ML20116M127

Interim Significant Const Deficiency Rept Re Performance of motor-operated Valve Supplied by Anchor-Darling.Initially Reported on 850315.Existing Motor Will Be Replaced W/Motor Described on Motor Data Sheet.Next Rept by 850621

ML20116M127
Person / Time
Site:	Hope Creek
Issue date:	04/15/1985
From:	Martin T Public Service Enterprise Group
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8505060118
Download: ML20116M127 (2)

Text

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Public Service Electric and Gas Company Thomas J. Martin 80 Park Plaza, Newark, NJ 07101 201-430 8316 Mailing Address: P.O. Box 570, Newark, NJ 07101 Vica President Engineering and Construction April 15, 1985 Dr. Thomas E. Murley, Administrator U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Dr. Murley:

SIGNIFICANT CONSTRUCTION DEFICIENCY MOTOR OPERATED VALVE - HPCI HOPE CREEK GENERATING STATION On March 15, 1985, a verbal report was made to Region I, Office of Inspection and Enforcement representative, Mr. J.

SCrosnider, advising of a potentially significant construc-tion deficiency concerning the performance of a motor operated valve supplied by Anchor-Darling. The following interim report is provided in accordance with 10CFR50.55 (e) .

Description of the Deficiency During the initial startup testing of HPCI steam supply valve 1-FD-HV-F001, the circuit breaker tripped when the motor oper-ator was energized. The valve, as supplied by Anchor-Darling, is equipped with a Limitorque direct current motor operator.

Our Architect / Engineer and Constructor, Bechtel, has investigated the problem with Limitorque Corporation. Limitorque has informed us that the actual locked rotor current for the installed motor is 343 amperes instead of the 87 amperes as shown on the motor data sheet. The circuit breaker had been set to trip at 140 amperes in accordance with sheet 58 of drawing E-1465-0. Con-sequently, the actual locked rotor current of 343 amperes caused the breaker to trip whenever the motor was energized. Startup Deviation Report (SDR) No. BJ-0068 has been issued to document and control the discrepant condition.

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< l Dr. T.-E. Murley 2 4/15/85 i

Safety Analysis Had the deficient condition gone undetected and uncorrected, tripping of the circuit breaker as described above would result in the failure of the HPCI steam supply valve to open and provide steam to the HPCI. turbine.

Since-the High Pressure Coolant Injection (HPCI) System is an Emergency Core Cooling System (ECCS) and required for safe shutdown of the plant, we conclude that the subject deficiency is reportable in accordance with 10CFR50.55 (e) .

Corrective Action The existing motor will be replaced with a motor as described on the motor data sheet. This motor will be compatible with existing circuitry.

Bechtel is reviewing with Anchor-Darling, the valve supplier, all other DC motor operated valves supplied to the Hope Creek project to ensure that the problem is isolated to the subject valve.

We anticipate providing you with a further report by June 21, 1985, detailing the results of the review and the status of corrective action.

Very 'ruly yours, i

C Office of Inspection and Enforcement Division of Reactor Construction Inspection Washington, D. C. 20555 NRC Resident Inspector - Hope Creek P. O. Box 241 Hancocks Bridge, NJ 08038 Records Center Institute of Nuclear Power Operations 1100 Circle'75 Parkway, Suite 1500 Atlanta, GA 30339