ML20086H682
| ML20086H682 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 08/01/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20086H685 | List: |
| References | |
| AO-75-45, NUDOCS 8401190553 | |
| Download: ML20086H682 (2) | |
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PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET PHILADELPHI A. PA.19101 1215)841-4000 p:
'4 August 1, 1975
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Mr. A. Giambusso Y,
Director
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Division of Reactor Licensing Office of Nuclear Reactor Regulations United Stats s Nuc1 car Regulatory Commission Washinoton, DC 20555 *
Dear Mr. Giambusso:
Subject:
Abnormal Occurrence The following occurrence was reported to Mr. J. Partlow, Region 1, Office of Inspection and Enforcement, United States Nuclear Regulatory Commission on July 24, 1975 Written notification was made to Mr. James P. O'Reilly, Region 1, Office of Inspection and Enforcement, United States Nuclear Regulatory Commission on July 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 Abnormal Occurrence.
Reference:
License Number DPR-56 Technical Specification
Reference:
4 7.A.2.f Report No. :
50-278-75-45 Report Date:
August 1, 1975 Occurrence Date:
July 23,1975 Faci li ty:
Peach Bottom Atomic Power Station R.D. 1, Delta, Pennsylvania 17314 Identification of Occurrence:
Leak in primary containment testable penetration.
Conditions Prior to Occurrence:
Unit 3 at approximately 50% power.
Description of Occurrence:
enpy SENT REGION During local leak rate test, a leak was found in th( inner bellows of a double belltus containment penetration.
0 000 33,0o s
5,,%,78-75-45 r%
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Mr. A. Giambusso
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August.1, 1973 Page 2 Designation of Apparent Cause of Occurrence:
' Unknown.
Analysis of' Occurrence:
Measurerrent of the test space pressure indicates that it is the same~as drywell pressure. Analysis of the test space gas shows it
. to have.the same oxygen ccncentration as the drywell atmosphere. A re-view of the nitrogen makeup to the' drywell since February 1975 shows no significant change in makeup requirements, Therefore, only the inner bellows is Icaking and the primary containment integrity has been maintained. The safety significance is minimal.
i Corrective Action:
The test space pressure will be monitored daily and compared with drywell pressure. The test space atmnsphere will be analyzed weekly and compared with drywell atmosphere analysis.
This monitoring program'will reveal a f ailure in the outer Ex211avs.
The bellows will be inspected during the next outage of sufficient length. Repair or replacement will depend on the results of that inspection.
Previous Data:
None.
Very truly yours, M.
Cooney Ass' t Gen' t Superintendent Generation Division
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cc:.Mr. J. P. O'Reilly l
Director, Region 1 Office of Inspection and Enforcement r
L United States Nuclear Regulatory Commission l
631 Park Avenue
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King of Prussia, PA 19406 i
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