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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
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The Light cllouston o mp a ny 8""'h3' I"I 33"i' C'""ating station Lighting & Power I>. O. nox 289
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May 22, 1991 ST.HL-AE-3781 File No.. G26 10CFR50.73 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 South Texas Project Electric Generating Station Unit 1 Docket No. STN 50-498 Licensee Event Report 91-015 Regarding an Engineered Safety Feature Actuati2p Caused by a Failed Light Emittinn Diode Pursuant to 10CFR50.73, Houston Lighting & Power Company (HL&P) submits the attached Licensee Event Report (LER 90 015) regarding a Engineered Safety Feature actuation caused by a failed light emitting diode.
If you should have any questions on this matter, please contact Mr. C. A. Ayala at (512) 972-862d or myself at (512) 972-7205.
) 4bn William J . Jump Manager, Nuclear Licensing SMH/kmd
Attachment:
LER 91-015 (South Texas, Unit 1) t m s.i m ot.ut 910530,179 910522 A Subsidiary of flouston industries incorporated 7Q PDR ADOCK 05000498 S PDR />/
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ST-HL- AE- 3781 llouston Light.ing & Power C,ompany File No ' G26 South Texas Project Electric Generating Station Paga 2 cc Regional Administrator, Region IV Rufus S. Scott Nuclear Regulatory Commission Associate General Counsel
-611 Ryan Plaza Drive, Suite 1000 Houston Lighting & Power Company Arlington, TX 76011 P. O. Box 61867 Houston, TX 77208 Ceorge Dick, Project Manager U.S. Nuclear Regulatory Commission INPO Washington, DC 20555- Records Center 1100 circle 75-Parkway J. I. Tapia Atlanta, GA 30339-3064 Senior Resident inspector c/o U. S. Nuclear Regulatory Dr. Joseph M. Hendrie Commission 50 Bellport Lane
-P., O. Box 910 Be11 port, NY 11713 Bay City 'D( 77414 D. R. Lacker J. R. Newman, Esquire Bureau of Radiation Control Newman & Holtzinger, P.C. Texas Department of Health 1615 L Street, N.W. 1100 West 49th Street Washington, DC 20036 Austin, TX 78756-3189 D. E. Ward /T. M. Puckett Central Power and Light Company
. P. O. Box 2121 Corpus Christi,-TX 78403 J . C. Lanier/M B. Lee City of Austin.
Electric Utility Department
-P.O. Box 1088 Austin, TX 78767 R.- J . Costello/M. T. Hardt
-City.Public Service Board P,.0. Box 1771-San Antonio, TX 78296 Revised 01/29/91 L4/NRC/
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On April 22, 1991, Unit I was in Mode 1 operating at 100% power. At 0200, during performance of a Train C Engineered Safety Feature Sequencer surveillance test, the Train C Auxiliary Feedwater (AFW) Pump inadvertently started. The pump was secured at 0208. The cause of this event was failure of a Light Emitting Diode (LED) in the Sequencer test circuitry. The LED has been replaced. An evaluation has determined that a similar failure of an LED in the Sequencer actuation circuitry, rather than the test circuitry, would prevent actuation of the associated ESF component. The functionality of the sequencer is tested quarterly. In addition, if such a failure occurred, an alarm would indicate the affected component had failed to start and operator action could be taken to statt the component. Therefore, since there has been only one such failure at STP, no additional corrective action is planned.
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On April 22, 1991, Unit I was in Mode 1 at 100 percent power. A surveillance test of the C train Engineered Safety Feature (ESP) Sequencer was being performed to check actuation relay function and circuit continuity. During performance of the test, C train Auxiliary Feedwater (AFW) Pump 13 inadvertently started at 0200. The ATV pump was secured at 0208. The incident was reported to the NRC at 0500.
The ESF sequencer surveillance test is performed in the Manual Local mode. In this mode, blocking relays are energized to prevent actuation of some of the sequenced loads. Output relay actuation is indicated on the Output Status Indicator display while circuit continuity is indicated on the External Circuit Continuity Monitor. Initially, all lights on both monitors are out.
As the output relays close for each load as it is sequenced, the corresponding lamp on the output Status Indicator illuminates and remains on for the remainder of the tes:. When this indication is received, a pushbutton on the External Circuit Continuity Monitor corresponding to the sequenced load is momentarily depressed allowing a current too low to operate the load to flow through the circuit. A light on this monitor illuminates to indicate circuit continuity and extinguishes when the pushbutton is released.
Dur'ng performance of the test, the lamp associated with AFW pump 13 on the External Circuit Continuity Monitor functioned properly while testing the continuity of the circuit. After all the output relays had sequenced but prior to resetting the sequencer at the end of the test, the lamp associated with the AFW pump lit and remained lit on the External Circuit Continuity Monitor. Actuation of the AFW pump followed. The light on the External Circuit Continuity Monitor for the AFW pump is illuminated by completing the circuit with the monitor pushbutton or by closure cf the blocking relay contacts.
Troubleshooting identified that a Light Emitting Diode (LED) in series with an optical isolator had failed open during the surveillance test. The optical isolator provides a current path for the blocking relay associated with the AFW circuit. Failure of the LED caused deenergization of the blocking relay for AFW pump 13, causing the AFW pump to start. The optical isolator was removed and installed on a new board containing a new LED. Functional testing of the blocking circuit was satisfactery.
Indication that blocking relays are energized is provided on the Sequencer Test / Status Control Panel. The blocking relay status contacts are connected in serie s to illuminate the indication. The indication will not illuminate if any one blocking relay fails to energize. Surveillance procedures require that test personnel verify that the lamp indicating that the blocking relays tDM91130301,U1 c cau ne.
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0l 0 0l3 or 0 l4 pESCRIPTION OF EVENT: (cont'd) are energized is illuminated. This is done after the sequencer is put into the Manual Local mode and before proceeding with the sequencing portion of the test. During the performance of this test, the blocking relays were successfully energized since the sequencing portion of the test had been completed without AFW actuation. This confirms that the LED failure and subsequent blocking relay deen 6erization occurred during the performance of the test.
LEDs are also used in the input and output relays that are part of the actuation citcuitry. Input and portions of the output relay circuits are continually tested while the sequencer is in the Auto Test mode. Detection of an open input or output circuit interrupts the Auto Test and generates a Trouble indication. Plant operations personnel perform a surveillance once per shift in Modes 1 through 4 to verify that the sequencer is functioning properly in the Auto Test Mode. A portion of the output ciretit, including the LED, is not tested in the Auto Test Mode. This portion of the output circuit is functionally tested during the quarterly surveillance performed at the time of this incident. Failure of an LED in the output circuit to the open position would prevent actuation of the associated component. Failure to actuate would be annunciated in the control room and the equipment can be manually started. Open circuit failure of an LED is an unusual condition.
More commonly, an IID will short, which affects indication but not circuit operability.
CAUSE OF EVENT:
The cause of this event was a failed open LED in the circuit associated with the blocking relay for the AFW pump. Failure of the LED created an open circuit which allowed the blocking relay to deenergize resulting in the start of the AFW pump ANALYSIS OF EVENT:
Unanticipated . zation of the AFW pump occurred during an ESF sequencer surveillance te . . Unplanned actuation of an Engineered Safety Feature is reportable in accordance with 10CFR30.73(a)(2)(iv). The LED that failed was part of a test circuit. Failure of this component would not have prevented proper operation of the ESF Sequencer under an actual emergency situation.
LEDs are used in the same configuration in other circuits suc'c as those associated with the input and output relays. Failure of an LED or any other component in these circuits to the open position would prevent receipt of a field input signal or. prevent closure of output relay contrcts to the tut \91130001.U1 a eo=M uem
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CORRECTIVE ACTIONS:
The faulty LED was replaced and the blocking circuit satisfactorily tested, i As noted above, LEDs are included in the ac:uation circuitry of the sequencer.
- Failure of any of these LEDs would prevent .ictuation of the associated ESF component. However, since the component can be manually started upon annunciation in the control room of the failure to actuate condition, coupled with the fact that this is the only such failure to have occurred in either unit's respective sequencers (6 total), no additional corrective actions are considered necessary.
ADDITIONAL INFORMATION:
A review of work history associated with the Unit 1 and Unit 2 ESF sequencer did not reveal a similar failure. A similar LED had previously failed in a shorted condition which prevented illumination of the LED but did not open the circuit.
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