Pages that link to "05000250/LER-2025-001, Lightning Caused Turbine Control System Failures Resulting in Reactor Trip"
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The following pages link to 05000250/LER-2025-001, Lightning Caused Turbine Control System Failures Resulting in Reactor Trip:
Displayed 2 items.
- ML25274A076 (redirect page) (← links)
- 05000250/LER-2025-001 (redirect page) (← links)
- 05000250/LER-2014-005 (← links)
- 05000250/LER-2001-004 (← links)
- 05000250/LER-2001-003 (← links)
- 05000250/LER-2001-002 (← links)
- 05000250/LER-2001-001 (← links)
- 05000250/LER-1982-008, Forwards LER 82-008/03L-0 (← links)
- 05000250/LER-1982-006, Forwards LER 82-006/03L-0 (← links)
- 05000250/LER-1982-007, Forwards LER 82-007/03L-0 (← links)
- 05000250/LER-1982-005, Forwards LER 82-005/03L-0 (← links)
- 05000250/LER-1982-004, Forwards LER 82-004/03L-0 (← links)
- 05000250/LER-1982-003, Forwards LER 82-003/03L-0 (← links)
- 05000250/LER-1983-001, Forwards LER 83-001/03L-0 (← links)
- 05000250/LER-1978-014, Forwards LER 78-014/03L-0 (← links)
- 05000250/LER-1978-013, Forwards LER 78-013/03L-0 (← links)
- 05000250/LER-1982-011, Forwards LER 82-011/03L-0 (← links)
- 05000250/LER-1983-002, Forwards LER 83-002/03L-0 (← links)
- 05000250/LER-1982-018, Forwards LER 82-018/01T-0 (← links)
- 05000250/LER-1983-006, Forwards LER 83-006/01T-0 (← links)
- 05000250/LER-1982-013, Forwards LER 82-013/03L-0 (← links)
- 05000250/LER-1982-015, Forwards LER 82-015/03L-0 (← links)
- 05000250/LER-1982-014, Forwards LER 82-014/01T-0 (← links)
- 05000250/LER-1982-019, Forwards LER 82-019/03L-0 (← links)
- 05000250/LER-1983-007, Forwards LER 83-007/01T-0 (← links)
- 05000250/LER-1982-016, Forwards LER 82-016/03L-0 (← links)
- 05000250/LER-1982-017, Forwards LER 82-017/03L-0 (← links)
- 05000250/LER-1983-005, Forwards LER 83-005/01T-0 (← links)
- 05000250/LER-1983-003, Forwards LER 83-003/03L-0 (← links)
- 05000250/LER-1981-013, Forwards Updated LER 81-013/02X-2 (← links)
- 05000250/LER-1986-001, Notifies That LER 86-001 Re Auxiliary Feedwater Sys Steam Supply Stop Check Valves Will Be Submitted by 860214,per 860207 Telcon Request (← links)
- 05000250/LER-2021-004, Cancelation of LER 2021-004, Through-Wall Leakage from Core Exit Thermocouple Tubing (← links)
- 05000250/LER-1982-010, Forwards LER 82-010/03L-0 (← links)
- 05000250/LER-1982-009, Forwards LER 82-009/03L-0 (← links)
- 05000250/LER-2024-002-01, Condition Prohibited by Technical Specifications (← links)
- 05000250/LER-2024-002, 0 for Turkey Point, Unit 3 - Condition Prohibited by Technical Specifications (← links)
- 05000250/LER-2023-004, Unplanned Automatic Scram During RPS Testing (← links)
- 05000250/LER-2023-003, Grid Disturbance in Switchyard Causes Automatic Reactor Trip (← links)
- 05000250/LER-2023-002, Manual Reactor Trip Due to Steam Generator Feedwater Regulating Valve Positioner Failure (← links)
- 05000250/LER-2023-001, RCS Pressure Boundary Degraded (← links)
- 05000250/LER-2021-003, Regarding Auxiliary Feedwater Actuation Due to Feedwater Isolation During Plant Shutdown (← links)
- 05000250/LER-2021-002, Unrecognized Technical Specification Surveillance Requirement Non-Compliance (← links)
- 05000250/LER-2021-001, Automatic Reactor Trip Due to Reactor Trip Breaker Cell Switch Malfunction (← links)
- 05000250/LER-2020-005-01, Technical Specification Action Not Taken for Unrecognized Inoperable Source Range Channel (Rev 1) (← links)
- 05000250/LER-2020-002-01, Manual Reactor Trip in Response to High Steam Generator Level Following Inadve1ient Opening of Feedwater Heater Bypass Valve (Rev 1) (← links)
- 05000250/LER-2020-005, Technical Specification Action Not Taken for Unrecognized Inoperable Source Range Channel (← links)
- 05000250/LER-2020-004, Re Manual Reactor Trip in Response to Automatic Trip of the 3B Steam Generator Feedwater Pump (← links)
- 05000250/LER-2020-003, Automatic Reactor Trip Due to High Source Range Flux During Reactor Startup (← links)
- 05000250/LER-2020-002, Re Manual Reactor Trip in Response to High Steam Generator Level Following Inadvertent Opening of Feedwater Heater Bypass Valve (← links)
- 05000250/LER-1988-031, Has Been Canceled.Resolution of LERs Missing from Lertrk/Scss/Dcs Discussed (← links)
- 05000250/LER-1986-034, :on 860921,during Performance of Secondary Plant Periodic Tests,Reactor Trip & Auxiliary Feedwater Actuation Occurred.Caused by Personnel error.Pre-amp for Source Range Neutron Flux Detector Replaced (← links)
- 05000250/LER-1986-036, :on 861106,requirements of Tech Spec 3.7 Exceeded When Both Emergency Diesel Generators Declared Out of Svc.Caused by Governor Solenoid Out of Adjustment. Governor Solenoid Properly Adjusted (← links)
- 05000250/LER-1986-035, :on 860925,charging Pumps 3A,3B & 3C Inoperable.Caused by Leaking Relief Valve on Charging Pump 3C.Relief Valve Replaced & Pump Returned to Svc (← links)
- 05000250/LER-1986-031, :on 860803,Tech Spec 3.0.1 Entered Due to Declaring Train 2 of Auxiliary Feedwater Out of Svc.Caused by Failure of Flow Control Valve to Open & Air Supply Solenoid Valve Leaking.Valve Replaced (← links)
- 05000250/LER-1986-039, :on 861227,reactor Tripped Following Loss of Turbine Electrical Load Due to Failed Turbine Governor Control Oil Pressure.Turbine Control Oil,Lube Oil & Seal Oil Piping Will Be Cleaned (← links)
- 05000250/LER-1987-007, :on 870128,requirements of Tech Specs 3.7.1d for Fuel Oil Storage Tank for Emergency Diesel Generators Not Met.Caused by Fuel Storage Tank Exceeding Criteria for Water & Sediment (← links)
- 05000250/LER-1987-006, :on 870123,w/both Units 3 & 4 at 100%, Requirements of Tech Spec 3.8.4.b Not Met.Caused by Erroneous Flow Indication of FI-1457A from Air in Sense Line of Associated Flow Transmitter.Line Vented (← links)
- 05000250/LER-1987-005, :on 870119,w/unit in Mode 2,control Room Ventilation Isolated & Switched to Recirculation Mode & Containment Vent Isolated.Caused by Process Radiation Monitor Spike.Equipment Being Evaluated (← links)
- 05000250/LER-1987-004, :on 870112,discovered That One Train of Auxiliary Feedwater Out of Svc When Both Units Above Hot Shutdown.Caused by Erroneous Flow Indication of Indicator FI-1457A.Flow Transmitter Replaced (← links)
- 05000250/LER-1986-023, :on 860504,discovered That Transfer of Motor Control Ctr D from Potentially Operable Bus to Potentially Inoperable Bus Could Occur.Caused by Failure to Account for Failure Mode for auto-transfer (← links)
- 05000250/LER-1987-003, :on 870112,annunciator E 8/3 Generator Field Ground Alarmed.Caused by Turbine Plant Cooling Water Leak in Exciter Housing.Leaking Exciter Air Cooler Isolated & Drained (← links)
- 05000250/LER-1986-022, :on 860502,while Preparing to Conduct Test of Emergency Diesel Generator B,Air Supply Valve to Start Motor of Emergency Diesel Generator a Closed.Caused by Personnel Error.Valve Reopened.Operator Counseled (← links)
- 05000250/LER-1979-031-03, /03T-2:on 791008,hex Nut Discovered Lodged in Internals of Main Steam Supply Valve to Moisture separator- Reheater 3C.Caused by Failure of Washer & Locking Device. Hex Nut & Locking Device Replaced (← links)
- 05000250/LER-1987-001, :on 870104,auxiliary Feedwater Pump Actuation Occurred Following Attempt to Start Steam Generator Feedwater Pump 3B.Auto-start Logic of Feedwater Pump Checked for Malfunction.Starts to Be Monitored (← links)
- 05000250/LER-1987-002, :on 870103,control Valve CV-3-739 Declared Out of Svc Due to Failed Solenoid Coil,Exceeding Tech Spec 3.3.3.Caused by Valve Being Left Out of Table 3.6-1.Failed Solenoid Replaced & Table 3.6-1 Revised (← links)
- 05000250/LER-1987-009, :on 870215,oil Pressure Decreased & Reactor Tripped.Caused by Insufficient Attention to Orifice Adjustment.Turbine Control Oil,Lube Oil & Seal Oil Piping Will Be Cleaned During Next Refueling Outage (← links)
- 05000250/LER-1987-008, :on 870211,w/unit at 96% Power,Control Room Ventilation & Containment Vent Isolation Occurred.Ground Caused Electrical Transient Initiating Spike.Radiation Monitors Reset & Grounded Cable Repaired (← links)
- 05000250/LER-1986-038, :on 861204,valve MOV-3-1403 & Auxiliary Feedwater Pump B Declared Out of Svc.Caused by Burned Motor Leads on Valve Actuator & Drift of Electronic Overspeed Trip Setpoint,Respectively (← links)
- 05000250/LER-1986-037, :on 861212,min Redundancy Requirements Not Met When Power Range Neutron Flux Detector N-41 Taken Out of Svc.Caused by Failure to Place Overpower Reactor Trip Signal in Tripped Condition.Procedure Revised (← links)
- 05000250/LER-1986-040, :on 861218,determined Deficiency Existed Re Potential for Loss of Three Air Conditioner Compressors & Handlers of Control Room Ventilation Sys.Caused by Position of Control Stick Between Two Positions (← links)
- 05000250/LER-1986-026, :on 860612,left Turbine Stop Valve Failed to Close.Caused by Mechanical Failure of Leslie Co Pilot Valve Sn 696856-2.Maint Will Be Performed.Operability Test Procedure Revised (← links)
- 05000250/LER-1986-033, :on 860815,plant Notified That Single Device Associated w/4,160-volt Bus Lockout Schemes Could Adversely Affect Ability of Emergency Diesel Generators.Cause Not Stated.Emergency Operating Procedures Revised (← links)
- 05000250/LER-1986-028, :on 860625,Part 21 Deficiency Re Potential Loss of Min Flow for Safety Injection Pumps Noted.Caused by Potential RCS Depressurization W/Loss of Instrument Air,Per IE Info Notice 85-094.Temporary Mod Performed (← links)
- 05000250/LER-1986-021, :on 860502,reactor Trip Occurred During Performance of Operating Procedure OP 1004.2.Caused by Operator at Trip Override Switch Not Instructing Second Operator to Proceed to Other Train (← links)
- 05000250/LER-1985-029, :on 850930,containment & Control Room Isolation Occurred.Caused by Pulling of Power Fuses on Process Radiation Monitoring Instruments During Repair.Instruments Repaired & Procedure Revised (← links)
- 05000250/LER-1985-028, :on 850930,480-volt Load Ctr Instantaneous Undervoltage Relay Setting Found in Excess of Tech Spec Limit from 841013-850513.Caused by Failure to Implement Tech Specs.Relay Reset & Procedure Changed (← links)
- 05000250/LER-1986-027, :on 860619,five Tech Spec Required Calibrs & Channel Functional Tests Not Performed.Caused by Personnel Error.Procedures Revised,New Procedures Implemented & Weekly Planning Meetings Instituted (← links)
- 05000250/LER-1986-029, :on 860709,discovered That Tech Spec Time Limit for Required Annual Surveillance of Fire Protection Sys Exceeded by 10 Days.Caused by Oversight & Lack of Coordination.Surveillance Completed on 860428 (← links)
- 05000250/LER-1986-030, :on 860627,reactor Trip & Subsequent Safety Injection Actuation Occurred,Due to Personnel Performing Sections of Operating Procedure 14004.1.Caused by Personnel Error.Affected Procedure Revised (← links)
- 05000250/LER-1986-009-01, :on 860410,discovered Difference in Piping Configuration of High Head Safety Injection Pump Seal & Thrust Bearing Coolers.Caused by Inadequate Procedure Controls.New Procedure Controls Implemented (← links)
- 05000250/LER-1986-025, :on 860612,Tech Spec 3.6.d.1 for Charging Pump Operability Exceeded.Caused by Cracked Weld on Discharge Line Due to Sys Vibration.Charging Pump Overhauled in Accordance W/Maint Procedures (← links)
- 05000250/LER-1986-013, :on 860312,bi-weekly Protection Surveillance T Average/Delta T Exceeded Allowable Grace Period. Caused by Failure to Sign Work Order & Data Sheets & Process Data in Timely Manner.Procedure AP 0190 Revised (← links)
- 05000250/LER-1986-024, :on 860611,intake Cooling Water Pump Declared Out of Svc for More than 24 H.Caused by Two Pieces of Wood Blocking Portion of Stationary Vanes.Wood Removed (← links)
- 05000250/LER-1986-012, :on 860305,subcritical Reactor Trip Occurred When source-range Detector Spiked.Caused by Low Detector Resistance & Short of Preamplifier Diode.Detector & Diode Replaced.Test Per Procedure Satisfactory (← links)
- 05000250/LER-1986-020, :on 860505,discovered Required Surveillance of motor-driven Fire Pump Not Performed Between 851007 & 1203. Caused by Inadequate Surveillance Program.Administrative Procedure 0190.16 Revised (← links)
- 05000250/LER-1986-019, :on 860427,emergency Diesel Generator Declared Out of Svc When Ready to Start Light Lost While 4,160-volt Bus 4B Out of Svc for Maint.Caused by Local Light Socket Short.Short Fixed & Fuse Replaced (← links)
- 05000250/LER-1986-018, :on 860416,shutdown Commenced When Intake Cooling Water Inlet Temps Increased W/Only Two of Three HXs Operable.Shutdown Terminated When Gasket to HX Replaced (← links)
- 05000250/LER-1986-017, :on 860411,momentary Turbine Runback at 93% Power Occurred When RPI Power Supply Swapped from Normal to Alternate Supply When Inverter Failed.Caused by Component Failure of Transformer.Rpi Amplifier Adjusted (← links)
- 05000250/LER-1984-016, :on 840513,isotopic Analysis for Iodines in RCS Not Performed within Required Time Interval.Caused by Poor Communication Between Operations & Chemistry Personnel.Addl Training Given & Sampling Procedure Revised (← links)
- 05000250/LER-1986-015, :on 860408,discovered That When Auxiliary Feedwater Pump a Trip & Throttle Valve Tripped,No Light Indicated in Control Room.Caused by Improper Installation of Limit Switch.Light Indication Repaired (← links)
- 05000250/LER-1986-016, :on 860409,auxiliary Feedwater (AFW) Sys Train B Declared Out of Svc Due to Erratic Flow Indications from Indicator FI-1401B.Tech Spec 3.8.4.a Violated.Flow Indicator Replaced & Surveillance Performed (← links)
- 05000250/LER-1985-020, :on 850723,possible Inability of MSIVs to Close During Uncontrolled Steam Release Discovered.Caused by Deficiency in MSIVs Built by Ametek,Inc & Designed by Bechtel.Design Will Be Modified Per FSAR (← links)
- 05000250/LER-2020-001, Technical Specification Action Not Taken for Unrecognized Inoperable Reactor Protection System (RPS) and Engineered Safety Feature Actuation System (ESFAS) Instrument Channel Functional Units (← links)
- 05000250/LER-1998-006-02, :on 981006,unescorted Access Was Granted to Contractor Employee Who Falsified Background Info.Caused by Individual Who Knowingly Provided False Info.Denied Access to Individual on 981006.With (← links)
- 05000250/LER-1986-009, :on 860224,w/unit at 100% power,in-depth Review of Important Plant Sys Determined Potential Concern W/Component Cooling Water Flow Through RHR Hxs.Tests Performed to Gather Data for Sys Alignment (← links)
- 05000250/LER-1998-005-02, :on 980924,suspended Safeguards During Severe Weather Due to Personnel Safety.Caused by Severe Weather Associated with Effects of Hurricane Georges.Fully Instituted Compensatory Measure.With (← links)
- 05000250/LER-1986-006, :on 860211,safety Injection Sys Actuated & Subsequent Reactor Trip Occurred.Caused by Const Activities on Unit 4 & Inadequate Instructions for Investigating Event. Procedures Revised (← links)
- 05000250/LER-1986-007, :on 860217,high Head Safety Injection Pump 4B Discovered Out of Svc During 860212 Startup.Caused by Oversight in Review of Unit 4 Clearances Allowing Pump to Be Declared in Svc W/Valves Closed (← links)
- 05000250/LER-1986-005, :on 860127 MSIV 3C Went to Partially Closed Position & Could Not Close Fully.Caused by Redundant Solenoid Valves Failure to Admit Instrument Air to Drive MSIV 3C.One Solenoid Valve Replaced (← links)
- 05000250/LER-1986-001-02, :on 860107,auxiliary Feedwater Sys Steam Supply Stop Check Valves 3-10-119,3-10-219 & 4-10-319 Declared Out of Svc Due to Broken Guide Studs.Caused by Insufficiently Rugged Disc Studs.Valves Inspected (← links)
- 05000250/LER-1986-002-01, :on 860109,lock-out of 4,160-volt Bus 3A Occurred.Caused by Const Worker Jarring Overcurrent Protection relay.Lock-out Signal Stripped Bus & Started Emergency Diesel Generator A.Fuse F2 Pulled (← links)
- 05000250/LER-1986-004, :on 860125,presence of Debris in Emergency Containment Coolers Discovered.Caused by Past Performance of Maint Procedure 4707.2 During Steam Generator Repair Outages.Debris Removed.Maint Procedure Revised (← links)
- 05000250/LER-1985-041, :on 851204,automatic Initiation of Auxiliary Feedwater Occurred.Caused by Trip of Steam Generator Feedwater Pump 3B Due to Failure to Reopen Pump Suction Valves After Cleanup (← links)
- 05000250/LER-1985-040, :on 851130,subcritical Trip Occurred.Caused by Removal of Reinsertion of N-32 Instrument Power Fuses W/O Placing Channel Level Trip Switch in Bypass Position. Operator Advised on Plant Procedures (← links)
- 05000250/LER-1986-010, :on 860228,failure to Perform Daily Check of Area Radiation Monitor Sys Channel Not Completed for 7 Days. Caused by Inoperable Door & Personnel Oversight.Door Repaired & Importance of Procedures Emphasized (← links)
- 05000250/LER-1986-011, :on 860228,excessive Interval Between Monthly Insps of Fire Protection Equipment Discovered.Caused by Erroneous Due Date Generated by Computer.Required Surveillances Independently Initiated (← links)
- 05000250/LER-1986-003-01, :on 860118,motor Control Ctr D auto-transfer Scheme Discovered Vulnerable to Single Failure,Loss of 3B Battery,Which Upon Loss of Offsite Power Could Result in Emergency Containment Cooler Actuation (← links)
- 05000250/LER-1986-008, :on 860214,unit Shut Down Due to Potential Inability of Intake Cooling Water Sys to Meet Flow Requirements for Dba.Procedures Written Re Isolation of Temp Control Valves (← links)
- 05000250/LER-1985-043, :on 851217,emergency Diesel Generator a Declared out-of-svc W/Generator B out-of-svc for Replacement of Control Cabinet Selector Switch.Caused by Erroneously Recorded High Temp Reading on Pyrometer (← links)
- 05000250/LER-1985-031, :on 851007,w/unit at 100% Power,Turbine Runback to Approx 540 Mwe Occurred.Caused by Failure of RPI Inverter Due to Positive Dc Spike Coming from 3AR2 Relay Coil.Fuses & Relay Coil Replaced (← links)
- 05000250/LER-1985-032, :on 851015,at 100% Power,Main Transformer Relay Actuated,Resulting in Electrical Generator Trip & Turbine Trip.Probably Caused by Jarring of Relays by Const Personnel (← links)
- 05000250/LER-1985-021-01, :on 850722,two Automatic Initiations of Auxiliary Feedwater Sys Occurred Due to Bypass Feedwater Control Valves Malfunctioning.Caused by Moisture in Instrument Air.Actuators Inspected & Cleaned (← links)
- 05000250/LER-1985-037, :on 851105,auxiliary Feedwater Train a Flow Indicator for Steam Generator HIC-1457A Indicated Flow in no-flow Condition.Caused by Air in Sense Lines & Zero Shift. Sense Line Vented & Transmitter Replaced (← links)
- 05000250/LER-1985-025, :on 850827 & 30,during App R Safe Shutdown Review,Addl Circuits That May Require Protection,Rerouting or Circuit Mods Identified.Caused by Addl NRC Guidance.Fire Watch Expanded (← links)
- 05000250/LER-1985-034, :on 851023,requirements of Tech Spec 3.4.1.e Exceeded.Caused by Failure of Ingersol Rand Model 8X20W 3A RHR Pump Mechanical Seal.Pump Seal Repaired & Pump Tested & Returned to Svc (← links)
- 05000250/LER-1985-036, :on 851025,RHR Sys Flow Interrupted Due to Automatic Closure of MOV-3-750.Caused by Erroneous High Pressure Signal Due to Failed Relay PC-403-A-2 in Pressure Comparator for Pressure Controller PC-403 (← links)
- 05000250/LER-1985-035, :on 851024,discovered That Accident Monitoring Instrumentation Operability Requirements of Tech Spec 3.5 Exceeded.Caused by Personnel Failure to Recognize post-LOCA Integrated Dose of Receiver.Receiver Relocated (← links)
- 05000250/LER-1985-044, :on 851230,turbine Runback Occurred.Caused by Failure of Primary Detector Coil in Rod Position Indicator for N-9.Applicable Plant Procedures Used to Verify N-9 Still Withdrawn at 228 Steps (← links)
- 05000250/LER-1985-021, :on 850722,two Automatic Initiations of Auxiliary Feedwater Sys Occurred Due to Valve Malfunction. Caused by Quality of Instrument Air Supplied to Valve Actuators.Actuators Inspected & Cleaned (← links)
- 05000250/LER-1985-033, :on 851016,discrepancy Discovered Between Assumptions Used in Most Current Westinghouse LOCA Analysis & Fsar.Sufficient Margin Exists Between Reported Values of Peak Clad Temp & ECCS Acceptance Criteria (← links)
- 05000250/LER-1985-023, :on 850801,safety Injection Sys Actuation Occurred Following Reactor Trip Resulting from Trip of Bs Inverter.Caused by Failure of Oscillator & Logic Power Supply Module.Power Restored (← links)
- 05000250/LER-1985-022, :on 850729,reactor Trip Occurred.Caused by Dirty Contacts on One Nuclear Instrumentation Sys Channel. Power Range Trip Relays Removed,Cleaned & Reinstalled (← links)
- 05000250/LER-1985-024, :on 850726,during Operability Test of Auxiliary Feedwater Pump C,Discharge Control Valve CV-3-2817 Failed to Fully Stroke Closed.Caused by Misadjusted Positioner.Valve Positioner Reset (← links)
- 05000250/LER-1985-019, On 850721,reactor Protection Sys Actuated, Turbine Tripped & Auxiliary Feedwater Initiated Due to Spurious Low Pressure Signal.Probably Caused by Lightning. Periodic Operability Test Performed (← links)
- 05000250/LER-1985-018-01, :on 850716,inverter 3C Supplying Power to 120-volt Vital Instrument Panel 3P06 Tripped.Cause Not Determined.Inverter Removed from Svc on 850719 for Replacement W/Different Model (← links)
- 05000250/LER-1985-030, :on 850919,Tech Spec Monthly Internal Surveillance for Updating Target Axial Flux Difference Exceeded.Caused by Personnel Error.New Target Axial Flux Difference Calculated from Measured Values (← links)
- 05000250/LER-1985-006, :Redundant Raw Water Tank II Installed,Which Holds 300,000 Gallons of Water Dedicated to Fire Suppression.New Raw Water Tank II Meets App R Iii.A Requirements Approved by NRC on 811109 (← links)
- 05000250/LER-1985-026, :on 850911,boric Acid Storage Tank a Found W/ Concentration of 22,800 Parts Per Million.Caused by Batch of Boron Added to Tank a Earlier in Day.Tank B Lined Up to Unit 3 & 200 Gallons of Water Added to Tank a (← links)
- 05000250/LER-1985-016, :on 850613,automatic Start of Emergency Diesel Generator a Occurred.Caused by Personnel Error.Generator Stopped & Returned to Normal Standby Condition,Per Operating Procedure 0-OP-023 (← links)
- 05000250/LER-1985-015-01, :on 850626,voluntary Unit Cooldown Initiated Using Guidance of Tech Spec 3.0.1 Due to Detection of RCS Leak.Cause of 850625 Reactor Vessel O-ring Leakage Still Under Investigation (← links)
- 05000250/LER-1985-017, :on 850617,Train B Safeguards Equipment Actuated by Spurious Safety Injection Signal Generated in ESF Sys.Caused by Operator Error.Operator Counseled on Correct Use of Procedures (← links)
- 05000250/LER-1983-015-03, /03L-0:on 830911,during Full Power Operation, Critical Heat Tracing Circuit 20 Declared Inoperable.Caused by Short Circuit in Train a & Closed Circuit on Train B. Unit Brought to Hot Shutdown.Circuit Repaired (← links)
- 05000250/LER-1985-012, :on 850429,during shutdown,generator-main Transformer Lockout Relay Tripped,Resulting in Actuation of ESF Equipment.Caused by Personnel Error.Personnel Counseled. Transformer turn-ratio Tested (← links)
- 05000250/LER-1985-013, :on 850502,during Scheduled Refueling Outage, Emergency Diesel Generator a Automatically Started.Caused by Incorrect Step in Procedure 3-OP-005 Used to Deenergize 4,160-volt Bus 3A.Procedures Changed (← links)
- 05000250/LER-1985-011, :on 850406,while in Refueling Shutdown,Two safety-related Snubbers Inside Containment on RCS Pressurizer Spray & Relief Line Removed Before Inservice Insp Could Be Performed (← links)
- 05000250/LER-1985-014, :on 850520,refueling Cavity,Spent Fuel Pool & Fuel Transfer Canal Levels Lowered Below Tech Spec Min. Caused by Personnel Oversight During Repair of Fuel Transfer Carriage Drive Motor Chain.Level Raised (← links)
- 05000250/LER-1985-010, :on 850330,subcooling Margin Monitors Considered Inoperable Per Tech Specs & Plant Shutdown.Caused by Failure of RCS Temp Elements to Meet Environ Acceptance Criteria.Elements Will Be Replaced (← links)
- 05000250/LER-1985-009, :on 850401,evaluation Required for Inoperable Mechanical Shock Arrestor (Snubbers) Not Completed within Allowable Time Limits.Caused by Snubbers Inadequately Evaluated (← links)
- 05000250/LER-1985-008, :on 850312,check Source Operability Verification of Two Sys Level Particulate,Iodine & Noble Gaseous Effluent Monitors Not Performed.Caused by Miscommunication Between Technicians (← links)
- 05000250/LER-1984-036, :on 841221,emergency Diesel Generator B Failed to Start from Control Room.Caused by No Load Governor Speed Adjustment Set Higher than Overspeed Protection Setpoint.No Load Speed Readjusted (← links)
- 05000250/LER-1984-038, :on 841222,during Daily Operability Testing, Leak Vent Line Discovered on Emergency Diesel Generator B. Caused by Vibration of Engine Coolant Discharge Line Causing Crown to Break.Vent Line & Crown Replaced (← links)
- 05000250/LER-1984-034, :on 841213,containment Isolation Valve CV-3-204 Remained Open.Caused by Malfunction of Solenoid Valve.Air Supply to Valve Secured.Solenoid Valve Removed,Tested & Replaced (← links)
- 05000250/LER-1984-033, :on 841213,reactor Trip Occurred Due to Generator Trip & Subsequent Turbine Trip.Caused by Fault in Exciter Created by Shorting of Dc to Ac Side of Rotor. Exciter Rotor Replaced (← links)
- 05000250/LER-1984-031, :on 841202,containment Isolation Valve CV-3-855 Would Not Indicate Closure in Control Room.Caused by Asco Solenoid Valve Malfunction.Asco Solenoid Valve Replaced (← links)
- 05000250/LER-1984-032, :on 841203,limiting Condition for Operation Re Auxiliary Feedwater Pump Availability Inadvertently Exceeded.Caused by Failure of Personnel to Apply Recent Interpretations of Tech Spec (← links)
- 05000250/LER-1984-030, :on 841129,surveillance Extension Period Allowed by Tech Spec 4.15.2.a.6 Expired When Functional Testing of Diesel Driven Fire Pumps Could Not Be Completed. Caused by App R Mods Made to Sys (← links)
- 05000250/LER-1984-029, :on 841127,turbine Runback to 50 MW & Approx 65% Reactor Power Occurred.Caused by Personnel Error.Load Decrease Stopped by Raising Governor Oil Pressure Which Increased Generator Load to Approx 225 MW (← links)
- 05000250/LER-1985-003, :on 840119,turbine Manually Tripped Following Permissive P-7 Disarming to Prevent Tave from Decreasing Enough to Cause Safety Injection signal.P-7 Rearmed Prior to Turbine Trip.Caused by Personnel Error (← links)
- 05000250/LER-1984-025, :on 840923,evaluation on Intake CWS Revealed Component CWS HXs May Not Meet Design Heat Removal Capability Under Design Inlet Condition.Temporary Limiting Condition for Operation Established (← links)
- 05000250/LER-1984-035, :on 841230,block Valve MOV-3-535 Up Stream from PORV PCV-3-456 Would Not Close Completely.Caused by Malfunctioned Torque Limit Switch on Valve.Torque Switch Replaced & Tested Returning Valve to Full Svc (← links)
- 05000250/LER-1984-028, :on 841030,min Degree of Redundancy for Reactor Protection Sys overtemp-delta Temp & overpower-delta Temp Reactor Trip Features Less than Tech Spec Requirements. Caused by Incorrect Variable Setpoints (← links)
- 05000250/LER-1985-005-01, :on 850205,during Work Order to Clean Four Batteries for Diesel Driven Fire Protection Pump,Battery Acid Fluid Noticed Forced Out of Four Batteries.Caused by Standby Charging Sys Overcharging (← links)
- 05000250/LER-1984-026, :on 841009,turbine Runback to 70% Reactor Power Occurred.Possibly Caused by Inadvertent Transfer of Power for Panel 3P07 from Normal Inverter 3A Spare Inverter As. Personnel Trained (← links)
- 05000250/LER-1985-004, :on 850129,reactor Tripped.Caused by ESF Actuation Due to Nonlicensed Operations Personnel Removing Unit 3 Motor Generator Sets a & B from Svc Rather than Unit 4 Sets.Personnel Counseled (← links)
- 05000250/LER-1984-023, :on 840822,while at 100% Power,Turbine Runback to 45% Power Occurred.Caused by Dropped Control Rod in Shutdown Bank a & Blown Stationary Gripper Fuse.Loose Cable Connector Replaced (← links)
- 05000250/LER-1984-022, :on 840721 & 22,daily Calibr of Nuclear Power Range (Thermal Power Calculation) Not Performed Per Tech Specs.Caused by Personnel Oversight.Checks for Calculations Made & Supervisory Discussions Held (← links)
- 05000250/LER-1984-021, :on 840714,reactor Tripped from Subcritical Condition.Caused by Power Interruption of Source Range Nuclear Instrumentation Control Power.Personnel Counseled.W/ (← links)
- 05000250/LER-1984-020, :on 840712,unit Shut Down Due to RCS Leak of Approx 13.5 Gpm.Leakage Caused by Broken Gland Flange on Valve 3-538.Valve Packing Gland Flange Replaced & All Rockwell 3/4-inch Valves Inspected (← links)
- 05000250/LER-1982-021-03, /03L-0:on 820511,self-initiated Audits Revealed Inadequate Surveillance of Emergency Diesel Generators for Tests Required by Tech Spec 4.8.1.a.5.Caused by Inadequate Review of Operating Procedure 4304.1 (← links)
- 05000250/LER-1984-027, :on 841002,damaged Undervoltage Trip Attachment Coil Tape,Cracked Insulating Link,Cracked Braze on Manual Closing Mechanism Bracket & Failed Bearing Manual Closing Mechanism Discovered (← links)
- 05000250/LER-1984-019, :on 840625,unit Shut Down Due to RCS Leak of Approx 10 Gpm.Caused by Packing Leak Due to Broken Gland Follower on Valve 3-532.Affected Loop Bistables Tripped & Valve 3-352 Manually Backseated (← links)
- 05000250/LER-1984-024, :on 840902,biweekly Test for Temp Average & Delta-T Not Performed.Caused by Oversight of Personnel in Not Completing Test within Allowed Time Interval.Method of Scheduling Changed (← links)
- 05000250/LER-1984-015, :on 840514,turbine Runback Occurred.Caused by Instrument Power Supply Failure on Nuclear Instrumentation Sys That Resulted in Rod Drop Signal.Conduit & Connector Refastened & Wiring Checked (← links)
- 05000250/LER-1984-014, :on 840424,turbine Operator Taking Standby Static Inverter a Out of Svc Erroneously Opened Output Breaker of Adjacent Static Inverter,Causing Reactor Trip. Plant Stabilized & Instruments Replaced (← links)
- 05000250/LER-1984-018, :on 840717,Part 21 Deficiency Identified Deenergizing of Interlocking Relays to safety-related Valves in RHR Pump Suction & Discharge Lines,Resulting in Inability to Open Valves.Caused by Loss of Power (← links)
- 05000250/LER-1982-020-03, /03L-0:on 820511,insufficient Data Recorded to Verify Satisfactory Performance of Emergency Diesel Generator Cooling Sys.Caused by Inadequate Review of Operating Procedure 4304.1.Procedures Revised (← links)
- 05000250/LER-1976-001-03, /-03L:on 760219,water Found Leaking from Charging Pump 3A.Cause of Crack in Pump Casing Not Yet Determined. Crack Weld Repaired & Pump Returned to Svc (← links)
- 05000250/LER-1976-002-01, /01T:on 760306,closing Spring of Emergency Diesel Generator 3B Breaker Not Charged.Caused by Worn Bushing on Charging Motor Drive Pawl.Spare Breaker Installed (← links)
- 05000250/LER-1976-003-03, /03L:on 760519,output 1 of Pressurizer Level Comparator LC-459A Tripped at 4.685 Volts Instead of 4.680 Volts.Caused by Setpoint Drift.Trip Setpoint Reset to Conservative Value (← links)
- 05000250/LER-1976-004-01, /01T:on 760611,boron Concentration of Injection Tank Below 20,000 Ppm Limit.Caused by Recirculation W/Low Concentration of Boric Acid Storage Tank B.Shutdown Initiated (← links)
- 05000250/LER-1976-005-01, /01T:on 760805,Westinghouse Informed of New Development on Results of Safety Analysis.Caused by Increase of Temp of Fluid in Upper Head & Increased Rod Bow Penalty (← links)
- 05000250/LER-1976-006-01, /01T:on 760909,closing Springs in Diesel Generator 3A Circuit Breaker Not in Charged Position.Caused by Worn Nylon Bushing Between Closing Spring Drive Motor & Linkage to Ratchet Wheel (← links)
- 05000250/LER-1976-008-01, /01T:on 761006,boron Concentration of Injection Tank Below 20,000 Ppm Limit.Cause Undetermined.Shutdown Initiated (← links)
- 05000250/LER-1976-009-03, /03L:on 761015,charging Pump 3B Removed from Svc Because of Damaged Rod Bearings.Caused by Insufficient Lubrication of Bearings.Pump Casing of Pump 3B Installed on Pump 3A & Pump 3A Returned to Svc (← links)
- 05000250/LER-1976-010-03, /03L:on 761125,trip Setpoint of Steam Flow Comparator FC-3-484 Found to Be Nonconservative.Caused by Failure of Two Filter Capacitors on Printed Circuit Board. Capacitors to Be Replaced (← links)
- 05000250/LER-1976-007-01, /01T:on 760805,heat Flux Hot Channel Factor & Enthalpy Rise Hot Channel Factor Allowable Max Reduced. Caused by Increased Limit for Upper Head Fluid & Rod Bow Penalty (← links)
- 05000250/LER-1984-017, :on 840607,primary Water Valve (3-220) Discovered Leaking.Leak Repair Required Isolation of Primary Storage Water Tank,Resulting in Unit Not in Compliance W/Tech Specs.Valve Stem & Diaphragm Replaced (← links)
- 05000250/LER-1984-009, :on 840306,turbine Runback Experienced During Operating Procedure 1004.2.Caused by Spurious Signal to Rod Drop Logic.Rack Will Be Monitored While Performing Reactor Protection Test to Prevent Recurrence (← links)
- 05000250/LER-1984-008, :on 840223,during Auxiliary Feedwater Sys Test, Pump B Removed from Svc When Flow Oscillations Observed. Caused by Defective Differential Pressure Cell.Cell Repaired & Pump B Returned to Svc (← links)
- 05000250/LER-1984-007, :on 840216,while at Steady Operation,Dual Unit Trip Occurred from 100% Power,Resulting in Loss of 4,160- Volt Buses 3C & 4C.Caused by Bolt in Breaker 4AC01 Cubicle Door Travel.Doors Checked for Proper Clearance (← links)
- 05000250/LER-1984-006, :on 840212,reactor Tripped.Caused by Electrical Relay Malfunction Resulting in Loss of Power to nonsafety- Related 4160-volt Bus.Design Review & Complete Testing of Automatic Turbine Governor Initiated (← links)
- 05000250/LER-1983-026-03, /03L-0:on 831215,util Advised by Const Personnel of Portable Air Compressor Rolling Down Containment Equipment Hatch Ramp & Striking Emergency Diesel Generator Fuel Oil Transfer Piping (← links)
- 05000250/LER-1984-004, :on 840104,auxiliary Feedwater Sys Periodic Test Initiated & Pump a Failed to Develop Required Flow. Caused by Misposition of Manual Governor Speed Control Knob. Knob Reset to Max Position (← links)
- 05000250/LER-1983-025-03, /03L-0:on 831216,during Cold Shutdown,Spurious Safeguards Actuation Signal Received & Emergency Diesel Generator B Failed to Start.Caused by Diesel Air Pressure Regulator Malfunction.New Regulator Installed (← links)
- 05000250/LER-1984-013, :on 840403,turbine Runback Occurred.Caused by Spurious Rod Drop in Nuclear Instrumentation Sys Channel N-44.Plant Stabilized at Approx 75% Power W/O Problem (← links)
- 05000250/LER-1984-012, :on 840329,automatic Transfer of 480-volt Power Supply Occurred.Caused by Accidental Jarring of Electrical Auxiliary Relay.Relay Reset (← links)
- 05000250/LER-1984-011, :on 840323,turbine Runback Experienced, Resulting in Automatic Load Reduction.Caused by Detector B Reading Low on Nis Power Range Channel 42,producing Overpower & Overtemp & Rod Drop Signal (← links)
- 05000250/LER-1984-010, :on 840417,mods Necessitated Number of Fire Barriers to Be Breached.Hourly Fire Watch Established. Penetrations in Fire Area Boundary Will Be Sealed Per App R Commitments (← links)
- 05000250/LER-1982-019-03, /03L-0:on 821223,while Performing Full Length Rod Control Cluster Periodic Exercise,Rod Control Cluster J3 of Shutdown Bank a Failed to Show Proper Movement.Cause Unknown.Cluster Performed Normally During Rod Exercise (← links)
- 05000250/LER-1983-023-03, /03L-0:on 831201,while Unit Shut Down,Discovered Spent Fuel Pit Exhaust Radiation Monitor Deenergized.Cause Undetermined.Sign Will Be Posted Identifying Breaker as Tech Spec Item (← links)
- 05000250/LER-1983-022-03, /03L-0:on 831002,during Scheduled Refueling Shutdown Operations,Motor Operated Valves 843A,843B & 869 Not Verified Closed W/Breakers Racked Out.Caused by Not Adhering to Procedures (← links)
- 05000250/LER-1983-021-03, /03L-0:on 831109,during Replacement,Three Auxiliary Feedwater Steam Supply Piping Check Valves Found to Be Schedule 40 Piping Instead of Schedule 80.Lines Meet Acceptance Criteria (← links)
- 05000250/LER-1981-016-03, 125-volt Dc Battery 3A Failed to Hold Charge.Root Cause Not Identified.Battery Replaced,Tested & Returned to Svc.Recommendations Received from Manufacturer (← links)
- 05000250/LER-1983-020-03, /03L-0:on 831011,while Reviewing off-normal Procedure,Deficiency Identified Which Could Lead Operators to Incorrectly Align Seal Cooling Water to RHR & Containment Spray Pumps While Swapping Headers (← links)
- 05000250/LER-1983-019-03, /03L-0:on 831008,RHR Flow Isolated Due to Pressure Transmitter PT-3-405 Exposure to Hydrostatic Test Pressure of 3,100 Psig.Caused by Unclear Drawing Configuration of Loop a Sample Line.Transmitter Replaced (← links)
- 05000250/LER-1983-016-03, /03L-0:on 831002,during Initiation of Cold Shutdown for Refueling,Letdown Isolation Valve CV-3-204 Failed to Close.Caused by Failed Solenoid Valve.Solenoid Valve Replaced (← links)
- 05000250/LER-1983-017-03, /03L-0:on 830926,personnel 830508 Failure to Take Grab Samples of Inoperable Prms (W/Indication of Secondary Activity) Discovered.Caused by Lab Personnel Error.Personnel Awareness Increased (← links)
- 05000250/LER-1984-005, :on 840125,reactor Trip Occurred.Caused by Accidental Trip of 4160-volt Bus Feeder Breaker by Const Worker.Const Stopped Until Administrative Site Procedure Prepared,Approved & Implemented (← links)
- 05000250/LER-1984-001, :on 840108,reactor Tripped from Approx 30% Power During Unit Evolution - Hot Shutdown to Power Operation.Caused by Spurious Signal,Resulting in Closure of Steam Generator a Feedwater Flow Control Valve (← links)
- 05000250/LER-1984-003, :on 840109,reactor Trip Occurred.Caused by Operator Inadvertently Tripping Reactor Trip Breaker a W/ Bypass Breaker a Open,Instead of Tripping Reactor Trip Breaker B.Procedure Reviewed (← links)
- 05000250/LER-1984-002, :on 840108,reactor Trip Occurred Due to Initiation of Safety Injection.Caused by Excessive Steam Usage in Secondary Sys & Steam Leakage Through Steam Supply Valves.Equipment Upgraded (← links)
- 05000250/LER-1983-007-01, /01T-0:on 830419,manual Valves on Steam Supply Lines to Auxiliary Feedwater Pump Turbines B & C Discovered Closed.Caused by Personnel Error in Rechanging Tags.Valves Immediately Locked Open & Pumps Satisfactorily Tested (← links)
- 05000250/LER-1982-016-03, /03L-0:on 821119,during Insp of Fire Protection Sys,Fire Barrier Penetration (Laundry Room West Doors) Found Nonfunctional.New Doors/Parts Ordered & Will Be Installed Upon Receipt (← links)
- 05000250/LER-1982-017-03, /03L-0:on 821119,during Control Room Mods,Two Fire Barrier Penetrations Disabled Intentionally for Longer than 7 Days.Action Taken to Implement Approved Design Mods to Control Room (← links)
- 05000250/LER-1983-024-03, /03L-0:on 831208,while in Shutdown,Spent Fuel Pit Exhaust Radiation Monitor Observed Deenergized.Caused by Motor Control Ctr (MCC) C Being Deenergized While Mods Performed.Monitor Returned to Svc (← links)
- 05000250/LER-1983-014-03, /03L-0:on 830816,while Sampling Gas Contents from Vol Control Tank,Unplanned Release Occurred in Auxiliary Bldg & Atmosphere Via Plant Vent.Caused by Insufficient Instructions on Valve lineup.w/830915 Ltr (← links)
- 05000250/LER-1983-012-03, /03L-0:on 830804,auxiliary Feedwater Pump a Failed to Deliver Flow to Steam Generators.Caused by Failed Differential Pressure Transmitter.Transmitter Replaced (← links)
- 05000250/LER-1983-011-03, /03L-0:on 830624,malfunction of Fire Ionization Detector 3-10 Caused Inside Containment Fire Detection Zone 3 to Be Disabled for Longer than 14 Days.Root Cause Unknown. Repairs to Be Performed During Next Outage (← links)
- 05000250/LER-1983-008-03, /03L-0:on 830614,conduit for Future Safety Parameter Display Sys Accidentally Damaged During Installation.One Containment Spray Pump Involved.Caused by Incorrect Drawing.Repairs Initiated (← links)
- 05000250/LER-1983-010-03, /03L-0:on 830711,monthly Update of Target Flux Difference,Operations Procedure 12304.6 Re Power Range Nuclear Instrumentation Calculation of Target Flux Difference,Not Performed (← links)
- 05000250/LER-1983-009-03, /03L-0:on 830610,during Operability Test of Auxiliary Feedwater Pump A,Pump Failed to Come Up to Speed & No Flow Delivered.Caused by Failed Differential Pressure Transmitter.Transmitter Replaced (← links)
- 05000250/LER-1983-005-01, /01T-0:on 830309,rod Control Clusters D8 & M8 of Control Bank D Simultaneonsly Dropped While Unit Operated at 100% Power.Caused by Momentary Short in Lead to Stationary Coils Due to Water Inside Cabinet.Leakage Stopped (← links)
- 05000250/LER-1983-003-03, /03L-0:on 830128,local Indication of Emergency Diesel Generator B Showed Low Starting Air Pressure of 150 Psig.Caused by Loose Tension Spring Nut on Low Starting Air Pressure Alarm Sensing Switch.Setpoint Adjusted (← links)
- 05000250/LER-1982-012-01, /01T-0:on 820917,insp Revealed That Electrical Penetration Did Not Meet Double Barrier Criteria of 10CFR50 & Testability Requirements of App J.Caused by Failure to Properly Document Plant Changes.Plant Change Implemented (← links)
- 05000250/LER-1983-002-03, /03L-0:on 830118,during Third & Fourth Quarters 1982,testing of Diesel Fuel Storage Tank Samples for Viscosity,Water & Sediment Levels Missed.Caused by Oversight.Sample Taken & Analyzed.Levels Acceptable (← links)
- 05000250/LER-1982-018-01, /01T-0:on 821201,during Full Power operation,3A Load Ctr de-energized Following Trip of 4-kV Breaker 3AA08. Cause Undetermined.Breaker Protective Relays Will Be Tested During Next Outage (← links)
- 05000250/LER-1981-013-02, Small Void in Concrete Found Immediately Below Equipment Hatch Barrel.Cause Not Stated.Similar Void Confirmed on Unit 4.Voids Repaired (← links)
- 05000250/LER-1982-013-03, /03L-0:on 820917,steam Turbine Pressure Control Valve CV-3707 Did Not Close Completely,Resulting in Poor Pressure & Causing Safety Relief Valve to Trip Auxiliary Feedwater Pump C.Caused by Foreign Matter Under Valve Seat (← links)
- 05000250/LER-1982-015-03, /03L-0:on 821104,during Normal operation,3A High Head Safety Injection Pump Failed to Start from Manual Operation.Cause Undetermined.Pump Breaker Racked Out & Back In.Repairs Made to Breaker (← links)
- 05000250/LER-1982-014-01, /01T-0:on 821106,monitor Tank Overflowed During Laundry Water Transfer to Monitor Tank.Caused by Procedural Violation.Floor Opening Capped,Procedure Revised & Personnel Reinstructed (← links)
- 05000250/LER-1990-008, :on 900415,Train B Safeguards Actuation Occurred During Performance of Surveillance Test Due to Component Failure (← links)
- 05000250/LER-1983-001-03, /03L-0:on 830107,insp of Leak Revealed Cracked Weld on Junction of 3C Charging Pump Discharge Line & Line Leading to Safety Relief Valve 3-283C.Cause Undetermined. Weld Repaired (← links)
- 05000250/LER-1978-016-03, /03L-0 on 781025:during Pwr Oper,Intake Cooling Water Pumps Were Running When 3B Pump Motor Failed.The 3B Pump Motor Failed Because of Short Circuit in the Motor Windings (← links)
- 05000250/LER-1978-016, Forwards LER 78-016/03L-0 (← links)
- 05000250/LER-1978-013-03, /03L-0:on 780929,condensate Storage Tank Contained Less than 185,000 Gallons for Appox 4 H.Caused by Steam Generator Blowdown W/No Demineralized Makeup Water (← links)
- 05000250/LER-1978-014-03, /03L-0:on 780929,comparator Power Supply FC-3-484 Malfunctioned.Caused by Faulty Regulating Amplifier in Comparator Power Supply Board.Amplifier Replaced & Comparator Tested Satisfactorily (← links)
- 05000250/LER-1982-011-03, /03L-0:on 820713,quarterly Surveillance Test of Seismograph Completed 3 Days After Last Allowable Tech Spec Date.Caused by Const Equipment Blocking Access to Seismograph.Test Successfully Completed on 820716 (← links)
- 05000250/LER-1982-010-03, /03L-0:on 820617,nonfunctional Vertical Pipe Support Discovered on Suction Line of 3A Component Cooling Water Pump.Caused by Cracking of Grout Under Plate,Resulting in Loss of Contact W/Ground.Support Regrouted (← links)
- 05000250/LER-1982-009-03, /03L-0:on 820617,tritium Activity Weekly Sampling Tests Not Performed.Caused by Out of Svc Liquid Scintillation Machine.Samples Counted on 820621.Normal Levels Recorded (← links)
- 05000250/LER-1982-008-03, /03L-0:on 820609,3A High Head Safety Injection Pump Failed to Start from Manual Operation of Normal Control Switch.Cause Not Determined.Breaker Control Panel Fuses Replaced & Breaker Racked Out & Backed in (← links)
- 05000250/LER-1982-006-03, /03L-0:on 820527,diesel Generator a Tripped at 2,500 Kw.Caused by Malfunctioning Relief Valve in Fuel Oil Supply.Valve Replaced & Generator Retested (← links)
- 05000250/LER-1982-007-03, /03L-0:on 820529,while Performing Containment Leak Insp,Broken Hangers & Broken Snubber Discovered on 3C Steam Generator Blowdown Lines.Caused by Hydraulic Shock to Blowdown Lines (← links)
- 05000250/LER-1982-005-03, /03L-0:on 820519,during Routine Startup,Augmented Surveillance of Hot Channel Factors Not Initiated When Threshold Power (98%) Was Passed.Caused by Procedural Error.Procedure Change Initiated (← links)
- 05000250/LER-1982-004-03, /03L-0:on 820517,during Routine Reactor Startup, Augmented Surveillance of Hot Channel Factors Not Maintained as Required.Caused by Computer Taken Out of Svc During Surveillance Sequence.Personnel Reinstructed (← links)
- 05000250/LER-1982-003-03, /03L-0:on 820301,while Performing Hot Functional Test,High Point Vent in Normal Charging Line to RCS Loop a Cold Leg Found W/Cracked Weld.Stress from Line Vibration Suspected.Crack Repaired by Plugging Vent Line (← links)
- 05000250/LER-1981-013-03, While Making Alterations to Equipment Hatch Ramp,Small Void in Concrete Immediately Below Equipment Hatch Barrel Discovered.Probably Caused by Design Problem.Concrete Void Repaired (← links)
- 05000250/LER-1982-002-03, /03L-0:on 820216,while Performing Periodic Test of Fire Pumps,West Pump Failed to Automatically Start at Min Accepted Starting Pressure.Caused by Trip Switch & Gauge Being Out of Calibr.Recalibr Performed & Pump Tested (← links)
- 05000250/LER-1982-002, Forwards LER 82-002/03L-0 (← links)
- 05000250/LER-1982-001-03, /03L-0:on 820103,fire Watch Patrol Failed to Inspect Inoperable Zone for 3-h Per Tech Spec Requirements.Caused by Misunderstanding by Contractor Personnel Re Agreement to Maintain Insps During Holidays (← links)
- 05000250/LER-1982-001, Forwards LER 82-001/03L-0 (← links)
- 05000250/LER-1981-017-03, /03L-0:on 811122,periodic Test of 3A & 4B High Head Safety Injection Pumps Was Not Completed within Required Time Interval.Surveillance Completed on 811129 & 1206 for 3A & 4B Pumps,Respectively (← links)
- 05000250/LER-1981-017, Forwards LER 81-017/03L-0 (← links)
- 05000250/LER-1981-015-03, /03L-0:on 811112,during Maint on B Emergency Diesel Generator,Both a & B Emergency Diesel Generators Were Inoperable.Caused by Broken Diaphragm in Starting Air Solenoid.Solenoid Replaced & Generator Returned to Svc (← links)
- 05000250/LER-1981-015, Forwards LER 81-015/03L-0 (← links)
- 05000250/LER-1981-016, Forwards LER 81-016/03L-0 (← links)
- 05000250/LER-1981-014-03, /03L-0:on 811016,electrical Penetration Fire Barrier on Switchgear Room Wall Found to Be Nonfunctional. Caused by Incomplete Installation Work.Fire Watch Patrol Established & Personnel Reinstructed Re Maint Procedure (← links)
- 05000250/LER-1981-014, Forwards LER 81-014/03L-0 (← links)
- 05000250/LER-1980-088, Forwards LER 80-088/03L-0 (← links)
- 05000250/LER-1981-012-09, /09T-0:on 811020,voltage Spike Discovered to Have Potential to Cause arc-over & Subsequent Open Circuit at Junction Between Coil Winding & Lead Wire.Caused by Design Deficiency.Affected Coils Replaced During Current Outage (← links)
- 05000250/LER-1981-012, Forwards LER 81-012/09T-0 (← links)
- 05000250/LER-1983-013-03, /03L-0:on 830802,unplanned Gas Release Occurred from Vol Tank to Auxiliary Bldg & Atmosphere.Caused by Improper Valve Lineups.Vol Control Tank Isolated from Gas Analyzer (← links)
- 05000250/LER-1981-013-01, /01T-0:on 810710,void Discovered in Concrete Immediately Below Equipment Hatch Barrel.Caused by Concrete Pour.Engineering Review Underway to Determine Method of Repair (← links)
- 05000250/LER-1981-009-03, /03L-0:on 810420,while Performing Low Power Physics Testing,Reactor Protection Bistables Associated W/ N-43 Found Not in Trip Mode While Instrument Used as Input. Caused by Procedural Inadequacy (← links)
- 05000250/LER-1981-009, Forwards LER 81-009/03L-0 (← links)
- 05000250/LER-1981-011-03, /03L-0:on 810506,two Electrical Penetration Fire Barriers Found Nonfunctional During Implementation of Surveillance Per Tech Specs.Caused by Incomplete Installation.Personnel Readvised of Fireproofing Procedure (← links)
- 05000250/LER-1981-011, Forwards LER 81-011/03L-0 (← links)
- 05000250/LER-1978-015-03, /03L-0 on 781010:19 Accessible Safety Related Snubbers Were Replaced One at a Time W/Mechanical Snubbers (← links)
- 05000250/LER-1978-015, Forwards LER 78-015/03L-0 (← links)
- 05000250/LER-1980-002, Forwards LER 80-002/03L-0 (← links)
- 05000250/LER-1978-018-03, /03L-0 on 781231:A Auxiliary Feedwater Pump Had Seized Shaft.Possibly Due to Overheating,Caused by Steam Leakage on Feedwater Past Sys Valves (← links)
- 05000250/LER-1978-018, Forwards LER 78-018/03L-0 (← links)
- 05000250/LER-1978-017, Forwards LER 78-017/03L-0 (← links)
- 05000250/LER-1979-023-03, /03L-0 on 790701:during Power operation,3B Charging Pump Experienced Package Failure & Excessive Seal Leakage.Caused by Failure of Primary & Secondary Packing. Packing Was Replaced & Pump Tested (← links)
- 05000250/LER-1979-023, Forwards LER 79-023/03L-0 (← links)
- 05000250/LER-1979-016-03, /03L-0 on 790429:high Level Alarm Annunciated. Caused by Instrument Drift of Tech Spec Min & High Level Alarms & Digital Level Indicator Transducer.Instruments Recalibr (← links)
- 05000250/LER-1979-016, Forwards LER 79-016/03L-0 (← links)
- 05000250/LER-1979-015-03, /03L-0 on 790426:B Emergency Diesel Generator Failed Loading Acceptance Criteria.Caused by Cracked half-inch Nipple to Fuel Pump Which Resulted in Partial Fuel Starvation.Nipple Replaced & Old Nipple Reanalyzed (← links)
- 05000250/LER-1979-015, Forwards LER 79-015/03L-0 (← links)
- 05000250/LER-1979-014-03, /03L-0 on 790424:ready to Start Light on B Emergency Diesel Generator Engine Control Panel Failed. Caused by Vibration of Lamp Socket.Tests Under Way to Determine If Neon Unit Would Be Better Suited (← links)
- 05000250/LER-1979-014, Forwards LER 79-014/03L-0 (← links)
- 05000250/LER-1979-001-31, /031-0 on 790213:A Fire Pump Found to Be Inoperable.Caused by Improper Operation of Power Supply Breaker.Procedural Methods Implemented to Ensure That Fire Pump Power Is Verified After Each Shift (← links)
- 05000250/LER-1979-001, Forwards LER 79-001/031-0 (← links)
- 05000250/LER-1979-019-03, /03L-0 on 790515:during Power Operation,Fewer than Three Required Intake Cooling Water Pumps Were Operable. Caused by Debris at Pump Suction Well.Pump Backflushed & Tested Satisfactorily (← links)
- 05000250/LER-1979-019, Forwards LER 79-019/03L-0 (← links)
- 05000250/LER-1979-021-01, /01T-0 on 790626:NSSS Vendor Notified Util of Potential Level Bias Which Could Delay Reactor Trip & Feedwater Initiation or Cause False Level Indications. License Amend Will Be Proposed to Increase Sys Setpoint (← links)
- 05000250/LER-1979-021, Forwards LER 79-021/01T-0 (← links)
- 05000250/LER-1979-022-01, /01T-0 on 790626:loss of 3B 4160 V Bus Would Not Result in Automatic Transfer of Shared D Motor Ctr to Alternative Supply from 4A 4160 V Bus.Operating Procedures Are Being Revised to Correct Situation (← links)
- 05000250/LER-1979-022, Forwards LER 79-022/01T-0 (← links)
- 05000250/LER-2018-001, Inoperable Containment Purge Exhaust Penetration (← links)
- 05000250/LER-2018-002, As-Found Cycle 29 Main Steam Safety Valve Setpoints Outside Technical Specification Limits (← links)
- 05000250/LER-2077-005, Letter Request to Amend Appendix a of Facility Operating Licenses. Proposal Submitted to Satisfy Commitment Made in Reportable Occurrence Report 250-77-5 of 05/02/1977 (← links)
- 05000250/LER-2076-003, Correction to Licensee Event Report Which Occurred on 5/17/1976 by Correcting Steam Generator 4 to Steam Generator 4C on Event Description (← links)
- 05000250/LER-2075-001, Reporting Unusual Event No. 251-75-1 of Revised ECCS Analysis, for Value for Peak Clad Temperature Is in Error (← links)
- 05000250/LER-2077-251-07, Pressurizer Heatup Rate (← links)
- 05000250/LER-1979-020, Has Been Cancelled (← links)
- 05000250/LER-1980-008, Forwards LER 80-008/01X-1,updating 800519 Initial Rept (← links)
- 05000250/LER-1999-001-02, :on 990623,manual RT from 100% Power Following Multiple Control Rod Drops Was Noted.Caused by Manual Action Taken by Reactor Control Operator.Inspected & Repaired Stationary Gripper Regulating Cards.With (← links)
- 05000250/LER-1998-007-02, :on 981020,containment Purge Supply,Valve Opened Wider than TS Limit.Caused by Improper Setting of Mechanical Stops.Incorporated Improved Standard Method of Measuring Angular Valve Position Into Sp.With (← links)
- 05000250/LER-1998-004-02, :on 980921,automatic Reactor Trip Occurred. Caused by Inadequate re-correlation of Intermediate Range Neutron Flux Instrumentation Reactor Trip Bistable. Enhanced Applicable Plant Procedures.With (← links)
- 05000250/LER-1998-003-02, :on 980619,discovered That Auxiliary Feedwater Sys Was Inoperable Due to Inadequate Inservice Testing of Valves.Caused by Misunderstanding of Testing Criteria.Util Revised Procedures & Verified Operability of Valves (← links)
- 05000250/LER-1998-003, Forwards LER 98-003-00 Re 980619 Discovery That Auxiliary Feedwater Sys Was Inoperable Due to Inadequate Inservice Testing of Check Valves (← links)
- 05000250/LER-1997-007, :on 970730,automatic Reactor Trip Occurred Due to Closure of B Msiv.Caused by Failed BFD22S Relay.Six Relays on 3A,3B & 3C MSIVs Were Replaced & Implemented Plant Change to Disable Electronic Trip Function on 3 AFW Pumps (← links)
- 05000250/LER-1997-007-01, Forwards LER 97-007-01 Re 970730 Automatic Reactor Trip That Occurred Due to Closure of B Msiv.Rept Is Being Submitted Per 10CFR50.73 (← links)
- 05000250/LER-1998-002-02, :on 980513,discovered Potential LOCA-initiated Electrical Fault Which Places ECCS Outside Design Basis. Caused by Inadequate Review of Effect on non-safety Circuit failures.Re-powered PC-*-600A Relays (← links)
- 05000250/LER-1998-002, Forwards LER 98-002-00 Re 980513 Discovery of Potential LOCA-initiated Electrical Fault Places Which Could Place ECCS Outside Design Basis (← links)
- 05000250/LER-1997-009, :on 971114,discovered That CR Console Switch for 3B SGFP Was Not in Start Position.Caused by Inadequate Procedural Guidance.Revised Procedures 3/4-OP-074,informed Personnel of Event & Performed Walkdown of CR (← links)
- 05000250/LER-1997-009-01, Forwards LER 97-009-01 Re Discovery That CR Console Switch for 3B SGFP Was Not in Start Position.Ler Is Being Revised to Include Attachment Providing Simplified Auxiliary Feedwater Initiation Logic Diagram for Loss of SGFPs (← links)
- 05000250/LER-1998-001-02, :on 980216,manual Reactor Trip Occurred Due to Loss of Turbine Control Oil Pressure W/Steam Leak in Auxiliary Feedwater Steam Supply Piping.Auxiliary Governor Maint Instructions Will Be Revised (← links)
- 05000250/LER-1997-008-01, :on 970909,containment Sump Debris Screens Outside Design Basis Due to Stress Damage Was Discovered. Caused by Inadequate Procedural Guidance & Personnel Error. Discrepancies Found on Screens Corrected (← links)
- 05000250/LER-1997-006-02, :on 970722,manual Reactor Trip Occurred Due to Failed Rod Control Power Supplies.Replaced Twelve Power Supplies in Rod Control Logic & Power Cabinets (← links)
- 05000250/LER-1997-005-01, :on 970618,RCP Oil Collection Sys Was Found Outside Design Basis.Caused Because Design Did Not Consider Component Parts to Be Potential Leakage Sources.Entire RCP Oil Collection Sys Was Reviewed (← links)
- 05000250/LER-1997-003-01, :on 970410,mode Changed W/O Meeting Requirements of TS 3.0.4 Due to Inadequate Procedural Guidance.Night Order Was Issued to Inform Personnel That S/G Blowdown Keylock Switches Were Left in Drain (← links)
- 05000250/LER-1997-004-01, :on 970411,auxiliary Feedwater Automatic Start Upon Trip of All Main Feedwater Pumps,Occurred.Caused by Mispositioned Valve Closing.Valves Listed as Inappropriately Positioned Were Repositioned (← links)
- 05000250/LER-1997-002-01, :on 970303,manual Reactor Trip Following Rod Control Urgent Failure Alarm Occurred.Caused by Phase Failure Detection on Stationary a Circuits of 2BD Rod Control Cabinet.Air Conditioning Replaced (← links)
- 05000250/LER-1997-001-01, :on 970118,missed Surveillance on CR Position Verification Occurred Due to Inoperable Rod Deviation Monitor.Faulty Circuit Common Connection Was Corrected & Rdm Operability Was Restored (← links)
- 05000250/LER-1996-004, :on 970107,identified Three Instances of Inadequate Surveillance Testing.Caused by Inadequate Surveillance Procedures.Surveillance Procedures Revised (← links)
- 05000250/LER-1996-004-03, Forwards LER 96-004-03 Re TS Surveillance Procedure Review for Identification of Inadequate Surveillance Testing,Per GL 96-01 (← links)
- 05000250/LER-1996-012-01, :on 961204,determined Containment Average Temp Being Determined Based on Only Two Temp Elements Instead of Three as Required by Tss.Caused by Log Only Requiring One Entry.Log Revised (← links)
- 05000250/LER-1996-011-01, :on 961009,potential for Overpressurizing Post Accident Containment Vent Filter Housings Occurred.Caused by Improper Change Mgt.Monitoring Sys Operating Procedures Revised (← links)
- 05000250/LER-1996-010-01, :on 960924,manual Reactor Shutdown Occurred. Caused by Failed Rod Control Sys Regulation Card in 2AC Power cabinet.2AC Power Cabinet DC Power Supplies,Cabling & Connectors Checked (← links)
- 05000250/LER-1996-009-01, :on 960729,failed to Reflect Heavy Load Design Info in Procedural Controls.Caused by Failure to Incorporate 1982 Procedure Changes.Suspended Lifting of Heavy Loads & Took Turbine Bldg Crane OOS (← links)
- 05000250/LER-1996-008, :on 960521,surveillance Method for Testing Emergency Diesel Generators (EDG) Determined Inadequate. Caused by Personnel Error.All Four EDGs Rapid Start Tested & EDG Surveillance Procedures Modified (← links)
- 05000250/LER-1996-007, :on 960329,inadvertent ESF Actuation Occurred During Refueling Outage Due to Cognitive Personnel Error. Personnel Involved Counseled & Integrated Safeguards Test Procedures Being Revised (← links)
- 05000250/LER-1996-006, :on 960327,manual RT Occurred Due to 3C Transformer Lockout & Loss of 3B SG Mfp.Replaced SAM Timer Relay in 3AC16 (← links)
- 05000250/LER-1996-005, :on 960326,certain Safety Injection Accumulator Filled Evolutions Resulted in cross-tied Configuration.C/A: Night Order Written & Operations Procedure 3/4-OP-064 Revised (← links)
- 05000250/LER-1996-003, :on 960222,two Arpi Inoperable & TS 3.0.3 Entered.Proposed License Amend Submitted to Revise Allowed Misalignment from +/-12 Steps to =/-18 Steps Between Arpi & Dpi at Less than 90% Power (← links)
- 05000250/LER-1996-002, :on 960209,automatic Turbine Trip/Rt Occurred Due to High SG Level.Caused by Personnel Error.Replaced Both Hinge Pins on B SGFP Discharge Check Valve (← links)
- 05000250/LER-1996-001, :on 960131,intake CWS Flow Rates Found W/ Potential to Be Less than Required by Design Basis.Caused by Influx of Aquatic Grass & Algae Onto Basket Strainers of Icw Flow Path.Mechanically Cleaned Strainers (← links)
- 05000250/LER-1995-007-01, :on 951017,manual RT Occurred Following Drop of Four Control Rods.Caused by Water Intrusion Into Rod Control Power Cabinet 2BD.Inspected Control Power Cabinet 2BD for Other Water Damage (← links)
- 05000250/LER-1995-006-01, :on 950913,analysis Showed That CCW Exchangers Susceptible to Damage Due to flow-induced Vibration.Ccw Sys Has Been Flow Balanced to Closer Tolerances (← links)
- 05000250/LER-1995-005-01, :on 950818,containment Pressure Testing Procedure Resulted in Inhibiting Both Trains of Containment Pressure from Initiated Esf.Revised Procedure to Require Testing of Each Train Separately (← links)
- 05000250/LER-1994-005, :on 941103,both Units Outside Design Basis Due to Design Defect in Safeguards Bus Sequencer Test Logic. Resumed Monthly Manual Testing of Sequencer (← links)
- 05000250/LER-1994-003-03, :on 940720 & 21,util Discovered That Several Required Valve Stroke Time Surveillances Had Not Been Performed.Caused by Personnel Error.Personnel Reassigned & Procedures and Surveillance Tracking Software Enhanced (← links)
- 05000250/LER-1995-004, :on 950407,unit Being Shutdown to Investigate Recurring non-urgent Failure Alarms from Redundant Rod Control Power Supplies.Reactor Manually Tripped.All Four PS-3 Power Supplies Replaced (← links)
- 05000250/LER-1995-003, :on 950309,intake Cooling Water Flow Rate Through CCW Heat Exchangers Fell Below Assumed Design Basis. Caused by an Influx of Aquatic Grass & Algae Onto Basket Strainers.Strainers Cleaned (← links)
- 05000250/LER-1995-002, :on 950215,inadequate Definition of Loops Filled Resulted in Units in Condition Prohibited by Ts. Issued TS Position Statement to Define Term Loops Filled as Used in TS 6.4.1.1.4 (← links)
- 05000250/LER-1994-006-03, :on 941226,C Main Feedwater Control Valve Failed Closed,Causing Reactor & Turbine Trips.Caused by Loose Screw Terminal Connection.I/P Transducers Replaced W/ New Model W/Different Design Wire Connection (← links)
- 05000250/LER-1994-005-03, :on 941103,design Defect in Safeguards Bus Sequencer Test Logic Places Both Units Outside Design Basis. Caused by 3A Sequencer Failed to Respond as Expected to Opposite Unit SI Signal (← links)
- 05000250/LER-1994-004-03, :on 941103,Unit 3 Outside Design Basis Due to Two of Three Required Safety Injection Pumps Inoperable. Control Switches for 3A & 3B Safety Injection Pumps Immediately Returned to Automatic (← links)
- 05000250/LER-1994-001, :on 940119,three Surveillance Failures Were Caused by Failure of Solenoids to Change Position When de-energized.Changed Solenoid Valves from de-energize to Actuate to Energize to Actuate Configuration (← links)
- 05000250/LER-1994-002-03, :on 940505,spurious Actuation of 3A Safety Injection Signal Occurred.Caused by Intermittent seal-in Contact Failure of Block relay.SIB-1 Relay Was Replaced & System Tested to Demonstrate Operability (← links)
- 05000250/LER-1994-001-01, :on 940119,failure of SV-4-2924 to Fully Change Position Occurred Due to Failure of SVs to Change Position When de-energized.Normally Energized SVs Being Replaced W/ Normally de-energized Valves (← links)
- 05000250/LER-1993-006-02, :on 930930,reactor Trip Signal & Reactor Trip Breakers Opened.Caused by Faulty High Voltage Power Supply. Faulty Power Supply Replaced,Source Range Channel Recalibrated & Channel Returned to Svc (← links)
- 05000250/LER-1993-001, :on 930115,Westinghouse Notified Util That Wet Annular Burnable Absorber Assemblies Not Mfg Per Design Specs.Caused by Failure to Translate Design Requirement to Drawing Absorber Design Modified (← links)
- 05000250/LER-1993-005-01, :on 930325,discovered That Setpoint for Overpressure Mitigating Sys Outside Limiting Design & Licensing Bases When RCS Is Water Solid.Caused by Erroneous Pressure Differential.Controls Instituted (← links)
- 05000250/LER-1993-004-01, :on 930324,notified That an Hourly Fire Watch Patrol Had Not Been Performed in Violation of Ts.Caused by Inadequate Training of Fire Watch Personnel.All Fire Watch Personnel Will Be Retrained Using New Manual (← links)
- 05000250/LER-1993-001-02, :on 930114,Westinghouse Notified Util That Wet Annular Burnable Absorber Assemblies Not Mfg Per Design Specs.Caused by Failure to Translate Design Requirement to Drawing.Absorber Design Modified (← links)
- 05000250/LER-1993-002-01, :on 930115,small Steam Leak Discovered on Abandoned Pressurizer Spray Valve Bypass Line.Caused by Welders Failing to Ensure Adequate Pullback of Pipe Cap.New Pipe Cap Welded on & Faulted Line Removed (← links)
- 05000250/LER-1993-003, :on 930116,discovered That Manual Discharge Valves of Both Trains of Containment Spray Sys Isolated While in Mode 4.Caused by Communication Errors.Night Order Issued Re Proper Procedure Use (← links)
- 05000250/LER-1992-014, :on 921125,small Steam Leak Discovered on Abandoned Bellows Rupture Telltale Line on Pressurizer Spray Valve.Caused by Inappropriate Application of Matl from Which Cap Fabricated.Pipe Cap Replaced (← links)
- 05000250/LER-1992-013, :on 921116,during Preparations for Emergency Diesel Generator Load Rejection Test Lockout of 3A 4 Kv Safeguards Bus Occurred Due to Incorrect Installation of Stationary Contact.T Bar Removed (← links)
- 05000250/LER-1992-012, :on 921031,station Personnel Discovered Unit 3 Airlock to Atmosphere Vent Valve Opened.Caused by Personnel Error.Procedure Revised,Providing Post maint,pre-refueling Verification & Associated Training (← links)
- 05000250/LER-1992-011-01, :on 921008,Unit 3 Source Range Neutron Detector N-31 Declared Out of Svc.Caused by Lack of Design Info/Plant Procedures Which Dictate Proper Gasket Matl.Source Range Neutron Detectors N-31 & N-32 Replaced (← links)
- 05000250/LER-1992-010-01, :on 921002,containment Ventiliation Isolation & Control Room Ventilation Isolation Occurred Due to Spurious Signal.New R11/R12 Skid Being Installed for Unit 3 & Will Be Tested for Sensitivity (← links)
- 05000250/LER-1992-008, :on 920723,discovered That Analog Channel Operational Test for Overpressure Mitigation Sys Did Not Check & Adjust Setpoint,Per TS 4.4.9.3.1.Caused by Inadequate Procedure.Procedures Revised (← links)
- 05000250/LER-1992-007, :on 920716,discovered That Valve & Motor Operator Position for RWST Outlet Valve Not Verified When Unit in Mode 5 or 6.Caused by Less than Adequate Procedure.Checkoff Procedure Revised (← links)
- 05000250/LER-1992-006, :on 920610,discovered That Recirculation of Waste Monitor Tank,Prior to Liquid Release,Not Conducted Per TS & Tank Recirculated to Less than One Tank Vol.Caused by Overestimation of Flow Rate.Calibrs Verified (← links)
- 05000250/LER-1992-003-01, :on 920323,identified Improper Pressure Transmitter Calibration.Caused by Inadequate Procedures. Transmitters Locations Will Be Checked & Calibration Procedures Will Be Revised (← links)
- 05000250/LER-1992-004, :on 920330,QA Auditor Determined That Vendor Lab Used Incorrect ASTM Test During 920130 Analyses of Fuel Oil.Procedure 0-NCSP-022.3, Receiving Fuel Oil Shipments Revised (← links)
- 05000250/LER-1992-005, :on 920420,two Main Steam Isolation Valves Declared Inoperable.Caused by Personnel Error.Msivs a & B Were Returned to Svc in Accordance W/Procedures as Soon as Valve Misalignment Was Identified (← links)
- 05000250/LER-1992-003-02, :on 920322,discovered That Plant Operated W/O Proper Transmitter Calibr Prior to 910826,per NRC Info Notice 91-075.Caused by Inadequate Procedures.Calibr Procedures Will Be Revised (← links)
- 05000250/LER-1992-002-02, :on 920319,steam/feedwater Flow Mismatch Bistables Not Tripped within 1 H Action Statement When Steam Flow Testing in Progress.Caused by Personnel Error.Procedure Revised to Add Bistables (← links)
- 05000250/LER-1991-010, :on 910123,TS 3/4.7.7 Violated by Inadequate Leak Testing of Fe-55 Source.Caused by Test Instruments Lack of Sensitivity.Proper Leak Tests Performed on Sealed Sources & Purchase/Test Procedures Revised (← links)
- 05000250/LER-1992-001-02, :on 920210,concluded That Operability of Switchgear w/racked-down Breakers Could Not Be Asssured. Caused by Incomplete Info Re Seismic Qualification of Switchgear.Procedures Revised (← links)
- 05000250/LER-1991-011, :on 911011,Appendix R Safe Shutdown Analysis Design Inadequacy Identified Due to Failure to Recognize Potential for Spurious Actuation of Auxiliary Relay.Manual Action List in Safe Shutdown Analysis Revised (← links)
- 05000250/LER-1991-012, :on 911007,delta-T Factor in Overpower Delta-T & Overtemp Delta-T Found Set at Design Value of 56.1 F Instead of TS Value.Caused by Procedure Error.Values Changed & Plant Procedures Developed (← links)
- 05000250/LER-1991-013, :on 911206,health Physics Notified That Small Amount of Liquid Leaked Onto Ground Where Vehicle Parked. Caused by Inadequate Container Lower Door Seal.Door Seals Caulked W/Flexible Silicon Sealant (← links)
- 05000250/LER-1991-009, :on 911018,axial Flux Difference Discovered Outside Tech Spec Target Band Limits for More than 15 Minutes.Caused by Inadequate Procedure.Ts Amend Request Submitted & Procedure Revised (← links)
- 05000250/LER-1991-008, :on 911003,reactor Tripped Manually Due to Loss of Main Turbine Generator Load.Caused by Mechanical Failure of Piping Nipple in Control Oil Sys Due to Pipe Vibration. Nipples Will Be Replaced During Next Outage (← links)
- 05000250/LER-1991-007, :on 910925,detector Cables for ex-core Nuclear Instrument intermediate-range Channel N-35 Found Disconnected.Caused by Lifted Leads Between N-35 Drawer & Detector.Maint Policy Issued (← links)
- 05000250/LER-1991-006, :on 910921,RWST Had Less than 320,000 Gallons of Borated Water Required by TS 3/4.5.4 & Safety Injection Pumps Not Aligned to Operable Flow Path.Caused by Procedural Inadequacy.Pumps Realigned (← links)
- 05000250/LER-1991-005-02, :on 910830,3A Component Cooling Water (CCW) Pump Started Automatically on Low Pressure Due to Personnel Error.Training Brief Will Be Written & Distributed to Appropriate Personnel to Discuss Subj LER (← links)
- 05000250/LER-1990-020, :on 901013,surveillance Interval of Tech Spec 4.8.2.1 Exceeded Due to Personnel Error.Personnel Involved Counseled & Procedure 4-OSP-201.3 Revised (← links)
- 05000250/LER-1991-004-03, :on 910822,inadvertent Start of 3A Diesel Generator Occurred.Caused by Inadequate Communication Between Startup Personnel & Licensed Operators.Procedures Revised & Personnel Trained (← links)
- 05000250/LER-1991-003-03, :on 910724,main Generator Lockout Signal Tripped Generator Output Breaker,Losing Power to Vital Busses.Caused by Inadequate Contact Between Potential Transformer Drawer Stabs & Wipes (← links)
- 05000250/LER-1991-002-02, :on 910723,reactor Protection Sys Actuation Occurred.Caused by Closing of Reactor Trip Breakers W/O Ensuring Planned Activities Would Affect Only One Protection Channel.Personnel Awareness Increased (← links)
- 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 (← links)
- 05000250/LER-1990-022, :on 901114,discovered That Tech Spec Required Fire Protection Surveillance Not Performed within Max Allowed Time Interval.Caused by Inadequate Administrative Controls.Memo Issued (← links)
- 05000250/LER-1990-021, :on 901018,determined That Length of Time CCW Headers Split for Movement of Heavy Loads Exceeded Appropriate Action Statement Time Limit That Should Have Been Imposed (← links)
- 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 (← links)
- 05000250/LER-1990-018, :on 900917,unit Missed Fire Protection Surveillance on Switchgear Room Louver Sprays (← links)
- 05000250/LER-1988-026, :on 881107,unit Violated FSAR Design Requirements Re Hurricane Flood Protection (← links)
- 05000250/LER-1990-003, :on 900220,determined That Spent Fuel Pool 3B Shaft Failure Resulted in Damage to Pump Mechanical Seal & Release of Borated Contaminated Water.Procedure O-PMM-061.1 Revised (← links)
- 05000250/LER-1990-017, :on 900817,fire Protection Surveillance Missed Due to Personnel Error.Missed Surveillance Discovered During QA Insp.Procedure O-SME-016.4 Revised to Include App a Fire Dampers (← links)
- 05000250/LER-1990-016, :on 900801,Tech Spec 3.0.1 Entered to Repair Boric Acid Filter Discharge Isolation Valve 3-348.Caused by Exposure to Higher than Normal Temps.Diaphragm Replaced on Valve & Wrap of Heat Tracing Rerouted (← links)
- 05000250/LER-1990-011, :on 900609,hi-hi Steam Generator Water Level Turbine Trip & Subsequent Reactor Trip Occurred.Caused by Malfunction of Feedwater Regulator hand-auto Station Open Switch 3C for Valve Controller FC-3-498F (← links)
- 05000250/LER-1990-015, :on 900720,roving Fire Watch Failed to Complete Tech Spec Required Rounds.Caused by Cognitive Personnel Error.Individual Escorted from Site & Access Authorization to Site Terminated (← links)
- 05000250/LER-1990-014, :on 900627,plant Mgt Declared Both PORV Block Valves Inoperable.Caused by Unconservative Min Required Thrust Values Specified by Valve.Util Plans to Readjust PORV Block Valve Operator Torque Switches (← links)
- 05000250/LER-1990-013, :on 900615,reactor Trip Occurred When Operator Raised Power Above 10% W/Turbine in Tripped Condition.Caused by Personnel Error.Event Reviewed W/Operations Personnel & Operator Training in Selfchecking Initiated (← links)
- 05000250/LER-1990-012, :on 900613,determined That Use of Single Reset Pushbutton for Both Trains of Containment Spray Outside Design Basis of Plants.Caused by Inadequate Design.Procedure Change Requests Generated (← links)
- 05000250/LER-1990-010, :on 900518,Mode 3 Entered W/O Having at Least One Channel of Reactor Vessel Level Monitoring Sys in Svc. Caused by Personnel Error.Heated Junction Thermocouple Breakers Closed & Procedures Revised (← links)
- 05000250/LER-1990-001, :on 891222 & 900112,liquid Effluent Radiation Monitor R-18 Failed & Ratemeter Did Not Have Display Indication.Caused by Control Circuit Malfunction.Low Voltage Power Supply Processor & Timer Cards Replaced (← links)
- 05000250/LER-1990-009, :on 900519,breathing Air Containment Isolation Valve CV-3-6165 Found Pinned Open While in Mode 3.Caused by Inadequate Procedural Controls.Valve CV-3-6165 Placed in Correct Normal Valve Position (← links)
- 05000250/LER-1989-020, :on 891223,reactor Trip Occurred Due to Closure of MSIV 4A.Caused by Corroded Terminal Board Installed in Incompatible Svc Environ.Procedures Revised to Improve Installation of Boxes (← links)
- 05000250/LER-1989-013, :on 890910,boric Acid Transfer (Bat) Pump Not Declared Out of Svc Prior to Refilling Seal Pot.Caused by Noncognitive Error by Util Maint Personnel.Bat Pump 3B Realigned (← links)
- 05000250/LER-1989-021, :on 890721,discrepancies in Process Control Program Identified.Caused by Document Not Specifying That Containers Must Be Among Those Listed in Process Control Program.Operating Procedure 11550.48 Revised (← links)
- 05000250/LER-1990-006, :on 900406,control Room Ventilation Sys for Common Control Room of Units Tripped While Performing Procedure TP-584.Caused by Personnel Error.Individual Counseled (← links)
- 05000250/LER-1990-007, :on 900408,CCW Pump 3B Automatically Started Due to Low Pump Discharge Header Pressure.Caused by Inadequate Procedural Controls in Operating Surveillance Procedure 3-OSP-030.7.Procedures Changed (← links)
- 05000250/LER-1989-014, :on 890912,discovered That Component Cooling Water Flow Rate to Emergency Containment Coolers Below DBA Requirements.Caused by Inadequate Administrative Controls. Mechanical Stops Readjusted to Prior Setting (← links)
- 05000250/LER-1990-005, :on 900316,health Physics Shift Supervisor Found to Be Contaminated While Exiting Containment Bldg. Cause Not Yet Identified.Frequency of Hot Particle Surveys for Check Valve Tent Increased (← links)
- 05000250/LER-1990-004, :on 900306,surveillance Test of Emergency Diesel Generator Not Completed.Caused by Misinterpretation by Sys Engineer of Safety Evaluation for 4,160 Volt Bus Outage.Personnel Reinstructed (← links)
- 05000250/LER-1990-003-01, :on 900220,mechanical Seal Failure Occurred on 3B Spent Fuel Pool Cooling Pump.Caused by Fatigue Failure Due to Formation of Notch Which Acted as Stress Intensifier. Spent Fuel Pump 3A Aligned as Primary Pump (← links)
- 05000250/LER-1990-002, :on 900118,discovered That post-maint Testing Not Performed on Phase a Containment Isolation Valve CV-3-6275B After Adjusting Valve Stem Packing.Caused by Personnel Error.Personnel Counseled (← links)
- 05000250/LER-1989-019, :on 891218,determined That Tech Spec 3.14.5 Action Statement Not Met on 891201 When Process Radiation Monitor Alarmed in Control Room & Personnel Evacuated Auxiliary Bldg W/O Establishing Fire Watch (← links)
- 05000250/LER-1989-017, :on 890125,Tech Spec 3.11.2 Requirement to Maintain Complete Inventory of Licensed Radioactive Matls at All Times Not Met.Caused by Inadequate Procedures. Procedures Revised & New Procedures Issued (← links)
- 05000250/LER-1989-016, :on 891110,determined That Catastrophic Failure of Reactor Coolant Pump 3A Motor Lube Oil Sys Would Result in Collection Tank Overflowing.Caused by Inadequate Design.Addl Tank Capacity Will Be Provided (← links)
- 05000250/LER-1989-015, :on 891019,charging Pumps Declared Inoperable Due to Inability to Maintain Pressurizer Level w/45 Gpm Letdown Orifice in Svc.Caused by Inadequate Troubleshooting. Suction/Discharge Valves for Pump Overhauled (← links)
- 05000250/LER-1988-018, :on 880822,refueling Water Storage Tank Supply to ECCS Isolated from Both Trains of Eccs,Including RHR, Containment Spray & Hpsi.Caused by Procedure Inadequacy. Procedures Revised to Exclude Monthly Cycling (← links)
- 05000250/LER-1988-015, :on 880729,valves in Flow Path Between Hydrogen Monitors & Containment Bldg Not Verified in Proper Position. Caused by Inadequate Administrative Controls.Procedures Revised to Verify Valve Position (← links)
- 05000250/LER-1989-012, :on 890707,discovered Liquid Scintilation Counter W/Internal Calibr Source Not Leak Tested Per Tech Specs.Caused by Inadequate Administrative Control. Administrative Procedure Issued on 890630 (← links)
- 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 (← links)
- 05000250/LER-1989-010, :on 890616,breaker Tripped Causing Power Loss to Rack 66 & Automatic Isolation of Containment & Control Room Ventilation Sys.Caused by Overload of Breaker 3P08-19. Clearance Tag Taped Across Ac Outlet (← links)
- 05000250/LER-1989-011, :on 890617,two Safeguards Actuations Occurred. Caused by Damaged Switch Contact Blocks & Personnel Error. Switch Contact Blocks Replaced & Personnel Counseled (← links)
- 05000250/LER-1989-006, :on 890312,limiting Condition for Operation for Intake Cooling Water Pumps Not Met.Caused by Train B Intake Cooling Water Pump Taken Out of Svc While Train a Emergency Diesel Generator Inoperable (← links)
- 05000250/LER-1989-004, :on 890210,reactor Trip Occurred.Caused by Defective Procedure During Steam Generator Protection Channel Testing.Procedure OP 14004.1 Revised to Correct Errors (← links)
- 05000250/LER-1989-005-01, :on 890215,auxiliary Feedwater Flow Automatically Initiated Following Attempt to Start Steam Generator Feedwater Pump.Caused by Wiring Error on Starting Circuit Relay.Wiring Error Corrected (← links)
- 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 (← links)
- 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 (← links)
- 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 (← links)
- 05000250/LER-1988-032, :on 881202,personnel Error Resulted in Loss of Power to Vital Instrument Bus & Isolation of Stated Ventilation Sys.Operator Counseled.Spare Inverter Relabeled as Spare & Procedures Revised (← links)
- 05000250/LER-1988-028, :on 881117,control Room Ventilation Sys Shifted to Recirculation Mode While Conducting Test of Channel B Air Intake Radiation Monitor RAI 6642.Caused by Maladjustment of Monitor During Calibr.Instruction Revised (← links)
- 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 (← links)
- 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 (← links)
- 05000250/LER-1988-011, :on 880529,discovered That Diesel Oil Storage Tank Isolation Valve 70-003 Locked Closed.Caused by Personnel Error.Technician Disciplined & Info Bulletin Re Work Controls & Procedural Compliance Issued (← links)
- 05000250/LER-1988-010, :on 880528,containment Ventilation & Control Room Ventilation Isolation Occurred While Containment Radiation Monitor Setpoint Being Checked.Drawer for Monitor R-11 Initiated Signals.Drawer Replaced (← links)
- 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 (← links)
- 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 (← links)
- 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 (← links)
- 05000250/LER-1987-017, :on 870528,29 & 0603,normal & Emergency Boration Flow Paths Lost.Caused by Damaged in-board Mechanical Seal on Boric Acid Transfer Pumps 4B.Mechanical Seal Inspected & Repaired (← links)
- 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 (← links)
- 05000250/LER-1987-018, :on 870526,determined That Subsequent to Large Break Loca,Procedures Would Allow Period of Time W/No Safety Injection Flow While Performing Switchover to Cold Leg Recirculation.Procedures Will Be Revised (← links)
- 05000250/LER-1987-015, :on 870522,design Basis Reconstitution Revealed Potential Loss of HVAC in Inverter & Battery Rooms.Caused by Mods to Original Plant Design.Maint & Insp Procedures Implemented for Air Conditioning Units (← links)
- 05000250/LER-1987-014, :on 870519,while Unit in Mode 6,determined That Design Discrepancy Existed in Containment Spray Sys.Caused by Flow Orifice in Discharge Line Not Incorporated in Field. Design Mods Will Be Implemented for Correction (← links)
- 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 (← links)
- 05000250/LER-1987-012, :on 870507,emergency Diesel Generator auto-started Due to Personnel Error in Failing to Lift Clearance Prior to Performing Steps of Procedure.Operator Counseled & Supervisor Briefing to Be Detailed (← links)
- 05000250/LER-1987-011, :on 870312,w/unit in Mode 5,intake Cooling Water Pump 3C Inadvertently Started.Caused by Jarring of Overcurrent Relay HGA 174X During Const.Const Workers Instructed to Use Caution Near Equipment (← links)
- 05000250/LER-1987-010, :on 870306,reactor Manually Tripped Due to Loss of Turbine Load.Caused by dirt-induced Grooves in Stub Shaft of Control Oil Sys.Turbine Control,Lube & Seal Oil Piping Will Be Replaced (← links)
- 05000250/LER-1985-007-01, :on 850221,discovered Plant Procedures Did Not Include All Flowpath Valves Which Should Be Visually Verified Periodically for Position & Functionally Cycled,Per Tech Specs Re Fire Protection Sys (← links)
- 05000250/LER-1984-040, :on 841222,during Load Rejection Tests,Short Duration Spike of 5,000 Volts Occurred on Emergency Diesel Generator.Speed Transients Experienced Acceptable.Generator Tech Specs Will Be Revised by 850401 (← links)
- 05000250/LER-1991-001-04, :on 910103,loss of Water Inventory in Surge Tank for Component Cooling Water Sys Detected.Caused by Through Wall Erosion/Corrosion of Tubes.Tubes Replaced & Addl Suspect Tubes Inspected (← links)
- 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 (← links)
- 05000250/LER-1989-009, :on 890519,design Inadequacy in App R Safe Shutdown Analysis Identified by Util Engineers.Caused by Design Inadequacy.Fire Watches Established for Unit 4 & Will Be Established for Unit 3 (← links)
- 05000250/LER-1988-027, :on 881006,mechanic Found to Be Contaminated When Exiting Containment Bldg.Specific Cause Unidentified. Addl Temporary Controls Implemented & Area Mopped (← links)
- 05000250/LER-1989-008, :on 890320,heat Trace Circuits 8A & 8B on Suction Lines of Boric Acid Transfer Pump Declared Out of Svc.Possibly Caused by Leaking Isolation Valve.Isolation Valve Disassembled for Insp (← links)
- 05000250/LER-1989-007, :on 890316,surveillance for Snubber Missed. Caused by Weakness in Snubber Testing Program.Snubber Removed & Functionally Tested & Replaced W/Spare Snubber.W/ (← links)
- 05000250/LER-1988-030, :on 881202,determined That Safety Injection Accumulator Level Tech Spec Limits Possibly Exceeded During Operation.Caused by Errors in Design Which Installed Transmitters.Transmitters Being Replaced (← links)
- 05000250/LER-1986-041, :on 860201,RHR Pumps Not in Operation,Per Tech Spec During Refueling Pool Fill During Previous Refueling Outage.Caused by Inadequate Review of Plant Procedures. Administrative Procedure 103.18 Revised (← links)
- 05000250/LER-1988-025, :on 881013,determined That Potential Interaction Existed Between Emergency Diesel Generator Pump Control Sys Which Could Have Prevented Fulfillment of Safety Function.Caused by Inadequate Design (← links)
- 05000250/LER-1988-024, :on 881001,RHR Pump Declared Out Svc Due to Leakage from Pump Seal.Cause Not Identified.Seal Cooler Flushed Prior to Reassembly to Remove Foreign Matl & Installation Technique Revised (← links)
- 05000250/LER-1988-023, :on 880926,chemistry Technician Reported That There Was No Flow Indication to Plant Process Radiation Monitor R-19.Caused by Solids from Steam Generator Blowdown. Sample Flows to R-19 Will Be Monitored (← links)
- 05000250/LER-1988-020, :on 880831,control Room Ventilation Sys Shifted to Recirculation Mode While Conducting Routine Test of Channel B Air Intake Radiation Monitor.Caused by Spurious Actuation Signal.Recirculation Mode Verified (← links)
- 05000250/LER-1988-018-06, :on 880822,determined That Refueling Water Storage Tank Supply to ECCS Isolated from Both Trains of ECCS Sys.Caused by Procedure Inadequacy.Procedure Revised to Exclude Monthly Cycling of Tank Outlet Valves (← links)
- 05000250/LER-1988-019, :on 880822,boric Acid Transfer Pump 3A Declared out-of-svc.Caused by Lack of Visible Water Level & Zero Nitrogen Pressure in Seal Pot & Failure of Pump Seal.Seal Replaced & Pump Returned to Svc (← links)
- 05000250/LER-1988-016, :on 880811,containment Spray Pump out-of-svc for Maint Exceeding Tech Specs Limits.Caused by Lack of Knowledge Re Need for break-in Period for New Bearings. Training Procedures to Be Revised (← links)
- 05000250/LER-1988-017, :on 880815,control Room Ventilation Sys Out of Svc in Excess of Tech Spec Time Limit Due to Intermittent Circuit Failure.Caused by Procedural Deficiency.Bridge Circuit Replaced & Plant Mod in Effect (← links)
- 05000250/LER-1988-014, :on 880714,RCS Leakage Surveillance Not Performed within Required Interval Due to Personnel Error. Note Placed in Night Book Stressing Need to Meet 18-30 H Tech Specs Requirements (← links)
- 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 (← links)
- 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 (← links)
- 05000250/LER-1988-007, :on 880427,3A Intake Cooling Water (Icw) Pump out-of-svc Due to Discharge Pressure Gauge Piping Failure. Caused by Corrosion of Coupling Attaching Pressure Gauge Piping to Icw Discharge Pipe.Piping Repaired (← links)
- 05000250/LER-1988-006, :on 880408,surveillance of Hydrogen & Oxygen Concentration of Inservice Gas Decay Tank Missed.Caused by Personnel Error.Surveillance Incorporated Into Chemistry Primary Daily Worksheet & Personnel Counseled (← links)
- 05000250/LER-1988-005, :on 880415,loss of Flowpath from Boric Acid Storage Tanks to RCS Occurred.Caused by Loose Screw in Motor/Pump Coupling.Boric Acid Transfer Pump 4A Realigned to Provide Boric Acid Flow Path to Unit 3 (← links)
- 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 (← links)
- 05000250/LER-1988-003, :on 880308,containment Ventilation & Control Room Ventilation Isolation Occurred.Caused by Minor Electrical Transient Upon Failure of One Light Filament. Failed Dual Filament Bulb Replaced (← links)
- 05000250/LER-1988-002, :on 880115,RCS Pressure Decreased to 625 Psig & Accumulators Started to Inject.Caused by Defective Controller for Valve PCV-3-455B.Controller Replaced (← links)
- 05000250/LER-1988-001, :on 880113,unit Experienced Turbine Runback Due to Dropped Control Rod Assembly & Manual Subcritical Reactor Trip Occurred When Addl Control Rods Dropped Into Core. Caused by Personnel Error.Personnel Counseled (← links)
- 05000250/LER-1987-034, :on 871229,manual Reactor Trip from Approx 70% Reactor Power Occurred,Caused by Stuck Contacts on Overspeed Controller 20% Underpower Relay.Contacts Freed & Cleaned. Inputs to Relay Satisfactorily Calibr (← links)
- 05000250/LER-1987-033, :on 871225,during Controlled Shutdown,Reactor Tripped When Source Range High Neutron Flux Trip Unblocked & Detector Went Out of Svc W/O Bypassing Trip Signal.Caused by Inadequate Procedure.Procedures Changed (← links)
- 05000250/LER-1987-032, :on 871217,control Room Ventilation Sys & Components Isolated Following Trip of Breaker 3P08-19.Caused by Ground in Field Wiring When One Relay Deenergized.Breaker Reset & Monitors Returned to Svc (← links)
- 05000250/LER-1987-031, :on 871209,control Room Ventilation Isolation Occurred Due to Loss of Power to Containment Radioactive Gas Monitor.Caused by Ground in Blowdown Effluent Radiation Monitor R19.R-19 & Other Drawers Cleaned (← links)
- 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 (← links)
- 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 (← links)
- 05000250/LER-1987-026, :on 871002,discovered That Hydrogen Recombiner Line Inadequately Tested After Piping Mod.Caused by Deletion of Requirement for Testing in Administrative Site Procedure ASP-2.Recombiner Line Tested & ASP-2 Revised (← links)
- 05000250/LER-1987-027, :on 870930,containment Vent Isolation Logic Actuated Due to Radiation Monitor Increase Above Setpoint. Caused by Transport of Contaminated Filter Through Auxiliary Bldg.Procedures Revised to Prevent Recurrence (← links)
- 05000250/LER-1987-024, :on 870913,reactor Controls Manipulated by Nonlicensed Person Under Supervision of Licensed Operator. Caused by Personnel Error.Personnel Counseled (← links)
- 05000250/LER-1987-023, :on 870913,safety Injection Sys Actuation & Subsequent Reactor Trip Occurred.Caused by Component Failure & Personnel Error.Event Response Team Formed to Investigate Causes & Initiate Corrective Action (← links)
- 05000250/LER-1987-025, :on 870914,QA Dept Noted That Surveillance Requirements of Tech Spec 4.1-2 Item 18 Had Not Been Met. Caused by Inadequate Procedure.Procedures 3/4-OSP-201.1 Will Be Revised & Surveillances Performed (← links)
- 05000250/LER-1987-022, :on 870731,operator Demonstrated Known Spurious & Spiking Problem in Nuclear Instrumentation Sys Intermediate Range Channels,By Opening Drawer for Sys. Caused by Faulty Locking mechanism.W/870831 1tr (← links)
- 05000250/LER-1987-021, :on 870701,auto Safety Injection Initiated from Spurious Containment High Pressure Signal.Nitrogen Supply Valve Manipulated to Verify Closed Causing Pressure Spike Thus Actuating Train A.Test Switch Replaced (← links)
- 05000250/LER-1987-020, :on 861211,component Cooling Water HXs for Unit Operated Outside Temp Limitations for Approx 17 H.Continuous Tube Cleaning Capability Will Be Installed & Similar Mods Planned for Unit 4 (← links)
- 05000250/LER-1987-019, :on 870605,discovered That Neither Unit 3 Nor 4 Had Met Surveillance Requirements of Tech Spec 3.10.8. Caused by Failure to Identify Surveillance Requirements Upon Issuance of License Amends.Procedures Revised (← links)
- 05000250/LER-1982-012, Forwards LER 82-012/01T-0 (← links)
- 05000250/LER-1981-010-03, /03L-0:on 810501,component Cooling Water Pump 3A Did Not Start During Routine Equipment Rotation.Caused by Closing Latch Spring in Pump Circuit Breaker Detaching, Preventing Charging of Closing Springs.Breaker Repaired (← links)
- 05000250/LER-1981-010, Forwards LER 81-010/03L-0 (← links)
- 05000250/LER-1981-004-03, During Power Operation Auxiliary Feedwater Pump a Failed to Meet Acceptance Criteria Per Tech Spec 4.10.1.Caused by Damaged Valve Plug. Cause of Damage Not Determined.Stem & Plug Replaced (← links)
- 05000250/LER-1981-004, Forwards Updated LER 81-004/03X-1 (← links)
- 05000250/LER-1981-008-03, /03L-0:on 810416,crack Found in Weld on Drain Line from Charging Sys Downstream of Regenerative Heat Exchanger. Probably Caused by Stress Due to Line Vibration.Defective Area Cut Out,Nipple Shortened & Weld Replaced (← links)
- 05000250/LER-1981-008, Forwards LER 81-008/03L-0 (← links)
- 05000250/LER-1981-007-03, /03L-0:on 810401,during Planned Maint,Disc Stud Nut Discovered Missing from 3A Main Feedwater Check Valve & Pivot Pins Missing from 3A Feedwater Bypass Check Valve. Improved Locking Device Will Be Installed During Outage (← links)
- 05000250/LER-1981-007, Forwards LER 81-007/03L-0 (← links)
- 05000250/LER-1981-006-03, /03L-0:on 810324,rept Not Submitted Per Tech Spec 6.9.2.b.2 When Action Mode of Tech Spec 3.1.5.d Was Entered. Caused by Misinterpretation of Reporting Requirements.Plant in Process of Obtaining Interpretations of Requiremen (← links)
- 05000250/LER-1981-006, Forwards LER 81-006/03L-0 (← links)
- 05000250/LER-1979-003-01, /01T-0:on 791101,NSSS Vendor Identified & Corrected Input Error in Two LOCA Analyses.Caused by Use of Incorrect Method.Procedures Revised (← links)
- 05000250/LER-1978-003-01, /01T-0:on 780324,util Notified by NSSS Vendor That Logic Inconsistency Identified in NRC Approved 10CFR50.46 App K,Eccs Evaluation Model.Cause Not Stated.Review Underway (← links)
- 05000250/LER-1978-003, Forwards LER 78-003/01T-0 (← links)
- 05000250/LER-1978-002-01, /01T-0:on 780324,util Notified by NSSS Vendor That Logic Inconsistency Identified in NRC Approved 10CFR50.46 App K,Eccs Evaluation Model.Cause Not Stated.Review Underway (← links)
- 05000250/LER-1978-002, Forwards LER 78-002/01T-0 (← links)
- 05000250/LER-1979-031, Forwards Updated LER 79-031/03X-1 (← links)
- 05000250/LER-1981-005-01, /01T-0:on 810310,drain Header to Floor of Component Cooling Water Pump & Heat Exchanger Room Backed Up.Caused by Overflow of Laundry Water from Monitor Tank. Laundry Water Transfer Terminated (← links)
- 05000250/LER-1981-005, Forwards LER 81-005/01T-0 (← links)
- 05000250/LER-1979-039-03, Foreign Matl Observed on as Found 3B Steam Generator Tubesheet Photographs.Caused by Piece of Unalloyed Plain Carbon Steel & Steam Generator Tube Plug Skirt.Sys to Monitor Startup Will Be Employed (← links)
- 05000250/LER-1980-024-03, /03L-0:on 801119,flow/feedwater Flow Mismatch W/ Low Steam Generator Water Level in Steam Generator a Caused Reactor Trip.Caused by Broken Valve Stem FCV-3-478 Due to Improper Load Distribution.Stems Replaced (← links)
- 05000250/LER-1980-024, Forwards LER 80-024/03L-0 (← links)
- 05000250/LER-1980-029-03, /03L-0:on 801230,during Power Operation,Boric Acid Transfer Pump 3A Found Leaking Water & Was Subsequently Removed from Svc.Caused by Fluid Leakage Into Sealed Stator Assembly.Pump Repaired & Returned to Svc (← links)
- 05000250/LER-1980-029, Forwards LER 80-029/03L-0 (← links)
- 05000250/LER-1981-001-03, /03L-0:on 810101,while Performing Surveillance on Emergency Diesel Generator B,Loss of Voltage Control Occurred.Caused by Fuse Failure.Fuses Were Replaced.Annual Surveillance Will Include Fuse Checks (← links)
- 05000250/LER-1981-001, Forwards LER 81-001/03L-0 (← links)
- 05000250/LER-1980-028-03, /03L-0:on 801229,dc Ground Experienced on Battery Bus 3B.Caused by Shorted Control Circuit Wiring Between 4160 V Breaker 3AB10 & Local Start Station Due to Burning Out of Breaker Trip Coil.Circuit & Conduit Rerouted (← links)
- 05000250/LER-1980-028, Forwards LER 80-028/03L-0 (← links)
- 05000250/LER-1981-003-01, /01T-0:on 810105,new Coil Assembly in Spare Parts Storage Found to Have Crack in Spool End Plate.Cause Not Stated.One Coil in Svc Found Cracked.Coil Replaced.All New Coils &/Or Relays Will Be Inspected Upon Receipt (← links)
- 05000250/LER-1981-003, Forwards LER 81-003/01T-0 (← links)
- 05000250/LER-1981-002-01, /01T-0:on 810103,during Planned Shutdown,Boric Acid Flowpath from Boric Acid Tanks Found Obstructed.Caused by Reduced Temp Resulting from Failure of One Channel of Heat Tracing Circuit 21.Temp Setpoint Increased (← links)
- 05000250/LER-1981-002, Forwards LER 81-002/01T-0 (← links)