05000327/LER-1999-002-03, :on 990916,EDG Started as Result of Cable Being Damaged During Installation of Thermo-Lag for Kaowool Upgrade Project.Caused by Inadequate pre-job Briefing. Involved Individuals Were Counseled on Event1999-10-15015 October 1999
- on 990916,EDG Started as Result of Cable Being Damaged During Installation of Thermo-Lag for Kaowool Upgrade Project.Caused by Inadequate pre-job Briefing. Involved Individuals Were Counseled on Event
05000327/LER-1998-003-01, :on 981109,Vital Inverter 1-IV Tripped.Caused by Failed Oscillator Board with Bad Solder Joint,Attributed to Mfg Defect.Replaced Component & Returned Inverter to Operable Status1999-05-27027 May 1999
- on 981109,Vital Inverter 1-IV Tripped.Caused by Failed Oscillator Board with Bad Solder Joint,Attributed to Mfg Defect.Replaced Component & Returned Inverter to Operable Status
05000327/LER-1999-001-04, :on 990415,exceedance of AOT Occurred Due to Failure of Centrifugal Charging Pump.Rotating Element Was Replaced,Testing Was Completed & Pump Was Returned to Svc1999-05-11011 May 1999
- on 990415,exceedance of AOT Occurred Due to Failure of Centrifugal Charging Pump.Rotating Element Was Replaced,Testing Was Completed & Pump Was Returned to Svc
05000327/LER-1998-004-02, :on 981120,failure to Perform Surveillance within Required Time Interval,Was Determined.Caused by Leaking Vent Valve.Engineering Personnel Evaluated Alternative Methods for Performing Channel Check1998-12-21021 December 1998
- on 981120,failure to Perform Surveillance within Required Time Interval,Was Determined.Caused by Leaking Vent Valve.Engineering Personnel Evaluated Alternative Methods for Performing Channel Check
05000327/LER-1998-003-04, :on 981109,automatic Reactor Trip Occurred. Caused by Component in Bridge Circuit of Vital Inverter Failed.Inverter Bridge Circuit Replaced1998-12-0909 December 1998
- on 981109,automatic Reactor Trip Occurred. Caused by Component in Bridge Circuit of Vital Inverter Failed.Inverter Bridge Circuit Replaced
05000328/LER-1998-002-05, :on 981016,turbine Trip Occurred Followed by Reactor Trip.Caused by Generator Lockout.Mod Being Evaluated to Physically Isolate Relays from Vibration of Transformers & Adding Two of Two Logic for Actuation of Sudden Pressure1998-11-10010 November 1998
- on 981016,turbine Trip Occurred Followed by Reactor Trip.Caused by Generator Lockout.Mod Being Evaluated to Physically Isolate Relays from Vibration of Transformers & Adding Two of Two Logic for Actuation of Sudden Pressure
05000328/LER-1998-001-05, :on 980827,turbine Trip Occurred Followed by Reactor Trip.Caused by Failure of Sudden Pressure Relay on B Phase Main Transformer.Control Room Operators Responded & Removed,Inspected & Replaced Failed Relays1998-09-28028 September 1998
- on 980827,turbine Trip Occurred Followed by Reactor Trip.Caused by Failure of Sudden Pressure Relay on B Phase Main Transformer.Control Room Operators Responded & Removed,Inspected & Replaced Failed Relays
05000327/LER-1998-002-03, :on 980716,inadequate Surveillance Testing Was Discovered.Caused by Misinterpretation of ANSI Standard. Revised Appropriate Procedures to Provide Required Guidance1998-08-14014 August 1998
- on 980716,inadequate Surveillance Testing Was Discovered.Caused by Misinterpretation of ANSI Standard. Revised Appropriate Procedures to Provide Required Guidance
ML20236P6441998-07-10010 July 1998
LER 98-S01-00:on 980610,failure of Safeguard Sys Occurred for Which Compensatory Measures Were Not Satisfied within Required Time Period.Caused by Inadequate Security Procedure.Licensee Revised Procedure MI-134
05000327/LER-1998-001-04, :on 980519,automatic Reactor Trip Occurred. Caused by Failure of Alternate Feedwater to 1A1-A 480-volt Shutdown Board.Normal Feedwater Breaker Placed in Svc & 480- Volt Shutdown Board Returned to Operation1998-06-18018 June 1998
- on 980519,automatic Reactor Trip Occurred. Caused by Failure of Alternate Feedwater to 1A1-A 480-volt Shutdown Board.Normal Feedwater Breaker Placed in Svc & 480- Volt Shutdown Board Returned to Operation
05000327/LER-1997-014-01, :on 971101,discovered That RCS PORVs Were Not Cycled in Mode 4 as Required by Ts.Caused by Inadequate Procedures.Procedure Revised & Unit Cooled Down to Mode 41997-12-0101 December 1997
- on 971101,discovered That RCS PORVs Were Not Cycled in Mode 4 as Required by Ts.Caused by Inadequate Procedures.Procedure Revised & Unit Cooled Down to Mode 4
ML20199C2951997-11-13013 November 1997
LER 97-S01-00:on 971017,vandalism of Electrical Cables Was Observed.Caused by Vandalism.Repaired Damaged Cables, Interviewed Personnel Having Potential for Being in Area at Time Damage Occurred & Walkdowns
05000328/LER-1997-001, :on 970117,missed Surveillance on Auxiliary Contacts of Reactor Trip Breakers Discovered.Caused by Adequate PMT for Reactor Trip Breaker Was Not Performed. Multi-disciplinary Team Formed to Perform Investigation1997-10-0606 October 1997
- on 970117,missed Surveillance on Auxiliary Contacts of Reactor Trip Breakers Discovered.Caused by Adequate PMT for Reactor Trip Breaker Was Not Performed. Multi-disciplinary Team Formed to Perform Investigation
05000327/LER-1997-011-01, :on 970725,operations Training Personnel Found 125 Vdc Vital Battery Board 4 Improperly Aligned.Caused by Personnel Error.Provided Appropriate Disciplinary Action for Individuals Involved in Event1997-09-17017 September 1997
- on 970725,operations Training Personnel Found 125 Vdc Vital Battery Board 4 Improperly Aligned.Caused by Personnel Error.Provided Appropriate Disciplinary Action for Individuals Involved in Event
05000327/LER-1997-012-01, :on 970801,manual Reactor Tripped Due to Loss of Control Air.Caused by Corrosion Products (Rust Debris) Inhibiting Full Closure of One of six-inch Gate Valves. Isolated Breached Control & Svc Air Sys Header1997-09-0202 September 1997
- on 970801,manual Reactor Tripped Due to Loss of Control Air.Caused by Corrosion Products (Rust Debris) Inhibiting Full Closure of One of six-inch Gate Valves. Isolated Breached Control & Svc Air Sys Header
05000327/LER-1997-011-01, :on 970725,vital Battery Board 4 Was Operating W/O Battery Source.Caused by Personnel Error.Revised Appropriate Instructions to Caution of Possibility of Breaker Misalignment1997-08-25025 August 1997
- on 970725,vital Battery Board 4 Was Operating W/O Battery Source.Caused by Personnel Error.Revised Appropriate Instructions to Caution of Possibility of Breaker Misalignment
05000327/LER-1997-010-01, :on 970626,failure to Properly Return Portion of Fire Protection Sys to Svc Following Mod Activities Was Noted.Caused by Failure to Follow Procedures.Manual Isolation Valve Was Opened1997-07-31031 July 1997
- on 970626,failure to Properly Return Portion of Fire Protection Sys to Svc Following Mod Activities Was Noted.Caused by Failure to Follow Procedures.Manual Isolation Valve Was Opened
05000327/LER-1997-009-02, :on 970521,failed to Perform Response Time Testing of Containment Radiation Monitor Following Maint Activities.Caused by Misinterpretation of Surveillance Requirements.Tested Radiation Monitor1997-06-20020 June 1997
- on 970521,failed to Perform Response Time Testing of Containment Radiation Monitor Following Maint Activities.Caused by Misinterpretation of Surveillance Requirements.Tested Radiation Monitor
05000328/LER-1997-009, :on 970401,licensed Failed to Maintain 2 Offsite Power Sources as Required by Ts.Caused Because Main Contact Compression Was Out of Tolerance.Start Bus 1A Was Transfered to Normal Feed Breaker1997-05-0606 May 1997
- on 970401,licensed Failed to Maintain 2 Offsite Power Sources as Required by Ts.Caused Because Main Contact Compression Was Out of Tolerance.Start Bus 1A Was Transfered to Normal Feed Breaker
05000327/LER-1997-007-01, :on 970404,DG Started When Drill Bit Being Used to Drill Into Electrical Panel in Main Control Room,Cut Into Cable.Caused by Drill Bit Penetrating Energized Wire Bundle Causing Short.Work Stopped on All Electrical Mods for S1997-05-0101 May 1997
- on 970404,DG Started When Drill Bit Being Used to Drill Into Electrical Panel in Main Control Room,Cut Into Cable.Caused by Drill Bit Penetrating Energized Wire Bundle Causing Short.Work Stopped on All Electrical Mods for Shift
05000327/LER-1997-004-01, :on 970320,failure to Properly Perform Surveillance Testing on Circuit Breakers Was Identified,Due to Inadequate Review of Surveillance Instruction Revs.Lcos Were Entered1997-04-21021 April 1997
- on 970320,failure to Properly Perform Surveillance Testing on Circuit Breakers Was Identified,Due to Inadequate Review of Surveillance Instruction Revs.Lcos Were Entered
05000327/LER-1997-006-01, :on 970322,failed to Perform Surveillance Requirement During Containment Entry Due to Personnel Error. RWP Was Closed to Prevent Further Use1997-04-21021 April 1997
- on 970322,failed to Perform Surveillance Requirement During Containment Entry Due to Personnel Error. RWP Was Closed to Prevent Further Use
05000327/LER-1997-005-01, :on 970319,two of Six Tested Main Steam Safety Relief Valves Not within TS Setpoint Tolerance.Appropriate LCOs Entered & Valves Found Outside TS Setpoint Tolerance Adjusted to within TS Tolerance & Retested1997-04-17017 April 1997
- on 970319,two of Six Tested Main Steam Safety Relief Valves Not within TS Setpoint Tolerance.Appropriate LCOs Entered & Valves Found Outside TS Setpoint Tolerance Adjusted to within TS Tolerance & Retested
05000327/LER-1997-003-02, :on 970305,failed to Properly Perform Surveillance Testing on Centrifugal Charging Pump Inlet Isolation Valve Logic.Caused by Inadequate Surveillance Instruction.Prepared Special Test Procedure1997-04-0404 April 1997
- on 970305,failed to Properly Perform Surveillance Testing on Centrifugal Charging Pump Inlet Isolation Valve Logic.Caused by Inadequate Surveillance Instruction.Prepared Special Test Procedure
05000328/LER-1996-004-02, :on 960919,reactor Trip Breaker Was Removed After It Was Found to Have Inoperable Auxiliary Contacts. Caused by Inadequate Procedure.Revised Breaker Procedure & Reemphasized Requirements for Working Steps Out of Sequence1997-03-28028 March 1997
- on 960919,reactor Trip Breaker Was Removed After It Was Found to Have Inoperable Auxiliary Contacts. Caused by Inadequate Procedure.Revised Breaker Procedure & Reemphasized Requirements for Working Steps Out of Sequence
05000327/LER-1997-002-01, :on 970214,TS AOT Exceeded for DG 2A-A.Caused by Mechanical Failure of DG 2A-A Governor Actuator on Engine 2.DG 2A-A Governor Actuators on Both Engines Replaced, Functional Tested & PMT Performed1997-03-13013 March 1997
- on 970214,TS AOT Exceeded for DG 2A-A.Caused by Mechanical Failure of DG 2A-A Governor Actuator on Engine 2.DG 2A-A Governor Actuators on Both Engines Replaced, Functional Tested & PMT Performed
05000327/LER-1997-001-02, :on 970125,failed to Perform Surveillance Testing on EDG Start Timer Relays Contained in Start Logic Circuitry.Caused by Inadequate Surveillance Procedures. Revised Procedures & Performed Testing1997-02-24024 February 1997
- on 970125,failed to Perform Surveillance Testing on EDG Start Timer Relays Contained in Start Logic Circuitry.Caused by Inadequate Surveillance Procedures. Revised Procedures & Performed Testing
05000328/LER-1997-001-01, :on 970117,failed to Perform Surveillance on Turbine Trip Contacts of Reactor Trip Breakers.Caused by Inadequate Procedure.Performed Test on Turbine Trip Contacts & Declared Rtb a Operable1997-02-18018 February 1997
- on 970117,failed to Perform Surveillance on Turbine Trip Contacts of Reactor Trip Breakers.Caused by Inadequate Procedure.Performed Test on Turbine Trip Contacts & Declared Rtb a Operable
05000327/LER-1995-001-01, :on 950118,accumulation of Gas in Residual Heat Removal Sys.Caused by Normal Leakage from Cold Leg Accumulators.Performed Monitoring & Venting of Gas Accumulation & Revised Quarterly Pump Tests1997-02-0606 February 1997
- on 950118,accumulation of Gas in Residual Heat Removal Sys.Caused by Normal Leakage from Cold Leg Accumulators.Performed Monitoring & Venting of Gas Accumulation & Revised Quarterly Pump Tests
05000328/LER-1996-007-03, :on 961207,ESF Actuation,Start of Feedwater Sys,Occurred as Result of Inadequate Return of Equipment to Svc.Refresher Training on Filling & Venting Fundamentals Will Be Conducted in Yrs Training Cycle1997-01-0606 January 1997
- on 961207,ESF Actuation,Start of Feedwater Sys,Occurred as Result of Inadequate Return of Equipment to Svc.Refresher Training on Filling & Venting Fundamentals Will Be Conducted in Yrs Training Cycle
05000327/LER-1996-012-01, :on 960330,two Cold Leg Accumulator Sample Isolation Valves & Missing Data Sheet in Surveillance Package Were Inoperable.Caused by LCO Not Being Entered. Isolation Valves Were Tested1997-01-0202 January 1997
- on 960330,two Cold Leg Accumulator Sample Isolation Valves & Missing Data Sheet in Surveillance Package Were Inoperable.Caused by LCO Not Being Entered. Isolation Valves Were Tested
05000328/LER-1996-006-04, :on 961206,automatic Reactor Trip Occurred. Caused by Loss of Power to Start Bus 2A,start of Four EDG & Loading of EDG 2B-B.Refurbished Breaker Installed in 2A Start Bus & Breaker Tested Acceptable1997-01-0202 January 1997
- on 961206,automatic Reactor Trip Occurred. Caused by Loss of Power to Start Bus 2A,start of Four EDG & Loading of EDG 2B-B.Refurbished Breaker Installed in 2A Start Bus & Breaker Tested Acceptable
05000327/LER-1996-011-01, :on 961118,discovered Rod Position Indication Sys Was Out of Step W/Demand Position Indication Sys.Caused by Incorrect Position Indication on Analog Rod Position. Began Dilution of Reactor Coolant Sys1996-12-18018 December 1996
- on 961118,discovered Rod Position Indication Sys Was Out of Step W/Demand Position Indication Sys.Caused by Incorrect Position Indication on Analog Rod Position. Began Dilution of Reactor Coolant Sys
05000327/LER-1996-010-01, :on 961116,manual Reactor Trip Occurred.Caused by Unexpected Feedwater Heater Isolation.Informed Personnel of Effects Changing Proportional Band on Operating Range of Associated Valve Controllers1996-12-16016 December 1996
- on 961116,manual Reactor Trip Occurred.Caused by Unexpected Feedwater Heater Isolation.Informed Personnel of Effects Changing Proportional Band on Operating Range of Associated Valve Controllers
05000328/LER-1996-005-04, :on 961011,manual Trip Occurred.Caused by Unexpected Loss of Load.Stabilized Unit,Replaced Turbine Impulse Pressure Switches & Replaced Failed Feedwater Isolation Valve Motor & Brake Assembly1996-11-12012 November 1996
- on 961011,manual Trip Occurred.Caused by Unexpected Loss of Load.Stabilized Unit,Replaced Turbine Impulse Pressure Switches & Replaced Failed Feedwater Isolation Valve Motor & Brake Assembly
05000328/LER-1996-004-04, :on 960919,after Reactor Trip Breaker Was Removed Breaker Found to Have Inoperable Auxiliary Contacts. Caused by Inadequate Evaluation of Procedural Change. Procedures Revised1996-10-23023 October 1996
- on 960919,after Reactor Trip Breaker Was Removed Breaker Found to Have Inoperable Auxiliary Contacts. Caused by Inadequate Evaluation of Procedural Change. Procedures Revised
05000327/LER-1996-009-01, :on 960718,auxiliary Building Secondary Containment Boundary/Fire Barrier Not Maintained as Required by Design.Caused by Failure to Follow Design Control Process1996-08-19019 August 1996
- on 960718,auxiliary Building Secondary Containment Boundary/Fire Barrier Not Maintained as Required by Design.Caused by Failure to Follow Design Control Process
05000327/LER-1996-008-01, :on 960709,failed to Perform Quarterly Backseat/Closure Test on Five Check Valves.Caused by Personnel Error.Test Procedure Written & Performed on Subject Check Valves1996-08-0808 August 1996
- on 960709,failed to Perform Quarterly Backseat/Closure Test on Five Check Valves.Caused by Personnel Error.Test Procedure Written & Performed on Subject Check Valves
05000327/LER-1996-006-02, :on 960623,failed Coupled Capacitor Potential Device Caused Actuation of Generator Backup/Transfomer Feeder Relay Tripping Turbine & Reactor.Removed & Replaced Ccpd1996-07-18018 July 1996
- on 960623,failed Coupled Capacitor Potential Device Caused Actuation of Generator Backup/Transfomer Feeder Relay Tripping Turbine & Reactor.Removed & Replaced Ccpd
05000327/LER-1996-007-01, :on 960614,rod Position Indicators for Control Bank D Rods M4 & M12 More than Required 12 Steps Out from Respective Demand Position Indicators.Caused by Incorrect Position Indication on Rod.Response Reduced1996-07-15015 July 1996
- on 960614,rod Position Indicators for Control Bank D Rods M4 & M12 More than Required 12 Steps Out from Respective Demand Position Indicators.Caused by Incorrect Position Indication on Rod.Response Reduced
05000328/LER-1996-003-05, :on 960605,reactor Trip Breakers Manually Opened Because Shutdown Bank D Dropped Into Reactor Core.On 960607 Manual Reactor Trip Initiated Due to Dropped Rod. Added Caution Statement to Apropriate Operations Prcedure1996-07-0505 July 1996
- on 960605,reactor Trip Breakers Manually Opened Because Shutdown Bank D Dropped Into Reactor Core.On 960607 Manual Reactor Trip Initiated Due to Dropped Rod. Added Caution Statement to Apropriate Operations Prcedure
05000327/LER-1995-010, :on 950717,turbine & Reactor Trips Occurred. Caused by Bellows Being Deformed When Sudden Pressure Relay Is Isolated & Heated.New Qualitrol Relays Installed & Placed in Service1996-07-0303 July 1996
- on 950717,turbine & Reactor Trips Occurred. Caused by Bellows Being Deformed When Sudden Pressure Relay Is Isolated & Heated.New Qualitrol Relays Installed & Placed in Service
05000327/LER-1996-005-02, :on 960526,ESF Actuation Occurred Resulting in DG Start.Cause Unknown.Diagnosed Condition,Reset Start Signal & Secured Actuated Equipment1996-06-21021 June 1996
- on 960526,ESF Actuation Occurred Resulting in DG Start.Cause Unknown.Diagnosed Condition,Reset Start Signal & Secured Actuated Equipment
05000328/LER-1996-002-05, :on 960822,discovered Failure to Properly Identify Steam Generator Tube May Have Exceeded Tech Spec Plugging Criteria.Caused by Misjudgement by Two Independent Analysts.Evaluation Performed1996-06-13013 June 1996
- on 960822,discovered Failure to Properly Identify Steam Generator Tube May Have Exceeded Tech Spec Plugging Criteria.Caused by Misjudgement by Two Independent Analysts.Evaluation Performed
05000327/LER-1996-004-02, :on 960509,normal Feeder Breaker Unexpectedly Tripped,Resulting in Loss of Power Signal & Start of Four Dgs.Caused by Failure of Breaker Mechanism.Spare Breaker Operating Mechanism Refurbished & Installed1996-06-0505 June 1996
- on 960509,normal Feeder Breaker Unexpectedly Tripped,Resulting in Loss of Power Signal & Start of Four Dgs.Caused by Failure of Breaker Mechanism.Spare Breaker Operating Mechanism Refurbished & Installed
05000328/LER-1996-001-05, :on 960418,inadvertent ESF Actuation & Loss of Power Signal & Load Sequencing Occurred During Maint. Caused by Personnel Error.Individual Involved in Event Was Counseled & Lessons Were Discussed1996-05-17017 May 1996
- on 960418,inadvertent ESF Actuation & Loss of Power Signal & Load Sequencing Occurred During Maint. Caused by Personnel Error.Individual Involved in Event Was Counseled & Lessons Were Discussed
05000327/LER-1996-003-01, :on 960325,failure to Perform Surveillance Requirements for Penetration Fire Barrier Insps as Required by Tech Specs Occurred.Caused by Personnel Error.Appropriate Disciplinary Action Taken W/Individuals1996-04-24024 April 1996
- on 960325,failure to Perform Surveillance Requirements for Penetration Fire Barrier Insps as Required by Tech Specs Occurred.Caused by Personnel Error.Appropriate Disciplinary Action Taken W/Individuals
05000327/LER-1996-002-01, :on 960215,SRs Associated W/Fire Protection Hose Stations Not Performed as Required by Ts.Caused by Inadequate Procedure Rev.Entered Action of LCO & Established Measures to Address Issue1996-03-15015 March 1996
- on 960215,SRs Associated W/Fire Protection Hose Stations Not Performed as Required by Ts.Caused by Inadequate Procedure Rev.Entered Action of LCO & Established Measures to Address Issue
05000327/LER-1996-001-02, :on 960121,discovered Fire Watch Patrol Did Not Patrol Some Assigned Areas in Control Bldg & on 960126,fire Watch Patrol Not Performed within Timeframe Required by Ts. Appropriate Disciplinary Action Taken1996-02-20020 February 1996
- on 960121,discovered Fire Watch Patrol Did Not Patrol Some Assigned Areas in Control Bldg & on 960126,fire Watch Patrol Not Performed within Timeframe Required by Ts. Appropriate Disciplinary Action Taken
05000328/LER-1992-008, :on 920627,reactor Tripped.Caused by Varying Resistance Readings Substandard Workmanship.Plant Instruction Written to Provide Guidance1996-02-0808 February 1996
- on 920627,reactor Tripped.Caused by Varying Resistance Readings Substandard Workmanship.Plant Instruction Written to Provide Guidance