ML20133D765

Final Deficiency Rept (Rdc 142(85)) Re Voltage Drop Associated W/Degraded Supply Voltage & Long Cable Lengths. Initially Reported on 850625.Design Changes Initiated to Increase Size of Cables to Affected Components

ML20133D765
Person / Time
Site:	Perry
Issue date:	07/25/1985
From:	Edelman M CLEVELAND ELECTRIC ILLUMINATING CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
(RDC-142(85)), NUDOCS 8508070448
Download: ML20133D765 (2)

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v THE CLEVELAND ELECTRIC ILLUMIN ATING COMP ANY P.O. BOX 5000 - CLEVELAND, OHIO 44101 - TELEPHONE (216; 622-9800 - ILLUMINATING BLDG. - 55 PUBLIC SOUARE Serving The Best Location in the Nation July 25, 1985 MURRAY R. EDELMAN VICE NESIDENT PY-CEI/OIE 0086 L NUCM A R 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 Evaluation

[RDC 142(85)]

Dear Mr. Keppler:

This letter is the final report pursuant to 10CFR50.55(e) concerning the potential for insufficient voltage to some equipment when source voltage is degraded and/or when long cable lengths are used to supply the equipment. This deficiency was reported by telephone to Mr. R. Knop of your office on June 25, 1985 by Mr. B. D. Walrath of The Cleveland Electric Illuminating Company. This deficiency has been evaluated per Deviation Analysis Report 246.

Description of Deficiency A review was conducted to assess the effects of degraded supply voltage and long cable lengths. This review identified instances where the voltage drops associated with these conditions could adversely affect the operation of plant equipment. Components in the following systems are affected:

P47: Control Complex Chilled Water M32: Emergency Service Water Pump House Ventilation M43: Diesel Generator Building Ventilation The other systems originally identified as having potentially degraded operation due to excessive voltage drop have been evaluated and found acceptable. This evaluation considered either the use of the manufacturer's test data, a component specific calculation, or a functional test of the equipment to demonstrate operability under degraded voltage conditions.

JUL 2 0 E05 8508070448 050725 i PDR ADOCK 05003440 PDR 1fq (,

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, Mr. Jcmes G. KSppler July 25, 1985 PY-CEI/OIE 8086 L Analysis of Safety Implications This deficiency could prevent or delay the start of the affected systems if a LOCA occurs when offsite power is in a degraded voltage condition.

Corrective Action Design changes (ECN-28522-86-2280 and associated cable pull slips) are being initiated to increase the size of the cables to the affected components in order to prevent excessive voltage drops.

If you have any questions, please call.

Sincerely, Murray R. Edelman Vice President Nuclear Group MREspab cc: Mr. J. A. Grobe USNRC, Site Office (SBB50)

Mr. D. E. Keating USNRC, Site Office (SBB50)

Director Office of Inspection and Enforcement 1 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Records Center, SEE-IN Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 -

Atlanta, Georgia 33039 l