05000265/LER-1981-009-03, /03L-0:on 810504,while Performing RHR Containment Cooling Valve Operability Test,Breaker for Valve MO-2-1001-37B Tripped During Attempt to Close Valve.Caused by Internal Corrosion Buildup

/03L-0:on 810504,while Performing RHR Containment Cooling Valve Operability Test,Breaker for Valve MO-2-1001-37B Tripped During Attempt to Close Valve.Caused by Internal Corrosion Buildup

ML20004D738
Person / Time
Site:	Quad Cities
Issue date:	05/26/1981
From:	Weinfurter E COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20004D733	List: 05000265/LER-1981-009, Forwards LER 81-009/03L-0 05000265/LER-1981-009-03, /03L-0:on 810504,while Performing RHR Containment Cooling Valve Operability Test,Breaker for Valve MO-2-1001-37B Tripped During Attempt to Close Valve.Caused by Internal Corrosion Buildup
References
LER-81-009-03L, LER-81-9-3L, NUDOCS 8106090702
Download: ML20004D738 (2)

LER-1981-009, /03L-0:on 810504,while Performing RHR Containment Cooling Valve Operability Test,Breaker for Valve MO-2-1001-37B Tripped During Attempt to Close Valve.Caused by Internal Corrosion Buildup

Event date:
Report date:
2651981009R03 - NRC Website

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EVENT DESCHfPTION AND PROSABLE CONSEQUENCES h Al While performing QOS 1000-5, RHR Containment Cooling Valve Operability Test, the l

breaker for valve MO-2-1001-37B tripped when attempting to close the valve. The l

g o i3l l consequences are minimal because the "A" contaf nment cooling loop was fully l

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LER NUMBER: LER/R0 81-09/03L-0 ll.

LICsASEE NAME: Commonwealth Edison Company Quad-Cities Nuclear Power Station 111.

FACILITY NAME: Unit Two o

IV.

DOCKET NUMBER: 050-265 V.

EVENT DESCRIPTION

On May 4, 1981 at 2330, while performing Residual Heat Removal System Containment Cooling Valve Operability Test, QOS 1000-5, the breaker for valve MO-2-1001-37B tripped during an attempt to close the valve.

MO 1001-378 is the motor operated valve to the suppression chamber spray header. Work Request Q12367 was written to investigate the problem.

This is the first failure of this valve.

VI.

PROBABLE CONSEQUENCES OF THE OCCURRENCE:

The consequences of this occurrence were minimized because the "A" Loop of RHRS was fully operable and available, had the need arisen. The containment cooling mode was still available in the "B" Loop and the suppression chamber cooling mode was available af ter the breaker for MO-2-1001-37B was reset. The LPCI mode of RHRS was not effected by the failure of valve M0-2-1001-378.

Vll. CAUSE:

The cause of this occurrence was high starting current in the valve's motor operator. The valve is a six inch Glove Valve manufactured by Crane Company, with a SMB-00, Limitorque Motor Operator.

No other problems could be found at this time.

Vill. CORRECTIVE ACTION:

A Work Request was initiated for Mechanical Maintenance to check the valve during the next refuel outage. The instantaneous peak amperage setting was changed from 20 amps to 35 amps, to make the breaker trip setting equivalent to that of other breakers for similar motor operators.

The 20 amp trip setting is a field setting which could have been set during init'al installation of the breaker.

Operating experience has snown, however, that the 35 amp trip setting is a proper trip setting so that starting current surges do not trip the breaker. The breaker trip setting was adjusted to 35 amps, and the valve stroked three times satisfactorily.

Adjustment of the breaker trip setting has no effect on the thermal over-load protection for the valve's motor operator. QOS 1000-5 was performed successfully at 0125, May 5, 1981.