ML20086H792
| ML20086H792 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/12/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20086H795 | List: |
| References | |
| AO-75-40, NUDOCS 8401200241 | |
| Download: ML20086H792 (2) | |
Text
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(Q PHil ADELPHIA ELECTRIC COMPANY
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2301 MARKET STREET PHILADELPHIA. PA.19101 9
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Mr. A. Giambusso Director D
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Division of Reactor Licensing Liv -
Office of Nuclear Reactor Regulations
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United States Nuclear Regulatory Commission 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 Commission on June 2, 1975 Written notification was made to Mr. James P. O'Reilly, Region I, Of fice of Inspection and Enf orcement, United States Nuclear Regulatory Commission on June 2, 1975 In accordance with Section 6 7 2.A of the Technical Specification, Appendix A of DPR-44 for Uni t 2 Peach Bottom Atomic Power Station, the following occurrence is being submitted to the Directorate of Reactor Licensing as an Abnormal Occurrence.
Reference:
License Number DPR-44 Technical Specification
Reference:
4 7. A. 2.f Report No.:
50-277-75-40 Report Date:
June 12, 1975 Occurrence Date:
June 2,~1975 Facility:
Peach Bottom Atomic Power Station R.D., Delta, Pennsylvania 17314 Identification of Occurrence:
Suspected excessive leakage through the "B" Loop RHR Inboard and Outboard Torus Cooling Valves (M0-2-10-34B and M0-2-10-39), and Outboard Injection Valve (M0 10- 154B).
Conditions Prior to Occurrence:
Unit 2 shutdown.
Description of Occurrence:
Prior to shutdown, preliminary local leak rate tests were per'-
fornied on the RHR valves using water as a test fluid. These tests showed minor water leakage. Following shutdown, confirmatory leak rate tests 8401200241 750612 h[b PDR ADOCK 05000277 8
Mr.A.Giambuskv#
50-277-75-40 June 12, 1975 Page 2 1
usin; air were performed on the RHR "A"
loop valves while the "B" RtR was placed in service in the shutdown cooling mode. After repair and return to service of the "A" RHR loop valves, the "B" RHR loop valves were immediately removed from service to repair without performing a confirmatory leak rate test using air. The preliminary data plus the confirmatory data taken on the "A" loop was deemed suf ficient to author-ize repair work and report the subject valve leakage as an abnormal oCCurrenCc.
Designation of Apparent Cause of Occurrence:
M0-2-10-348 had loose seat rings.
Leakage on the M0-2-10-39 and M0-2-10-1548 valves is attributed to valve wear.
Analysis of Occurrenge:
Normal operating pressure of the RHR pumps during the design basis accident is greater than 49.1 psig, thereby, precluding outicakage into the RHR system.
Even if the containment atmosphere leaked back through these valves, the Icakage would enter the RHR system which is a closed system and was tested satisfactorily as part of the Type A I LR T,
Safetv ino'ications of this occurrence are therefore minimal.
Corrective Ar. tion:
The subject valves will be disassembled, inspected, repaired, reassembled, and retested.
Failure Data:
None of these particular valves.:
Very truly yours,
/ ML M M.
. Cooney
' t Gen' t Su[erintendent A
Generation Division cc:
Mr. J. P. O'Reilly Director, Region 1 Office of Inspection and Enforcem2nt United States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
.