ML20086H062
| ML20086H062 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/03/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Boyd R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20086H066 | List: |
| References | |
| AO-75-70, NUDOCS 8401130381 | |
| Download: ML20086H062 (2) | |
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c)8 Mr. Roger S. Boyd Acting Director Division of Reactor Licensing Office of Nuclear Reactor Regulations gyg gpy United States Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Boyd:
Subject:
Abnormal Occurrence The f ollowing occurrence was reported to Mr. Walt Baunack, Region 1, Office of Inspection and Enforcement, United States Nuclear Regulatory Commission, on October 24, 1975 Written notification was made to Mr. James P. O'Reilly, Region 1, Of-fice of Inspection and Enforcement, United States Nuclear Regulatory Conmission on October 24,
-1975 In accordance 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 Abnormel Occurrence.
Reference:
License Number DPR-56 Technical Specification
Reference:
3 7.D.
l Report No.:
50-278-75-70
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Report Date:
November 3, 1975 Occurrence Date: October 24, 1975 Facility:
Peach Bottom Atomic Power Station R.D'. 1, Delta, Pennsylvania 17314 Identification of Occurrence:
Drywell Purge Supply Isolation Valve (AO-3520) opening.
Conditions Prior to Occurrence:
Reactor power 57%.
Description of Occurrence:
Valve A0-3520 apparently operated without manual initiation.
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8401130381 751103 PDR ADOCK 05000278 COPY SENT REGION
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Mr. Roger S. Boyd 50-278-75-70 November 3,1975 Page 2 Designation of Apparent Caute of Occurrence:
It appears that an air piping modification made to similar valves to correct a similar problem in early 1974 was implemented in-correctly on this valve.
Analysis of Occurrence:
The other isolation valve in series with this valve would have isolated if necessary. Therefore, there is minimal safety significance.
Corrective Action:
The valve was failed clesed until the piping error was corrected. An inspection of all other valves of similar piping arrange-ment that were to be modified were inspected in both plants. During the inspection, A0-3511 and S0-3512, Torus Exhaust to Standby Gas Treatment 'were also f ound to be piped incorrectly. The piping on all.
three valves was corrected, and they will be monitored to ensure that they do not operate without any initiation signal.
Failure Data:
Abnormal Occurrence Report 50-278-74-15.
Very truly yours, ooney Su rintendent Generation Division - Nuclear cc: Mr. J. P. O' Rei l ly Director, Region 1 Office of Inspection and Enforcement United States Nuclear Regulatory Cannission 631 Park Avenue King of Prussia, PA 19406
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