LER-1981-007, /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 |
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U. S. NUCLEAR f.E!ULATORY COMP'.lSSloN NRC FORM 366 (7 77)
!.lCENSEE EVENT REPORT
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3 EVENT DESCRIPTION AND PROB #3LE CONS"QUENCES h to :J l At 10:45 a.m. the unit operator observed that there was no position indication on I
1A Recirculation Pump discharge valve M0-1-202-5A.
The_ breaker for the valve motor l g;.gl was found tripped and it could not be reset. This caused LPCI mode of RHR to be l
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RHRS being inoperable in accordance with Technical Specification 3.5.A.5 g-i fgl plant operation was not affected by this occurrence.
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LER NUMBER: LER/R0 81-7/03L-0 11.
LICENSEE NAME:
Connonwealth Edison Company Quad-Cities Nuclear Power Station lit.
FACILITY NAME: Unit One IV.
DOCKET NUMBER:
050-254 V.
EVENT DESCRIPTION
At 10:45 a.m. on March 13, 1981, Unit One was in the RUN mode operating at a steady power level of 812 MWe and 2486 MWt.
At 10:45 a.m. the unit operator observed that the 1A Recirculation Pump discharge valve MO-1-202-SA showed no position indication. An equipment attendant, sent to investigate the problem, determined that the breaker, at notor control center 18/19-5, for the valve motor had tripped. The breaker was reset and it tripped again.
Technical Speci fication 3.5. A.3. requires the LPCI mode of the RHR system to be operable when irradiated fuel is in the reactor. Since the breaker tripped and the valve could not be operated, LPCI was declared inoperable.
This was due to the fact that LPCI loop-select depends on closure of valve MO-1-202-5A in the event of a recirc pipe break on the B recirc loop.
LPCI injection into the A loop with the SA valve remaining open would have likely resulted in water being injected into the shroud rather than into the core. Work Request Qll582 was written to investigate the cause and repair.
VI.
PROBABLE CONSEQUENCES OF THE CCCURRENCE:
Technical Specification 3.5 A.5. requires that both core spray subsysters, the containment cooling mode of RHR, two RHR pumps and two standby diesel generators be demonstrated to be operable at the time that LPCI is declared inoperable. Two RHR pumps used for containment cooling had been demonstrated to be operable on the previous day and remained operable thereafter. The renaining items were demonstrated to be operable per the Technical Specification at the time of declaring LPCI inoperable.
Safe plant operation was not affected by this occurrence.
Vll.
CAUSE
The 12 conductor control cable for the valve notor consists of cable #12506 from the notor control center to tne drywell, the drywell penetration itself, and cable #12507 within the drywell from the penetration to the valve motor. Several conductors of cable #12507 were shorted togetner, causing the breaker to trip and the position indication in the Control Room to be Icst.
Vill. CORRECTIVE ACTION:
Cable #12507 runs through conduit and cable trays in the drywell and could not be visually inspected in its entirety. An electrical test revealed that several conductors of the cable had shorted. A temporary 5-conductor flexible cable was installed to replace the shorted conductors. The cable and hardware used to install it were approved under the Quality Assurance program. The ca'aie was run in open air and is routed away from heat sources within the drywell.
The cable was tested satisfactorily by stroking valve MO-1-202-5A and checking to see that the recirculation pump tripped when valve MO-1-202-SA was closed.
Work Request Qll606 was wr8 tten to permanently install cable #12507 at the time of the next convenient scheduled Unit One outage of sufficient length.
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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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