05000529/LER-1990-002-02, :on 900314,discovered That Monthly Valve Lineup for Train a Essential Auxiliary Feedwater Pump Not Performed within Required Interval.Caused by Personnel Error.Involved Individual Counseled
RC-97-0071, Forwards Response to Violations Noted in Insp Repts 50-395/96-15.Corrective Actions:Fuel Handling Bridge Gripper Indexing Commenced,Based on Interpretation
05000423/LER-1989-004, :on 890216,fire Detection Discovered Inoperable Approx for 10 H.Caused by Personnel Error.Fire Watch Established.All on-shift Personnel Briefed Re Importance of Prompt Evaluation & Response to Fire Alarms
05000446/LER-1998-002-01, :on 980308,automatic Reactor Trip Caused Subsequent to Turbine Trip Were Noted Due to Loss of Turbine Plant Cooling Water.Caused by Actual Lo Lo Levels in at Least Two Sgs.Level Switches Was Tested
05000333/LER-1999-006-01, :on 990609,LCPI Mode of RHR Sys Was Inoperable. Caused by Loss of Automatic Startup Capability of RHR Pumps. Repaired Defective Fuse Contact & Conducted Equipment Failure Evaluation.With
05000416/LER-1997-005-03, :on 970930,inadequate Retest of Containment Airlock Air Seal Sys Occurred.Caused by Inadequate Use of Administrative Controls.Performed Maint Leak Test of N010A Air Tube Fitting & Revised Surveillances
05000309/LER-1986-002, :on 851106 & 860417,automatic Reactor Trip on Loss of Load Occurred Due to Main Turbine Trip on High Steam Generator Level.Caused by Controller Malfunction & Faulty Potentiometer.Controller Replaced
05000338/LER-1996-004, :on 960910,identified Seismic Concerns Re Containment Particulate & Gaseous Radiation Monitors.Caused by Personnel Error in Understanding Regulatory Requirements. Performed Review of Design Changes
05000458/LER-1997-002-03, :on 970506,small Leak at Inlet of Vent Valve for RRS FCV B.Root Cause Is Undetermined.Valve Was Replaced Prior to Returning to Power Operations
05000295/LER-1985-029-03, :on 850808,during Aircraft Fire Detection Sys Test (PT-210),diesel Generator 1A & 1B Room Ventilation Fan Outlet Butterfly Dampers Failed to Close at Proper Time. Caused by Stuck Pilot Valves.Valves Replaced
05000327/LER-1992-024, :on 921212,discovered That Continuous Fire Watch Had Not Been Established within Required Timeframe Due to Inattention to Detail by Fire Operator.Individuals Were Counseled on Importance of Attention to Detail
05000282/LER-1996-009, :on 960517,surveillance Revealed Three of Four Sensors Could Not Be Calibr Without Entering Containment. Caused by Filling Calibr Gas Bottles After Adjusting Regulator Output Pressure
05000259/LER-1996-002-02, :on 960328,EDG auto-started Due to Undervoltage Condition as Result of Personnel Error.Functional Tests on Breakers Associated W/Shutdown Bus Stopped & EDG Shutdown & Placed in Standby Readiness
05000370/LER-1996-001-03, :on 960208,unit 2 RWST Level Instrumentation Inoperable Due to Cold Water Condition.Caused by Insufficient Monitoring.Fw Level Transmitter Panel Will Be Verified
05000353/LER-1995-004, :on 950214,partial Group VI C Primary Containment Isolation Occurred Due to Momentary Spurious Low Rv Water Level Isolation Signal & Use of Radio Transmitter Headsets.Restricted Use of Radio Headsets in Area
05000325/LER-1991-005, :on 910227,nonconservative Setpoint for High Steam Flow Isolation Instruments Resulted in Manual HPCI Isolation.Due to Error Induced by Formation of Loop Seals. Pressure Sensing Line Rerouted
05000336/LER-1994-011-01, :on 940427,review of Cumulative Problems Discovered on B DG Was Performed.Caused by Natural End of Life for O Ring Joint.Three Cylinder Liners Were Replaced
05000328/LER-1994-005-02, :on 940419,determined Containment Leak Rate TS Limits Exceeded.Caused by Failure of Relief Valve Bellows & Check Value Leaking Through Seat.Failed Valve Replaced.W/
05000333/LER-1993-022, :on 931029,wires Between RPS Scram Contractor Were Not Installed Inside Protective Conduits.Caused by Inadequate Design & Design Review.Corrective Action:Eight Resistors Were Relocated
05000331/LER-1994-003, :on 940124,determined That TS Table 3.2-A Action Statement for Off Gas Vent RMs Not Complied W/During Routine Maint on 940119 Due to Improperly Prepared Work Document.License Amend Process Revised
05000482/LER-1993-014, :on 900501,essential Svc Water Low Flow Prior to Refueling Outage Occurred.Cause Unknown.Reportability Determination Process Revised,Rers Logged & Entered Into Tracking Database
05000263/LER-1993-010-01, :on 931027,main Control Room Emergency Filtration Train Found Outside Design Basis.Caused by in-leakage Across Inlet Dampers.Both Crv/Eft Trains Modified to Eliminate Outside in-leakage
05000263/LER-1993-006, :on 930323,RPM Actuation Occurred from High Pressure Caused by Inadequate Procedure.Turbine Stop & Control Valve Tightness Test Procedures & Plant Simulator Revised
05000368/LER-1990-010, :on 900401,personnel Failed to Complete Control Element Assembly Position Log.Caused by Surveillance Program Deficiencies & Lack of Mgt Involvement.Shift Briefing Completed & Procedure Change Incorporated
05000499/LER-1990-017-01, :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
05000353/LER-2019-001, Regarding Valid Actuation of the Reactor Protection System Due to a Trip of D214-24 Load Center
05000281/LER-1991-005-02, :on 910602,reactor Coolant Sys Leakage Exceeded Tech Spec Limits.Caused by Mechanical Failure of Isolation Valve.Preparation of Design Change Has Been Underway That Will Install RTDs on Main RCS Lines
05000280/LER-1994-007, :on 940614,Kaman Process Vent Radiation Monitors Were Declared Inoperable.Caused by Moisture Entrapment in System.Annunciator Response Procedure 0-RM-A-C-4 Was Performed
05000280/LER-1993-014-01, :on 931122,Delta Flux Not Logged While Alarm Inoperable.Caused by Abnormal Procedures.Procedure O-AP-20.02 Will Be Revised
05000281/LER-1993-004-02, :on 930823,reactor Tripped Due to Turbine - Generator Trip.Caused by Loss of Field Relay.Reactor Trip Breakers Verified Open & Control Rods Verified Inserted Into Core
05000280/LER-1987-002-02, :on 870104,three Control/Relay Room Chillers Tripped on High Condenser Discharge Pressure.Caused by Insufficient Svc Water Flow to Condenser of Chiller Unit. Valve Lineup to & from Chiller Checked
05000400/LER-1992-005-02, :on 920527,WRGM Declared Inoperable & Removed from Svc Due to Personnel Error.Additional Training Provided for Personnel Involved
05000400/LER-1990-023-01, :on 901124,emergency Diesel Generator a Inadvertently Started.Caused by Operator Failure to Correcty Verify Component Under Test.Operator Counseled Re self- Verification
05000250/LER-1988-013, :on 880707,discovered That Monthly Channel Functional Test Surveillance Procedure Did Not Check Sys Alarm.Caused by Personnel Error.Surveillance Procedure Corrected & Personnel Counseled
05000316/LER-1995-006-01, :on 950908,Unit 2 Reactor Thermal Power Trip Occurred.Caused by Cognitive Error by Operations Personnel. Surveillance Procedure Revised to Add Caution on Operation of Reactor Trip Breaker Control Switch
05000315/LER-1988-005, :on 880705,two CO2 Protected Areas Isolated W/O Compensatory Action Required Per Tech Specs.Caused by Personnel Error/Procedural Noncompliance.Administrative Actions Re Involved Individuals Taken
05000316/LER-1986-026, :on 860912,determined That Valve Alignment Used Placed Unit in Unanalyzed Condition Per LOCA Analysis in Fsar.Caused by Misunderstanding of Tech Spec 3.5.2 Re ECCS Operability.Administrative Controls Created
05000529/LER-1995-004-01, :on 950706,identified Four Occassions Between 950407 & 0630 When Conditional Surveillance in TS LCO 3.8.4.1 Action a Not Performed Due to Inattention to Detail. CR Copy of Temporary Procedure 40TP-9ZZ04 Corrected
05000528/LER-1989-013, Forwards Suppl 1 to LER 89-013-00.Rept Being Submitted to Include Info Requested by Part 21
05000530/LER-1989-004, :on 890104,exhaust Rocker Arm for Cylinder 8L Failed,Resulting in Emergency Diesel Generator Trip.Caused by Crack in Rocker Arm.On 890107,ESF Actuation Occurred.Also Reported Per Part 21.Rocker Arm Redesigned
05000530/LER-1989-013-01, :on 890926,control Room Operator Inadvertently Turned Wrong Handswitch During post-maint Testing Which Resulted in ESFAS Actuation.Caused by Personnel Error. Disciplinary Measures Taken
05000528/LER-1990-009, :on 900620,identified That License Holders Had Not Received Biennial Medical re-exams,per 10CFR55.21.Caused by Inadequate Tracking Sys & Medical Personnel Failure to Follow Procedures.Procedures Developed
05000528/LER-1988-006, :on 880321,determined That Allowable Surveillance Test Interval Had Been Exceeded for Incore Detector Sys.Caused by Personnel Error & Inadequate Programmatic Controls.Personnel Counseled
05000528/LER-1991-001, :on 910110.determined That Postulated Break in Reactor Coolant Pump High Pressure Seal Cooler Could Result in RCS Leak Outside Containment.Caused by Tube Rupture in Seal Cooler.Rcs Activity Monitored
05000530/LER-1990-002, :on 900222,locked High Radiation Area Gate Found Open & Unguarded.Caused by Personnel Error.Radiation Protection Personnel Verified Room Unoccupied & Secured Gate Per Approved Procedure
05000390/LER-1917-012, Regarding Error in Plant Emergency Procedures Leads to a Condition Prohibited by the Technical Specifications
05000244/LER-1996-009, :on 960723,determined That Leak Rate Outside Containment Was Greater than Program Limit.Caused by Weld Defect.Isolated Leak & Cut Out & Replaced Leaking Pipe
05000335/LER-1988-006-02, :on 880723,steam Generator Tubes W/Greater than 40% Degradation Not Plugged Per Tech Spec Requirement.Caused by Personnel Error.Plugging List Reviewed & Automated & Newly Installed Plugs Will Be Verified
05000249/LER-2015-001, Regarding Main Steam Line Flow Switches Found Outside Tech Spec Allowed Value
05000445/LER-2010-004, For Comanche Peak Regarding Component Cooling Water Train Inoperable Due to Inadequate Post Work Test Procedure
05000244/LER-2007-001, Regarding Loss of Electrical Generation Results in Plant Trip
05000334/LER-2006-003, Regarding Inadvertent Technical Specification Noncompliance Due to Inoperable Containment Isolation Valve
05000397/LER-2005-002, Regarding High Pressure Core Spray System Inoperability Due to Cracks in the Pump Motors Upper Air Deflector
05000321/LER-2004-004, Regarding Momentary False Low Reactor Water Level Signal Results in Safety System Actuations
05000390/LER-2001-004, Turbine/Reactor Initiated by an Invalid AMSAC Signal
05000259/LER-1998-002-01, :on 980521,determined That Flow Switch Calibr Test Did Not Ensure Calibr of Both Instrument Channels as Required by Tss.Caused by Technical Inaccuracies in Surveillance Instruction.Surveillance Instructions Revised
05000400/LER-1992-012-02, :on 920802,one of Three Secondary Relays Failed to Actuate,Causing TS 3.0.3 to Be Entered.Caused by Failure of under-voltage Relay to Actuate.Procedure Will Be Revised to Provide Guidance for Tripped Condition
05000293/LER-1997-020, :on 971104,RHR Operating Procedure Did Not Reflect Analysis.Caused by Inadequate Translation of Analysis Parameters to Operating Procedure Parameters. Revised Procedure 2.2.19.5
05000327/LER-1992-009, :on 920416,transient Induced or Spurious Mitigating sys-actuation Circuitry Signal & Loss of Offsite Power Experienced.Caused by Incorrect Location of AMSAC Circuitry in AFW Pump.Criteria Revised