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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20029D6321994-05-0202 May 1994 LER 94-002-01:on 940115,centrifugal Charging Pump 1A Discharge Bypass Valve Found in Open Position Contrary to Requirements of TS 3.1.2.3.Caused by hydro-pneumatic Transient.Valves Labeled W/Caution statements.W/940502 Ltr ML20029D6351994-04-27027 April 1994 LER 94-006-01:on 940214,reactor Manually Tripped Following Unanticipated Test Results.Caused by Mod Which Failed post- Mod Test.Test Terminated & Solid State Rod Control Sys Returned to Original Design configuration.W/940427 Ltr ML20029C6951994-04-18018 April 1994 LER 94-011-00:on 940310,safety Injection Actuation Was Received on Trains A,B & C.Cause Was Failure to Adhere to Procedure.Corrective Actions:Restored Cooling Shutdown & Removed Personnel from watchbill.W/940418 Ltr ML17352B2581994-03-25025 March 1994 LER 94-007-00:on 940224,station Procedure for Testing Reactor Trip Bypass Breakers Did Not Satisfy Ts.Caused by Inadequate Procedure Preparation & Review.Surveillance Procedure Enhancement Program underway.W/940325 Ltr ML20046C5471993-08-0606 August 1993 LER 93-018-00:on 930707,discovered Remote Position Indication Verification Test for SI Sys Accumulator Vent & Header Valves Had Not Been Performed in 2 Yrs Due to Change to IST plan.W/930806 Ltr ML20046C4901993-08-0505 August 1993 LER 93-019-00:on 930709,determined That TS Requirement of MSIV Was Not Met Due to Inadequate Design of Field Change to Testing Function of Solid State Protection Sys.Corrected Missing Jumpers & Overlap Testing discrepancy.W/930805 Ltr ML20046B1291993-07-29029 July 1993 LER 93-012-00:on 930614,lost Spent Fuel Pool Cooling for Approx 13 Hours Due to Insufficient Control Board Awareness. Design Change to Install Annunciator in Control Room to Inform of Loss of Spent Fuel cooling.W/930729 Ltr ML20046A6791993-07-21021 July 1993 LER 93-011-00:on 930401,pressurizer Safety Valve Setpoints Found Outside Required TS Tolerance.Caused by Setpoint Drift Due to Inherent Valve Characteristics.Mod of Test Procedures Underway ML20046A6511993-07-20020 July 1993 LER 93-017-01:on 930527,concluded That,Based on 930521 Determination,That Feedwater Isolation Bypass Valves Inoperable Since Pneumatic Positioners & Solenoids Remained in Svc Beyond Qualified Life.Control Scheme Modified ML20045J0281993-07-15015 July 1993 LER 93-016-01:on 930503,TS Violations Occurred Due to Circuitry for SG Power Operated Relief Valves & Post Accident Monitoring Instruments Being Inoperable.Replaced Missing Screws from Unit 1 QDPS.W/930715 Ltr ML20045H9171993-07-14014 July 1993 LER 93-008-01:on 930505,discovered That RHR Pump Suction MOV Had Not Been Environ Qualified Since 901129 Because Replacement of Drain T Not Completed.Drain T Missing from RH-0060B Replaced & Bulletin Issued to Maint Dept ML20045H9881993-07-13013 July 1993 LER 93-012-01:on 930405,TS Violation Occurred Due to Incorrect Settings of Several Molded Case Circuit Breakers. Reset Affected Unit 1 Breakers to Correct Settings. W/930713 Ltr ML20045E1531993-06-25025 June 1993 LER 93-017-00:on 930527,determined That Feedwater Isolation Bypass Valves Inoperable Since Pneumatic Positioner & Solenoids Remained in Svc Beyond Qualified Life.Caused by Incorrect Interpretation of Design Documents.Mod Underway ML20045E1491993-06-25025 June 1993 LER 93-010-00:on 930526,discovered That Screen Drive Coupling on Essential Cooling Water Traveling Screen 2A Damaged.Caused by Aging of Elastomeric Element.Couplings Replaced & Preventive Maint initiated.W/930625 Ltr ML20045B2731993-06-0909 June 1993 LER-93-016-00:on 930503,TS Violation Occured Due to Circuitry for SG PORVs & RCS Subcooling Monitor Being Inoperable.Caused by Less than Adequate Work Practices. Screws Missings from Qdps Replaced & Walkdown Performed ML20045A3831993-06-0404 June 1993 LER 93-008-00:on 930505,heat Removal Motor Operated Valve Inoperable in Excess of Allowable Outage Time.Caused by Failure to Recognize Condition.Condition Corrected by Replacing T Drain ML20044G4301993-05-25025 May 1993 LER 93-009-00:on 930426,Tech Spec Violation Occurred Due to Use of Inappropriate Ref Value Data for RHR Pump Inservice Test.Surveillance Procedures Revised to Include Appropriate Ref values.W/930525 Ltr ML20044F6281993-05-21021 May 1993 LER 93-015-00:on 930423,plant Personnel Determined That May 1990 Control Room Makeup & Cleanup Filtration Sys Svc Time Exceeded.Caused by Failure to Develop Run H Tracking Method. Run Times for Cleanup & Makeup Fans monitored.W/930521 Ltr ML20044F1321993-05-20020 May 1993 LER 93-009-01:on 930217,TS 3.0.3 Entered Due to Potentially Undersized Fuses in Ssps.Caused by Random Age Related Failure of Ssps Fuse.Fuses in Selected Equipment Replaced During Fuse & Breaker Field Verification Effort ML20044E0371993-05-14014 May 1993 LER 93-005-01:on 930214,control Room Operator Left CR Unmanned During Mode 4 Operation for 41 S.Caused by Inappropriate Action by Unit Supervisor.Event Will Be Included in Licensed Operator Requalification Training ML20024H2571991-05-24024 May 1991 LER 91-014-00:on 910420,erratic Containment Extended Range Pressure Channel Output Occurred.Caused by Bad Control Card. Weekly Channel Checks Performed,Control Card Replaced & Channel calibrated.W/910524 Ltr ML20024H2081991-05-22022 May 1991 LER 91-015-00:on 910422,train C AFW Pump Inadvertently Started Due to Failure of Led in Sequencer Test Circuitry. Faulty Led Replaced & Blocking Circuit Satisfactorily tested.W/910522 Ltr ML20029C1221991-03-15015 March 1991 LER 91-004-00:on 910215,loss of Offsite Power Actuation Occurred During Routine Maint.Caused by Lack of Attention to Work Performance Methods.Training Conducted for Maintenance personnel.W/910315 Ltr ML20029B0421991-02-25025 February 1991 LER 91-002-00:on 910126,automatic Actuation of Safety Injection Sys Occurred in One of Three Train C Trains.Caused by Inadequate Work Instructions for Maint Activity.Training Bulletin Issued & Supervisors counseled.W/910225 Ltr ML20024F7451990-12-12012 December 1990 LER 90-017-00:on 901104,discovered That Train a of Class IE 120-volt Distribution Panel DP001 Energized from Alternate Power Supply.Caused by Less than Adequate Administrative Controls.Log Will Be utilized.W/901212 Ltr ML20044B1691990-07-0606 July 1990 LER 90-011-00:on 900612,chemical Technician Supervisor Discovered That No Sample Collected in Condenser Air Removal Sys Radiation Monitor Moisture Collection Tank. Caused by Inadequate procedure.W/900706 Ltr ML20043G2091990-06-14014 June 1990 LER 90-010-00:on 900515,determined That Leak & Contamination Test Interval for Some Radioactive Sources Exceeded Tech Specs.Caused by Insufficient Detail in Procedures.Test Program revised.W/900614 Ltr ML20043G5191990-06-14014 June 1990 LER 90-010-00:on 900515,unplanned Actuation of ESF Train C Standby Diesel Generator Occurred.Caused by Personnel Error. Training Bulletin Will Be Issued to Maint Personnel Re event.W/900613 Ltr ML20043G1791990-06-13013 June 1990 LER 90-009-00:on 900512,incorrect Wiring in Solid State Protection Sys Discovered.Caused by Inadvertent Installation of Extra Wire by Mfg.Extra Wire Removed & Sys Successfully tested.W/900613 Ltr ML20043G2101990-06-13013 June 1990 LER 90-009-00:on 900514,discovered That Printer for Toxic Gas Analyzer XE-9325 Was Not Updating & Surveillances for Toxic Gas Monitor XE-9325 Incorrectly Performed on 900511. Caused by Inadequate training.W/900613 Ltr ML20043G7681990-06-0808 June 1990 LER 90-008-00:on 900508,Tech Spec Required Shutdown Initiated Due to Primary Coolant Sys Leakage.Caused by High Cycle Fatigue Failure of Weld on Upstream Side of Drain Valve.Drain Valves replaced.W/900608 Ltr ML20043E7001990-06-0404 June 1990 LER 90-008-00:on 891007,Tech Spec Violation Occurred Due to Failure to Perform post-maint Testing.Caused by Incorrect Determination That No post-maint Testing Required.Personnel counseled.W/900604 Ltr ML20043C7401990-05-30030 May 1990 LER 90-007-00:on 900430,discovered That All Three Trains of ESFAS Placed in Test & Incapable of Actuating for Approx 35 Minutes.Caused by Inadequate Prerequisite Conditions in Maint Procedure.Procedure Being modified.W/900530 Ltr ML20043C4791990-05-29029 May 1990 LER 90-007-00:on 900426,standby Diesel Generator 22 Room High Sump Level Alarm Actuated in Control Room.Caused by Flooding & Inadequate Spec of Sealing & Testing Requirements.Seals on Removable Panels caulked.W/900529 Ltr ML20043B6611990-05-25025 May 1990 LER 90-006-00:on 900426,control Room Ventilation Sys Actuated to Recirculation Mode Due to High Level Trip of Vinyl Acetate Channel on Gas Analyzer.Caused by Failure of electro-mechanical Positioner.Part replaced.W/900525 Ltr ML20043A7811990-05-15015 May 1990 LER 90-005-00:on 900414,simultaneous Reactor & Turbine Trip Occurred Due to Failure of Main Turbine Electrohydraulic Control Line.Caused by Fatigue Stress of Weld.Valve Modified to Add anti-swirl Baffles & anti-rotation pins.W/900515 Ltr ML20042F2191990-05-0202 May 1990 LER 90-005-00:on 900329,feedwater Booster Pump 11 Tripped Upon Actuation of Ground Fault Relay & Standby Pump 13 Started But Did Not Deliver Sufficient Flow to Prevent Trip. Cause Not Found.Inlet Filters to Be cleaned.W/900502 Ltr ML20042E3561990-04-0505 April 1990 LER 89-015-01:on 890704,reactor Trip Occurred.Caused by Failure of Relay in Generator Breaker Trip Circuit.Relays in Generator Breaker Trip Circuits Replaced W/Correct Models & Checked to Ensure Proper rating.W/900405 Ltr ML20012C7211990-03-16016 March 1990 LER 90-003-00:on 900214,discovered That Train B Fuel Handling Bldg Exhaust Air Filter Outlet Damper Would Not Open.Caused by Wiring Error Due to Failure of Technicians to Follow Work Instructions.Technicians counseled.W/900316 Ltr ML20012B4381990-03-0101 March 1990 LER 90-002-00:on 900202,Train s Reactor Trip Breaker Opened, Initiating Turbine & Reactor Trip & Feedwater Isolation on Low Average RCS Temp.Cause Unknown.Universal Logic Cards Replaced & Monitoring Instruments installed.W/900301 Ltr ML20006E3781990-02-16016 February 1990 LER 90-001-00:on 900103,containment Ventilation Isolation Occurred Due to Loss of Power to Radiation Monitor Actuation Relay.Caused by Technician Lifting Power Lead. Technicians Trained & counseled.W/900216 Ltr ML20006E4001990-02-12012 February 1990 LER 90-001-00:on 900108,Train s Low Steam Line Pressure Blocking Switch Placed in Blocked Position,Causing Actuation of Safety Injection & ESF Sys.Caused by Lack of Instructions.Training Program modified.W/900212 Ltr ML20006D4231990-02-0202 February 1990 LER 90-002-00:on 900103,redundant Solenoid Valve Which Actuates Train C Feedwater Valve Failed.Caused by Excessive Particulate Buildup.Solenoids Cleaned & Hydraulic Oil Flushed & Filtered to Remove particulate.W/900202 Ltr ML20006D5591990-02-0202 February 1990 LER 89-023-01:on 891216,standby Diesel Generator 11 Failed Tech Spec Required Operability Test & Declared Inoperable. Caused by Contact Oxidation & Low Contact Pressure.Chiller Auxiliary Relay Cleaned & adjusted.W/900202 Ltr ML20006B4731990-01-25025 January 1990 LER 89-024-00:on 891226,required Sample from Safety Injection Accumulator 1C of Boron Concentration Not Taken. Caused by Insufficient Administrative Controls to Track Surveillance Tests.Bulletin Will Be issued.W/900125 Ltr ML20006B2551990-01-19019 January 1990 LER 89-022-00:on 891205,discovered That ASME Section XI Pressure Test of Train C of Component Cooling Water Sys Not Performed Prior to Returning Sys to Svc.Sys Inoperable from 890909-1206.Test Control Procedures revised.W/900119 Ltr ML20006B2221990-01-16016 January 1990 LER 89-023-00:on 891216,standby Diesel Generator 11 Failed Tech Spec Required Operability Test & Attempt to Secure Essential Chiller 12C Resulted in Trip.Caused by Failure of Voltage Regulator.Regulator Returned to mfg.W/900116 Ltr ML20005E2471989-12-29029 December 1989 LER 89-028-00:on 891130,control Room Ventilation Sys Actuated to Recirculation Mode as Result of Spurious Signal. Caused by Memory Error Causing Microprocessor to Energize Relay Incorrectly.Troubleshooting planned.W/891229 Ltr ML19332D7741989-11-24024 November 1989 LER 89-018-01:on 890922,discovered That Const Installation Procedure for Reg Guide 1.97,Rev 2 Instrumentation Did Not Include Details to Ensure Qualification Per 10CFR50.49 or IEEE 323-1974.Caused by Installation error.W/891124 Ltr ML19332C8661989-11-21021 November 1989 LER 89-027-00:on 891025,discovered That Closed Limit Switch on Main Turbine Throttle Valve 2 Disconnected.Caused by Failure of Limit Switch Linkage.Review to Be Performed of Limit Switch Linkage design.W/891122 Ltr 1994-05-02
[Table view] Category:RO)
MONTHYEARML20029D6321994-05-0202 May 1994 LER 94-002-01:on 940115,centrifugal Charging Pump 1A Discharge Bypass Valve Found in Open Position Contrary to Requirements of TS 3.1.2.3.Caused by hydro-pneumatic Transient.Valves Labeled W/Caution statements.W/940502 Ltr ML20029D6351994-04-27027 April 1994 LER 94-006-01:on 940214,reactor Manually Tripped Following Unanticipated Test Results.Caused by Mod Which Failed post- Mod Test.Test Terminated & Solid State Rod Control Sys Returned to Original Design configuration.W/940427 Ltr ML20029C6951994-04-18018 April 1994 LER 94-011-00:on 940310,safety Injection Actuation Was Received on Trains A,B & C.Cause Was Failure to Adhere to Procedure.Corrective Actions:Restored Cooling Shutdown & Removed Personnel from watchbill.W/940418 Ltr ML17352B2581994-03-25025 March 1994 LER 94-007-00:on 940224,station Procedure for Testing Reactor Trip Bypass Breakers Did Not Satisfy Ts.Caused by Inadequate Procedure Preparation & Review.Surveillance Procedure Enhancement Program underway.W/940325 Ltr ML20046C5471993-08-0606 August 1993 LER 93-018-00:on 930707,discovered Remote Position Indication Verification Test for SI Sys Accumulator Vent & Header Valves Had Not Been Performed in 2 Yrs Due to Change to IST plan.W/930806 Ltr ML20046C4901993-08-0505 August 1993 LER 93-019-00:on 930709,determined That TS Requirement of MSIV Was Not Met Due to Inadequate Design of Field Change to Testing Function of Solid State Protection Sys.Corrected Missing Jumpers & Overlap Testing discrepancy.W/930805 Ltr ML20046B1291993-07-29029 July 1993 LER 93-012-00:on 930614,lost Spent Fuel Pool Cooling for Approx 13 Hours Due to Insufficient Control Board Awareness. Design Change to Install Annunciator in Control Room to Inform of Loss of Spent Fuel cooling.W/930729 Ltr ML20046A6791993-07-21021 July 1993 LER 93-011-00:on 930401,pressurizer Safety Valve Setpoints Found Outside Required TS Tolerance.Caused by Setpoint Drift Due to Inherent Valve Characteristics.Mod of Test Procedures Underway ML20046A6511993-07-20020 July 1993 LER 93-017-01:on 930527,concluded That,Based on 930521 Determination,That Feedwater Isolation Bypass Valves Inoperable Since Pneumatic Positioners & Solenoids Remained in Svc Beyond Qualified Life.Control Scheme Modified ML20045J0281993-07-15015 July 1993 LER 93-016-01:on 930503,TS Violations Occurred Due to Circuitry for SG Power Operated Relief Valves & Post Accident Monitoring Instruments Being Inoperable.Replaced Missing Screws from Unit 1 QDPS.W/930715 Ltr ML20045H9171993-07-14014 July 1993 LER 93-008-01:on 930505,discovered That RHR Pump Suction MOV Had Not Been Environ Qualified Since 901129 Because Replacement of Drain T Not Completed.Drain T Missing from RH-0060B Replaced & Bulletin Issued to Maint Dept ML20045H9881993-07-13013 July 1993 LER 93-012-01:on 930405,TS Violation Occurred Due to Incorrect Settings of Several Molded Case Circuit Breakers. Reset Affected Unit 1 Breakers to Correct Settings. W/930713 Ltr ML20045E1531993-06-25025 June 1993 LER 93-017-00:on 930527,determined That Feedwater Isolation Bypass Valves Inoperable Since Pneumatic Positioner & Solenoids Remained in Svc Beyond Qualified Life.Caused by Incorrect Interpretation of Design Documents.Mod Underway ML20045E1491993-06-25025 June 1993 LER 93-010-00:on 930526,discovered That Screen Drive Coupling on Essential Cooling Water Traveling Screen 2A Damaged.Caused by Aging of Elastomeric Element.Couplings Replaced & Preventive Maint initiated.W/930625 Ltr ML20045B2731993-06-0909 June 1993 LER-93-016-00:on 930503,TS Violation Occured Due to Circuitry for SG PORVs & RCS Subcooling Monitor Being Inoperable.Caused by Less than Adequate Work Practices. Screws Missings from Qdps Replaced & Walkdown Performed ML20045A3831993-06-0404 June 1993 LER 93-008-00:on 930505,heat Removal Motor Operated Valve Inoperable in Excess of Allowable Outage Time.Caused by Failure to Recognize Condition.Condition Corrected by Replacing T Drain ML20044G4301993-05-25025 May 1993 LER 93-009-00:on 930426,Tech Spec Violation Occurred Due to Use of Inappropriate Ref Value Data for RHR Pump Inservice Test.Surveillance Procedures Revised to Include Appropriate Ref values.W/930525 Ltr ML20044F6281993-05-21021 May 1993 LER 93-015-00:on 930423,plant Personnel Determined That May 1990 Control Room Makeup & Cleanup Filtration Sys Svc Time Exceeded.Caused by Failure to Develop Run H Tracking Method. Run Times for Cleanup & Makeup Fans monitored.W/930521 Ltr ML20044F1321993-05-20020 May 1993 LER 93-009-01:on 930217,TS 3.0.3 Entered Due to Potentially Undersized Fuses in Ssps.Caused by Random Age Related Failure of Ssps Fuse.Fuses in Selected Equipment Replaced During Fuse & Breaker Field Verification Effort ML20044E0371993-05-14014 May 1993 LER 93-005-01:on 930214,control Room Operator Left CR Unmanned During Mode 4 Operation for 41 S.Caused by Inappropriate Action by Unit Supervisor.Event Will Be Included in Licensed Operator Requalification Training ML20024H2571991-05-24024 May 1991 LER 91-014-00:on 910420,erratic Containment Extended Range Pressure Channel Output Occurred.Caused by Bad Control Card. Weekly Channel Checks Performed,Control Card Replaced & Channel calibrated.W/910524 Ltr ML20024H2081991-05-22022 May 1991 LER 91-015-00:on 910422,train C AFW Pump Inadvertently Started Due to Failure of Led in Sequencer Test Circuitry. Faulty Led Replaced & Blocking Circuit Satisfactorily tested.W/910522 Ltr ML20029C1221991-03-15015 March 1991 LER 91-004-00:on 910215,loss of Offsite Power Actuation Occurred During Routine Maint.Caused by Lack of Attention to Work Performance Methods.Training Conducted for Maintenance personnel.W/910315 Ltr ML20029B0421991-02-25025 February 1991 LER 91-002-00:on 910126,automatic Actuation of Safety Injection Sys Occurred in One of Three Train C Trains.Caused by Inadequate Work Instructions for Maint Activity.Training Bulletin Issued & Supervisors counseled.W/910225 Ltr ML20024F7451990-12-12012 December 1990 LER 90-017-00:on 901104,discovered That Train a of Class IE 120-volt Distribution Panel DP001 Energized from Alternate Power Supply.Caused by Less than Adequate Administrative Controls.Log Will Be utilized.W/901212 Ltr ML20044B1691990-07-0606 July 1990 LER 90-011-00:on 900612,chemical Technician Supervisor Discovered That No Sample Collected in Condenser Air Removal Sys Radiation Monitor Moisture Collection Tank. Caused by Inadequate procedure.W/900706 Ltr ML20043G2091990-06-14014 June 1990 LER 90-010-00:on 900515,determined That Leak & Contamination Test Interval for Some Radioactive Sources Exceeded Tech Specs.Caused by Insufficient Detail in Procedures.Test Program revised.W/900614 Ltr ML20043G5191990-06-14014 June 1990 LER 90-010-00:on 900515,unplanned Actuation of ESF Train C Standby Diesel Generator Occurred.Caused by Personnel Error. Training Bulletin Will Be Issued to Maint Personnel Re event.W/900613 Ltr ML20043G1791990-06-13013 June 1990 LER 90-009-00:on 900512,incorrect Wiring in Solid State Protection Sys Discovered.Caused by Inadvertent Installation of Extra Wire by Mfg.Extra Wire Removed & Sys Successfully tested.W/900613 Ltr ML20043G2101990-06-13013 June 1990 LER 90-009-00:on 900514,discovered That Printer for Toxic Gas Analyzer XE-9325 Was Not Updating & Surveillances for Toxic Gas Monitor XE-9325 Incorrectly Performed on 900511. Caused by Inadequate training.W/900613 Ltr ML20043G7681990-06-0808 June 1990 LER 90-008-00:on 900508,Tech Spec Required Shutdown Initiated Due to Primary Coolant Sys Leakage.Caused by High Cycle Fatigue Failure of Weld on Upstream Side of Drain Valve.Drain Valves replaced.W/900608 Ltr ML20043E7001990-06-0404 June 1990 LER 90-008-00:on 891007,Tech Spec Violation Occurred Due to Failure to Perform post-maint Testing.Caused by Incorrect Determination That No post-maint Testing Required.Personnel counseled.W/900604 Ltr ML20043C7401990-05-30030 May 1990 LER 90-007-00:on 900430,discovered That All Three Trains of ESFAS Placed in Test & Incapable of Actuating for Approx 35 Minutes.Caused by Inadequate Prerequisite Conditions in Maint Procedure.Procedure Being modified.W/900530 Ltr ML20043C4791990-05-29029 May 1990 LER 90-007-00:on 900426,standby Diesel Generator 22 Room High Sump Level Alarm Actuated in Control Room.Caused by Flooding & Inadequate Spec of Sealing & Testing Requirements.Seals on Removable Panels caulked.W/900529 Ltr ML20043B6611990-05-25025 May 1990 LER 90-006-00:on 900426,control Room Ventilation Sys Actuated to Recirculation Mode Due to High Level Trip of Vinyl Acetate Channel on Gas Analyzer.Caused by Failure of electro-mechanical Positioner.Part replaced.W/900525 Ltr ML20043A7811990-05-15015 May 1990 LER 90-005-00:on 900414,simultaneous Reactor & Turbine Trip Occurred Due to Failure of Main Turbine Electrohydraulic Control Line.Caused by Fatigue Stress of Weld.Valve Modified to Add anti-swirl Baffles & anti-rotation pins.W/900515 Ltr ML20042F2191990-05-0202 May 1990 LER 90-005-00:on 900329,feedwater Booster Pump 11 Tripped Upon Actuation of Ground Fault Relay & Standby Pump 13 Started But Did Not Deliver Sufficient Flow to Prevent Trip. Cause Not Found.Inlet Filters to Be cleaned.W/900502 Ltr ML20042E3561990-04-0505 April 1990 LER 89-015-01:on 890704,reactor Trip Occurred.Caused by Failure of Relay in Generator Breaker Trip Circuit.Relays in Generator Breaker Trip Circuits Replaced W/Correct Models & Checked to Ensure Proper rating.W/900405 Ltr ML20012C7211990-03-16016 March 1990 LER 90-003-00:on 900214,discovered That Train B Fuel Handling Bldg Exhaust Air Filter Outlet Damper Would Not Open.Caused by Wiring Error Due to Failure of Technicians to Follow Work Instructions.Technicians counseled.W/900316 Ltr ML20012B4381990-03-0101 March 1990 LER 90-002-00:on 900202,Train s Reactor Trip Breaker Opened, Initiating Turbine & Reactor Trip & Feedwater Isolation on Low Average RCS Temp.Cause Unknown.Universal Logic Cards Replaced & Monitoring Instruments installed.W/900301 Ltr ML20006E3781990-02-16016 February 1990 LER 90-001-00:on 900103,containment Ventilation Isolation Occurred Due to Loss of Power to Radiation Monitor Actuation Relay.Caused by Technician Lifting Power Lead. Technicians Trained & counseled.W/900216 Ltr ML20006E4001990-02-12012 February 1990 LER 90-001-00:on 900108,Train s Low Steam Line Pressure Blocking Switch Placed in Blocked Position,Causing Actuation of Safety Injection & ESF Sys.Caused by Lack of Instructions.Training Program modified.W/900212 Ltr ML20006D4231990-02-0202 February 1990 LER 90-002-00:on 900103,redundant Solenoid Valve Which Actuates Train C Feedwater Valve Failed.Caused by Excessive Particulate Buildup.Solenoids Cleaned & Hydraulic Oil Flushed & Filtered to Remove particulate.W/900202 Ltr ML20006D5591990-02-0202 February 1990 LER 89-023-01:on 891216,standby Diesel Generator 11 Failed Tech Spec Required Operability Test & Declared Inoperable. Caused by Contact Oxidation & Low Contact Pressure.Chiller Auxiliary Relay Cleaned & adjusted.W/900202 Ltr ML20006B4731990-01-25025 January 1990 LER 89-024-00:on 891226,required Sample from Safety Injection Accumulator 1C of Boron Concentration Not Taken. Caused by Insufficient Administrative Controls to Track Surveillance Tests.Bulletin Will Be issued.W/900125 Ltr ML20006B2551990-01-19019 January 1990 LER 89-022-00:on 891205,discovered That ASME Section XI Pressure Test of Train C of Component Cooling Water Sys Not Performed Prior to Returning Sys to Svc.Sys Inoperable from 890909-1206.Test Control Procedures revised.W/900119 Ltr ML20006B2221990-01-16016 January 1990 LER 89-023-00:on 891216,standby Diesel Generator 11 Failed Tech Spec Required Operability Test & Attempt to Secure Essential Chiller 12C Resulted in Trip.Caused by Failure of Voltage Regulator.Regulator Returned to mfg.W/900116 Ltr ML20005E2471989-12-29029 December 1989 LER 89-028-00:on 891130,control Room Ventilation Sys Actuated to Recirculation Mode as Result of Spurious Signal. Caused by Memory Error Causing Microprocessor to Energize Relay Incorrectly.Troubleshooting planned.W/891229 Ltr ML19332D7741989-11-24024 November 1989 LER 89-018-01:on 890922,discovered That Const Installation Procedure for Reg Guide 1.97,Rev 2 Instrumentation Did Not Include Details to Ensure Qualification Per 10CFR50.49 or IEEE 323-1974.Caused by Installation error.W/891124 Ltr ML19332C8661989-11-21021 November 1989 LER 89-027-00:on 891025,discovered That Closed Limit Switch on Main Turbine Throttle Valve 2 Disconnected.Caused by Failure of Limit Switch Linkage.Review to Be Performed of Limit Switch Linkage design.W/891122 Ltr 1994-05-02
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K9441999-10-15015 October 1999 SER Accepting Util Alternative Proposed Relief Request RR-ENG-2-4 for Second 10-year ISI Interval at Stp,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(i) ML20217K9151999-10-15015 October 1999 SER Authorizing Util Relief Request RR-ENG-2-3 for Second 10-year ISI Interval of Stp,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(i) NOC-AE-000676, Monthly Operating Repts for Sept 1999 for South Texas Project,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for South Texas Project,Units 1 & 2.With ML20217D0531999-09-30030 September 1999 Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr ML20217D0481999-09-30030 September 1999 Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 Colr ML20211P8411999-09-0909 September 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Surface Exam to Perform Boroscopic VT-1 Visual Exam of Pump Casing Welds within Pump Pits for Welds Covered by Relief Request RR-ENG-24 ML20211P7811999-09-0909 September 1999 SER Approving Second 10-year Interval Inservice Insp Program Plan Relief Request RR-ENG-2-8 (to Use Code Case N-491-2) for South Texas Project,Units 1 & 2 ML20211Q6731999-09-0909 September 1999 Safety Evaluation Accepting First 10-yr Interval ISI Program Plan Request for Relief from ASME Code Case N-498 NOC-AE-000643, Monthly Operating Repts for Aug 1999 for South Texas Project,Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for South Texas Project,Units 1 & 2.With ML20212E5191999-08-31031 August 1999 Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment ML20211F4531999-08-24024 August 1999 Safety Evaluation Supporting Licensee Proposed Alternative to Defer Partial First Period Exams of flange-to-shell Weld to Third Period & Perform Required Ultrasonic Exams,Both Manual & Automated,During Third Period ML20211F5111999-08-23023 August 1999 Safety Evaluation Supporting Licensee Proposed Alternative Contained in Request for Relief RR-ENG-30 ML20210C9411999-07-31031 July 1999 Rev 1 to SG-99-07-002, South Tx,Unit 1 Cycle 9 Voltage- Based Repair Criteria 90-Day Rept, Jul 1999 ML20210R3631999-07-31031 July 1999 Monthly Operating Repts for July 1999 for South Tx Project, Units 1 & 2.With ML20210D9161999-07-23023 July 1999 Safety Evaluation Accepting Inservice Testing Relief Request RR-56 Re Component Cooling Water & Safety Injection Sys Containment Isolation Check Valve Closure Test Frequency ML20210D4821999-07-21021 July 1999 1RE08 ISI Summary Rept for Steam Generator Tubing of South Texas Project Electric Generating Station Unit 1 ML20210D4491999-07-21021 July 1999 Revised Chapters to Operations QA Plan, Including Rev 9 to Chapter 1.0, Organization & Rev 6 to Chapter 16.0, Independent Technical Review NOC-AE-000583, LER 99-S03-00:on 990619,failure to Revitalize Sdg Number 11 Was Noted.Caused by Failure to Communicate Status of Sdg. Subject Sdg Revitalized on 990619 & Licensee Will Develop Security Force Instruction Re Sdgs.With1999-07-15015 July 1999 LER 99-S03-00:on 990619,failure to Revitalize Sdg Number 11 Was Noted.Caused by Failure to Communicate Status of Sdg. Subject Sdg Revitalized on 990619 & Licensee Will Develop Security Force Instruction Re Sdgs.With ML20207H6361999-07-0808 July 1999 Safety Evaluation Approving 2nd 10 Yr Interval ISI Program Plan Request to Use ASME Section XI Code Case N-546 for Licenses NPF-76 & NPF-80,respectively ML20216D7481999-07-0707 July 1999 1RE08 ISI Summary Rept for Welds & Component Supports of STP Electric Generating Station,Unit 1 NOC-AE-000593, Monthly Operating Repts for June 1999 for Stp,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Stp,Units 1 & 2. with NOC-AE-000570, LER 99-S01-00:on 990527,discovered That Unescorted Access Had Been Inappropriately Granted.Caused by Failure to Follow Procedure.Util Verified That Individual Did Not Have Current Unescorted Access at STP or Any Other Util.With1999-06-28028 June 1999 LER 99-S01-00:on 990527,discovered That Unescorted Access Had Been Inappropriately Granted.Caused by Failure to Follow Procedure.Util Verified That Individual Did Not Have Current Unescorted Access at STP or Any Other Util.With ML20196G5821999-06-23023 June 1999 LER 99-S02-00:on 990601,failure to Maintain Positive Control of Vital Area Security Key Was Noted.Caused by Lack of Attention to Detail.Discussed Event with Operator Involved IAW Constructive Discipline Program ML20195J6871999-06-17017 June 1999 Safety Evaluation Supporting Proposed Alternative Contained in RR-ENG-2-5.Proposed Alternative Authorized Per 10CFR50.55a(a)(3)(i) for 2nd ISI Interval ML20196A2391999-06-15015 June 1999 Change QA-042 to Rev 13 of Operations QAP, Reflecting Current Organizational Alignment for South Texas Project & Culminating Organizational Realigment That Has Been Taking Place During Past Several Months NOC-AE-000563, Monthly Operating Repts for May 1999 for Stp,Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Stp,Units 1 & 2. with ML20206U5411999-05-18018 May 1999 Non-proprietary Errata Pages for Rev 2,Addendum 1 to WCAP-13699, Laser Welded Sleeves for 3/4 Inch Diamete Tube Feedring Type & W Preheater SGs Generic Sleeving Rept ML20206A7721999-04-30030 April 1999 STP Electric Generating Station Unit 1 Cycle 9 Colr NOC-AE-000543, Monthly Operating Repts for Apr 1999 for Stp,Units 1 & 2. with1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Stp,Units 1 & 2. with ML20205H0321999-03-31031 March 1999 Change QA-040 to Rev 13 of Operations QA Plan NOC-AE-000507, Monthly Operating Repts for Mar 1999 for Stp,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Stp,Units 1 & 2. with ML20205A3781999-03-22022 March 1999 STP Electric Generating Station Simulator Certification Four Yr Rept for Units 1 & 2 ML20204B2711999-03-15015 March 1999 Safety Evaluation Authorizing 990201 Request to Authorize Alternative to Regulations Per 10CFR50.55a(a)(3)(i) That Would Revise Start of Second 120-month IST Interval to No Later than 011201 ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results NOC-AE-000468, Monthly Operating Repts for Feb 1999 for South Texas Project Electric Generating Station.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for South Texas Project Electric Generating Station.With ML20207D1101999-02-24024 February 1999 Change QA-039 to Rev 13 of Operations QA Plan, for STP ML20203H8361999-02-17017 February 1999 Safety Evaluation Supporting Request for Relief from ASME Code Requirements for Class 3 Piping for Plant ML20202H9621999-02-0303 February 1999 SER Accepting Change to EALs Used in Classification of Emergency Conditions ML20202E8471999-01-31031 January 1999 2RE06 ISI Summary Rept for SG Tubing of STP Electric Generating Station,Unit 2 ML20216G2011999-01-31031 January 1999 City Public Svc of San Antonio Annual Rept 1998-1999 ML20199G5961999-01-31031 January 1999 Cycle 7 Voltage-Based Repair Criteria Rept for Jan 1999 ML20199K7711999-01-21021 January 1999 Safety Evaluation Accepting ISI Program Request for Relief for ASME Cose Repair Requirements for Code Class 3 Piping ML20199G8161999-01-19019 January 1999 SER Accepting Util 970707 Response to NRC 970509 RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers. NRC Finds No Significant Safety Hazards Based on Application of Util Ampacity Derating Methodology ML20199H4981999-01-11011 January 1999 2RE06 ISI Summary Rept for Welds & Component Supports of Stp,Unit 2 ML20206Q3751999-01-0404 January 1999 2RE06 ISI Summary Rept for Sys Pressure Tests (Class 1 & 2) ML20206Q3721999-01-0404 January 1999 2RE06 ISI Summary Rept for Repairs & Replacements ML20216G2171998-12-31031 December 1998 Houston Industries 1998 Annual Rept. App a 1998 Financial Statements & Us Securities & Exchange Commission Form 10-K Encl NOC-AE-000403, Monthly Operating Repts for Dec 1998 for South Texas Project Unit 1 & 2.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for South Texas Project Unit 1 & 2.With ML20216G1521998-12-31031 December 1998 Central & South West Corp 1998 Summary Annual Rept & Securities & Exchange Commission Form 10-K ML20198M3431998-12-28028 December 1998 SER Accepting Util Request for Relief from ASME Code Repair Requirements for ASME Code Class 3 Piping for South Texas Project,Unit 2 1999-09-09
[Table view] |
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November 10, 1989 ;
ST-HL-AE-3290 File No.: G26 l 10CFR50.73 l i
U. S. Nuclear Regulatory Commission Attention: Document Control Desk ;
Washington, DC 20555 >
South Texas Project Electric Generating Station Unit 1 Docket No. STN E0-498 ;
Licensee Event Report 89-020 Regarding Unplanned Engineered Safety Features Actuations Due to an Inverter Failure Pursuant to 10CFR50.73 Houston Lir,hting & Power (HL&P) submits the i attached Licensee Event Report 89-020 regarding an unplanned Engineered Safety
- Features actuations due to an inverter failure. This event did not have any adverse f.rnpact on the health and safety of the public. 3 If you should have any questions on this matter, please contact Hr. C. A. Ayala at (512) 972-8628.
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R.' W. Chevning [
Vice President l Nuclear Operations ,
I RWC/BEM/n1 t
Attachments LER 89-020, South Texas, Unit 1 ,
t 8911150093 891 10 -
PL*R ADOCK 050>0498 N 22; s PDC NL.LER89020 U1 A Subsidiary of Ilouston Industries lucorporated t -- ..
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( cet Regional Admissistrator, Region IV Rufus S. Scott Nuclear Regulatory Commission Associate General Counsel 61,1 Ryan Plaza Drive Suite 1000 Houston Lighting & Power Company Arlington, TX 76011 P. O. Box 1700 Houston, TX 77001 l George Dick, Project Manager U. S. Nuclear Regulatory Commission INPO Washington, DC 20555 Records Center 1100 Circle 75 Parkway J. 2. Tapia Atlanta, GA 30339-3064 i Senior Resident Inspector
- c/o U. S. Nuclear Regulatory Commission Dr. Joseph H. Hendrie P. O. Box 910 50 Be11 port Lane Bay City, TX 77414 Be11 port, NY 11713 R. J. Evans D. X. Lacker Resident Inspector Bureau of Radiation Control c/o U. S. Nuclear Regulatory Commission Texas Department of Health P. O. Box 910 1100 West 49th Street Bay City Texas 77414 Austin, TX 78756-3189 J. R. Newman, Esquire Newman & Holtzinger, P.C.
1615 L Street, N.W.
Washington, DC 20036 R. L. Range /R. P. Verret Central Power & Light Company P. O. Box 2121 Corpus Christi, TX 78403 R. John Miner (2 copies)
Chief Operating Officer City of Austin Electric Utility 721 Barton Springs Road 1
Austin, TX 78704 R. J. Costello/M. T. Hardt City Public Service Board P. O. Box 1771 San Antonio, TX 78296 Revised 11/08/89 NL.DIST
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.mi n ac, ,o ,. .m .. . .., . 4. n . . . n ei On October 11, 1989, Unit I was in Mode 3 prior to restart froio a refueling outage. At approximately 1533 hours0.0177 days <br />0.426 hours <br />0.00253 weeks <br />5.833065e-4 months <br />, the inverter which feeds the Channel IV Class IE Vital AC distribution panel failed. This caused Engir etired Safety Features actuations of the Control Room, Reactor Containment Building and Fuel Handling Building HVAC eystems due to lose of power to their respective radiation monitors. The cause of this event was f ailure of a bridge rectifier circuit on the inverter DC to DC converter board. The circuit appeared to have failed due to excessive output voltage over an extended period of time which overheated the components. The inverter has been repaired and the DC to DC converter voltage adjusted. Preventive maintenance procedures will be revised to require periodic DC to DC converter board output voltage adjustments. Inverters will be added to the existing plant thermography program which will assist in identifying equipment that could be approaching a similar failure.
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"** bl3.". ' O.1T; South Texas, Unit 1 vows a ==. - . = .asm aar an. .,ne, 0 l5 l o_ j o l 0 l 4 l 9l 8 8l9 0 l 2l0 0l0 0l 2 or 0l4 DESCRIPTION OF EVENT: ,
On October !!, 1989. Unit I was in Mode 3 prior to restart from a refueling outage. At approximately 1533 hours0.0177 days <br />0.426 hours <br />0.00253 weeks <br />5.833065e-4 months <br />, power was lost to the Class 1E 120 Volt AC vital distribution panel DP002. This caused Engineered Safety Features (ESF) actuations of Control Rocm, Reactor Containment Building and Fuel Handling Building HVAC systema due to loss of power to their respective i radiavtan monitors. Once it waa determined that the actuations occurred as a !
result of the power failure, oporations personnel took action to restore power to panni DP002 at 1552 hours0.018 days <br />0.431 hours <br />0.00257 weeks <br />5.90536e-4 months <br /> and restore the HVAC systems to their normal mode. ;
Inspection of the inverter which supplies panel DP002 revealed a failed output bridge rectifier on the DC to DC converter board. This board supplies power to various inverter circuit cards. As a result of a previous failure on a similar DC to DC converter card on another inverter, a corrective action was.
identified which required periodic measurement of output voltages and adj ustment if necessary. Heasurements were taken of the DC to DC converter board output voltace in January of 1989 per the instrue tions of a preventive ,
maintenance procedure. At that time, the voltage was oetermined to be high and a Work kequest was written to adjust the voltage to its correct value. i This adjustment was performed on October 11, 1989, approximately four hours prior to the board failure. The maintenance and engineering personnel {
performing the adjustment noted evidence of overheating of some of the board's i components. This finding was being evaluated and board replacement was being considered at the time of the failure.
Cg1SE OF EVENT:
i The most likely cause of this event has been identified as excessive output voltage of the inverter DC to DC converter board for an extended period of time which resulted in heating and preinature f ailure of the output bridge ;
rectifier. This problem may have been aggravated when the board was disturbed to perform the output voltage adjustment earlier that day, i
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ANALYSIS OF EVENT:
This event resulted in the unplanned Engineered Safety Features actuations of the Control Room, Fuel Handling Building and Reactor Containment Building HVAC systems. Had a radiological release occurred during this event, these systems would have already been in their safest mode. While any unnecessary challenge to an ESF system is undesirsble, actuation of these systems represunts a minimal hazard since it could not cause, exacerbate or prevent mitigation of an accident.
Unplanned actuation of an ESF system is reportable pursuant to 10CFR50.73(a)(2)(iv).
CORRECTIVE ACTION:
The following corrective actions are being taken as a result of this event:
- 1. The inverter DC to DC converter board has been replaced, its voltage adjusted and the inverter has been returned to service.
- 2. The other similar inverters have been checked for proper DC to DC converter board output voltage. They have also been subjected to thermographic examination which will assist in detecting excessive component temperatures.
- 3. The preventiva maintenance procedures for similar inverters will be revised to include instructions to adjust the DC to DC converter board output when it is found out of tolerance in lieu uf only measuring this output. This will assure that DC to PC converter board output voltage is l promptly adjusted when needed. This action will be completed by December 18, 1989.
- 4. periodic inspection of inverters will be added to the plant thermography program by December 31, 1989. This will assist in identifying emponents which are experiencing e;teessive heating prior to f ailure.
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ADDITIONAL INFORMATION: i i
The failed inverter is a 25 KVA, single phase, 120 volt AC unit manufactured l
by Elgar Corporation. The model number is INV 253-1-105.
Two previous events have been reported regarding the failure of components on -
I the DC to DC converter board of this same model of inverter:
L LER 88-021 (Unit 1) reported an inverter failure which caused numerous !
EST actuations.
LER 89 023 (Unit 2) reported a non-safety related inverter which failed 6 and caused a turbine trip and reactor trip. ,
In each case the specific component which f ailed on the DC to DC converter i board has been different. ;
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