The lead to the control power relays was connected and the valve was stroked several times satisfactorily. Repairs were completed within a few hours of the occurrence. Failure Data: ( t None. Very.truly yours, M. . Cooney A t Gen' t Superintendent Generation Division ec: Mr. J. P. O'Reilly Director, Region 1 1 0ffice of Inspection and Enforcement United States Nuc1 car Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 4 4 1 n _}}