05000254/LER-1981-009-03, /03L-0:on 810407,while 1A RHR Svc Water Pump Being Run for Packing Adjustment,Pump Failed to Meet Flow Requirements of 3,500 Gpm at 198 Psig.Caused by 3 Pieces of Wood in Pump Suction.Packing Sleeve & Bearings Replaced

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/03L-0:on 810407,while 1A RHR Svc Water Pump Being Run for Packing Adjustment,Pump Failed to Meet Flow Requirements of 3,500 Gpm at 198 Psig.Caused by 3 Pieces of Wood in Pump Suction.Packing Sleeve & Bearings Replaced
ML20008F972
Person / Time
Site: Quad Cities Constellation icon.png
Issue date: 04/28/1981
From: Buss R
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20008F968 List:
References
LER-81-009-03L-02, LER-81-9-3L-2, NUDOCS 8105120416
Download: ML20008F972 (1)


LER-1981-009, /03L-0:on 810407,while 1A RHR Svc Water Pump Being Run for Packing Adjustment,Pump Failed to Meet Flow Requirements of 3,500 Gpm at 198 Psig.Caused by 3 Pieces of Wood in Pump Suction.Packing Sleeve & Bearings Replaced
Event date:
Report date:
2541981009R03 - NRC Website

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37 40 41 42 43 44 47 33 34 35 36 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 l11all The cause of this occurrence is three pieces of wood found in the pump suction.

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One piece of drif t wood and two wedges used for dewatering the Cribhouse were l,tijl removed from the pump. A cracked packing sleeve and two bearings were replaced.

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LER NUMBER: LER/R0 81-9/03L-0 ll.

LICENSEE NAME: Commonwealth Edison Company Quad-Cities Nuclear Powe'r Station Ill.

FACILITY NAME: Unit One IV.

DOCKET NUMBER: 050-254 V.

EVENT DESCRIPTION

On April 7,1981, at 1015, the 1 A RHR Service Water Pump was being run for the Maintenance Department to adjust the packing on the pump. Pump Operability Test QOS 1000-4 Indicated that the pump was not meeting the pressure and flow requirements of 3500 gpm against a pressure of 198 psig.

as established by Technical Specification 4.5.B.I.b.

A work request was written to clean and inspect the pump's discharge check valve. This was found not to be the cause of the low flow rate.

Instrumentation was checked to be satisfactory. A comparison of the flow rates of the 1A and 18 RHR Service Water Pumps showed that the lA pump was not meeting the pressure and flow requirements. Work Request Q11996 was written to inspect ar.d repair the pump as necessary.

VI.

PROBABLE CONSEQUENCES OF THE OCCURRENCE:

The containment cooling mode of the RHR system consists of two loops, each containing two RHR Service Water pumps.

Loss of one RHR Service Water pump does not seriously Jeopardize the containment cooling capability, as any one of the remaining three pumps can satisfy the cooling requirements.

Continued reactor operation is permissible if the affected pump is made operable within 30 days and as long as the other active components of the loops remain operable (Technical Specification 3 5.B.2.).

During this occurrence, the redundant components were available and the pump was returned to service within the limiting repair period. Therefore, the effect on reactor safety was minimized.

Vll. CAUSE:

The pump is an Ingersoll-Rand centrifugal pump. When the pump was taken apart, three pieces of wood were found in the impeller of the suction end of the pump. These inhibited the pump's normal flow production. A piece of drif t wood was found, and the other two pieces were wedges that were unable to be retrieved during the last dewatering of the Cribhouse.

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CORRECTIVE ACTION

Af ter the cause of the occurrence was discovered, the immeolate action was to repair the pump. The wood was removed, and a cracked packing sleeve and two bearings were replaced. The pump was returned to service on April 16, 1981, and tested satisfactorily.