ML20086J089
| ML20086J089 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 01/14/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso Office of Nuclear Reactor Regulation |
| References | |
| AO-75-2, NUDOCS 8401230167 | |
| Download: ML20086J089 (2) | |
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l PHILADELPHIA ELECTRIC COMPANY
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(21si e414ooo WL%n January 14, 1975 Mr. A. Giambusso Deputy Director of Reactor Projects United States Atomic Energy Commission Directorate of Licensing Washington, DC 20545 Deer Mr. Giambusso:
The folicwing occurrence was reported to Mr. Walt Baunack, A.E.C. Region i Regulatory Operations Office on January 4,1975 Written notification was made to Mr. James P. O'Reilly, Region 1 Regu-latory Operations Of fice on January 6,1975 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 Licensing as an Abnormal Occurrence.
Re ference:
License Number DPR-56 Technical Specification
Reference:
4.7.A Report No.:
50-278-75-2 Repor t Date:
January 14, 1975 Occurrence Date:
January 4, 1975 Facility:
Peach Bottom Atomic Power Station R.D. 1, Delta, Pennsylvania 17314 Identi fication of Occurrence:
Drywell equipment door leak.
Conditions Prior to Occurrence:
Unit 3 shutdown. Primary coolant temperature'approximately
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150 F.
Description of Occurrence:
During a routine local Icak rate test,of the drywell equipment door on the Unit 3 containment leakage from the double 0-ring gasketed joint was found to be excessive.
Leakage was past both seals into the-drywell and into the reactor building. Additional testing verified that Icakage from the containment to the reactor building was slightly in
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excess of 2,000 cc's per minute.
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D Mr. A. Giambesso January 14, 1975 Page 2 Designation of A > parent Cause of Occurrence:
Investigation showed that the outer sealing gasket on the.
hatch was twisted and pinched over a 3 inch section.
Analysis of the Occurrence:
This occurrence resulted in a leakage from the drywell to the reactor building of slightly more than 2,000 cc's per minute. The total measured Icakage to date is 8,632 cc's per minute.
The combination of these two values still results in a leakage rate which is within 60% LA (16,400 cc's per minute). The safety implications of this occurrence are therefore minimal.
Corrective Action:
Tha equipment hatch was removed and new gaskets installed after being coated with a thin film of high temperature grease. The hatch was reinstalled. A local leak rate test performed af ter. repairs resulted in negligible leakage. A local leak rate test performed on a similar closure associated with the drywell air lock also indicated negligible leakage.
i Failure Date:
r None.
Very truly yours, i
l M. J. Cooney j
Ass't Gen'1 Superintendent Generation-Division-cc: Mr. J. P. O'Rei l l y Director, Region 1 Uni ted States Atomic Energy Commission -
631 Park Avenue King of Prussia, PA 19406 1
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