ML20116H353
| ML20116H353 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 04/18/1985 |
| From: | Edelman M CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| (RDC-127(85)), NUDOCS 8505020172 | |
| Download: ML20116H353 (2) | |
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?/l f THE CLEVELAND ELECTR P.O. BOX 5000 - CLEVELAND. OHIO 44101 - TELEPHONE (216) 622-9800 - lLLUMINATIN 3 BLOG.
- 55 PUBLICSOUARE Serving The 3est Location in the Nation MURRAY R. EDELMAN VICE PRESIDENT NUCHAR April 18, 1985 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 Voltage Drop Affecting RCIC Valves [RDC 127 (85) ]
Dear Mr. Keppler:
This letter is the second interim report pursuant to 10CFR50.55(e) on the potential significant deficiency regarding starting voltage drops in power feeder cables for three valves in the Reactor Core Isolation Cooling System.
Mr. J.
McCormick-Barger of your office was notified on January 30, 1985, by Mr. T. A. Boss of The Cleveland Electric Illuminating Company that this problem was being evaluated per our Deviation Analysis Report Number 222.
An interim report was submitted on February 28, 1985.
This report contains a description of the deficiency, our planned actions to complete our evaluation, and the date for submittal of our next report on thi's subject.
Description of Deficiency Calculations have indicated that three Reactor Core Isolation Cooling (RCIC) system valves, lE51-F013, lE51-F045, and lE51-F510, may be incapable of operating due to excessive voltage drop in the valve motor circuit conductors when the valve operator is energized.
8505020172 850418 DR ADOCK 05000440 g
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Mr. JEmen G. Kappler. April 18, 1985 Completion of Evaluation Our. Architect / Engineer, Gilbert Commonwealth, Inc., is currently completing.an analysis of all'DC powered valves within the RCIC system to determine if the DC voltage that would be present, in the event of a Control Rod Drop Accident with a simultaneous loss of the battery charger, is sufficient to provide the required torque for valve operation.
The completion of this analysis will allow us to assess the potential impact on the operation of the RCIC system.
We expect to submit our final report on this subject by May 22, 1985.
Please call if there are any questions.
Sincerely,
.h Murray R. Edelman Vice President Nuclear Group MRE:sab cc:
Mr. J. A. Grobe USNRC, Site Office Mr. D. E. Keating USNRC, 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, Georgia 30339