LER-1981-002, /03L-0:on 810107,Unit 1 Emergency Diesel Generator Tripped & Failed to Restart.Caused by Loose Fuse in 125 Vdc Engine Starting & Fuel Control Circuit & Misalignment of Output Breaker Auxiliary Contacts.Fuse Holder Tightened |
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33 JS 36 31 40 41 42 43 44 41 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h ltloll Investigation showed a loose fuse in the 125 VDC engine starting and fuel control l
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gl contacts was also found. The fuse holder was tightened and the breaker auxiliary l
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service at 1705 on January 7,1981.
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LER NUMBER:
81-2/03L-0 ll.
LICENSEE NAfiE: Commonwealth Edison Company Quad-Cities Nuclear Power Station Ill.
FACILITY NAME: Unit One IV.
DOCKET NUMBER: 050-254 V.
EVENT DESCRIPTION
On January 7,1981, at 0855, the Unit One Diesel Generator and its circuit breaker to the emergency 4-KV Bus 14-1 tripped. The Diesel Generator had been running for ten minutes while performing surveillance QOS 6600-1 following the routine monthly preventative maintenance inspection (QMP 200-1). Attempts to restart the Diesel failed when proper speed control of the Diesel could not be achieved. The Diesel Generator was taken out of serv:ce at 0930.
VI.
PROBABLE CONSEQUENCES OF THE OCCURRENCE:
Work Request Number Q310309 was issued to repair the Unit One Diesel Generator. Technical Specification 3.9.E.1. was immediately satisfied by demonstrating the operability of LPCI, Core Spray, and all loops of the containment cooling mode of the RHR System; and the availability of two 345 KV of f-site sources of auxiliary power. Continued reactor operation is permissible for 7 succeeding days, provided the above systems are demonstrated operable immediately and daily thereaf ter, or the Diesel Generator is returned to service and demonstrated operable.
In addition, the Unit 1/2 Diesel Generator was demonstrated operable immediately prior to initially taking the Unit One Diesel Generator out of service for the maintenance inspection. The continued availability of three redundant sources of power to the Emergency Bus and the complete operability of all ECCS and containment cooling systems minimized the impact of the equipment failure on overall reactor safety.
Vll. CAUSE:
Upon investigation, a loose fuse was found in the holder of the 125 VDC engine starting and fuel control circuit. The poor contact in the circuit caused a low, erratic voltage on the synchronizing motor in the Woodward Governor on the Diesel.
The resulting loss of speed control caused the Diesel and its circuit breaker to trip. After tightening the loose fuse holder an attempt was made to verify the Diesel Generator's cperability from the Control Room at 1105 on January 7 At this time the Diesel ran properly and the Generator was synchronized to the Bus, but the Diesel Generator output circuit breaker would not close.
Failure of the breaker to properly close was found to be a slight misalignment of the auxiliary contacts.
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CORRECTIVE ACTION
i The clips on the fuse holder were tightened to make a good contact.
This action corrected the erratic engine speed control that caused the system failure. The breaker auxillary contacts were also adjusted i
and tested for proper alignment.
Unit One Diesal Generator was returned to service at 1705 on January 7, 1981, and ran successfully for two hours.
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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 LER 81-001/03L-0 | | | 05000265/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000254/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000254/LER-1981-002-03, /03L-0:on 810107,Unit 1 Emergency Diesel Generator Tripped & Failed to Restart.Caused by Loose Fuse in 125 Vdc Engine Starting & Fuel Control Circuit & Misalignment of Output Breaker Auxiliary Contacts.Fuse Holder Tightened | /03L-0:on 810107,Unit 1 Emergency Diesel Generator Tripped & Failed to Restart.Caused by Loose Fuse in 125 Vdc Engine Starting & Fuel Control Circuit & Misalignment of Output Breaker Auxiliary Contacts.Fuse Holder Tightened | | | 05000265/LER-1981-002-03, /03L-0:on 810116,pressure Controller for Electromatic Relief Valve 2-203-3B Tripped in Excess of Tech Specs Limit.Caused by Instrument Drift,Possibly Contributed to by Faulty Microswitch.Switch Replaced | /03L-0:on 810116,pressure Controller for Electromatic Relief Valve 2-203-3B Tripped in Excess of Tech Specs Limit.Caused by Instrument Drift,Possibly Contributed to by Faulty Microswitch.Switch Replaced | | | 05000254/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000254/LER-1981-003-03, /03L-0:on 810114,pressure Switch PS-1-1001-90D Tripped High.Caused by Instrument Setpoint Drift.Switch Recalibr | /03L-0:on 810114,pressure Switch PS-1-1001-90D Tripped High.Caused by Instrument Setpoint Drift.Switch Recalibr | | | 05000265/LER-1981-003-01, /01T-0:on 810202,outboard Steam Isolation Valve MO-2-2301-5 Closed But Would Not Reopen.Caused by Insufficient Torque in Hot Condition to Lift Valve.Valve Limit Switches Adjusted | /01T-0:on 810202,outboard Steam Isolation Valve MO-2-2301-5 Closed But Would Not Reopen.Caused by Insufficient Torque in Hot Condition to Lift Valve.Valve Limit Switches Adjusted | | | 05000265/LER-1981-003, Forwards LER 81-003/01T-0.Detailed Event Analysis Also Encl | Forwards LER 81-003/01T-0.Detailed Event Analysis Also Encl | | | 05000265/LER-1981-004-01, /01T-0:on 810220,four Low Condenser Vacuum Switches Tripped in Excess of Tech Specs During Test.Caused by Setpoint Drift.Switches Recalibr | /01T-0:on 810220,four Low Condenser Vacuum Switches Tripped in Excess of Tech Specs During Test.Caused by Setpoint Drift.Switches Recalibr | | | 05000265/LER-1981-004, Forwards LER 81-004/01T-0 | Forwards LER 81-004/01T-0 | | | 05000254/LER-1981-004, Forwards LER 81-004/03L-0 | Forwards LER 81-004/03L-0 | | | 05000254/LER-1981-004-03, /03L-0:on 810116,while Performing Qis 10 Monthly Functional & Quarterly Calibr Test,Reactor Low Level Switch LS-1-263-57A Tripped Above Tech Spec Requirement.Caused by Instrument Setpoint Drift.Switch Recalibr | /03L-0:on 810116,while Performing Qis 10 Monthly Functional & Quarterly Calibr Test,Reactor Low Level Switch LS-1-263-57A Tripped Above Tech Spec Requirement.Caused by Instrument Setpoint Drift.Switch Recalibr | | | 05000265/LER-1981-005-03, /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 | /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 81-006/03L-0 | | | 05000265/LER-1981-006-03, /03L-0:on 810312,differential Pressure Between Drywell & Suppression Chamber Was Lost.Caused by Isolation of Differential Pressure Sys Due to Short in Electrical Circuit Resulting in Blown Fuse.Fuse Replaced | /03L-0:on 810312,differential Pressure Between Drywell & Suppression Chamber Was Lost.Caused by Isolation of Differential Pressure Sys Due to Short in Electrical Circuit Resulting in Blown Fuse.Fuse Replaced | | | 05000254/LER-1981-006-03, /03L-0:on 810302,flexible Air Line to Target Rock Main Steam Safety/Relief Valve Found Broken During Routine Insp of Drywell.Caused by Improper Installation of Flexible Air Line.Air Line Replaced W/Longer One | /03L-0:on 810302,flexible Air Line to Target Rock Main Steam Safety/Relief Valve Found Broken During Routine Insp of Drywell.Caused by Improper Installation of Flexible Air Line.Air Line Replaced W/Longer One | | | 05000254/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000265/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000265/LER-1981-007-03, /03L-0:on 810322,MSIV AO-2-203-2A Failed to Initiate half-scram in Reactor Protection Sys Channel B. Caused by Sticking Limit Switch Due to Steam Leak on RCIC Testable Check Valve | /03L-0:on 810322,MSIV AO-2-203-2A Failed to Initiate half-scram in Reactor Protection Sys Channel B. Caused by Sticking Limit Switch Due to Steam Leak on RCIC Testable Check Valve | | | 05000254/LER-1981-007-03, /03L-0:on 810313,no Position Indication Found on Recirculation Pump 1A Discharge Valve MO-1-202-5A.Caused by Tripped Valve Motor Breaker Due to Several Shorted Conductors in Cable 12507 Leading to Valve Inside Drywell | /03L-0:on 810313,no Position Indication Found on Recirculation Pump 1A Discharge Valve MO-1-202-5A.Caused by Tripped Valve Motor Breaker Due to Several Shorted Conductors in Cable 12507 Leading to Valve Inside Drywell | | | 05000254/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000265/LER-1981-008-03, /03L-0:on 810326,two Instrument Cable Risers Found to Have Open Penetrations.Caused by Failure to Seal After Plant Mods.Fire Watch Established & Penetrations Sealed | /03L-0:on 810326,two Instrument Cable Risers Found to Have Open Penetrations.Caused by Failure to Seal After Plant Mods.Fire Watch Established & Penetrations Sealed | | | 05000265/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000254/LER-1981-008-03, /03L-0:on 810407,reactor Core Insulation Cooling Sys Received Spurious High Steam Flow Automatic Isolation Signal.Caused by Faulty Micro Switch in DPIS 1-1360-1B. Switch Replaced & Instrument Calibr | /03L-0:on 810407,reactor Core Insulation Cooling Sys Received Spurious High Steam Flow Automatic Isolation Signal.Caused by Faulty Micro Switch in DPIS 1-1360-1B. Switch Replaced & Instrument Calibr | | | 05000254/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 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 | /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 | | | 05000265/LER-1981-009, Forwards LER 81-009/03L-0 | Forwards LER 81-009/03L-0 | | | 05000254/LER-1981-009, Forwards LER 81-009/03L-0 | 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 | /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 | | | 05000254/LER-1981-010-03, /03L-0:on 810414,valve AO-1-1301-35 Observed Closed Causing Reactor Core Isolation Cooling to Be Inoperable.Caused by Shorted Solenoid Coil on Valve Operator.Solenoid Replaced.Valve Tested Satisfactorily | /03L-0:on 810414,valve AO-1-1301-35 Observed Closed Causing Reactor Core Isolation Cooling to Be Inoperable.Caused by Shorted Solenoid Coil on Valve Operator.Solenoid Replaced.Valve Tested Satisfactorily | | | 05000254/LER-1981-010, Forwards LER 81-010/03L-0 | Forwards LER 81-010/03L-0 | | | 05000265/LER-1981-010, Forwards LER 81-010/03L-0 | Forwards LER 81-010/03L-0 | | | 05000265/LER-1981-010-03, /03L-0:on 810515,diesel Generator Declared Inoperable When Trouble Alarm Received & Room Found Full of Smoke.Caused by Control Power Ground Fault.Ground & Damaged Components Repaired | /03L-0:on 810515,diesel Generator Declared Inoperable When Trouble Alarm Received & Room Found Full of Smoke.Caused by Control Power Ground Fault.Ground & Damaged Components Repaired | | | 05000265/LER-1981-011, Forwards LER 81-011/03L-0 | Forwards LER 81-011/03L-0 | | | 05000254/LER-1981-011, Forwards LER 81-011/03L-0 | Forwards LER 81-011/03L-0 | | | 05000265/LER-1981-011-03, /03L-0:on 810608,during Routine Maint,Diesel Generator 1/2 Was Removed from Svc Prior to Demonstrating Diesel Generator 2 Operability,In Violation of Tech Spec. Caused by Personnel Error.Personnel Reinstructed | /03L-0:on 810608,during Routine Maint,Diesel Generator 1/2 Was Removed from Svc Prior to Demonstrating Diesel Generator 2 Operability,In Violation of Tech Spec. Caused by Personnel Error.Personnel Reinstructed | | | 05000254/LER-1981-011-03, /03L-0:on 810618,diesel Fire Pump B Out of Svc for More than 7 Days.Caused by Wood Debris Found in Suction Piping.New Strainers Ordered for Both Pumps | /03L-0:on 810618,diesel Fire Pump B Out of Svc for More than 7 Days.Caused by Wood Debris Found in Suction Piping.New Strainers Ordered for Both Pumps | | | 05000265/LER-1981-012-03, /03L-0:on 810518,during Surveillance Testing,Valve MO-2-1001-7B Failed to Reopen.Caused by Failure of Auxiliary Contacts in Circuit Breakers to Disengage.Valve Manually Opened & Contacts Replaced | /03L-0:on 810518,during Surveillance Testing,Valve MO-2-1001-7B Failed to Reopen.Caused by Failure of Auxiliary Contacts in Circuit Breakers to Disengage.Valve Manually Opened & Contacts Replaced | | | 05000254/LER-1981-012-03, /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 | /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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