LER-1981-010, /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 |
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LICENSEE EVENT REPORT COsTROtstOCm' l
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60 61 DOCKET NUMBER 08 69 EVENT DATE 74 75 HEPORT DATE 80 g
EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h g o,2 j l At 0340 on May 15, 1981, the Control Room received a Unit Two Diesel Generator j
trouble alarm. An Operator was immediately dispatched to find the Diesel Generator l
g o,.,, l room full of smoke.
F ?nding no evidence of fire and the local alarm, " DIESEL l
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GENERATOR MOTORING" the Diesel Generator was declared inoperable. As per Technical j
Io isl L Speci fication 4.9.E., the shared Diesel Generator and all associated low pressure l
go gg y l core and containment cooling systerPs were demonstrated operable. Probable l
- j7; l consequences are minimal since off-site power was available at all times and the I
i o,; i l provisions of Technical Speci fication 4.9.E. were satisfied.
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40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h li l al l The cause of this occurrence was eauirment failure.
A 125 VDC cont rol oower around l
internal to the breaker which ties the Diesel Generator to the emergency bus' l
Wyl fault The l
caused a spurious riosure of the breaker which notored the Diesel Generator.
,,,,,j Exte.sIve testing l l,j,gl corrective action was to repai r the ground and damaged components.
and inspections of the Diesel Generator were then done to prove f ull operability l
i,i i L on May 19, 1981.
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K ESCHIPTION I 21 - 1 bi @l 68 09
- 80. C 8107160301 810610 Daryl G Clark 399-654-2241, ext. 170 PDR ADOCK 05000265 PHONE:
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LEP NUMBER: LER/R0 81-10/03L-0 11.
LICENSEE NAME:
Commonwee'th Edison Company Quad-Cities Nuclear Power Station Ill.
FACILITY NAME: Unit Two IV.
DOCKET NUMBER:
050-265 V.
EVENT DESCRIPTION
At 0340 on May 15, 1981, the Control Room received the Unit Two Diesel Generator Trouble Alarm, RHR System 2 Supply from Emergency Diesel Alarm, 4 KV Bus Overcurrent Alarm and Diesel Generator 2 Low Frequency Alarm.
The bus 24 to 24-1 ammeter was also indicating a current in excess of 600 amperes. An Operator was immediately dispatched to the Diesel Generator room where he found the room full of smoke.
A thorough inspection revealed no evidence of a fire in the room.
The only local alarm was " Diesel Generator Motoring".
Not knowing the cause of the problem or the extent of damage, the Unit Two Diesel Generator and its associated 4 KV bus were declared inoperable. As required in Technical Speci fication 4.9.E., the 1/2 Diesel Generator and all low pressure core cooling and containnent cooling systems associated with the 1/2 Diesel were tested immediately.
Two off-site lines capable of supplying 345 KV power were available. The Uni t Two Diesel Generator to bus 24-1 ci rcuit breaker was taken out-of-service to prevent a possible spurious closure of the breaker and to allow inspection of the generator.
VI.
PR03ABLE CONSEQUENCES OF THE OCCURRENCE:
The probable consequences of this occurrence were minimal.
The Diesel Generator is designed to fast start and supply power to the Division 11 low pressure core cooling systems if off-site power is lost.
The shared Diesel Generator is a redundant system which can supply power to either unit and power Division I low pressure core cooling equipment.
The 1/2 Diesel Generator and its associated equipnent were available at all times while the Unit Two Diesel Generator was inoperable. Also, l
of f-si te power was availeble. The ability to safely shutdown and place the reactor in the cold shutdown mode was not affected as a result of this occurrence.
l Vll. CAUSE:
The cause of this occurrence has been designated as equipnent failure.
The 4 KV breaker in bus 24-1 which connects the Unit Two Diesel Generator with the emergency bus spuriously closed in, causing the bus to energize l
the generator stator and notor the generator.
The cause of the breaker i
closing in was postulated to be a ground fault in the 125 volt DC control power circuit which operates that breaker.
Four wi res inside the breaker
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Vll. CAUSE:cubicle were found to Save the insulation worn off.
One of these wires probably shorted to ground or another wire causing the breaker closing mechanism to energize, thus closing tne breaker.
Damage to the generator was limited to the three power current transformers which go to a neutral ground detector. These transformers are directly wired into the 4 KV circuit coming off the generator. The transformers had overheateJ resulting in internal damage to the transforcers, also, a lead to the primary winding of one of the transformers was burned off.
The emergency Diesel Generator is manufactured by the Electro-Motive Division of General Motors Corporation, model A-20-Cl; rated at 4160 i
volts, 452 amps, 3250 KVA. The 4 KV circuit breaker is manufactured by General Electric Company, model MC-4.76.
There have been no previous failures of this type at quad-Cities Station.
Vill. CORRECTIVE ACTION:
The immediate corrective action taken was to verify operability of the 1/2 Diesel Generator and its associated emergency bus.
Extensive inspections and tests were performed on tha generator and equipnent connected to it.
The rotor and stator were meggered and revealed no indications of faults or degraded insulation.
A visual inspection of generator internals showed signs of localized heating on the rotor pole faces and slight flaking of the insulation. The loose insulation was removed and new insulation material was applied.
New power current transformers were installed in the neutral ground detector circuit. The four wi res with worn insulation in the 4 KV breaker cubicle were replaced.
No other problems were found in the breaker cubicle. At 0957 on May 17, 1981, the Diesel Generator was successfully started and loaded to 2500 kilowatts on bus 24-1.
Vibration readings were taken with the Diesel Generator loaded and unloaded to verify no damage wat incurred in the shaf t or coupling.
Approximately 15 minutes af ter loading the generator, all generator electrical indication was lost in the Control Room. The output breaker was immediately opened and the Diesel was shutdown.
Operability of the 1/2 Diesel Generator and the associated low pressure core and containnent cooling systems were readily verified. Two off-site lines capable of supplying 345 KV power were available. The problem was found to be a failed diode in the voltage regulator circuit. The diode had probably e/erheated when the generator was motored, but had not completely failed.
The failed diode was replaced, and on May 19,1981, at 0952, the Diesel Generator was successfully started and loaded to the bus to verify operability.
To prevent recurrence, modi ficaGon M-4-2-77-21 will be installed during the next Unit Two Refueling Outage in the fall of 1981. This modification will trip the Diesel Generator to bus 24-1 breaker from loss of excitation, generator neutral voltage, generator reverse power, and overcurrent relays.
This modification will also be installed on the 1/2 Dicral Generator during the Unit Two fall Refueling Outage.
These protective tripning devices were installed on the Unit One Diesel Generator in the fall of 1980.
This modification should be adequate to p event recurrence.
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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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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 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| | 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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