IA-92-382, Package Consisting of General Records Schedule 23,NRC Manual Chapter Bulletin 0231-30,NRC Manual Chapter 0231, Maint & Disposition of NRC Official Files & Records & Mgt Directive 3.53, NRC Records Mgt Program
05000410/LER-1993-010, :on 931108,HPCS Was Inoperable Due to Equipment Deficiency,Inadequate Managerial Methods & Poor Work Practices.Replaced Deficient Contactors & Restored Tap Setting.Also Reportable Per Part 21
05000410/LER-1987-025, :on 870519,secondary Containment Isolation Signal Generated Due to Technician Relanding Lifted Lead Prematurely.Caused by Breakdown in Communications.Gaitronics Phone &/Or Headset Jack Installed
05000296/LER-1988-008-04, :on 881221,reactor Protection Sys Circuit Protector Tripped,Deenergizing Bus 3B & Causing Half Scram. Caused by Voltage Fluctuations in MG 3B Set Resulting in Pitting on Contact Surfaces.Protectors Reset
05000296/LER-1988-002-03, :on 880811,unplanned RWCU Isolation Occurred. Caused by Personnel Error.Temp Indicating Switch Recalibr & Sys Returned to Svc
05000296/LER-1988-007-04, :on 880929,diesel Generator 3C Overheated Due to Inadvertent Isolation of Emergency Equipment Cooling Water.Caused by Valve Misalignment & Error in Flow Diagrams.Surveillance Instruction Revised
05000296/LER-1988-001-04, :on 880605,breakers Connecting Diesel Generators 3A,3C & 3D to 4 Kv Shutdown Boards Opened Just After Closing & Would Not Reclose.Caused by Open Signal Sealed in Logic.Also Reportable Per Part 21
05000296/LER-1989-003, :on 890307,unplanned ESF Actuations Occurred. Caused by Voltage Transient Due to Start of Control Bay Chiller 3B Because of Design of Circuit Protectors Being Sensitive to Minor Electrical Disturbances
05000296/LER-1988-004-03, :on 880909,discovered That air-operated Temp Control Valves for Shutdown Board Room Air Handling Units Will Fail on Loss of Control Air.Caused by Inadequate Interface Review.Flow Diagram Revised
05000400/LER-1987-019, :on 870412,manual Plant Trip Initiated Due to Loss of Feedwater Trains & Decreasing Steam Generator Levels.Caused by Condensate Pump High Temp Trip.Pressure & Steam Generator Levels Restored
05000400/LER-1987-021, :on 870414,circulating Water Sys Flow to Main Condenser Restricted,Resulting in High Condensate Temps,Trip of Both Feedwater Trains & Manual Trip of Turbine & Reactor. Caused by Debris on Pump Suction Screens
05000400/LER-1992-007-02, :on 920712,automatic Turbine Trip & Reactor Trip Occurred Due to Failure of Low Pressure Turbine Exhaust Boot Seal.Repairs to Low Pressure Turbine Exhaust Boot Seal Completed on 920713
05000400/LER-1990-022-01, :on 901108,missed Surveillance Test for Secondary Waste Sample Tank Due to Incorrect Procedure Rev
05000400/LER-1990-013, :on 900503,valve Misalignment Caused Unplanned Release from Waste Gas Sys to Waste Process Bldg Vent Stack 5.Valve Position Corrected,Procedures Changed & Training of Personnel Initiated
05000400/LER-1989-021-02, :on 891227,ESFAS Actuation Occurred Due to Loss of Main Feedwater Pump.Caused by Personnel Error.Sampling Valve Repaired,Appropriate Procedure Revised & Applicable Personnel Trained on low-flow Trips
05000400/LER-1990-006, :on 900309,discovered That Evolution Violated Requirements of FSAR to Keep Individual Tanks Isolated from Another Tank.Caused by Failure to Address Evolution in Operating Procedure.Procedure Revised
05000400/LER-1990-014, :on 900516,discovered That Two Liquid Radioactive Releases Initiated on 900513 Were in Excess of Flow Rate Specified on Release Permits.Caused by Personnel Error.Max Release Rate Must Be Recorded
05000400/LER-1992-002-02, :on 920119,problems Encountered W/Plant Process Computer.Caused by Failure to Restart Program That Performs Sump Leak Rate Calculations & Data Transmission Error.Computer Sys Will Be Upgraded
05000400/LER-1989-012-01, :on 890630,required Continuous Sampling of Release of Secondary Waste Sample Tank Not Performed.Caused by Personnel Error.Grab Sample of Secondary Waste Analyzed W/No Radioactivity Detected.Procedure Revised
05000400/LER-1989-008-01, :on 890410,deficiencies Discovered in Testing of Thermal Overload Bypass Circuit for motor-operated Valve. Caused by Procedural Inadequacies Which Resulted in Insufficient Testing of Circuit
05000400/LER-1989-009-01, :on 890501,discovered That Monitoring for Radioactivity in Turbine Bldg Floor Drain Effluent Not Performed from 890429-30.Caused by Isolation of Sample Collection Path for Calibr of Detector
05000400/LER-1989-005-01, :on 890222,reactor Trip on Low Steam Generator Level W/Steam/Feedwater Flow Mismatch Occurred During Calibr Test Procedure.Caused by Performance of Section of Procedure Intended to Be Conducted.Procedure Revised
05000400/LER-1988-030, :on 881008,steam Generator Pressure in turbine- Driven Auxiliary Feedwater Pump Steam Supply Heater Noted. Caused by Inadequate Shift Turnover During Valve Repair During Outage.Valve Seated Properly
05000400/LER-1990-016, :on 900529,invalid Testing of Fuel Handling Bldg Emergency Exhaust Filtration Unit Occurred.Caused by Inadequate Location of Duct Flowrate Measurements.Test Procedure for Filtration Units Will Be Revised
05000400/LER-1988-026, :on 880831,cracking of Insulation on Wires & on Terminal Blocks in Top Works Portion of Valves Noted.On 880909 Concluded Valves Inside Containment Not Qualified for Harsh Environ Following Postulated Accident
05000400/LER-1988-029, :on 880915,short Equipment Start Pulses Generated,Causing Safety injection,motor-driven Auxiliary Feedwater & Emergency Svc Water Pumps to Start.Caused by Failure of Relay in Sequencer Test Circuit
05000400/LER-1987-053, :on 870813,valve 1BD-11 Discovered Inoperable After Failing Inservice Insp Test.Caused by Valve Failure Due to Binding of Carbon Seal Rings Between Valve Cage & Valve Plug.Valve Repaired
05000400/LER-1987-061, :on 871016,flow Rate Instruments for Waste Processing Bldg Vent Stacks 5 & 5A Declared Inoperable. Caused by Personnel Error.Meeting Held to Discuss Similar Event.Operator Involved Counseled on Item
05000400/LER-1987-054, :on 870915,determined That More Limiting Single Failure Might Exist & on 870916,two Addl Potential Failure Modes Identified & Plant Shut Down.Caused by Design Error. Solid State Protection Sys Modified
05000400/LER-1988-001-02, :on 880115,emergency Operating Procedure (EOP) Deficiency for Switchover to Recirculation After LOCA Discovered.Caused by Failure to Incorporate FSAR Change Into Plant Procedures.Eops Revised
05000400/LER-1987-028, :on 870502,manual Turbine Trip Initiated During Performance of Power Ascension Test Procedure 9108-S-14. Caused by Tandem Trip of Both Heater Drain Pumps.Evaluation of Feedwater Response to Transients Continues
05000400/LER-1987-048, :on 870811,failure to Take 9:30 Am Reading of Axial Flux Difference (Afd) as Required by Tech Specs Discovered.Caused by Personnel Error.Operator Disciplined. Addl Guidance Being Provided to Operators
05000400/LER-1987-027, :on 870426,during Test,Redundant Transmitter Pressurizer Pressure Channels Declared Inoperable.Caused by Two Out of Three Channels Out of Calibr & Reading Low. Channels Recalibr & Test Completed
05000400/LER-1987-034, :on 870611,air Leakage by Inner & Outer Doors of Personnel Air Lock Excessive.Caused by Flat Spots on O-ring Seal.Seals on Inner & Outer Doors Replaced & Procedure OMM-001 Revised
05000400/LER-1987-033, :on 870607,experienced Trouble W/Engine Barring Device Not Rotating Engine as Required Using Plant Svc Air. Caused by Low Plant Svc Air Pressure.Mod Installed Attaching Engine Barring Device to Starting Air Tank Air
05000400/LER-1987-012, :on 870311,turbine & Reactor Trips Occurred During Troubleshooting at Main Turbine Supervisory Control Panel.Turbine Trip Caused by Depressing Test Push Button on Turbine Supervisory Control Panel
05000400/LER-1988-005-01, :on 880201,discovered That Two Valves for Turbine Bldg Vent Stack 3A Wide Range Gas Monitor Were Mispositioned.Caused by Procedural Deficiency.Valve Lineup for Monitor Skid Corrected
05000400/LER-1988-008, :on 880217,emergency Svc Water Pump Started Then Tripped.Caused by Problem W/Overcurrent Relay. Overcurrent Relay Replaced & Emergency Safeguards Sequencer Sys Test Procedure Revised
05000400/LER-1987-065, :on 871124,P-13 Channel Declared Inoperable Due to Incorrect First Stage Turbine Pressure Setpoints for P-13 Permissive.Caused by Personnel Error.Applicable Compensatory Action & Plant Change Request Initiated
05000250/LER-1989-018, :on 891212,use of Single Manual SI Block/ Unblock Switch for Both Trains of SI Outside Design Basis. Caused by Inadequate Original Plant Design.Info Re Potential Single Failure Mode Provided to Personnel
05000250/LER-1990-019, :on 901003,alarm Received on Control Room Annunciator X-7/6 Indicating Heat Tracing Trouble.Caused by Inadequate Work Control.Boric Acid Transfer Pumps Aligned & Event Discussed W/Shift Supervisor
05000251/LER-1990-006-02, :on 900705,automatic Start of Component Cooling Water Pump 4B Occurred Due to Low Pump Discharge Header Pressure.Caused by Personnel Error.Responsible Individual Required to Review Procedure
05000251/LER-1990-007-02, :on 900726,component Cooling Water Pump 4A Automatically Started.Caused by Error Made by Nonlicensed Personnel.Pressure Controller PC-4-611 Recalibrated
05000250/LER-1988-021, :on 880913,pressurizer PORV Stroke Time Exceeded Tech Spec Design Basis Value of 3.0 for Heat Input Case.Caused by Undersized Air & Nitrogen Backup Supply Line to Actuators.Procedures Revised
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
05000250/LER-1988-022, :on 880920,emergency Diesel Generator a Declared out-of-svc Due to High Fuel Oil Pressure.Diesel Generator B out-of-svc Since 880917.Caused by Excessive Particles in Filter.Filter Replaced
05000250/LER-1989-002, :on 890116,normal Plant Cooldown Initiated Due to Small Boundary Leak of Rcs.Caused by Transgranular Stress Corrosion Cracking in Mapping Sys Thimble Guide Tube J-12 & J-7.Guide Tubes Involved Repaired or Replaced
05000250/LER-1987-030, :on 871027,determined That Existing Min Recirculation Design Configuration for RHR Sys Potentially Inadequate.Recirculation Flow Path for RHR Pumps Original Design of Plant.Mods Developed
05000250/LER-1987-013, :on 870514,Tech Spec Required Surveillance of Spent Fuel Pit Exhaust Monitor Missed.Caused by Personnel Error.Procedure O-PMI-67.11 Will Be Revised & Other Surveillance Procedures Will Be Reviewed
05000250/LER-1988-009, :on 880527,determined That Tech Spec Surveillances for Station Battery Pilot Cell Rotation Not Properly Implemented in 1987.Caused by Personnel Error & Procedure Inadequacy.Training Bulletin Issued
05000250/LER-1987-016, :on 870526,while in Mode 6,partial Actuation of Train a Safeguards Equipment Occurred.Caused by Sticking Safety Injection Block Switch.Switch Inspected,Cleaned & Returned to Svc
05000251/LER-1987-007-01, :on 870310,air Leakage During Leak Rate Testing of Personnel Hatch Exceeded Tech Spec Requirements.Caused by Malfunctioning Equilizing Valve Not Being Able to Fully Close.Valve Replaced
05000251/LER-1989-009-01, :on 890823,boric Acid Transfer Pump Seal Pot Found W/No Visible Level Resulting in No Flow Path to Rcs. Caused by Design of Boric Acid Transfer Pump Double Seals. Review Continuing for Alternate Seal Design
05000250/LER-1988-027, :on 881006,mechanic Found to Be Contaminated When Exiting Containment Bldg.Specific Cause Unidentified. Addl Temporary Controls Implemented & Area Mopped
05000250/LER-1988-029, :on 881121,specialist Accidently short- Circuited Power Terminal Lead Which Resulted in Closure of RHR Suction Isolation Valve MOV-3-750.Caused by Personnel Error.Personnel Briefed
05000250/LER-1988-012, :on 880614,QA Audit Caused Investigation Into Delay in Issuing Fire Protection Impairment Form for Four Penetration Seals in Switchgear Room.Caused by Inadequate Controls.Seal Surveillance Being Generated
05000250/LER-1988-008, :on 880613,flowpath Which Could Result in Insufficient NPSH to Certain Pumps During LOCA Recirculation Identified.Procedures Revised to Maintain Valve 887 Locked in Fully Open Position
05000251/LER-1988-005-01, :on 880425,calibr of Nuclear Instrumentation Sys Power Range Detectors Performed Late.Caused by Personnel Error.Digital Data Processing Sys Repaired & Group Responsible for Performance Discussed Event
05000251/LER-1988-002-01, :on 880202,containment & Control Room Ventilation Isolation Occurred.Caused by Personnel Error While Performing Mod to Remove Remote Alarm Function.Planner & Technician Involved Counselled
05000251/LER-1987-028, :on 871218,two Intake Cooling Water Pumps Declared Out of Svc Which Exceeded Limits of Tech Spec 3.4.5.Caused by Broken Lower Headshaft Coupling.Coupling Replaced & Pump Returned to Svc
05000250/LER-1987-029, :on 871015,determined That Waste Gas Sys Operated in Configuration Not Described in Fsar.Caused by Inadequate Procedural Rev.Procedure 3/4-OP-47.1 Revised to Ensure That Valve 4627 Closed
05000250/LER-1987-028, :on 871015,discovered That Required Tech Spec Surveillance of Control Rod Positions Missed During Peak Shift on 870912.Caused by Personnel Error.Personnel Counseled.Logs Being Reviewed for Improvement
05000251/LER-1987-028-01, :on 871218,unit Shutdown Commenced When Two Intake Cooling Water Pumps Declared Inoperable.Caused by Broken Shaft Coupling & Frozen Bushing.Broken Shaft Coupling & 4B Icw Pump Replaced & Satisfactorily Tested
05000251/LER-1987-014-01, :on 870711,dripping from Auxiliary Feedwater Steam Line Discovered.On 870714,leak Identified as Pinhole on Reducer.Cause Unknown.Fitting & Portion of Adjacent Piping Removed for Analysis
05000251/LER-1987-021-01, :on 870729,process Radiation Monitor Spiked High Actuating Containment Vent & Control Room Ventilation Isolation Logic.Caused by Work Being Performed on Condenser Air Ejector Radiation Monitor.Drawer Reset
05000251/LER-1987-012-02, :on 870705,during Unit 3 Engineered Safeguards Integration Test,Auto Start of Component Cooling Water Pump 4B Occurred.Caused by Low Header Pressure on Increased Cooling Water Flow.Procedure Will Be Enhanced
05000250/LER-1988-004, :on 880318,auxiliary Feedwater Pumps Actuated Due to Drop in Steam Generator Level.Caused by Reactor Control Operator Failure to Monitor Steam Generator Level. Operator Counseled Re Awareness of Actions
05000251/LER-1987-018-01, :on 870712,operation in Excess of 24 H W/Greater than 2% Calculated Quadrant Power Tilt Ratio W/O Running Flux Map or Reducing Overpressure,Overtemp Occurred. Caused by Personnel Error.Personnel Counseled
05000251/LER-1987-011-02, :on 870608,automatic Actuation of Component Cooling Water Pump 4C Occurred.Caused by Low Sys Pressure Due to Leak in 4A Component Cooling Water Hx.Hx Removed from Operation & Leak Repaired
05000316/LER-1987-008-01, :on 870722,ESF Actuation Occurred Due to Extreme High Level in Steam Generator 24.Caused by Erratic Response of Main Feedwater Pump Delta P Controller. Plant Procedures Implemented
05000315/LER-1994-008, :on 940129,determined That Filter System Was Inoperable.Caused by Debris on Fan Unit Bypass Damper Sealing Area.Debris Was Removed & Affected Seals Made Good Contact W/Damper Seals
05000315/LER-1992-012, :on 921028,Turbine Trip/Reactor Trip Occurred During Power Increase to 30% to Perform Routine Calometric Test.Caused by Failure to Reset Thrust Bearing Wear Detector Setpoint.Procedures to Be Drafted
05000315/LER-1991-009, :on 910927,discovered That CO2 pop-off Chain for Fire Damper Not Wired to CO2 Piping,Rendering Fire Damper Inoperable.Caused by Personnel Error.Wire Removed & Approved Clip Reattached to Chain
05000315/LER-1990-008, :on 900619,discovered That Isolation Relay Circuitry for Low Header Pressure Auto Start Switch for Essential Svc Water Pumps Installed Incorrectly.Caused by Design Errors.Plant Mod Packet Initiated
05000315/LER-1989-015-01, :on 891128,pyralarm Fire Detection Zone 3 Made Inoperable When Welding in Laundry Room Caused Standing Alarm.Fire Watch Patrol Not Assigned within 1 H.Caused by Personnel Error.Event Reviewed W/Operators
05000315/LER-1989-004, :on 890324,leakage Found on Containment Penetrations Exceeded Tech Spec 3.6.1.2.b Requirement.Caused by Excessive Leakage Rate of Valves WCR-924,ECR-26 & ECR-31. Faulty Valves Repaired & Restested
05000315/LER-1989-008-01, :on 890420,power Range Neutron Flux Instrumentation Monthly Channel Functional Surveillance Test Procedures Do Not Satisfy Intent of Tech Spec 3.3.1.1.Caused by Lack of Specific Guidance.Rev Initiated
05000315/LER-1990-004-01, :on 900508,reactor Operator Inadvertently Started Containment Recirculation Fan Instead of Hydrogen Recombiner During Surveillance Test.Caused by Inadequate Work Practice.Condenser Restored
05000315/LER-1989-011-01, :on 890901,discovered Snubber Installed on Pressurizer Spray Line Not Tested Since Aug 1987.Caused by Failure to Include Snubber on Testing Job Order.Procedure Changed to Add Two Separate Steps
05000315/LER-1988-007-01, :on 880908,flow Passage Insp of Ice Condenser Revealed Frost & Ice Buildup.Caused by Sublimation of Ice or High Humidity in Containment Air.Flow Passages Manually Cleaned to Remove Accessible Frost
05000315/LER-1989-010-01, :on 890705,determined That 414 Seismic/ Expansion Gap Seals Should Have Been Included in Formal Fire Seal Insp Program.Caused by Failure to Recognize Seals as Requiring Surveillance Per Tech Specs
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-1990-013-01, :on 901215,during Tech Spec Surveillance,Plant Battery Declared Inoperable When Single Cell Voltage Decreased Below Test Limit.Caused by Improper Setpoint. Setpoints Verified & Corrected as Needed
05000315/LER-1987-024, :on 871229,deficient Design Discovered Which Could Result in Failure to Provide Proper Local Shutdown & Indication Panel Fuse/Breaker Coordination.Caused by Improper Application of Selectivity Ratios
05000316/LER-1989-011, :on 890613,discrepancies Determined to Have Rendered Sys Outside of Design Basis Error Allowances During post-accident Conditions.Caused by Failure to Install Outer Heat Shrink.Splice Boxes Corrected
05000316/LER-1989-013, :on 890617,reactor Trip Breakers Opened When ESF Signal Initiated from Set I,Intermediate Range Nuclear Instrumentation Channel.Caused by Miscommunication. Importance of Complete Turnover Stressed
05000315/LER-1989-009, :on 890705,disovered That Testing Document for Valve 1-CS-443-2 Not Signed Off.Record Search Conducted & No Evidence Found to Indicate That post-maint Testing Performed.Caused by Personnel Error
05000315/LER-1989-003-01, :on 890318,ESF Actuation Occurred.Caused by Standing High Flux Trip on Intermediate Range Nuclear Instrumentation Channel I Which Had Not Reset Prior to Power Dropping Below Permissive P-10
05000316/LER-1987-015-01, :on 871120,facility Entered Tech Spec 3.0.3 Due to Corrective Maint.Caused by Time Needed to Repair Separated Voltage Cable Connector Broken Due to Frequent Use.Connector Replaced
05000316/LER-1987-014-01, :on 871215,programming Error Causing Alarm to Be Inoperable,Discovered.Caused by Personnel Error.Computer Operators Counseled in Proper Method of Computer Software Troubleshooting & Program Installation
05000315/LER-1988-012, :on 881111,turbine Room Sump Not Sampled & Analyzed in Accordance W/Tech Specs.Caused by Personnel Error.Procedures Updated to List Required Sampling Frequencies & Analysis for Sys
05000315/LER-1988-010, :on 881011,unit Shut Down After Determination That Electrical Cables Not Configured Per Design Drawings. Caused by Pressurizer & Reactor Head Vent Valves Not Being in Configuration.Design Change Initiated
05000316/LER-1989-003, :on 890119,valve Stem Seal Leak Allows Air Into Sensor Capillary Tubing Causing Reactor Vessel Level Indication Sys Calibr Shift.Caused by Leakage of High Point Fill Valve Stem Seals
05000315/LER-1988-002-01, :on 880326,ice Buildup in Ice Condenser Flow Passages Declared Inoperable.Caused by Sublimation of Ice or High Humidity in Containment Air.Flow Passages Manually Cleaned to Remove Frost
05000315/LER-1987-023-01, :on 871109 Problem Discovered Re Fuses Required for Isolation Between Local Shutdown & Indication Panels. Problems Confirmed on 871222.Caused by Engineer Design Oversight.Design Changes Made
05000315/LER-1988-003-01, :on 880520,determined That Low Setpoint Trip Should Have Been time-response Tested.Probably Caused by Lack of Specific Detail in Tech Specs.Test Procedures Revised to Include Low Setpoint Testing
05000315/LER-1987-021, :on 871013,ESF Actuation Occurred Due to Feedwater Flow/Steam Mismatch Coincident W/Low Level on Steam Generator 11.Caused by Failure of East Main Feedwater Pump Shaft Driven Oil Pump.Bearings Replaced
05000316/LER-1987-009, :on 870825,gland Seal Leakoff Condenser Effluent Radiation Monitor Found Inoperable.Caused by Failure to Perform Adequate Review of Monitor Status During Shift Surveillance.Procedures Revised
05000316/LER-1989-006, :on 890224,ESF Actuation Occurred from Instrumentation Indicating Low Level Coincident W/Feedwater Flow/Steam Flow Mismatch on Steam Generator 24.Cause Unknown.Procedures Implemented
05000316/LER-1987-010-01, :on 870902,insps Revealed Frost & Ice Buildup on Lattice Frames of Greater That 3/8 Inch in 46 Flow Passages & 6 of 24 Ice Condenser Bays.Caused by Abnormal Degradation.Ice Condenser Defrosted
05000315/LER-1987-014, :on 870812,failure to Comply W/Tech Spec Requirements for Testing of Turbine & Motor Driven Auxiliary Feed Pumps & Emergency Diesel Generators Occurred.Caused by Procedural Deficiencies.Procedure Revised
05000316/LER-1987-005-01, :on 870602,ESF Actuation Occurred Due to Low Low Steam Generator Level in Steam Generator 23.Caused by Personnel Error.Appropriate Administrative Action Taken Re Personnel.Procedures Implemented
05000316/LER-1987-006-01, :on 870615,containment Spray Pumps Declared Inoperable Due to Improperly Performed Tech Spec Surveillances Testing.Caused by Improper Labeling of Flow Instrumentation Being Maintained.Pumps Tested
05000315/LER-1987-008, :on 870604,ESF Actuation Occurred Due to Extreme High Level in Steam Generator 12.Caused by Mispositioning of Both Level Controller & Feedwater Flow Selector Switch.Level Controller Refurbished
05000316/LER-1987-003, :on 870107,overpower Delta Temp Bistables Failed to Trip During Instrumentation Calibr.Caused by Procedural Deficiency & Personnel Error.Procedure Revised
05000316/LER-1987-002, :on 870305-06,frost & Ice Buildup on Lattice Frames & Between Walls & Ice Baskets Adjacent to Walls Exceeded Tech Spec 4.6.5.1.b.3 Limits.Cause to Be Investigated by Westinghouse.Internal Investigation Begun
05000335/LER-1989-001-03, :on 890517,inadvertent Liquid Release from Waste Mgt Sys Occurred.Caused by Personnel Deviation from Procedure OP 1-0510022 W/O Prior Initiation of Temporary Change Due to Out of Svc Valve
05000529/LER-1988-015, :on 881203,chemistry Technician Discovered That New Fuel Area Radiation Monitor RU-19 Inoperable.Caused by Malfunction of Clock in Computer Internal to Monitor. Monitor Reset & Operated Properly
05000530/LER-1991-011-01, :on 911104,auxiliary Feedwater Flow Transmitters Equalizing Valve Found Improperly Aligned. Cause Not Determined.Valves Aligned Properly
05000528/LER-1989-007, :on 890412,discovered Two of Four Pressurizer Code Safety Valves Out of Tech Spec Tolerance of 2,500 Psia Plus or Minus 1%.Caused by Performance Limitation.Valves Adjusted & Retested Satisfactorily
05000529/LER-1989-005-02, :on 890310,loss of Power to Alternate Plant Ventilation Effluent Radiation Monitor Occurred.Caused by Electrical Loads in Excess of Circuit Capacity.Design Mod Issued to Supply Dedicated Power to Loads
05000528/LER-1990-003, :on 900320,log Power Channels Declared Inoperable When Plant Protection Cabinets Deenergized for Scheduled Maint.Caused by Personnel Error.Wiring in Cabinets Reworked & Cabinets Returned to Svc
05000528/LER-1988-016, :on 880514,reactor Trip Occurred.Caused by Nonconservative Operator Performance During Reactor Startup. Info Utilized for Estimated Critical Condition Will Be Corrected
05000530/LER-1988-004-02, :on 880406,loss of Power Event Occurred Which Resulted in Train B ESF Load Sequencer Sys Actuation.Caused by Error in Work Document Being Utilized to Replace Current Transformer.Maint Testing Stopped
05000528/LER-1989-005, :on 890412,determined That Deficiencies Identified by Control Components,Inc of Atmospheric Dump Valves Constituted Reportable Part 21 Condition.Caused by Improperly Seated Piston Ring.Valve Replaced
05000528/LER-1986-063-01, :on 860920,discovered That Error in Radioactive Source Tracking Sys Resulted in Radioactive Sealed Source Not Being Leak Tested Once Per 6 Months.Caused by Personnel Error.Entries Verified
05000528/LER-1991-006, :on 910517,ESF Actuation Occurred Due to Radiation Monitor Failure.Caused by Malfunctioning Central Processing Unit & Random Access Memory Board on Train B. Boards Replaced
05000530/LER-1988-008-02, :on 890220,determined That Excessive Moisture Condensation Occasionally Discovered in Unit Resulted in Invalid Sample Results.Caused by Cooling of High Humidity Sample Stream.Temporary Heat Trace Installed
05000530/LER-1987-003-02, :on 870929,condition Identified That,If Not Corrected,Could Have Resulted in Improper Operation of Two Shutdown Cooling Isolation Valves in Redundant Trains.Caused by Vendor Error.Bolting Replaced
05000528/LER-1988-005, :on 880123,backhoe Operator Inadvertently Damaged Post Indication Valve (Piv)(Kp)(Isv) & Caused Fire Suppression Water to Discharge Into Protected Area.Caused by Inadequate Procedure.Procedures Implemented
05000528/LER-1987-024, :on 870902,two Dma Interface Cards Providing Input to Core Operating Limit Supervisory Sys Found Incorrectly Installed.Caused by Cognitive Personnel Error. Computer Technician Counseled
05000530/LER-1989-005-01, :on 890628,sample Flow Rate for Vent low-range Radioactive Effluent Monitor Below Low Flow Alarm Setpoint, Rendering Monitor Inoperable.Caused by Loose Set Screw on Coupling.Set Screw on Sample Pump Tightened
05000530/LER-1990-004, :on 900414,reactor Trip Occurred.Caused by Control Element Assembly Dropping Into Core Due to Optical Isolator Card Malfunction.Card Replaced & Retested
05000529/LER-1987-006-01, :on 870307,during Surveillance Test,Limiting Condition for Operation 3.0.3 Entered When Tech Spec 3/4.6.3 Action Statements Could Not Be Met.Caused by Inoperability of Msivs.Tech Spec Change Request Submitted
05000529/LER-1987-016-01, :on 870718,contents of Chemical Waste Neutralization Tank Released to Onsite Evaporation Pond Exceeding Tech Spec 3.11.1.1 Limit for Mo-99.Caused by Personnel Error.Briefing Session Planned
05000529/LER-1988-015-01, :on 881203,new Fuel Area Radiation Monitor RU-19 Discovered Inoperable.Caused by Malfunction in Clock in Computer Internals to Monitor.Area Survey Conducted W/Negative Results & Night Order Issued
05000397/LER-1990-005, :on 900209,nonsafety-related Circuit Breaker on Power Panel Tripped,Resulting in ESF Actuation.Caused by Equipment Mfg Error Involving Defect in Circuit Breaker Tripping Mechanism.Defective Breaker Replaced
05000397/LER-1990-018, :on 900904,ESF Actuation of Containment Instrument Air Sys Occurred as Result of Inadvertent Manual Relief Valve Blowdown.Manual Actuator Removed & Lighting Fixture Secured
05000397/LER-1990-014, :on 900703,HPCS Sys Pump Suction Switchover from Condensate Storage Tanks to Suppression Pool Occurred Due to Suppression Pool High Water Level Condition.Caused by Procedural Inadequacy.Procedures Modified
05000397/LER-1989-007, :on 890316,discovered That Two Tech Spec Surveillance Procedures Re Fire Protection Zones for Standby Svc Water Pump Houses & Power Generation Control Cabinet Inconsistent.Action Statements Implemented
05000397/LER-1989-019, :on 890524,inboard RHR Shutdown Cooling Supply Valve Automatically Isolated When Electrician Lifted Wire Deenergizing Valve Control Relay.Personnel Counseled & Training in Plant Procedures Initiated
05000397/LER-1989-008, :on 890419,discovered That on 881202,Tech Spec Amend Request Submitted to NRC Describing Diesel Generator Trip Bypass Verification That Had Not Been Performed W/Ler Not Issued within 30 Days After Determination
05000397/LER-1989-003, :on 890209,control Room Emergency Filtration Sys Adsorber Charcoal Sample Not Taken After 720 H of Operation.Caused by Misinterpretation of Tech Specs.Charcoal Sample Analyzed & Procedure Revised
05000397/LER-1989-005-01, :on 890311,of 185 Control rods,34 Drifted Inward from One to Seven Notches Due to Momentary Low Scram Air Header Pressure.Caused by Main Steam Radiation Monitor Design Deficiency
05000397/LER-1989-022, :on 890530,loss of Secondary Containment During Core Alterations Due to Unisolatable Lines Occurred.Caused by Simultaneous Activities.Rhr Heat Exchanger Isolation Valves Closed to Reestablish Integrity
05000397/LER-1988-014, :on 880512,RWCU Sys Resin Tank Spill Occurred. Caused by Open RWCU Sample Line Isolation Valves RWCU-V-442 & 443.RWCU-V-442 & 443 Tagged Shut & de-energized & Radwaste Control Room Operator Involved Counseled
05000400/LER-1988-006, :on 880208,emergency Svc Water Sys Declared Inoperable.Caused by Isolation Valve Failures.Valves Repaired & Retested.On 880212,after Concern Raised,Manual Valve Closed,Pending Permanent Design Change
05000397/LER-1988-002, :on 880122,discovered RCIC Pump Suction Line Failed to Meet Containment Isolation & Single Failure Design Criteria.Caused by Ae Design Error.Check Valve Installed & Ltr Re Error Sent to B&R.Part 21 Related
05000397/LER-1988-019, :on 880527,determined That Control Room Emergency Filtration Sys Actuation Occurred on 880520.Caused by Technician Failure to Reset Trip Logic During Response Time Test Due to Inadequate Procedure
05000397/LER-1988-018, :on 880522,noted That Green Status Indicating Light for Div Two Emergency Diesel Generator Start Circuit Not Energized.Control Power Transfer Switch Was Not in Required Position.Switch Replaced
05000389/LER-1989-003-01, :on 890321,unit Received Containment Isolation Actuation Signal.Caused by Personnel Error.Splash Guard Installed on 12 Cylinder Engine for Diesel Generators 2A & 2B to Prevent Spurious Pressure Trips
05000389/LER-1989-008-02, :on 890924,plant Engineer Failed to Follow Approved Plant Procedures & Performed Improper Surveillance on Safety Injection Header Check Valves.Caused by Personnel Error.Involved Check Valves Tested
05000389/LER-1989-009-12, :on 891128,containment Local Leak Rate on Containment Penetration 10 Containing Exhaust Line for Containment Purge Sys Exceeded Tech Specs.Cause Not Determined.Valve Seat Travel Stop Adjusted
05000335/LER-1989-002-03, :on 890614,diesel 1B Fuel Oil Transfer Pump Discharge Found in Locked Closed Position.Caused by Personnel Error by Util non-licensed Operator.Valve Reopened & Locked Open & Operators Counseled
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
05000389/LER-1988-004-01, :on 880407,sample of Reactor Coolant Specific Activity on Dose Equivalent I-131 Was Taken 8 H Past Tech Specs Limits.Caused by Program Error on Thermal Power Change Alarm Setpoint.Program Error Corrected
05000389/LER-1987-007-02, :on 871125,reactor Tripped on Loss of Load Due to Turbine Trip Caused by Failure of Main Generator Exciter Bearing.Root Cause Is Personnel Error.Electrical Maint Personnel Trained & Procedures Revised
05000335/LER-1987-014-02, :on 871008,unidentified RCS Leakage Greater than Tech Spec Limit Discovered.Caused by Weld Joint Failure Due to Previous Misalignment of Listed Flanges.Reactor Shut Down & Required Repairs Performed
05000335/LER-1987-015-02, :on 871014,Mode 4 Entered W/O Shield Bldg Integrity.Caused by Inadequate Procedural Controls of Shield Bldg Doors Once Checked as Being Closed.Operating Procedure 1-0030120 Will Be Revised
05000389/LER-1987-003-03, :on 870409,during Troubleshooting,Jumper Placed on Wrong Terminal of Main Steam Isolation Signal (MSIS) Actuation Pushbutton Circuitry,Causing Actuation of Msis. Caused by Cognitive Personnel Error
05000389/LER-1988-003-03, :on 880313,normal/isolate Switch for Letdown Isolation Valve Discovered in Isolate Position Due to False Electrical Signals Generated on 880313.Caused by Operator Misinterpretation of Wiring Diagram
05000387/LER-1989-019, :on 890526,determined That Damaged Fire Seals Inoperable.Caused by Failure to Identify Penetration Seal Damage on Fire Rating/Operability of Penetrations.Fire Watch Established
05000250/LER-1989-003-01, :on 890124,control Room Ventilation Sys Shift to Recirculation Mode During Channel Check Occurred.Caused by Flaw in Design of Radiation Monitor Circuit Module.Work Instruction Revised
05000250/LER-1989-001, :on 890110,emergency Diesel Generator (EDG) B & Intake Cooling Water Pump 3A Out of Svc During Same Time. Caused by Operability Test Being Performed.Edg Returned to Svc on 890110 & Pump Checked
05000250/LER-1987-007-01, :on 870128,diesel Fuel Storage Tank Sample Did Not Meet Tech Spec Surveillance Requirements.Caused by Not Using Sampling Techniques in Accordance W/Std ASTM Sampling Procedures.Procedure Revised
05000251/LER-1987-014, :on 870711,water Dripping from Auxiliary Feedwater(Afw) Steam Line Discovered & on 870717,AFW Train 1 Declared Inoperable.Cause of Leak Unknown.Affected Piping & Fitting Replaced