ML20024D629
| ML20024D629 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 07/29/1983 |
| From: | Edelman M CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 10CFR-050.55E, RDC-76(83), NUDOCS 8308050380 | |
| Download: ML20024D629 (2) | |
Text
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'o P o Box 5000 - CLEVELAND, OHIO 44101 - TELEPHONE (216) 622-9800 - lLLUMINATING BLDG - 55 PUBLICSQUARE Semng The Best Locanon in the Nation MURRAY R. EDELMAN Nc'uAR uly 29, 1983 Mr. James G. Keppler Regional Administrator, Region III Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 RE:
Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Safety Relief Valves Supplied by the General Electric Company
[RDC 76(83)]
Dear Mr. Keppler:
This letter serves as an interim report pursuant to 10CFR50.55(e) on the significant deficiency concerning the Viton seals used on Safety Relief Valves (SRV) supplied by General Electric Company (GE) to the Perry Nuclear Power Plant (PNPP).
Mr. E. Riley of The Cleveland Electric Illuminating Company notified Mr. P. Pelke of your office of the potential significant deficiency on June 30, 1983.
This letter contains a description of the deficiency, planned corrective action, and the scheduled date for submittal of our next report on this subject.
Description of Deficiency Due to the failure of several seals, the Main Steam SRVs, Dikkers Style G471-6/125.04 supplied by GE, failed qualification testing to NUREG 0588. The seals which failed were in the pneumatic actuator needed to operate the SRVs for Automatic Depressurization System functions. The SRV was tested as a normal qualification function to evaluate the ability of the valve to perform its safety-related function for PNPP's environments. After aging, the valves were exposed to radiation. levels simulating accident conditions, which may exceed those to which the SRVs would actually be subjected. During this testing, several seals manufactured of Viton E 60C material failed.
Even though it can now be postulated that the pneumatic actuator may fail, it should be noted that the mechanical safety relief function of the valve during a system high pressure event was not found to be impared as a result of qualification testing.
M e308050300 830729 PDR ADOCK 05000440 p
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2-July 29, 1983 Mr. James C. Keppler Corrective Action
. The Viton seals will be replaced with EPDM seals which have a higher radiation threshold.
In addition, the accident level radiation exposures for the SRVs are being re-evaluated. The SRV with new seals (EPDM) will then be retested to the re-evaluated parameters.
The next report will be issued upon completion of the retest, which is currently scheduled for June 1,1984.
Sincerely, Murray R.
delman Vice President Nu tear Group MRE:pab cc:
Mr. M. L. Cildner NRC Site Office Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 U.S. Nuclear Regulatory Commission c/o Document Management Branch Washington, D.C.
20555 Records Center, SEE-IN Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Caorgia 30339 t
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