ML20099F638
| ML20099F638 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 02/28/1985 |
| From: | Edelman M CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| (RDC-127(85)), NUDOCS 8503140308 | |
| Download: ML20099F638 (2) | |
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P.o. BOX 5000 - CLEVELAND. OHIO 44101 - TELEPHONE (216) 622-9800 - ILLUMINATING BLDG - 55 PUBLIC SQUARE Tii E C L E '! E ! A ?' O Fi ^ C i n i fl
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Serving The Best Location in the Nation MURRAY R. EDELMAN VflCE PRESIDENT February 28, 1985 NUCLEAR 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 serves as the 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 Cc,.7any that this problem was being evaluated per our Deviation Analysis Report Number 222.
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 this subject.
Description of Deficiency Calculations have indicated that three Reactor Core Isolation Cooling (RCIC) valves, 1E51-F013, IE51-F045, and IE51-F510, may be incapable of operating due to excessive voltage drop in the valve motor circuit conductors when the valve operator ia energized.
Completion of Evaluation Our Architect / Engineer, Gilbert Commonwealth, Inc., completed a study which indicated that the valves should operate even with a reduced starting voltage.
Field testing has shown that the valves do operate as installed; however, the testing performed did not simulate the DC voltage that would be present should the RCIC system be activated in the event of a Control Rod Drop Accident with a simultaneous loss of the battery charger. Therefore, additional testing is l
required to determine if the valves would operate properly under the above l
conditions.
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8 MAR 4 1985 5 @
Mr. James G. K pplcr F&brurery 28, 1985 We will submit our next report to you on or before April 19, 1985.
Please call if there are any questions.
Sincerely,
[
tt Murray. Edelman Vice President Nuclear Group MRE:pab cc:
Mr. J. A. Grobe i
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 i
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