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 |
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| 2541981009R03 - NRC Website |
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8 80 St DOCKET NUMBER SS 89 EVENT DATE 74 75 REPORT OATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l a 121 l At 1015 the 1 A RHR Service Water Pump was being run for packing ad justment. The f
pump did not meet the flow requirements of 3500 gpm at 198 psig. The consequences I
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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.
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| 05000265/LER-1981-001-03, /03L-0:on 810116,during High Drywell Pressure Calibr & Functional Test,Pressure Switch PS-1-1001-88D Trip Point Found Above Tech Spec Limit.Caused by Setpoint Drift.Switch Recalibr & Tested | /03L-0:on 810116,during High Drywell Pressure Calibr & Functional Test,Pressure Switch PS-1-1001-88D Trip Point Found Above Tech Spec Limit.Caused by Setpoint Drift.Switch Recalibr & Tested | | | 05000254/LER-1981-001-03, /03L-0:on 810105,while Placing Standby Gas Treatment Sys B in Normal Shutdown Lineup,Discharge Valve MO-1/2-7507B Failed to Close When Operated from Control Room.Caused by Worn Breaker Auxiliary Contacts | /03L-0:on 810105,while Placing Standby Gas Treatment Sys B in Normal Shutdown Lineup,Discharge Valve MO-1/2-7507B Failed to Close When Operated from Control Room.Caused by Worn Breaker Auxiliary Contacts | | | 05000254/LER-1981-001, Forwards LER 81-001/03L-0 | Forwards LER 81-001/03L-0 | | | 05000265/LER-1981-001, Forwards LER 81-001/03L-0 | Forwards 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Failed to Operate While Performing Surveillance Testing.Caused by Failure of High Side Switch in DPIS-2-1360-1B.Switch Adjusted,Recalibr & Satisfactorily Tested | /03L-0:on 810224,switch in DPIS-2-1360-1B Failed to Operate While Performing Surveillance Testing.Caused by Failure of High Side Switch in DPIS-2-1360-1B.Switch Adjusted,Recalibr & Satisfactorily Tested | | | 05000265/LER-1981-005, Forwards LER 81-005/03L-0 | Forwards LER 81-005/03L-0 | | | 05000254/LER-1981-005-01, /01T-0:on 810220,during Testing,Three of Four Condenser Low Vacuum Scram Switches Found Outside Setting Per Tech Spec 3.1-3.Caused by Instrument Setpoint Drift.All Switches Recalibr | /01T-0:on 810220,during Testing,Three of Four Condenser Low Vacuum Scram Switches Found Outside Setting Per Tech Spec 3.1-3.Caused by Instrument Setpoint Drift.All Switches Recalibr | | | 05000254/LER-1981-005, Forwards LER 81-005/01T-0 | Forwards LER 81-005/01T-0 | | | 05000265/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 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Caused by Instrument Drift.Switch Recalibr & Tested | /03L-0:on 810624,pressure Switch 1-5600-PS-3 Tripped Below Tech Spec Level During Loss of Electrohydraulic Fluid Pressure Calibr & Functional Test. Caused by Instrument Drift.Switch Recalibr & Tested | | | 05000254/LER-1981-012, Forwards LER 81-012/03L-0 | Forwards LER 81-012/03L-0 | | | 05000265/LER-1981-012, Forwards LER 81-012/03L-0 | Forwards LER 81-012/03L-0 | | | 05000254/LER-1981-013, Forwards LER 81-013/03L-0 | Forwards LER 81-013/03L-0 | | | 05000265/LER-1981-013, Forwards LER 81-013/03L-0 | Forwards LER 81-013/03L-0 | |
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