Pages that link to "05000397/LER-2007-001, Regarding Automatic Depressurization System Logic Signal Instrument Inadvertently Disabled"
Jump to navigation
Jump to search
The following pages link to 05000397/LER-2007-001, Regarding Automatic Depressurization System Logic Signal Instrument Inadvertently Disabled:
Displayed 8 items.
- 05000397/LER-2007-001 (redirect page) (← links)
- 05000397/LER-2014-004 (← links)
- 05000397/LER-2004-007 (← links)
- 05000397/LER-2001-002 (← links)
- 05000397/LER-2001-001 (← links)
- IR 05000397/2007003 (← links)
- 05000397/LER-1985-003, Forwards LERs 85-003 & 85-004 Submitted on 850131 W/O Appropriate Signatures.W/O LER 85-003 (← links)
- 05000397/LER-1987-031, Forwards LER 87-031,per 10CFR50.73 (← links)
- 05000397/LER-2024-001, Failure to Track Operability of Requirements of Transversing In-Core Probe Valves (← links)
- 05000397/LER-2021-002-01, Integrated Leak Rate Test (← links)
- 05000397/LER-2021-002, Integrated Leak Rate Test (← links)
- 05000397/LER-2021-001, Breach of Secondary Containment (← links)
- 05000397/LER-1987-021, :on 870703,inadvertent Isolation of Nuclear Steam Supply Shutoff Sys Occurred.Caused by Technician Failure to Have Operations Reset half-trip Logic.Personnel Counseled Re Proper Communications W/Operations (← links)
- 05000397/LER-1987-019, :on 870628,reactor Scram & Partial Containment Isolation Occurred Due to Reactor Protection Sys (RPS) Full Trip.Caused by Concurrent Component Failures in Both RPS Channels.Pressure Switch Replaced (← links)
- 05000397/LER-1986-038, :on 861120,reactor Scram Occurred.Caused by Rapid Decrease in Reactor Water Level Upon Incorrect Alignment of Condensate Cleanup Block Valves & Feedwater Diversion to Empty Line.Operators Counseled (← links)
- 05000397/LER-1986-031, :on 860910,RCIC Inboard Steam Line Isolation Valves Closed on Erroneous RCIC Equipment Area High Temp Signal.Caused by Technicians Inadvertently Connecting Test Equipment to Wrong Circuit.Personnel Counseled (← links)
- 05000397/LER-1986-030, :on 860903,reactor Scram Occurred Due to Low Reactor Water Level.Caused by Reactor Feedwater Pump Trip & Failure of Recirculation Flow Control Valve to Run Back. Preventive Maint Procedure Will Be Written (← links)
- 05000397/LER-1986-035, :on 861101 & 08,emergency Filtration Sys Initiated on High Chlorine Signal.No Root Cause Determined. Chlorine Detectors Will Be Removed After Tech Spec Approval (← links)
- 05000397/LER-1986-034, :on 861017,control Room Emergency Filtration Sys Automatically Initiated on High Chlorine Signal.No Cause Established.Tech Spec Amend Requested to Delete Chlorine Detection Requirements.W/Undated Ltr (← links)
- 05000397/LER-1986-032, :on 861007,review of Plant Records Revealed That Control Rod Block intermediate-range Neutron Monitoring Quarterly Calibr Not Performed.Caused Insufficient Programmatic Controls.Items Now Tracked (← links)
- 05000397/LER-1986-023, :on 860710,reactor Scram Occurred Following Opening of Incorrect Circuit Breaker During Electrical Ground Isolation.Caused by Personnel Error.Engineer Drawing & Circuit Breaker Labeling Will Be Changed (← links)
- 05000397/LER-1986-037, :on 861120,plant Shut Down After Connector for Signal Cable of Acoustic Monitoring Channel 5C Determined to Be Not Environmentally Qualified.Caused by Inadequate Maint Work Request.Vital Work Requests Reviewed (← links)
- 05000397/LER-1986-036, :on 861110,control Room Emergency Filtration Sys Automatically Initiated on False High Chlorine Signal. Caused by Broken chlorine-sensitive Paper Tape.Chlorine Monitor Investigated & Tape Replaced (← links)
- 05000397/LER-1986-018, :on 860526 & 29,diesel Generator 2 Failed During post-mod Diagnostic Testing.Cause Undetermined. Procedure Will Be Written to Provide More Detailed Guidance Re post-mod Retesting (← links)
- 05000397/LER-1986-029, :on 860822,drywell Hydrogen Analyzers Calibr Using 2% & 6% by Vol Hydrogen Gas Rather than 0% & 25% Required by Tech Specs.Caused by Personnel Error.Analyzers Recalibr.Tech Spec Amend Requested (← links)
- 05000397/LER-1986-027, :on 860903,evaluation Concluded That Engineering Criteria Supplied by Burns & Roe,Inc,In Electrical Spec 2808-218 Nonconservative.Procedures Utilizing Faulty Data Will Be Modified (← links)
- 05000397/LER-1986-044, :on 861222,liquid Radwaste Effluents Discharged W/Radioactive Liquid Effluent Monitor Inoperable & Only One Predischarge Batch Sample Obtained & Analyzed.Caused by Personnel Error.Personnel Counseled (← links)
- 05000397/LER-1986-043, :on 861217 & 19,control Room Emergency Filtration Sys Automatically Initiated on High Chlorine Signal.Cause Unknown.Control Room Emergency Filtration Sys Returned to Normal Lineup (← links)
- 05000397/LER-1986-021, :on 860620,plant Shutdown Commenced Due to Leakage from RCS Pressure Isolation Valve Exceeding 1 Gpm. Caused by Damage to Valve Seat,Disk & Internal Surfaces from Cavitation.Valve Replaced (← links)
- 05000397/LER-1986-022, :on 860627,during Planned Outage While Electrical Loads Supplied by Offsite Power Source,Standby Diesel Generators Automatically Started.Caused by Momentary Loss of Power from nonplant-related Trip (← links)
- 05000397/LER-1986-042, :on 861201,plant Nonconformance Rept Issued to Document Omission of Fire Door C228 from Two Surveillance Procedures.Caused by Personnel Error.Door Verified Operable & Locked & All Surveillance Procedures Checked (← links)
- 05000397/LER-1986-039, :on 861123,control Room Emergency Filtration Sys Initiated on False High Chlorine Signal.Caused by Incorrect Lamp (5.6V) Inadvertently Installed.Lamp Replaced (← links)
- 05000397/LER-1986-040, :on 861125,technicians Failed to Obtain Drywell Samples Every 12 H as Required.Caused by Failure of Personnel to Follow Procedures.Personnel Counseled (← links)
- 05000397/LER-1986-041, :on 861126,1202,05 & 06,control Room Emergency Filtration Sys Automatically Initiated on High Chlorine Signal for No Apparent Reason.Investigation of Chlorine Monitor Did Not Reveal Any Malfunctions (← links)
- 05000397/LER-1986-017, :on 860608,RWCU Sys Automatically Isolated Due to High Differential Flow.Caused by Personnel Error.Rwcu Sys Returned to Svc in Blowdown Mode W/Reduced Blowdown Flow.Personnel Counseled (← links)
- 05000397/LER-1986-020, :on 860610,while Recovering from Overspeed Trip Test,Reactor Scrammed.Caused by Inadequate Turbine Operating Procedure.Procedure Modified to Include Addl Info Re Tv/Gv Transfer & Expected Plant Response (← links)
- 05000397/LER-1986-026, :on 860725,following Reactor Scram,Containment Isolation at RWCU Sys Actuated Due to High Differential Flow.Caused by Inadequate Design.Sys Returned to Svc in Blowdown Mode W/Reduced Blowdown Flow (← links)
- 05000397/LER-1986-014, :on 860523,discovered That Two Containment Exhaust Purge Sys Test Connection Isolation Valves Not Tested at 24-month Interval.Caused by Personnel Error. Surveillance Procedure Modified (← links)
- 05000397/LER-1986-010, :on 860513,Diesel Generator 1 Fuel Storage Tank Below Min Inventory.Caused by 24 H Diesel Generator Run When Diesel Generator 2 Out of Svc.Fuel Storage Tank Filled & in Compliance (← links)
- 05000397/LER-1986-012, :on 860512,isolation Function of Nuclear Steam Supply Shutoff Sys Actuated Due to Deenergization of Reactor Protective Sys Supply Bus A.Caused by Inadequate Procedures. Inboard Isolation Valves Restored (← links)
- 05000397/LER-1986-011, :on 860509,nuclear Steam Supply Shutoff Sys Actuated Due to Momentary Loss of Instrument Power. Cause Unknown.Reactor Protection Sys Half Scram & Isolation Signals Reset (← links)
- 05000397/LER-1986-007, :on 860217,control Room Emergency Filtration Sys Automatically Initiated on High Chlorine Signal.Cause Undetermined.Method of Circulating Water Treatment Will Be Changed (← links)
- 05000397/LER-1986-004, :on 860316,during Reactor Shutdown,Reactor Scram Occurred & Pressure Transient Caused Nuclear Instrumentation intermediate-range Monitor Channels to Exceed High Upscale Trip Setpoint (← links)
- 05000397/LER-1986-003, :on 860314,reactor Scram Occurred Due to Incorrect Switch Position During APRM Channel a Functional Test.Caused by Personnel Error.Technicians Counseled & Trained in Proper Actions (← links)
- 05000397/LER-1986-005, :on 860401,refueling Mode 5 Entered Prior to Completing Instrument Surveillances Required by Tech Specs. Caused by Inadequate Procedures.Tech Specs Received & Surveillances Performed (← links)
- 05000397/LER-1986-024, :on 860721,standby Diesel Generator 2 (DG2) Started.Caused by Internal Electrical Fault on One of Three Condensate Booster pumps.DG2 Secured Per Plant Procedure & Returned to Normal Backup (← links)
- 05000397/LER-1986-016, :on 860612,RWCU Sys Isolation Occurred.Caused by Instrument Technician Using Wrong Switch While Performing Channel Functional Test for RWCU High Delta Flow.Labels for Test Switches Will Be Improved (← links)
- 05000397/LER-1986-015, :on 860606,RWCU Sys Isolated During Leak Detection Sys Temp Indicator Calibr.Caused by Technician Incorrectly Lifting Lead.Technician Counseled & Training Package Modified to Include Calibr Procedure (← links)
- 05000397/LER-1986-019, :on 860415,deficiencies Identified in RHR Valve 9 in Limitorque motor-operated Valve During Insp.Similar Environ Qualification Deficiencies Found in 27 Valves.All Deficiencies Corrected (← links)
- 05000397/LER-1986-008, :on 860505,potential Transformer Secondary Fuse Blew,Resulting in Spurious Voltage Loss Signal to SM-8 Undervoltage Protection Cricuitry.Caused by Electrical Maint Technician Error.Technician Counseled (← links)
- 05000397/LER-1986-009, :on 860426,secondary Containment Sys Emergency Operation Initiated When Control Power Fuse in Reactor Bldg Ventilation High Radiation Monitoring Circuitry Blew.Cause Undetermined (← links)
- 05000397/LER-1986-006, :on 860421,reactor Protective Trip Occurred During Installation of Shorting Links for Reactor Protection Sys.Caused by Operator Error,Resulting in Short Circuit. Operator Counseled & Procedure Enhanced (← links)
- 05000397/LER-1986-002, :on 860226,control Room Emergency Filtration Sys Automatically Initiated on High Chlorine Signal Under Normal Conditions.Cause Unknown.Method of Circulating Water Treatment Will Be Changed (← links)
- 05000397/LER-1986-001, :on 860209,spurious Actuation of Control Room Emergency Filtration Sys Occurred Due to Chlorine Monitor Tape Depletion.Caused by Inadequate Design & Personnel Error.Tape Replaced (← links)
- 05000397/LER-1985-057, :on 851011,during Fire Damper Insp Surveillance,Reactor Bldg Outside Air Fire Damper ROA-FD-12 Discovered Not Installed.Rhr HX B Passageway Area Placed on Fire Watch.Procurement of Damper Initiated (← links)
- 05000397/LER-1985-059, :on 851113,scram Occurred Due to Failure of Power to Control Reactor Feedwater Sys Reactor Pressure Vessel Level Instrument Channel.Caused by Failed Critical Instrument Power Inverter.Study Underway (← links)
- 05000397/LER-1985-060, :on 851117,automatic RWCU Sys Isolation Occurred Due to RWCU High Delta Flow Exceeding Trip Setpoint.Cause Attributed to Air in Sensing Lines.Rwcu Sys Returned to Svc in Blowdown Mode (← links)
- 05000397/LER-1985-051, :on 850722,incorrect Values for Single Loop Operation Used in Aprm,Reactor Protection Sys Thermal Power Trip Calibr Procedure.Caused by Failure to Perform Calibr W/ Latest Approved Procedure.Values Reset (← links)
- 05000397/LER-1985-063, :on 851207,automatic Start of Both Standby Diesel Generators DG-1 & DG-2 Occurred Due to Momentary Undervoltage Condition.Caused by 230-kV Transmission Sys Undervoltage Condition (← links)
- 05000397/LER-1985-050, :on 850723,during 18-month Surveillance on Cable Spreading Room pre-action Fire Protection Sprinkler, Solenoid Valve Controlling Flow to Sprinkler Header Did Not Open.Cause Unstated.Valve Repaired (← links)
- 05000397/LER-1985-058, :on 851014,uncontrolled Quantities of Primary Containment Atmosphere Released to Environ W/O Being Treated During 24 H of Purge Operation.Caused by Failure of Standby Gas Treatment Fan 1B2.Purge Terminated (← links)
- 05000397/LER-1985-053, :on 850804,reactor Scram Occurred During Instrument Surveillance of ATWS Recirculation Pump Trip Feature.Caused by Faulty Instrument Isolation Valve.Valve Replaced & Training Program Implemented (← links)
- 05000397/LER-1985-054, :on 850807,operator Failed to Perform Fire Tour Per Tech Spec 3.7.7 in Cable Spreading Room.Caused by Operator Error.Fire Tour Reestablished at Shift Turnover & Operator Counseled (← links)
- 05000397/LER-1985-052, :on 850801,discovered Procedure Deviation Issued on 850608 Incorrectly Changed Containment Isolation Valve Closure Time.Procedure Mod Issued (← links)
- 05000397/LER-1985-049, :on 850720,core Pressure Drop Baseline Data Not Obtained While Increasing Power Above 50% Rated Core Thermal Power in Single Recirculation Loop Operation.Power Reduced to Thermal Power Limit for Data (← links)
- 05000397/LER-1985-056, :on 850930,erroneous High Chlorine Signal from Ventilation Chlorine Detector Started Control Room Emergency Filtration Sys.Caused by Breakage of Chlorine Sensitive Paper Tape.Paper Tape Replaced & Alarms Reset (← links)
- 05000397/LER-1985-055, :on 850910,listed Itt Hydramotor Valve Actuators Deemed Unreliable.Internal Seals Found in Excess of Qualified Life.Aviton Seal Upgrade Kits Will Be Installed.Evaluation Ongoing (← links)
- 05000397/LER-1985-046, :on 850629,reactor Manually Scrammed & Main Turbine Manually Tripped.Caused by Fire in Reactor Feedwater Pump 1B While Remaining Pump Secured for Maint.Fire Extinguished,Plant Shut Down & Pump Repaired (← links)
- 05000397/LER-1985-044, :on 850628,fuel Oil Intended for Use in Auxiliary Boilers Inadvertently Added to Standby Diesel Generator Fuel Oil Storage Tanks.Caused by Personnel Error. Storage Tanks Sampled & Analyzed (← links)
- 05000397/LER-1985-048, :on 850702,discovered Suppression Pool Not Adequately Refilled After Recent Mod.Cause Unstated.Level Transmitters Vented,Refilled & Recalibr.Pool Level Restored to Normal Levels (← links)
- 05000397/LER-1985-047, :on 850701,discovered That One Reactor Protection Sys Relay for Turbine Throttle Valve Not Energized When Open.Scram Occurred During Valve Reset.Caused by Limit Switch Failure.Switches Recalibr (← links)
- 05000397/LER-1985-045, :on 850625,automatic Reactor Water Cleanup Sys Isolation Occurred While Repressurizing Demineralizer B After Completion of Backwash & Precoat.Caused by Air in Sensing Lines of Flow Instrumentation (← links)
- 05000397/LER-1985-043, :on 850619,during Fire Barrier Surveillance, Connection Box,Conduit & Two Cables Found W/Missing Thermolag Fire Protective Coating.Barriers Not Installed During Initial Const.Fire Watch Established (← links)
- 05000397/LER-1985-041, :on 850618,Channel B Logic Input to Main Turbine & Feedwater Turbine B Did Not Respond.Caused by Cable Not Reconnected Following Replacement & Rerouting During Startup Test Program.Cable Terminated (← links)
- 05000397/LER-1985-030, :on 850507,while Returning RHR Loop a to ECCS Lineup,Reactor Protection Sys Actuation Occurred.Caused by Simultaneous Opening of Valves RHR-V-6A & RHR-V-4A,causing Reactor Pressure Vessel Water Level Decrease (← links)
- 05000397/LER-1985-029, :on 850503,control Rods Inserted Until 15% Power Obtained When Rod Sequence Control Sys Failed to Automatically Initiate to Enforce Predetermined Control Rod Programming at 20% Rated Thermal Power (← links)
- 05000397/LER-1985-031, :on 850508,during Surveillance of Main Steam Line Hi Radiation,Reactor Protection Sys a & B Placed Simultaneously in Trip Condition.Caused by Spurious Noise Spikes.Surveillance Procedures Modified (← links)
- 05000397/LER-1985-011, :on 850203,two 3/4-inch Drain Lines Observed W/Slight Leakage.Caused by Low Load High Cycle Fatigue.Lines Repaired,Per ASME Section XI Procedures (← links)
- 05000397/LER-1985-040, :on 850606,two Reactor Protection Sys Actuations Occurred.Caused by Reactor Recirculation Sys Pump 1B Testing Evolution.Temporary Reactor Recirculation Sys Pump 1B Testing Procedure Canceled (← links)
- 05000397/LER-1985-028, :on 850426,unsealed Penetration in Reactor Bldg Fire Barrier Floor Discovered.Caused by Failure to Install Fire Seal During Const.Hourly Fire Watch Patrol Placed on Penetration Until Seal Installation Completed (← links)
- 05000397/LER-1985-042, :on 850621,primary Containment Valve in Traversing in-core Probe Purge Line Identified to Be in Noncompliance W/License Commitments.Redesign Prepared & Implemented.Further Investigation Underway (← links)
- 05000397/LER-1985-039, :on 850606,normal Tech Spec Change Request Initiated Re Fuse Size Listing Due to Discovery of Errors in Listing.On 850614,util Notified of Need for NRC Approval Before Resuming Operation.Approval Obtained (← links)
- 05000397/LER-1985-038, :on 850607,insp of Itt General Hydromotor Valve Actuators Revealed 11 Missing Stiffner Plates.Caused by Removal of Plates During Const.Stiffner Plates Reinstalled (← links)
- 05000397/LER-1985-036, :on 850601,control Room Emergency Filtration Unit Started.Caused by First Trip Not Being Reset After Testing.Step to Verify Reset Status Independent of Operator Action Added (← links)
- 05000397/LER-1992-032, :on 920702,unplanned Actuation of ESF Component Occurred Due to Decrease in Reactor Water Level Resulting from Voided Feedwater Piping.Water Level Restored within Normal Operating Parameters (← links)
- 05000397/LER-1985-037, :on 850609,two Circuit Breakers Discovered Inoperable During Scheduled Maint Outage of 4160-volt safety-related Switchgear.Caused by Failure of Spot Welded Pivot Pin.Part 21 Related (← links)
- 05000397/LER-1985-035, :on 850531,diesel Fuel Oil Supply Line on Engine 1 Developed Leak & Diesel Manually Shut Down by Operator.Caused by Broken Copper Tubing in Fuel Line.Faulty Line Replaced & Other Fuel Oil Lines Inspected (← links)
- 05000397/LER-1985-033, :on 850525,noise Spike in Intermediate Range Monitor Channels Resulted in Reactor Protection Sys Actuation.Caused by Movement of Intermediate Range Monitor by Water Spray.Caution Signs to Be Put in Area (← links)
- 05000397/LER-1985-032, :on 850418,required 18-month Surveillance Tests Found Not Performed on Some Output Signals from Reactor Vessel Water Level lo-lo Instruments.Level 2 & High Drywell Procedures Deficient from 831220-850419 (← links)
- 05000397/LER-1985-034, :on 850525,inadvertent ESF Injection to Reactor Pressure Vessel Occurred During Cold Shutdown.Caused by Faulty Logic seal-in Lamp Indication.Procedural Changes Made to Identify Logic Status More Positively (← links)
- 05000397/LER-1992-042, Forwards Public Version of LER 92-042,Rev 0.Root Cause Is Inadequate Policy Re Free Release of Potentially Contaminated Liquids.Conclusions of Ongoing MORT Analysis Will Be in Suppl to LER (← links)
- 05000397/LER-1985-027, :on 850412,automatic Isolation of Div 1 balance-of-plant Relay Cabinet Occurred.Caused by Inadequate Procedure.Logic Reset.Surveillance Procedures Revised.W/ (← links)
- 05000397/LER-1985-025, :on 850404,operations Failed to Notify Chemistry Lab When Transferring Drywell Purge Operation from Standby Gas Treatment Sys to Reactor Bldg Ventilation Sys.Caused by Personnel Error (← links)
- 05000397/LER-1984-127, :on 841218,during Wiring Changes to Auxiliary Steam Sys,Automatic Isolation of Reactor Water Cleanup (RWCU) Sys Occurred.Logic Signal Reset & RWCU Sys Returned to Svc (← links)
- 05000397/LER-1984-130, :on 841220,during Review of Procedure to Verify Containment Integrity,Several Primary Containment Isolation Valves Not Verified in Accordance W/Tech Specs.Verification Procedure Revised (← links)
- 05000397/LER-1985-002, :on 850101,lockout Relays 86XU & 86XUOA Tripped Main Generator/Turbine at BPA Substation & Resulted in Reactor Scram.Caused by Failed Potential Transformer (← links)
- 05000397/LER-1984-129, :on 841228,turbine Trip & Subsequent Reactor Scram Occurred Due to Turbine Control Valve Fast Closure. Caused by Failure of Auto Stop Relief Valves.Valves Cleaned & Reinstalled (← links)
- 05000397/LER-1984-128, :on 841221,automatic Start of Control Room Emergency Filtration Sys Occurred When False High Chlorine Signal Generated Due to Tape Depletion.Tape Replaced & Alarm Reset (← links)
- 05000397/LER-1985-021, :on 850307,reactor Recirculation Flow Control Valve B Hydraulic Power Unit (HY-HP-3B) Tripped Off & Valves HY-V-17B,18B,19B,20B,33B,34B,35B & 36B Closed. Investigations Yielded No Apparent Cause (← links)
- 05000397/LER-1985-020, :on 850227,four Excess Flow Check Valve Bypasses Found Partially Opened While Performing Field Measurements Required to Generate Design Change Package. Probably Caused by Personnel Error (← links)
- 05000397/LER-1985-022, :on 850307,two HPCS Initiation Status Lamps Damaged During Process of Replacing Nameplate Tags on Control Room Panel P-625.HPCS Sys Automatic Initiation Logic Rendered Inoperable While Bulbs Replaced (← links)
- 05000397/LER-1984-126, :on 841211,temp Monitoring of Primary Containment & RHR Pump Rooms a & B Not Accomplished Per Tech Specs.Caused by Incorrect Wording of Surveillance Procedure.Procedure Deviation Processed (← links)
- 05000397/LER-1985-012, :on 850212,during Reactor Bldg Ventilation Sys Maint,Reactor Water Cleanup Sys Isolation Occurred.Caused by Pipe Routing in Area Causing High Temp Trip.Heating & Ventilation Sys Procedures Revised (← links)
- 05000397/LER-1985-013, :on 850214,reactor Protection Sys Actuation Occurred.Caused by Failure to Properly Reset Half Scram Condition Prior to Proceeding W/Surveillance Testing.Scram Reset & Surveillance Testing Continued (← links)
- 05000397/LER-1985-001, :on 850111,existence of 10CFR21 Condition Determined Due to Nonconservative Engineering Assumptions Associated W/Calculating Environ Profiles Used to Qualify Reactor Bldg Equipment (← links)
- 05000397/LER-1985-017, :on 850214,temp Monitor in Leak Detection Sys Covering Reactor Water Cleanup Pump Room 1 Spuriously Actuated Delta Temp High Alarm,Initiating Signal to Close Outboard Containment Isolation Valve (← links)
- 05000397/LER-1985-008, :on 850131,standby Electrical Diesel Generators Did Not Reach Required Voltage for Closure of Output Breakers.Caused by Procedural Error.Control Circuitry Modified.Procedures Changed (← links)
- 05000397/LER-1984-107, :on 841008,control Room Emergency Filtration Sys Fan Automatically Started on Hi Chlorine Signal.Caused by Optics Indicating Lamp Backing Out of Socket,Cutting Off Light to Photo Cells.Light Tightened (← links)
- 05000397/LER-1984-108, :on 841006,licensed Operator Placed Reactor Mode Switch in Run Mode.Procedure Performed Out of Sequence, Prior to Ensuring Pressure at Rated Conditions.Operators Briefed on Procedures (← links)
- 05000397/LER-1985-003-01, :on 850125,erroneous 500-kV Circuit Breaker Open Position Signal Received.Turbine Governor Valves Automatically Closed,Resulting in Reactor Scram.Caused by Disturbance in Microwave Link (← links)
- 05000397/LER-1985-004-01, :on 841226,discovered That Weekly Surveillance of Fire Pump Batteries Not Completed within Scheduled Maint Sys Time Limit.Fire Pump Battery Found to Be within Spec. Event Determined Reportable on 850116 (← links)
- 05000397/LER-1984-106, :on 840927,investigation Revealed Incorrect Piping Installation of Reactor Vessel Fuel Zone Level Transmitter,Causing Recorder to Indicate Onscale W/Increasing Flow in Jet Pump (← links)
- 05000397/LER-1984-102, :00:on 840930,after Installing Electronic Module, Unit Alarmed on Hi Chlorine,Causing Control Room Emergency Filtration Fan to Auto Start.Alarm Reset (← links)
- 05000397/LER-1984-105-01, :on 840924,div I Control Room Emergency Filtration Unit WMA-FN-54A Automatically Actuated.Caused by Spikes on Remote Air Intake Radiation Monitor WOA-RIS-31A. Units Reset & Returned to Normal Lineup (← links)
- 05000397/LER-1984-103, :on 840930,plant Shut Down Due to Failure of Div I Critical Switchgear Cooling Supply Fan Motor.Caused by Premature Failure of Motor Insulation Sys.Motor & Fan Bearing Replaced (← links)
- 05000397/LER-1984-099, :on 840928,RCIC Automatically Isolated by Leak Detection Sys High Area Temp Switch LD-TS-602A. Caused by Instrument Meter Movement Overdeflection. Procedure 7.0.0 Revised (← links)
- 05000397/LER-1984-100, :on 840919,two Reactor Recirculation Sys Primary Containment Valves Failed to Meet Specified Max Closing Time During Surveillance Test.Procedure Deviation Processed (← links)
- 05000397/LER-1984-101, :on 840919 & 1002,reactor Water Cleanup Sys Isolated on Spurious Trip Signals (ESF Actuation),Actuating Nuclear Steam Supply Shutoff Sys Div 1 Isolation Relay. Caused Unidentified.Isolation Signal Reset (← links)
- 05000397/LER-1984-072, :on 840705,06,31,0808,10 & 0918,reactor Water Cleanup Sys Solutions Occurred Due to Erroneous High Delta Flow Trips.Caused by Inadequate Response of Reactor Vessel Transmitter.Transmitter Replaced (← links)
- 05000397/LER-1985-004, :on 850116,determined That 841226 Discovery of Failure to Perform Weekly Fire Pump Battery Surveillance Reportable.Caused by Deficiency in Program Scheduling. Surveillance Scheduling Procedures Revised (← links)
- 05000397/LER-1984-047, :on 840525,significant Design Deficiency Discovered in Biological Shield Well W/O Penetration Fire Protection Seals.Cause Not Stated.Penetrations Sealed. Hourly Fire Watch Patrol Established (← links)
- 05000397/LER-1984-131, :on 841229,full Reactor Protection Sys (RPS) Actuation Occurred.Caused by Incomplete Resetting of RPS Scram Subchannel A2.RPS Logic Reset.No Cause for Apparent Malfunction Could Be Identified (← links)
- 05000397/LER-1984-123, :on 841202,normal Div I Critical Switchgear Room Cooling Lost Due to Manual Shutdown Caused by Vibration of Fan Unit.All Div I Equipment Declared Inoperable.Fan Shaft Replaced & Bearings Installed (← links)
- 05000397/LER-1984-122, :on 841002,fire Door Supervisory Alarm Circuit on Door to Diesel Generator Terminated Due to Drawing Error. Door Discovered Inoperable on 841026.Hourly Fire Watch Posted (← links)
- 05000397/LER-1984-121, :on 841026,samples from Three Diesel Fuel Oil Storage Tanks Delivered to Warehouse for Shipment.Acceptable Results Not Received Until 841128 Because Samples Not Shipped Rush.Procedure Modified (← links)
- 05000397/LER-1984-125, :on 841127,during Reactor Feed Pump Testing at 95% Power,Reactor Power Fluctuations Resulted in Low Pressure Feedwater Heater 4C High Level Trip.Power Reduced (← links)
- 05000397/LER-1984-124, :on 841203,reactor Scram Occurred Due to Reactor Level Decreasing to Level Strip Setpoint.Caused by Personnel Failure to Follow Procedures for Transfer of Level Control (← links)
- 05000397/LER-1984-117, :on 841116,RHR Sys Automatically Isolated During Circuit Testing After Mods to Leak Detection Sys. Caused by Failure to Put RHR in Test Position During Test. Personnel Given Addl Training (← links)
- 05000397/LER-1984-079, :on 840809,reactor Scrammed Due to Loss of Power to Feedwater Pump.Caused by Startup Transformer Overload Producing Voltage Drop on Secondary Transformer. Electrical Configuration Restored (← links)
- 05000397/LER-1984-120, :on 841109,auto-start of Control Room Emergency Filtration Unit Occurred.Caused by Failure to Reset Primary Containment High Pressure Trip After Performance of Trip Procedure.Personnel Counseled (← links)
- 05000397/LER-1984-082, :on 840802,23 & 1004,during Shutdown,Rcic Isolated on Spurious High Steam Flow Indication.Caused by Mispositioned Line Break Detection Setpoint on RCIC Differential Pressure Switches (← links)
- 05000397/LER-1984-118, :on 841111 & 13,severe Fluctuations Detected in Div II Uninterruptable Power Supply.Caused by Defective Div II Inverter.Inverter Repaired & Returned to Svc (← links)
- 05000397/LER-1984-119, :on 841110,automatic Reactor Water Cleanup (RWCU) Sys Isolation Occurred While Shifting RWCU Flow Return from Main Condenser to Reactor Vessel.Caused by Air in Instrument Sensing Line.Sensing Line Vented (← links)
- 05000397/LER-1985-014, :on 850214,high Pressure Reactor Scram Initiated Due to Actuation of Turbine Bypass Valve 7 Inches Mercury Low Condenser Vacuum Interlock.Normal Scram Recovery Procedures Followed (← links)
- 05000397/LER-1985-015, :on 850213,fire Detection Instrument Discovered to Have Been Removed from RHR Valve Room During Plant Mod. from 840909-850213 No Fire Detection or Fire Watch Patrol Monitored RHR Valve Room (← links)
- 05000397/LER-1985-019, :on 850216,temp Monitoring of RHR Pump Room Areas Not Accomplished in Accordance W/Tech Specs.Caused by Incorrect Transference of Instructions from Plant Procedure Deviation to Actual Procedure Used on 850216 (← links)
- 05000397/LER-1985-018, :on 850224,containment Monitoring Sys Temp Indicator Exceeded 150 F for Greater than 8 H.Caused by Circulating Water Sys Cooling Towers Alternately Being Taken Out of Svc for Electrical Repairs (← links)
- 05000397/LER-1984-114, :on 841028,gland Steam Condenser Bypass Valve Closed,Tripping Two Condensate Booster Pumps & Causing Loss of Feedwater & Reactor Scram.Caused by Personnel Error. Training Will Be Provided (← links)
- 05000397/LER-1985-016, :on 850213,reactor Scrammed & HPCS Sys Automatically Initiated.Caused by Incorrect Differential Pressure Instrument Being Valved Into Svc.Instruments Verified for Proper Calibr (← links)
- 05000397/LER-1984-075-01, :on 840709,standby Diesel Generator 1B Incurred High Vibration Alarm.Caused by Slip Ring End Bearing Turning on & Destroying Insulation & Allowing Shaft to Rub on Bearing Housing (← links)
- 05000397/LER-1984-111, :on 841018,discovered Battery Surveillance Test Not Performed.Caused by Computer Program Being Incorrectly Set Up.Computer Program Fault Corrected & Surveillance Program Reexamined (← links)
- 05000397/LER-1984-115, :on 841023,automatic Reactor Protection Sys Trip Occurred.Caused by Increase in Vessel Level Due to Broken Actuator & Position Feedback Arm.Actuator Removed & Replaced W/Stainless Steel Tube (← links)
- 05000397/LER-1984-116, :on 841021,startup Surveillance on APRMs Revealed That Neutron flux-high Setdown Trip Set Beyond Tech Spec Limits.Investigation Initiated to Determine Cause. Trips Reset (← links)
- 05000397/LER-1984-113, :on 841021,reactor Protection Sys (RPS) Actuation Occurred.Cause Not Stated.Reactor Level Restored, RPS Trip Signal Reset & Plant Cooldown Continued (← links)
- 05000397/LER-1984-073, :on 840708,spurious Hi Chlorine Alarm from WOA-SR-15 Caused Control Room Emergency Filtration Sys to Auto Start.Caused by Component Failure in Electronics Module on Chlorine Analyzer.Alarm Reset (← links)
- 05000397/LER-1984-109, :on 841013,while Investigating High electro- Hydraulic Fluid Temps on Main Turbine,Turbine Governor & Bypass Valves Observed Oscillating.Caused by Radio Frequency Interference (← links)
- 05000397/LER-1984-110, :on 841003,two Control Room Remote Air Intake Valves for Remote Air Intake 1 Failed to Close.Caused by Failure of Hydraulic Cylinder Seal.Valve Actuators Replaced (← links)
- 05000397/LER-1984-112, :on 841020,setpoint Change Incorrectly Entered, Resulting in Reactor Scram.Caused by Poor Visibility of Digital Electrohydraulic Display.Maint Work Request Issued to Minimize Glare & Improve Visibility (← links)
- 05000397/LER-1985-009, :on 850119,reactor Water Cleanup Sys Isolated. Caused by Spurious Reactor Water Cleanup Sys High Flow Trip. Isolation Signals Reset (← links)
- 05000397/LER-1985-010, :on 850127,reactor Water Cleanup Sys Isolation Occurred.Caused by Spurious Reactor Water Cleanup Sys High Delta Flow Trip.Isolation Signals Reset (← links)
- 05000397/LER-1985-007, :on 850131,one Generator Primary Protection Lockout Relay,Spuriously Tripped Causing Abnormal Electrical Operations.Caused by 500 Kv Breakers Opening & Causing Overspeed Condition (← links)
- 05000397/LER-1984-094, :on 840905,control Room Emergency Filtration Sys Activated by Hi Chlorine Alarm.Caused by Burned Out Optics Source Lamp in Ventilation Chlorine Detector WOA-SR-16.Lamp Replaced & Alarm Reset (← links)
- 05000397/LER-1984-093, :on 840824,false Hi Chlorine Signal from Control Room Ventilation Chlorine Detector Actuated Control Room Emergency Filtration Sys.Caused by Depletion of Chlorine Sensitive Tape.Tape Replaced (← links)
- 05000397/LER-1984-092, :on 840821 & 24,false Hi Chlorine Alarms on Control Room Ventilation Chlorine Detector Caused Automatic Start of Control Room Emergency Filtration Sys.Caused by Photocell Failure.Photocell Replaced (← links)
- 05000397/LER-1984-091, :on 840823,RHR Isolation & Reactor Low Water Level Trip Occurred While Placing RHR Sys in Shutdown Cooling Mode.Caused by High Shutdown Cooling Suction Flow. Shutdown Cooling Flow Path Reestablished (← links)
- 05000397/LER-1984-089, :on 840816,scram Initiated During Surveillance Test on Control Rod Block Recirculation Flow Comparator & Main Steam Line Radiation Monitors.Plant Personnel Completed post-scram Activities (← links)
- 05000397/LER-1984-086, :on 840814,equipment Operator Failed to Complete Fire Tour Assigned Per Tech Specs.Fire Tour Reestablished & Continued Per Tech Spec 3.7.7.Operator Reprimanded (← links)
- 05000397/LER-1984-090, :on 840807,open Main Steam Line Drain Valves Provided Direct Flowpath from Reactor Pressure Vessel (RPV) to Main Condenser Causing RPV Level to Decrease to +13 Inches & Reactor Protection Sys Actuation (← links)
- 05000397/LER-1984-085, :on 840811 & 17,surveillance Performed on Standby Diesel Generators 1 & 2,DG1A & DG1B W/O Prelube Warmup.Memo Issued Outlining Understanding & Providing Interim Relief from Tech Specs (← links)
- 05000397/LER-1984-088, :on 840814,RHR Standby Svc Water Monitor Loop B Determined Inoperable Since 840807 Due to Leaking Pump Seal at Sample Rack.Caused by Inadequate Procedures.Faulty Pump Seal Replaced (← links)
- 05000397/LER-1984-084, :on 840812,notification Received Re Grass Fire Approaching Plant Boundaries.Cause Not Stated.Diesel Generators Brought on Line to Supply safety-related Electrical Loads.Fire Terminated (← links)
- 05000397/LER-1984-081, :on 840816 & 18,reactor Water Cleanup & RCIC Sys Isolations Occurred During Surveillance of Leak Detection Sys Temp Monitor.Caused by Logic Switch in Normal Position.Isolation Signal Reset (← links)
- 05000397/LER-1984-083, :840802,manual Scram Implemented Due to High Reactor Water Conductivity.Caused by Condenser Water in Leakage.Condenser Tube Plugged & Sys Returned to Svc (← links)
- 05000397/LER-1984-078, :on 840801,07 & 08,control Room Emergency Filtration Units Automatically Actuated.Caused by Spikes on Corresponding Control Room Outside Air Radiation Monitors. Filtration Units & Radiation Monitors Reset (← links)
- 05000397/LER-1984-080, :on 840801,turbine Stop Valve Closure Reactor Trip Occurred as Result of Pressurizing Turbine first-stage Shell Above 30% Power.Plant Recovered Per Operating Procedure PPM 3.3.1 (← links)
- 05000397/LER-1984-077, :on 840720 & 21,control Room Emergency Filtration Unit Automatically Actuated.Caused by Spikes on Corresponding Control Room Outside Air Radiation Monitor. Emergency Filtration Unit Reset (← links)
- 05000397/LER-1984-076, :on 840728,during Declaration of Unusual Event Subsequent to Finding Possible Bomb,Hourly Fire Watch Tour Not Performed.Tours Resumed Immediately Upon Termination of Unusual Event Status.Only One Tour Missed (← links)
- 05000397/LER-1984-074, :on 840712,results of Sample from Radwaste Tank EDR-TK-4B Inadvertently Recorded on FDR-TK-9 Data Sheet & FDR-TK-9 Released.Caused by Contractor Error.Discharge Stopped.Procedure for Tank Release Modified (← links)
- 05000397/LER-1984-075, :on 840709 & 13,standby Diesel Generator 1B Incurred High Vibration Alarm.Caused by Slip Ring End Bearing Turning on Shaft Insulation.Bearing Insulation Modified (← links)
- 05000397/LER-1984-071, :on 840716,loss of Power to Portion of Failsafe Relaying Resulted in 1/2 BOP Containment Isolation. Caused by Inadvertent Shorting of Reactor Protection Sys Branch Circuit.Containment Isolation Reset (← links)
- 05000397/LER-1984-061, :on 840614,open Floor Drain Found on 522-ft Elevation of Reactor Bldg.Plant Walkdown Revealed Two Other Drains.Fire Watches Instituted.Drains Will Be Piped Into Floor Drain Sys & Not Sealed as First Planned (← links)
- 05000397/LER-1984-104, :on 841004,reactor Tripped.Caused by Four Turbine Bypass Valves Fully Opening & Closing Due to Vendor Representative Removing & Replacing Circuit Card from Digital Electrohydraulic Control Cabinet (← links)
- 05000397/LER-1984-069, :on 840628,control Room Emergency Filtration Unit Automatically Actuated Due to Spike on Corresponding Control Room Outside Air Radiation Monitor.Caused by Maint on Undervoltage Relays.Alarm Reset (← links)
- 05000397/LER-1984-070, :on 840630-0711,surveillances of Standby Diesel Generator Performed.W/O Prelube/Warmup in Violation of Tech Spec.Caused by Change Requiring Prelube/Warmup Per Manufacturer Recommendations.Change Initiated (← links)
- 05000397/LER-1984-097, :on 840904,automatic Isolation of Reactor Water Cleanup Sys Occurred.Caused by High Delta Flow Signal.Insp Confirmed No Leaks Exist & Sys Returned to Normal (← links)
- 05000397/LER-1984-059, :on 840608 & 18,surveillance Performed on Standby Diesel Generators 2 & 1,respectively,w/o Prelube/ Warmup.Caused by Changes to Tech Specs.Tech Specs Changed to Allow Starting W/O Prelube/Warmup (← links)
- 05000397/LER-1984-098, :840904,10 & 17,control Room Emergency Filtration Units Actuated.Caused by Spurious Spikes on Control Room Radiation Monitors.Radiation Levels Verified & Monitors Reset.Cause Under Investigation (← links)
- 05000397/LER-1984-095, :on 840910,during Power Ascension Test,Reactor Scram Occurred.Caused by Test Switch Connected to Reactor Protection Sys Rather than Reactor Pump Trip Logic,Due to Misreading of Test Procedure Drawing (← links)
- 05000397/LER-1984-096, :on 840901,deluge Sys Actuated Due to Steam Leak.Fire Pump & Two pre-action Sys Tripped & Fire Alarm Received for Water Filtration Bldg.Caused by Shut Cooling Water Supply Valve to FP-P-110 Diesel Engine (← links)
- 05000397/LER-1984-057, :on 840605 & 12,false High Chlorine Signal from Ventilation Chlorine Detector,On Sample Rack WOA-SR-15, Started Control Room Emergency Filtration Sys.Caused by Depletion of Paper Tape.Tape Replaced (← links)
- 05000397/LER-1984-058, :on 840607,control Room Emergency Filtration Unit Inadvertently Initiated Due to Technician Performing Maint on Associated Radiation Monitoring Sample Rack.Caused by Voltage Transient.Alarms Reset (← links)
- 05000397/LER-1984-056, :on 840601,reactor Protection Sys Tripped on High Reactor Pressure Due to Closure of All Four Main Turbine Bypass Valves.Caused by Failure of Electronic Circuit Card.Defective Card Replaced (← links)
- 05000397/LER-1984-054, :on 840529,turbine Governor & Intercept Valves Tripped Closed.Caused by Incorrect Overspeed Protection Control Test Techniques.Procedure Deviation Issued to Secure Testing Function (← links)
- 05000397/LER-1984-048, :on 840530,fuses Used in Class IE 250-volt Dc Sys Discovered Inappropriately Applied.Portions of Fuses Required to Return 250-volt Sys to within Design Basis Immediately Replaced.Balance Fuses Rescheduled (← links)
- 05000397/LER-1984-049, :on 840522,control Room Emergency Filtration Units Spuriously Actuated Due to Spike on Associated Radiation Monitoring Sys.Spike Caused by Starting of HVAC Supply Fan.Monitors & Filtration Units Reset (← links)
- 05000397/LER-1984-055, :on 840528,spurious Trip Signal from RCIC Steam Supply High Flow Differential Pressure Switch Isolated RCIC Sys at No Flow Condition.Isolation Signal Reset & RCIC Sys Restored to Svc (← links)
- 05000397/LER-1984-050, :on 840526,control Room Emergency Filtration Unit Actuated Due to Spike on Outside Air Radiation Monitors.Caused by Tripping of RCIC Turbine.Alarms Reset (← links)
- 05000397/LER-1984-053, :on 840528,control Room Emergency Filtration Unit Actuated Due to Spike on Outside Air Radiation Monitors.Caused by Closure of RCIC Valve.Alarms Reset & Noise Suppression Devices Installed (← links)
- 05000397/LER-1984-051, :on 840528,reactor Scrammed on Low Level.Caused by Operator Error.Condensate Filter Demineralizer Isolation Resulted in Loss of Main Feed Pumps.Reactor Scram Procedure Implemented (← links)
- 05000397/LER-1984-052, :on 840528,control Room Emergency Filtration Unit Actuated Due to Spike on Outside Air Radiation Monitors.Caused by Closure of RCIC Valve.Alarm Reset & Noise Suppression Devices Installed (← links)
- 05000397/LER-1984-046, :on 840522,control Room Emergency Filtration Unit Automatically Actuated.Caused by Excessive Electrical Noise Induced Into Radiation Monitoring Sys.Monitors & Emergency Filtration Units Reset (← links)
- 05000397/LER-1984-045, :on 840518,reactor High Pressure Trip Occurred as Result of Main Steam Bypass Valve Closure Due to Low Hydraulic Fluid Pressure,When Main Turbine Manually Tripped. Main Steam Bypass Valves Reopened (← links)
- 05000397/LER-1984-043, :on 840519,during Pressurization of Monitor a, Isolation Signal & Load Shedding Logic Initiated Resulting in Loss of Control Power to Reactor Feedwater Level Control Sys.Caused by Monitors B & D Not Reset (← links)
- 05000397/LER-1984-044, :on 840513,during Power Ascension Test,Pressure Fluxuation in Digital electro-hydraulic Sys Emergency Trip Header Caused Reactor Trip Due to High Pressure.Caused by Improper Bypass Reset Solenoid Valve Seating (← links)
- 05000397/LER-1984-042, :on 840517,reactor Manually Shut Down Due to Loss of Control of Vessel Water.Caused by Malfunction of Mechanical Linkage from Servo Control Motor.Linkage Repositioned & Refastened (← links)
- 05000397/LER-1984-041, :on 840509 & 19,surveillance Performed on Standby Diesel Generators 2 & 1 W/O Prelube/Warmup, Respectively.Tech Specs Will Be Changed to Allow Starting of Diesel Generator W/O Prelube/Warmup (← links)
- 05000397/LER-1984-040, :on 840510,during Preventive Maint on HPCS Diesel Generator Pressure Switch,Contacts Miscounted on Interlock Relay & Jumper Installed,Causing Lockout.Note Added to Calibr Sheet (← links)
- 05000397/LER-1984-039, :on 840426,when Motor Operated Valve RCIC-V-45 Given Close Signal,Noise Spike Induced Radiation Monitoring Instruments WOA-RIS-31A & 32A Causing Control Room Ventilation to Auto Isolate (← links)
- 05000397/LER-1990-025, :on 901023,HPCS Sys Declared Inoperable.Caused by Equipment Failure.Plant Policy Reviewed,Design Differential Pressure Calculation Process Revised & Thrust Calculation HPCS-V-23 Revised (← links)
- 05000397/LER-1984-026-01, Revised LER 84-026-01:on 840419 & 27,water Found in Train B of Standby Gas Treatment Sys.Caused by Pressure Surges in Preaction & Deluge Portions of Fire Protection Sys.Design Change in Progress (← links)
- 05000397/LER-1984-036, :on 840423,during Initial Power,Test Equipment Installed to Facilitate Troubleshooting Feedwater Control Sys Injected Test Signal Into Feedwater Control Circuit. Caused by Improperly Positioned Bypass Switch (← links)
- 05000397/LER-1984-068, :on 840628,control Room Emergency Filtration Unit Automatically Actuated Due to Spike on Corresponding Control Room Outside Air Radiation Monitor.Caused by RCIC Valve Closing During Testing.Alarm Reset (← links)
- 05000397/LER-1984-027-01, Revised LER 84-027-01:on 840322,main Steam Relief Valve Solenoids Failed Due to Grounding in Solenoid Coils.Voltage Spike Suppression Diodes Installed Across Each Solenoid Circuit.Ge Conducting Review of Failures (← links)
- 05000397/LER-1984-008-01, Revised LER 84-008-01:on 840128,suppression Pool Level Indicator & Pool Level Fell Below Tech Spec Limits.Caused by Simultaneous Loss of Control Room Indication & Operation of Loop a of RHR Sys.Indication Reenergized (← links)
- 05000397/LER-1984-065, :on 840623,following Startup of Pump RHR-P-2B, Pump Motor Current Determined to Be High & Pump Secured & Isolated.Caused by Loose Pump Motor Half Coupling Retaining Nut.Pump Repaired & Other Pumps Modified (← links)
- 05000397/LER-1984-066, :on 840620,control Room Filtration Unit Actuated.Caused by Spike on Corresponding Radiation Monitor.Radiation & Chlorine Levels Verified & Radiation Monitors Reset & Returned to Normal Lineup (← links)
- 05000397/LER-1984-064, :on 840623,100 Amp Circuit Breaker CB2B in Reactor Protection Sys Power Distribution Panel C72-POO1 Tripped Twice.Caused by Bad Connection on Cable BPRPS-9026. Connection Reworked & Breaker Reset (← links)
- 05000397/LER-1984-067, :on 840620,control Room Emergency Filtration Units Automatically Actuated.Caused by Spike on Corresponding Radiation Monitoring Sys.Radiation Levels Verified & Radiation Monitors Reset (← links)
- 05000397/LER-1984-062, :on 840620,Tech Spec Surveillance Requirements on Rod Sequence Control Sys Not Performed in Required Time Frame.Caused by Personnel Error.Surveillance Tests Performed (← links)
- 05000397/LER-1984-063, :on 840617,control Room Emergency Filtration Unit Automatically Actuated Due to Spike on Control Room Outside Air Radiation Monitor.Caused by Starting of Svc Water Pump.Alarm Reset (← links)
- 05000397/LER-1984-060, :on 840613,reactor Low Water Level Trip Occurred Due to Loss of Feedwater Flow.Caused by Low Suction Pressure Trip of Condensate Booster Pumps.Rcic Sys Manually Initiated to Restore Level (← links)
- 05000397/LER-1984-021, :on 840306,while Resetting Scrams,Scram Discharge Vol Drain Down Times Excessively Long.Caused by Two Packets of Desiccant Found in Valve Body & Seven in Upstream Piping.Dessicant Removed (← links)
- 05000397/LER-1984-023, :on 840308 & 09,surveillance Performed on Standby Diesel Generator 1 & 2,respectively,w/o Prelube/ Warmup,In Violation of Tech Spec.Caused by Tech Spec Changes.Tech Spec Modified (← links)
- 05000397/LER-1984-016, :on 840317,during Routine Calibr Check,Full NSSS & Div I & II Balance of Plant Isolation Occurred.Caused by Operator Error in Positioning Reactor Protection Sys Power Transfer Switch (← links)
- 05000397/LER-1983-003-01, Updated LER 83-003-01:on 831222,walk Down Revealed Fire Dampers Not Meeting Fire Rating Requirements,Violating Tech Specs.Caused by Personnel Error.Defective Dampers Replaced (← links)
- 05000397/LER-1984-019, :on 840308,when Missing Alarm Light Replaced, Current Surge/Voltage Spike Caused Momentary Hi Chlorine Alarm & Started Control Room Emergency Filtration Sys.Alarm Reset & H&V Returned to Normal (← links)
- 05000397/LER-1984-018, :on 840306,while Performing Surveillance Procedure Testing,Control Room Emergency Filtration Fan Initiated.Caused by Procedural Error.Sys Restored to Previous State (← links)
- 05000397/LER-1984-015, :on 840307,dc Input Circuit Breaker & Fuse Tripped Due to Loss of Power.Caused by Inverter Static Switch Transferring to Inverter Source.Fuse Replaced & Inverter Returned to Svc (← links)
- 05000397/LER-1984-011, :on 840302,during Intermediate Range Monitor B Surveillance Test,Reactor Protection Sys (RPS) Actuation Occurred When Only 1/2 Scram Anticipated.Caused by Loose Connection in RPS Trip Sys a Scram Circuitry (← links)
- 05000397/LER-1984-012, :on 840221,24 & 0302,diesel Generator Fuel Oil Tank Chemistry Results Not Received in Required Time, Violating Tech Spec 4.8.1.1.2.d.3.Caused by Misunderstanding Between Util & Lab (← links)
- 05000397/LER-1984-014, :on 840219,reactor Protection Sys (RPS) Trip Occurred.Caused by Water Rejection Flow from Reactor Pressure Vessel Isolated W/O Reducing Water Injected.Power to RPS Buses a or B Will Not Be Transferred (← links)
- 05000397/LER-1984-013, :on 840213,during Shutdown Conditions,Both post-LOCA Hydrogen Recombiner (CAC-HR-1A & 1B) Motors Tripped on Electrical Overload.Caused by Differences Between Nameplate Date & Design.Fuses Resized (← links)
- 05000397/LER-1984-009, :on 840207 & 09,standby Diesel Generators 1 & 2 Surveillances Performed W/O Prelube/Warmup.Caused by Recent Changes to Tech Specs Not Requiring Warmup.Tech Specs Changed &/Or Modified (← links)
- 05000397/LER-1984-002, :on 840111,control Room Outside Air Radiation Monitors Associated High Radiation Alarms Tripped.Caused by Excessive Electrical Noise Induced Into Radiation Monitoring Sys (← links)
- 05000397/LER-1989-001, :on 890112,discovered Four New Unanalyzed Failure Modes in Containment Nitrogen Inerting Sys.Caused by Inadequate Design Procedures.Design Change Initiated to Install low-temp Cutoff Device (← links)
- 05000397/LER-1984-035, :on 840420,reactor Water Cleanup Sys Isolation Valves 1 & 4 Cycled Closed Via Leak Detection Sys High Delta Flow Signal.Caused by Transfer from Recirculation to Blowdown.Engineering Evaluation Requested (← links)
- 05000397/LER-1984-037, :on 840411,during Initial Heatup,Piping in Primary Containment Inspected for Movement & Loose Parts Detector Channel 6 Damaged.Caused by Detector &/Or Cable Malfunction.Replacement Planned During Outage (← links)
- 05000397/LER-1984-032, :on 840411,inner Door of Primary Containment Airlock Started to Open While Personnel Closing Outer Door.Interlock Mechanism Found Disengaged.Interlock Engaged, Outer Door Closed & Normal Airlock Continued (← links)
- 05000397/LER-1984-030, :on 840412,ground on RCIC Sys motor-operated Valve Induced Spikes to Control Room Outside Air Radiation Monitoring Sys as Valve Stroked.Caused by Ground Varistor. Varistor Reworked (← links)
- 05000397/LER-1984-029, :on 840409 & 19,surveillance Performed on Standby Diesel Generators 1 & 2,respectively,w/o Prelube/ Warmup,In Violation of Tech Spec 4.8.1.1.2.a.4.Caused by Changes to Tech Spec (← links)
- 05000397/LER-1984-028, :on 840328,unscheduled Reactor Protection Sys Actuation Occurred Due to Scram Discharge Vol High Level. Caused by Leakage from Reactor Pressure Vessel to Isolated Discharge Vol.Personnel Cautioned (← links)
- 05000397/LER-1984-026, :on 840321,ionization Detector Activated & Tripped pre-action Sys,Starting Fire Pumps.Pressure Surge Tripped Another pre-action Sys & Lifted Two Deluge Valves for Standby Gas Treatment Trains a & B (← links)
- 05000397/LER-1984-024, :on 840317,during Instrument Calibr,Control Room Emergency Filtration Units Initiated Due to Inadvertent Deenergization & Reenergization of Test Equipment.Personnel Cautioned.No Other Corrective Action Necessary (← links)
- 05000397/LER-1984-025, :on 840319,control Room Air Radiation Monitors WOA-RIS-31A,31B,32A & 32B Tripped Associated High Radiation Alarms & Started Control Room Emergency Filtration Units. Caused by Electrical Noise (← links)
- 05000397/LER-1984-017, :on 840318,Div II Control Room Emergency Fan Initiated.Caused by Personnel Error.Procedure Revised & Subsequent Surveillances Ran Successfully W/No Inadvertent Actuations (← links)
- 05000397/LER-1984-022, :on 840319,electrician Inadvertently Bumped Clapper of Auxiliary Undervoltage Relay,Which Tripped Supply Breaker to Div 3 ESF Bus.Caused by Human Error. Personnel Advised of Precautions (← links)
- 05000397/LER-1984-007, :on 840127 & 31,reactor Protection Sys Tripped. Caused by Personnel Failing to Correctly Identify Ref & Variable Leg of Transmitter.Red Caution Tags Installed to Prevent Misidentification (← links)
- 05000397/LER-1984-008, :on 840128,suppression Pool Level Exceeded Tech Spec Limits.Caused by Water in Ref Leg.Surveillance Procedures Modified to Insure That Level Transmitter Atmospheric Ref Leg Periodically Drained (← links)
- 05000397/LER-1984-006, :on 840125,circuit Breaker Which Supplies RHR-P-2C Would Not Rack In.Caused by Cracked Latch Lever Guide Tube.Tube Replaced & Breaker Racked Into Svc (← links)
- 05000397/LER-1984-005, :on 840123 & 0208,inadvertent Auto Start of HPCS Diesel Generator DG-1C Occurred.Caused by Failure to Properly Tag Out Unit for Maint Activity.Personnel Retrained (← links)
- 05000397/LER-1984-004, :on 840119,intermediate Range Monitor Channels A,B & D Inoperable After Initial Criticality Achieved.Caused by Short Electrical Connection Between Signal Cable & Detector & Failed Electronic Component (← links)
- 05000397/LER-1984-003, :on 840120,during Initial Low Power Physics Testing,Intermediate Range Monitors A,B & D Did Not Respond to Increasing Neutron Flux,Causing Reactor to Be Shut Down. Caused by Personnel Error (← links)
- 05000397/LER-1983-009-03, /03L:on 831222,fire Damper WOA-SMD-1A Manually Propped Open.Caused by Link Holding Damper Open Fusing Due to Influx of Dust to Activating Detector.New Link Installed (← links)
- 05000397/LER-1983-008-03, /03L:on 831222,damper WOA-SMD-1B Malfunctioned. Guillotine Damper Binded in Track & Was Left in Open Position.Cause Unknown (← links)
- 05000397/LER-1983-007-03, /03L:on 831222,fire Hydrant FP-HT-1G Did Not Drain & Froze During Cold Weather.Caused by Contractor Inadvertently Blocking Drain Port for Hydrant While Pouring Concrete.Hydrant Repaired (← links)
- 05000397/LER-1983-006-03, /03L:on 831222,fire-rated Door D-104 Violated, Causing Loss of Fire Boundary Integrity.Caused by fire-rated Door Closing,Pinching Welding Lead & Melting Hole in Door. Door Replaced (← links)
- 05000397/LER-1983-005-03, /03L:on 831223,fire-rated Seals Removed to Perform Const Work,Causing Loss of Fire Boundary Integrity,Per Tech Specs.Caused by Plant Mod.Seals Will Be Replaced After Const Work Completed (← links)
- 05000397/LER-1983-004-03, /03L:on 831222,loss of Fire Detection Instrumentation Occurred at 606-ft Elevation of Reactor Bldg.Caused by Condensation Shorting Out Detection Sys.Power Supply Replaced & Condensation Source Being Corrected (← links)
- 05000397/LER-1983-003-03, /03L:on 831222,walk Down Revealed That Fire Dampers WMA-FD-1,2,7,8,9,10,11,14,15,18 & DRA-FD-34-1 Did Not Comply W/Ul Fire Rating.Caused by Vendor Cutting Dampers to Required Size (← links)
- 05000397/LER-1983-002-03, /03L-0:on 831231,discovered Fire Protection Storage Water Level in FP-TK-100 Less than 280,000 Gallons. Caused by Air Binding of Filter Effluent Pump While FP-P-107 in Manual Mode Due to Inadequate Procedural Instructions (← links)
- 05000397/LER-1983-001-03, /03L-0:on 831225,while Loading First Fuel Bundle, Rod Block Protective Interlock Lost.Caused by Misinterpretation of Tech Spec Intent.Calibr & Survillance Procedures Changed (← links)
- 05000397/LER-2019-001, Loss of Diesel Starting Air During Maintenance Leads to Loss of High Pressure Core Spray System (← links)
- 05000397/LER-2018-001-01, Automatic Reactor Scram Due to Main Transformer Trip (← links)
- 05000397/LER-2018-001, Automatic Reactor Scram Due to Main Transformer Trip (← links)
- 05000397/LER-1917-007, Regarding Valve Closure Results in Momentary Increase in Secondary Containment Pressure (← links)
- 05000397/LER-1917-006, For Condition Prohibited by Technical Specifications Due to Incomplete Action Statement (← links)
- 05000397/LER-1917-005, Regarding Valve Closure Results in Momentary Increase in Secondary Containment Pressure (← links)
- 05000397/LER-1999-001, :on 990628,ESF Signal Closed All Eight MSIVs While Plant Was Shutdown.Caused by Failure of Relay RPS-RLY-K10D.Subject Relay Was Replaced & Tested on 990630. with (← links)
- 05000397/LER-1998-012, :on 980715,failure to Comply with Requirements of TS SR 3.8.4.7 Was Noted.Caused by Inadequate Work Practices.Training Session Was Held with Personnel.With (← links)
- 05000397/LER-1998-003, :on 980311,WNP-2 Experienced Scram Signal as Result of Low Rpv.Caused by Less than post-SCRAM Operational Strategy for Resetting Scram Signal in Conditions.Changes in post-SCRAM Operational Strategy Implemented (← links)
- 05000397/LER-1998-002, :on 980311,reactor Scram & Plant Transient Occurred,Due to Failed Closed Main Steam Isolation Valve. Caused by Loss of Pneumatic Actuating Supply Pressure. Problem Evaluation Request Written for Failure of MS-V-22D (← links)
- 05000397/LER-1998-001, :on 980203,automatic Start of HPCS EDG Was Noted.Caused by Operator Error.Operations Crew Stabilized Plant at Approximately 75% Reactor Power & Investigation of Event Was Initiated (← links)
- 05000397/LER-1997-010, :on 970906,discovered That TS SR 3.4.5.1 for Identified Portion of RCS Total Leakage Would Not Be Able to Perform within Time Limits of SR 3.0.2.Caused by Inadequate Methods.Method of Meeting SR 3.4.5.1 Established (← links)
- 05000397/LER-1997-011, :on 971010,HPCS Battery Charger Failed.Caused by Failure of a Phase Firing Control Circuit Board Due to Aging During 7 Yrs of Use.Hpcs Sys Was Immediately Declared Inoperable (← links)
- 05000397/LER-1997-004, :on 970327,plant Operators Manually Scrammed Reactor as Required by TS Due to Indication of Entry Into Region a of power-to-flow Map.Caused by Inadequate Attention to Detail.Established Event Evaluation Teams (← links)
- 05000397/LER-1997-008, :on 970716,wire Seal Used to Lock Containment Instrument Air Pressure Control valve,CIA-PCV-2B,found Not Intact.Cause of Misadjustment of CIA-PCV-2B Unknown.Event Will Be Communicated to Plant Employees (← links)
- 05000397/LER-1997-009, :on 970717,discovered Error in Recently Performed Inservice Testing procedure,OSP-TIP/IST-R701. Caused by Procedure Inadequacy.Plant Procedure OSP/TIP/IST-R701 Will Be Changed (← links)
- 05000397/LER-1997-007, :on 970611,voluntary Rept of Automatic Start of DG-1 & DG-2 Was Experienced.Caused by Undervoltage Condition on Electrical Busses SM-7 & SM-8.Circulating Water Pump CW-P-1C Control Switch Placed in pull-to-lock (← links)
- 05000397/LER-1997-006, :on 970527,non-performance of Surveillance Requirement 3.6.1.3.2 for Blind Fanges,Was Noted.Caused Because Misunderstanding of Intent of Specs.Added Five Structural Assemblies for Sp (← links)
- 05000397/LER-1997-005, :on 970327,valid Reactor Scram Signal Received Due to Low Water Level Condition During Preparations for SRV Testing.Caused by Risks & Consequences of Decisions Not Completely Identified.Restored Water Level (← links)
- 05000397/LER-1997-003, :on 970320,notification of Noncompliance W/Ts as TS SRs for Response Time Testing Were Not Being Met for Specified Instrumentation in Rps,Pcis & Eccs.Requested Enforcement Discretion for One Time Exemption (← links)
- 05000397/LER-1997-002, :on 970218,determined That Rod Block Monitor (RBM) Calibr Values Were Not Set IAW Tech Specs.Caused by Calibr Procedures Inadequacies.Revised & re-performed RBM Channel Calibr Procedures (← links)
- 05000397/LER-1997-001, :on 970211,reactor Water Cleanup Sys Blowdown Flow Isolation Setpoint Was Slightly Above TS Allowable Valve Occurred Due to Calculation Error.Lds Fss LD-FS-15 LD-FS-16 Were Declared Inoperable (← links)
- 05000397/LER-1996-009, :on 961220,miscalculation of Instantaneous Overcurrent Relay Settings Resulted in Inoperability of safety-related Equipment.Caused by Utilization of Inappropriate Design.Testing Was Completed (← links)
- 05000397/LER-1996-008, :on 961205,failure to Comply with TS Action Requirement for Emergency Core Cooling Sys Actuation Instrumentation Occurred Due to Unidentified Inoperability Condition.Pmr Initiated (← links)
- 05000397/LER-1996-007, :on 961122,electrical Breakers Were Not Seismically Qualified in Test/Disconnect Position.Circuit Breaker Mfg Did Not Consider Raced Out Breaker Position During Testing.Relocated Circuit Breakers (← links)
- 05000397/LER-1996-006, :on 960709,average Power Range Monitor Rod Block Downscale Surveillance Not Performed Prior to Entry Into Mode 1.Caused by long-standing Misinterpretation of Requirements of Tss.Procedures Revised (← links)
- 05000397/LER-1996-004, :on 960624,plant Was Manually Scrammed by Control Room Personnel Due to Reactor Water Level Transient Experienced During Testing of Digital Feedwater Sys.Caused by Programming Error.Sys Was Corrected (← links)
- 05000397/LER-1996-005, :on 960624,determined Missed Surveillance Test Re Channel Check of Average Power Range Monitor.Caused by Inadequate Procedures.Revised Surveillance Procedure Re When APRM Checks Must Be Performed (← links)
- 05000397/LER-1996-003, :on 960615,required Surveillance Test Not Performed When Required by TS 3.4.1.3.Caused by Inadequate Procedures.Implementing Surveillance Procedure & Reactor Plant Startup Procedures Revised (← links)
- 05000397/LER-1996-002, :on 960504,critical Bus SM-8 Lost Power When Supply Breaker 3-8 Tripped.Caused by Personnel Error. Operators Counselled & Procedures Revised (← links)
- 05000397/LER-1996-001, :on 960425,inadvertent ESF Actuations Occurred Due to Tripping of Temporary Power Supply to IN-3.Caused by Personnel Error.Operations Restored to IN-3 Loads & Reset ESF Actuations (← links)
- 05000397/LER-1995-011, :on 950919,failed to Comply W/Ts SR for RCIC Sys Due to Analysis Deficiency That Resulted in Inadequate Surveillance Test Procedure.Surveillance Procedure Revised to Correct Deficiency (← links)
- 05000397/LER-1995-009, :on 950907,unexpected Closure of Inboard & Outboard MSIV Occurred During Performance of Surveillance Test.Caused by Activity Performed Under Procedure That Did Not Define Necessary Steps.Updated Procedure (← links)
- 05000397/LER-1995-010, :on 950609,HPCS DG Declared Inoperable Due to Discovery That TS Test Method Incomplete.Caused by Inadequate Testing Procedure.Test Procedure for HPCS DG Reviewed & Special Test Procedures Written (← links)
- 05000397/LER-1995-006, :on 950405,reactor Scram Occurred During Surveillance Testing Due to Protective Sys Relay Failure. Replaced Failed Relay Before Plant Startup (← links)
- 05000397/LER-1995-006-01, Forwards LER 95-006-01 Re Reactor Scram During Surveillance Testing Due to Protective Sys Relay Failure (← links)
- 05000397/LER-1995-008, :on 940125,TS Wording Lead to Potential TS Violation.Caused by Lack of Clarity in Ts.Submitted Improved TS for Plant to Provide Addl Clarity (← links)
- 05000397/LER-1995-005, :on 950222,inoperable IRM Had Been Relied Upon to Meet TS Requirements During Reactor Startup.Caused by Lack of Neutron Source to Test Instrumentation. Sys Knowledge Gained Will Be Incorporated (← links)
- 05000397/LER-1995-007, :on 950222,emergency Diesel Start Occurred Due to Voltage Transient on BPA Grid.Confirmation Was Received at 17:51 H That Disturbance Had Originated in BPA Grid (← links)
- 05000397/LER-1995-004, :on 950226,malfunction in Main Turbine DEH Control Sys Caused All Four High Pressure Turbine Governor Valves to Rapidly Close.Caused by Blown Fuse.Suspected Faulty Circuit Card Replaced (← links)
- 05000397/LER-1995-002, :on 950218,automatic Reactor Scram Occurred. Caused by Erroneous Positioning of Control During Performance of Scheduled Periodic Functional Test.Control Repositioned (← links)
- 05000397/LER-1994-018, :on 941115,util Failed to Comply W/Ts Action Requirement While Inoperable Control Rod Block Instrumentation Resulted in Exceeded Allowed Outage Time. Placed Channel a Trip Function in Tripped Condition (← links)
- 05000397/LER-1994-018-01, Forwards LER 94-018-01,incorporating New Findings,Corrective Actions & Updates of Original Info (← links)
- 05000397/LER-1995-003, :on 940817,CR Indication Lost for PASS Inboard Ci Valve & Cycling for Restoration Erratic & Showed Continuous Closed Indication.Caused by Unclear TS Requirement.Ts Bases Will Be Revised (← links)
- 05000397/LER-1995-001, :on 950113,failed to Satisfy Single Failure Criteria for Containment Isolation Function Due to Electrical Separation Plate in Control Panel Missing. Replaced Missing Barrier (← links)
- 05000397/LER-1994-021, :on 941123,holes Cut in MCR Floor Penetration 5016 Precludes Redundant Emergency Fans WMA-FN-54A(B) from Pressurizing CR Sufficiently to Meet Applicable Surveillance.Holes Resealed on 941123 (← links)
- 05000397/LER-1994-019, :on 941121,gasket Missing from MCR Air Handler WMA-AH-51B Precludes Associated Emergency Fan WMA-FN-54B from Sufficiently Pressurizing Cr.Caused by Improper Authorization.Manager Counseled Supervisor (← links)
- 05000397/LER-1994-020, :on 941111,postulated That MCR Fire Could Induce Hot Short That Could Result in Spurious Closure of Mo Ci Valve CIA-V-20.Caused by Inadequate Analysis.Continuous Fire Watch Established for Area (← links)
- 05000397/LER-1994-017, :on 941020,TS Limit Exceeded Due to Improper Calibr of Suppression Pool Narrow Range Level Transmitters. Suppression Pool Level Was Returned to Appropriate TS Operating Level at 1558 Hr (← links)
- 05000397/LER-1994-013, :on 940622,determined That Containment Isolation Provisions for Both Containment Monitoring Sys Inoperable.Caused by Design Error.Design Change Will Be Implemented (← links)
- 05000397/LER-1994-015, :on 940704,actuation of HPCS Sys Diesel Engine & half-scram Condition Occurred Due to Tubing Valve Manipulation.Procedure Entitled, Startup Instrument Rack Valve Line-up Changed on 940706 (← links)
- 05000397/LER-1917-004, Regarding Manual Reactor Scram Due to High Main Condenser Back Pressure (← links)
- 05000397/LER-1994-010, :on 940810,initiated Fire Safe Shutdown Due to Lack of Adequate Analysis of Potential Fire Impact on Min Flow Control Valve Circuitry.Interim C/A Put in Place & Potential Long Term C/A Being Evaluated (← links)
- 05000397/LER-1993-030, :on 931028,cable Tray Cover Deficiencies Discovered Due to Inadequate Mgt Methods to Identify & Resolve Cable Tray & Conduit Electrical Separation Problems. Established Fire Tours of Affected Areas (← links)
- 05000397/LER-1994-014, :on 940706,ESF Actuation Occurred Due to Lineup Error.Caused by Noncompliance W/Testing Procedures. Improper Lineup Was Corrected (← links)
- 05000397/LER-1992-037, :on 920815,reactor Manually Acrammed Due to Indications of Core Instability.Caused by Unanticipated Interaction of Operating Conditions & Components.Revised Operating Strategies & Related Procedures (← links)
- 05000397/LER-1994-011, :on 940624,determined That Weekly Manual Scram Channel Functional Test Had Not Been Performed.Caused by Inadequate Communication Between Operations SRO Personnel. Programmatic Change & Counseling Personnel (← links)
- 05000397/LER-1994-016, :on 940701,determined That CR Scram Time Had Not Been Conducted During Previous Outages.Caused by Nonconservative Interpretation of Ts.Two Training Programs for Plant Have Been Implemented Covering TS (← links)
- 05000397/LER-1994-012, :on 940623,discovered Water in Bottom of Control Room Emergency Filter Unit WMA-FU-54B.Caused by Leaky Manual Isolation Valve.Revised Deluge System Valve Station Lineups (← links)
- 05000397/LER-1993-031-01, Provides Info Re WNP-2,Operating License NPF-21, LER 93-031-01,corrective Actions That Were Completed (← links)
- 05000397/LER-1993-022, :on 930524,two Control Rod Withdrawal Events Were Identified as Having Violated Ts.Caused by Control Rod Maintenance & Testing Not Sufficient.Sys to Improve HCU & Control Rod Implemented (← links)
- 05000397/LER-1994-002, :on 940215,seals Conservatively Declared Inoperable,Following Completion of Preliminary Analysis of Seal Program.Caused by Original Const Inadequate in Some Initial Seal.Fire Watch Established (← links)
- 05000397/LER-1994-005, :on 940326,control Rod Failed to Scram Due to Degradation of Pilot Valve Elastomers.Caused by Inservice Aging.Scram Time Tests Performed Weekly of Operable Control Rods & SSPVs Replaced (← links)
- 05000397/LER-1993-001, :on 930213,determined That Both Trains of SPC of RHR System Were Inoperable Due to LOP Coincident W/Lpci Safety Function.Reviews & Safety Evaluations Has Been Enhanced (← links)
- 05000397/LER-1991-036, :on 911226,missed ASME Section XI Test for Fuel Pool Cooling Relief Valve FPC-RV-117B Violated TS Sections 4.0.2 & 4.0.5.Cause Not Identified.Required Surveillance Testing Performed on FPC-RV-117B (← links)
- 05000397/LER-1994-008, :on 940426,CROs Observed Slight Reactor Power Fluctuations on Six Aprms.Caused by Degraded Condition of Reactor Recirculation (RRC) FCV Position Transmitter. Replaced RRC FCV Position Transmitters (← links)
- 05000397/LER-1994-009, :on 940419,CI Provisions for Two Containment Monitoring Systems Were Inoperable Due to Inboard Valves Not Functioning as Ci Valves in Event of Loca.Corrective Action:Replace EFC Valves W/Check Valves (← links)
- 05000397/LER-1994-007, :on 940410,RCIC Level 8 Isolation Instrument Calibr Outside TS Allowable Value.Caused by Failure to Self Check.Corrective Actions:Personnel Involved Counseled.W/ (← links)
- 05000397/LER-1994-006, :on 940330,discovered Broken HPCS-B1-DG 3 Battery Flag Terminal Weld.Caused by Poor Equipment Design. Damaged Battery Cell Replaced (← links)
- 05000397/LER-1993-010, :on 940304,24 Reportable Problems Identified by Failure of Procedures to Fully Implement.Cause Was Less than Adequate Barrier & Controls for Program Changes.Corrective Actions Include Procedure & TS Changes (← links)
- 05000397/LER-1994-004, :on 940307,two in-series Containment Isolation Valves MS-V-16 & MS-V-19 Inoperable Since 931217.Caused by Ambiguous Wording in Dec 1993 Operability Assessment. Procedures Modified & Training Provided (← links)
- 05000397/LER-1994-001, :on 931230,untested Fuel Transfer to EDG Fuel Oil Storage Tanks Occurred.Caused by Inadequate Design Change Documentation & Operating Procedure.Procedures Revised (← links)
- 05000397/LER-1994-003, :on 940222,inadequate Motor Operator Capability RCIC Sys Steam Supply Bypass Valve Failed to Automatically Close Following Helb.Caused by Inaccurate Vendor Info.Rcic Valve Deactivated in Normal Position (← links)
- 05000397/LER-1993-010-07, Forwards LER 93-010-07 Re Two Addl Reportable Findings of TS Surveillance Improvement Project.Rept Provides Updated Status of Corrective Actions (← links)
- 05000397/LER-1993-031, :on 931109,engineering Evaluation Determined That MCR HVAC Sys Will Not Maintain CR Temp.Caused by Inadequate Design Margin in Original Design.Per Written to Document Potential Analysis Concerns (← links)
- 05000397/LER-1992-020, :on 920508,discovered Low Elements for Low Pressure Core Spray Min Flow Control Not Properly Installed. Procedures Modified to Include Check of Instrument Startups Prior to Running Pump (← links)
- 05000397/LER-1993-028, Application for Amend to License NPF-21 for Exclusion of Single RWCU Helb,In Ref to LER 93-028-00,submitted Via (← links)
- 05000397/LER-1993-029, :on 930805,discovered Primary Coolant Steam Leak.Caused by Weld Defect.Weld Crack Repaired on 930806. Weld Record for Applicable Weld Also Reviewed & No Discrepancies Identified (← links)
- 05000397/LER-1993-027, Primary Coolant Steam Leak Discovered During Scram Recovery.Event Also Described in LER 93-027. Encl LER 93-029 Provides Separate Report,Per 10CFR50.73 (← links)
- 05000397/LER-1993-014, :on 930803,discovered Inadequate Backup Overcurrent Protection for Containment Penetrations Due to Inadequate Design Analysis Using Inaccurate & Incomplete Documentation.Changed Plant Procedure (← links)
- 05000397/LER-1993-026, :on 930619,failed to Complete Weekly Battery Surveillance Requirements within Allowed TS Interval Due to Scheduling Oversight.Initiated & Completed PPM 7.4.8.2.1.20 (← links)
- 05000397/LER-1993-025, :on 930615,Group 1 Nuclear Steam Supply Shutoff Sys Isolation Occurred During Performance of TS Surveillance Test on Turbine Throttle Valves.Caused by Procedure Deficiency.Procedure Changed (← links)
- 05000397/LER-1993-024, :on 930615,ESG Actuation of Containment Instrument Air Backup Nitrogen Bottle Programmer Occurred. Caused by Personnel Error & Procedure Deficiency.Test Procedures to Be Strengthened (← links)
- 05000397/LER-1991-010, :on 910422,inability to Isolate Primary Containment Due to Wiring Separation Error Caused by Inadequate Work Instructions.Initiated Hourly Fire Tour for Accessible Areas (← links)
- 05000397/LER-1993-009, :on 930217,existence of Noncondensible Gases in Reference Leg of RPV Instrumentation Due to Design Deficiency.Procedures Developed & Revised & Evaluation Performed (← links)
- 05000397/LER-1993-023, :on 930605,concluded That Flexible Conduit Associated W/Pressure Switches Not Seismically Supported. Caused by Improper Construction Instructions.Walkdown of Quality Class I Racks Performed (← links)
- 05000397/LER-1992-034-02, Forwards LER 92-034-02.Supplemental Rept Describes Completion of Penetration Seal Rework & Changes to Flood Watch Requirements (← links)
- 05000397/LER-1992-034, :on 920713,determined That Nonwater Tight Penetration Seals in ECCS Pump Rooms Could Result in Common Mode Failure from Flooding.Inadequate Penetration Seals in ECCS Pump Rooms Except for Door Seals Reworked (← links)
- 05000397/LER-1992-037-02, Forwards LER 92-037-02.Rev Provides Updated Info Re C/As for Manual Reactor Scram Due to Core Instability.Commitment to Obtain Amend to TS to Eliminate Requirements for Calculating T Deleted.Confusion Eliminated Through Trai (← links)
- 05000397/LER-1992-008-01, :on 920301,SGTS Fan Flow Limiter Setpoint Error Discovered.Caused by Analysis Deficiencies.Sgts Fan Flow Limiter Setpoint Changed & Rev 2 of Jco Approved W/New Offsite Dose Calculations (← links)
- 05000397/LER-1992-023, :on 930519,review of non-licensed Operator Tour Log Revealed Missed TS Surveillance & Fire Tour Data Due to Less than Adequate Work Practices.Investigation Into Event Expanded.No Violations Noted (← links)
- 05000397/LER-1993-002, :on 930121,low RPV Level Reactor Scram Initiated by RPS in Response to Low Water Level Condition. Caused by Inadvertent Actuation of Deluge Sys.Plant Procedure PPM 8.3.120 Will Be Revised (← links)
- 05000397/LER-1993-020, :on 930511,MSRV Position Indicators Not Tested Per TS Requirements Due to Poor Procedures,Inconsistency of Three Specs Re MSRVs & TS 3/4.3.7.5 for MSRV Acoustic Monitors Not Met at Required Times (← links)
- 05000397/LER-1993-021, :on 930514,discovered Potential for Water Accumulation in CAC Sys.Due to Inadequate Original Analysis of Sys Design.Drains Installed in Lowest Elevations of CAC Sys Piping (← links)
- 05000397/LER-1990-017, :on 900830,31,0906,17 & 18,HPCS Sys Inoperable as Result of 125-volt Dc Battery Inoperability.Caused by Functional Design Deficiency.Mod Planned to Battery Racks & Encls.Also Reported Per Part 21 by Limitorque (← links)
- 05000397/LER-1993-008, :on 930211,determined That Logic Sys Functional Test Requirements for Emergency Bus Undervoltage Logic Not Fully Implemented.Caused by Inadequate Procedures.New Procedures Developed (← links)
- 05000397/LER-1993-007, :on 930210,low RPV Level Reactor Scram Initiated by RPS in Response to Actual Low Water Level Condition.Caused by Connector Pin Corrosion.Suppression Pool Level Lowered (← links)
- 05000397/LER-1993-019, :on 930510,ESF Isolations & Actuations Occurred Due to 500 Kv Load Break Disconnect Failure. RHR Loop a Shutdown Cooling Restored & Plant Sys Returned to Normal Lineup Status (← links)
- 05000397/LER-1991-017, :on 910708,EDGs Automatically Started While on Backfeed Due to Undervoltage Condition,Initiated by 500 Kv Grid Disturbance.Caused by Personnel Error.Returned Unit to Startup Power Source (← links)
- 05000397/LER-1988-005, :on 880208,determined That CR Emergency Filtration Sys,Train B Bypass Flow Greater than TS Limit of 0.05 Gpm from 870923-880120.Caused by Installation Deficiency.Flow Restrictor Installed (← links)
- 05000397/LER-1993-018, :on 930428,discovered Design Condition That Could Have Impacted Plants Ability to Mitigate Accident Conditions.Caused by Less than Adequate Change Mgt.Abnormal Operating Procedures Will Be Revised (← links)
- 05000397/LER-1993-017, :on 930426,discovered That Fire Damper Seismic Qualification Concerns Identified in 1985 Through 1987,but Not Reported.Caused by Failure to Include Fire Dampers on safety-related Mechanical List.No C/A Required (← links)
- 05000397/LER-1993-010-01, Forwards LER 93-010-01,discussing Items of Reportability, Corrective Action Taken & Action Taken to Preclude Recurrence (← links)
- 05000397/LER-1993-013, :on 930318 & 0412,design Errors Noted in Component Safety Classification & Design Requirements Document Programs for RCIC Primary Containment Release path.RCIC-V-31 Closed & motor-operator Deenergized (← links)
- 05000397/LER-1993-013-01, Forwards LER 93-013-01,discussing Items of Reportability, Corrective Action Taken & Action Taken to Preclude Recurrence (← links)
- 05000397/LER-1993-011, :on 930310 & 0409,determined That Previously Performed Surveillance Testing Did Not Demonstrate Operability of Hoists Associated W/Refueling Platform.Caused by Personnel Error.Listed Procedures Changed (← links)
- 05000397/LER-1993-011-01, Forwards LER 93-011-01,discussing Items of Reportability, Corrective Action Taken & Action to Preclude Recurrence (← links)
- 05000397/LER-1993-016, :on 930331,containment Atmosphere Control Sys Primary Containment Isolation Valves Discovered Open, Resulting in Exceeding Leakage Limits.Caused by Less than Adequate Procedures.Valves Closed by Removing Jumper (← links)
- 05000397/LER-1993-015, :on 930331,unusual Event Declared as Result of Inoperability of HPCS Sys from Low Svc Water Flow Through HPCS Pump Room Cooler,Coincident w/930318 Inoperability of Rcic.Caused by Component Defect.Flow Revised (← links)
- 05000397/LER-1993-001-01, :on 930310,determined That Previously Performed Surveillance Testing Had Not Been Fully Adequate to Demonstrate Operability of Hoists.Caused by Error by Nonlicensed Util Personnel.Calibration Revised (← links)
- 05000397/LER-1993-012, :on 930311,Sys Engineer Learned That Fast Open Function of Main Turbine BPV Was Not Operable.Caused by Less than Adequate Surveillance Procedures.No Immediate Corrective Actions Were Required (← links)
- 05000397/LER-1991-005, :on 910402,determined That Oxygen Concentration in Wetwell Not Being Verified Once Per Seven Days,Per TS Due to Inadequate Procedures.Contractor Hired to Review TS SRs Against Plant Procedures (Pp) & Pp 7.0.0 Revised (← links)
- 05000397/LER-1991-009-01, Informs NRC That Seismic Monitor Will Remain at Present Location & Required 10 Day Rept Will Be Submitted Each Time Monitor Is Inoperable for More than 30 Days,Per Change Delineated in Ref Special Rept,Ler 91-09 & LER 91-09- (← links)
- 05000397/LER-1991-019, :on 910716,determined That Failure to Rept Five Periods in Excess of 30 Days of Inoperability of Rv Seismic Monitor in Violation of Ts.Caused by Inadequate Procedures. Procedures Revised (← links)
- 05000397/LER-1993-006, :on 930206,manual Reactor Scram Initiated Due to Reactor Recirculation Pump Trip While Operating in Area of Increased Awareness.Caused by Component Design Not within Parameter Limits.Procedures Changed (← links)
- 05000397/LER-1993-005, :on 930202,inadequate Documentation & Review of Operability Status Results in Unavailability of Wetwell Purge Exhaust Valve.Caused by Technical Inadequacies.Wetwell Valves Adjusted & Returned to Operable Status (← links)
- 05000397/LER-1993-004, :on 930127,determined That Two Inadequately Installed Fuses Could Have Caused Loss of RHR Capability During Seismic Event.Caused by Improper Installation of Fuses.Fuse Deficiencies Will Be Evaluated (← links)
- 05000397/LER-1991-006-01, Corrected Forwarding Ltr for LER 91-006-01,superceding Which Contained Incorrect Rept Number (← links)
- 05000397/LER-1993-003, :on 930121,determined That Under Certain Ac Electrical Distribution Sys Alignments,Fault Could Result in Unavailability of Both Offsite Power Sources.Caused by Inadequate Sys Analysis.Delay Times Revised (← links)
- 05000397/LER-1991-006, :on 910412,plant Shutdown Due to Inoperability of Div 1 Edg.Caused by Inadequately Cleaning DG 1 Lube Oil Sys & Oil Changes Recommended by Mfg Inadequate to Reduce Contamination.Addl Reservoir Installed (← links)
- 05000397/LER-1988-008, :on 880318,determined That 11 Plant TS Fire Penetration Seals Discovered Impaired.Caused by Inadequate Control of Fire Seal Penetrations.Maint Work Requests Written to Repair Penetrations (← links)
- 05000397/LER-1988-031, :on 880902,determined That Due to Single Failure CR HVAC Sys Could Operate in Recirculation Mode. Caused by Lack of Communication Between Ae Design Groups.Cr HVAC Recirculation Mode of Operation Analyzed (← links)
- 05000397/LER-1989-006, :on 890316,entry Into TS 3.0.3 Caused by Errors Discovered in Calculation for Dose Received by CR Operators During Loca.Cr Calculation Revised to Assume Zero Percent Mixing of Leakage from Containment (← links)
- 05000397/LER-1992-043, :on 921202,determined That Discrepancy Existed Between Plant Procedures & Monitoring Range of RPV Instrumentation in MCR & at Remote Shutdown Panel.Caused by Insufficient Communication.Procedures Revised (← links)
- 05000397/LER-1992-034-01, Forwards LER 92-034-01,describing Identification of Addl Unqualified Penetration Seals in ECCS Pump Room & Providing Status of Penetration Seal Rework (← links)
- 05000397/LER-1992-045, :on 921210,an Unplanned Automatic Isolation of RCIC Occurred Due to Surveillance Procedure Deficiency & Training Inadequacy.Rcic Steam Supply Instruments Will Be Improved & Personnels Will Be Trained (← links)
- 05000397/LER-1992-046, :on 921215,night Technicians Failed to Collect Main Condenser Offgas Sample within TS Time Requirements, Due to Personnel Error.Memo Issued That Will Address Requirements for Shift Personnel (← links)
- 05000397/LER-1992-044, :on 921208,HPCS Sys Pump Suction Valve Switchover Occurred,Due to Spurious Actuation of Either One or Both CST Pipe Break Detectors.Engineering Will Evaluate Replacement of Detectors & Alternate Design (← links)
- 05000397/LER-1992-041, :on 921027,offsite Power Source Determined Inoperable During Brief Periods of Prior Operaton Due to Low Voltage Condition on 230 Kv Grid.Caused by Design Deficiency & Inadequate Mgt Methods.Ts Procedure Changed (← links)
- 05000397/LER-1992-035, Responds to NRC 920831 Request for Addl Info Re LER 92-035 on Inadequate Testing of Scram Discharge Vol Vent & Drain Valves.Improvements to Plant Evaluation Requests Underway & Incident Review Board Established in June 1992 (← links)
- 05000397/LER-1992-038, :on 921014,technicians Failed to Perform Main Condenser Offgas Sample Analysis Per TS 3.3.7.12,due to Personnel Error & Inadequate Work Mgt Methods.C/A Included Counseling,Equipment Repair & Further Training (← links)
- 05000397/LER-1992-040, :on 920930,determined That Start & Load Time for Standby & HPCS DG Not Measured During Monthly Surveillance Testing.Caused by Deficiencies in Mgt Methods. Expedited Effort Initiated to Amend Procedure (← links)
- 05000397/LER-1992-039, :on 920921,RWCS Isolated on High Differential Flow While ROs Were Attempting to Place filter-demineralizer RWCU-DM-1B Back Into Service.Caused by Inadequate Mgt Methods.Degraded Equipment Repaired & Procedures Updated (← links)
- 05000397/LER-1992-035-01, Forwards LER 92-035-01.Suppls Provides Details & Clarifications Requested in NRC .Futher Review Indicates That Changes to post-mod Testing Plan Were Contributing Cause for Event (← links)
- 05000397/LER-1992-025, :on 920522,during Insp of HPCS Pump Motor,Small Piece of Aluminum Upper Air Deflector Found Lodged Inside Motor Stator.Caused by Personnel Error.Evaluation of ECCS Will Be Performed to Prevent Future Damage (← links)
- 05000397/LER-1987-025-01, Lengthens Replacement Period of Circuit Breakers in RPS Electrical Protection Assemblies,From 3 Yrs as Previously Committed to in LER 87-025-01 to 8 Yrs,Based on trouble-free Experience to Date W/Replacement of Circuit Break (← links)
- 05000397/LER-1990-009, :on 900430,three Separate Spurious Trips of RPS Electrical Protection Assembly (EPA) Circuit Breaker Occurred.Caused by Degraded Component in Logic Board of Epa. RPS-EPA-3F Breaker & Logic Board Replaced (← links)
- 05000397/LER-1990-019, :on 900912,determined That Discrepancy Existed W/Pressure Suppression Limit Curve in EOPs During NRC Team Insp of Eops.Caused by Procedural Discrepancy. Procedure Revised to Reflect Correct Curve & EOPs Reviewed (← links)
- 05000397/LER-1990-019-01, Forwards LER 90-019-01,identified in Response to Insp Rept 50-397/90-20 W/Expected Submittal Date of 910114.Rev Delayed Due to Higher Priority Work.Ler Became Part of LER Suppl Backlog (← links)
- 05000397/LER-1992-025-01, :on 920528,HPCS Pump Motor & Small Piece of Aluminum Upper Air Deflector Found Lodged in Motor Stator & Cracks Found in Deflector.Caused by Use of Improper Work Practices.Deflectors Replaced.Not Reportable Per Part 21 (← links)
- 05000397/LER-1992-036, :on 920719,primary Containment Lighting Circuit Not Deenergized as Required by Tech Specs.Caused by Technical Inaccuracy in Procedure for Plant Startup.Plant Startup Procedures & Drywell Entry Revised (← links)
- 05000397/LER-1992-033, :on 920706 & 920711,determined That SRV Failed to Reseat at Required Pressure Per Ts.Caused by Two Adjusting Rings within SRV Found Set at Wrong Position. Training Will Be Provided to Shop Personnel (← links)
- 05000397/LER-1992-031, :on 920701,potential for Exceeding Continuous Rating of Divs I & II DG 1 & 2 Identified Due to Inadequate Circuit Electrical Separation.Caused by Design Deficiency. Items Placed on Hourly Fire Tour (← links)
- 05000397/LER-1992-030, :on 920630,containment Isolation Occurred, Resulting in Shutdown of nonsafety-related HVAC Equipment & Actuation of Containment Isolation Valves.Caused by Poor Work Place Layout.Event Reviewed W/Personnel (← links)
- 05000397/LER-1992-029, :on 920624,RHR Shutdown Cooling Isolation Occurred & Shutdown Cooling Supply Line Inboard Isolation Valve Automatically Closed.Caused by Inadequate Personnel Work Practices.Shutdown Cooling Reestablished (← links)
- 05000397/LER-1992-028, :on 920617,diesel Room Normal Air Handling Fans Precluded Performance of Required Design Function.Caused by Equipment Design Deficiency.Loop Test Procedure Will Be Revised (← links)
- 05000397/LER-1992-019, :on 920430,determined That Automatic Depressurization Sys Potentially Inoperable Due to Inadequate Installation Instructions of Solenoid Pilot Valve Power Cables.Design Change Implemented (← links)
- 05000397/LER-1992-027, :on 920613,lack of Breaker Coordination Due to Instantaneous Trip Circuitry.Amptector Discriminator Circuit for Each of Six Feeder Breakers Disabled (← links)
- 05000397/LER-1992-026, :on 920605,determined That Mo of RHR Train a May Have Prevented Full Closure of Drywell Spray Supply Valve.Caused by Inadequate Testing of Plant Equipment.Mo Repaired & Tested to Perform Design Function (← links)
- 05000397/LER-1992-017, :on 920508,personnel Determined That Heat Removal Capability of Train a RHR Heat Exchanger Less than Design Allowable.Caused by Insufficient Monitoring of Plant Components.Corrective Actions Not Required (← links)
- 05000397/LER-1992-024, :on 920519,discovered Inadvertent Emergency Ventilation Actuation.Caused by Work Practices Being Less than Adequate.Technicians Were Counseled (← links)
- 05000397/LER-1992-014, :on 920326,920414 & 920512,engineers Identified TS Violations Associated W/Flow Measurements in Hpcs,Lpcs & RHR Sys,Respectively.Caused by Inadequate Design Analysis. Tests Performed to Verify Flows (← links)
- 05000397/LER-1992-022, :on 920514,plant Engineer Determined That Labyrinth Seals Installed in Replacement CAC Blowers Were Not Environmentally Qualified.Caused by Inadequate Work Practices & Procedures.Personnel Counseled (← links)
- 05000397/LER-1992-021, :on 920513,discovered That Certain QC-2 Instruments Were Not Appropriately Isolated from QC-1.Caused by Less than Adequate Design.No Corrective Action Was Taken (← links)
- 05000397/LER-1992-018, :on 920428,determined That Six Locations Not Provided W/Emergency Lighting Capacity & Operator Actions Required for Fire Outside Main CR Not in Procedures.Caused by Inadequate Design.Lighting Provided (← links)
- 05000397/LER-1992-016, :on 920424,determined That RCIC Sys Not Adequately Transferred to Remote Shutdown Panel.Caused by Misapplication of Design Inputs.Power Supply for RCIC Control Sys (48-volt Dc) Will Be Modified (← links)
- 05000397/LER-1991-003, :on 910201,review of Sp for Testing Downstream Standby Gas Treatment HEPA Filters Indicated That Methods Used Not in Compliance W/Tss Due to Inadequate air-aerosol Mixing.Appropriate Procedures Modified (← links)
- 05000397/LER-1992-013, :on 920318,annunciator for RHR B/C VLV Open Permissive Found Lit & RHR Pressure Switch Found Isolated During Startup.Cause Not Determined.Pressure Switch Returned to Svc & Annunicator & Permissive Cleared (← links)
- 05000397/LER-1992-012, :on 920318,determined That Removal of Access Plugs Over RHR Pump Rooms a & B Exposed Both Rooms to Potential Flooding from Common Source.Caused by Faulty Mgt Methods.Interim Guidance Provided (← links)
- 05000397/LER-1992-015, :on 920413,unexplained Pressure Drop in ADS B Section of Containment Instrument Air Sys Header Occurred. Caused by Inadequate Written Procedures.Valve CIA-V-41B Inspected & PPM-8.9.130 Replaced (← links)
- 05000397/LER-1992-011, :on 920305,discovered That Method of CRD Hydraulic Isolation Did Not Meet TS Requirements.Caused by Less than Adequate Procedures Due to Omission of Relevant Info in Procedure.Exhaust Water Valve Closed (← links)
- 05000397/LER-1992-010, :on 920303,standby Gas Treatment Differential Pressure Controller Setpoint Error Identified.Caused by Analysis Deficiency.Setpoint Methodology Program to Review Selected non-harsh Setpoints Extended (← links)
- 05000397/LER-1992-009, :on 920302,determined That Containment Instrument Air Pressure Switch Setting Changes Required. Caused by Analysis Deficiency.Pressure Switches Were Reset in Accordance W/New Setpoint Calculations (← links)
- 05000397/LER-1992-008, :on 920301,standby Gas Treatment Sys Fan Flow Limiter Setpoint Error Identified.Caused by Analysis Deficiency.Investigation Into Instrument Setpoint Accuracy Ongoing (← links)
- 05000397/LER-1991-029, :on 911031,discovered That Incorrect Containment Atmospheric Control Recycle Flow Control Controllers Installed in Both Divs in Control Room.Caused by Less than Adequate Design.Procedures Changed (← links)
- 05000397/LER-1992-007, :on 920225,both Divs of Primary Containment Atmosphere Control Hydrogen Recombiner Sys Inoperable & Plant Shutdown Initiated.Caused by Less than Adequate Design.Design Changes Implemented (← links)
- 05000397/LER-1991-013-02, Responds to NRC Re Violations Noted in Insp Rept 50-397/91-46.Corrective Actions:Quality Action Team Has Been Authorized to Recommend Potential Improvements in TS Surveillance Program,As Documented in LER 91-013-02 (← links)
- 05000397/LER-1992-005, :on 920219,thermal Overloads Prevented Motors from Performing Safety Functions.Caused by Misapplication of Design Inputs.Motors Replaced (← links)
- 05000397/LER-1992-006, :on 920220,reactor Bldg to Suppression Chamber Vacuum Breaker Setpoints Were Incorrectly Set.Caused by Analysis Deficiency.Setpoint Documentation Changed & Procedures Deviated & Setpoints Reset (← links)
- 05000397/LER-1992-004, :on 920227,noted Scram Discharge Vol Level Switches Not Tested Post Scram as Required.Caused by Testing Not Being Performed.Corrective Actions Were Not Required (← links)
- 05000397/LER-1992-003, :on 920123,circulating Fan CAC FN-1B Failed to Start During Performance of Surveillance Test.Caused by Tripped Overloads.Thermal Overloads Reset & Surveillance Test Performed (← links)
- 05000397/LER-1992-002, :on 920113,determined That MSIV Leakage Control Sys Fan Testing Incorrectly Performed.On 920127, Determined That Setpoint for Pressure Switch Did Not Ensure Proper Sys Operation.Ts Waiver Obtained (← links)
- 05000397/LER-1992-001, :on 920102,high Pressure Core Spray Declared Inoperable Due to Battery Inoperability.Caused by Instructional Presentation Deficiencies in TS Requirements. Notes Were Added to Surveillance Procedure (← links)
- 05000397/LER-1991-035, :on 911220,plant Manually Scrammed to Complete Controlled Shutdown Due to High Coolant Conductivity. Caused by Failed Tube in Main Condenser.Condenser Tube Plugged (← links)
- 05000397/LER-1991-022, :on 910905,inboard RHR Sys Shutdown Cooling Supply Valve Automatically Isolated on High Suction Line Flow Signal.Caused by Instrumentation Drift.Sys Realigned & Loop B Placed Back in Svc (← links)
- 05000397/LER-1991-033, :on 911120,250 Volt DC Bus Inoperable Due to Lack of Adequate Fuse Coordination.Caused by Less than Adequate Design Analysis.Fuses Replaced (← links)
- 05000397/LER-1991-034, :on 911123,residual Heat Removal Sys Differential Pressure Indicating Switch Found Isolated.Cause Indeterminate.Surveillance completed.RHR-DPIS-12B Restored to Svc (← links)
- 05000397/LER-1991-032, :on 911119,reactor Scram Occurred as Result of Main Turbine Governor Valve Fast Closure.Caused by Failed Capacitor in Feedwater Summation Circuitry.Plant Maneuvered to Safe Shutdown Condition (← links)
- 05000397/LER-1991-030, :on 911104,small Leak Noted in Welded Connection Between RHR Sys Drain Valve & RHR Loop a Shutdown Cooling Return Valve.Caused by Const Fabrication Defect.Rhr Valve V-161A Isolated from RCS (← links)
- 05000397/LER-1991-031, :on 911104,determined That intermediate-range Monitor Control Rod Block Channel Calibrs Not Performed at TS Required Frequency.Caused by Less than Adequate Procedures.Calibr Procedures Performed (← links)
- 05000397/LER-1991-027, :on 910930,question on Jet Operability & Surveillance Applicability in Operational Conditions 1 & 2 Below 25% Rated Thermal Power Raised.Caused by Inadequate Procedure.Ts Amend Request Will Be Submitted (← links)
- 05000397/LER-1991-028, :on on 910930,containment Airlock Door Seal Leakage Test Not Performed within Allowable Surveillance Interval.Caused by Inadequate Personnel Work Practices. Master Startup Checklist Amended (← links)
- 05000397/LER-1991-026, :on 910918,main Control Room Received Alarms, Indicating RWCU HX Room High Temp & RWCU Outboard Isolation Valve Automatically Closed.Caused by Failed Electric Component.Circuit Input Card Replaced (← links)
- 05000397/LER-1991-025, :on 910911,train a of Containment Atmosphere Control Sys Rendered Inoperable for More than 30-day Limit Permitted by Ts.Caused by Loss of Oil from Recombiner Blower.Train a & Recombiner Blower Repaired (← links)
- 05000397/LER-1991-024, :on 910909,unanalyzed Condition Associated W/ Postulated Main Steam Line Failure Outside Containment Discovered by Ge.Caused by Failure to Consider Iodine Source Term.Procedure Re Cold Startup Changed (← links)
- 05000397/LER-1991-023, :on 910906,HPCS Sys Pump Suction Switchover from Condensate Storage Tanks to Suppression Pool Occurred During Maint Testing.Caused by Incomplete Planning & Scheduling.Operators Realigned HPCS Suction (← links)
- 05000397/LER-1991-013, :on 910507,non-compliances W/Tech Specs Identified as Part of Program of Surveillance Procedure Verification.Further Evaluation Performed.Quality Action Team to Be Chartered to Evaluate Program (← links)
- 05000397/LER-1991-021, :on 910801,determined That Tritium Sampling Was Not Being Performed During Startup,Shutdown & 15 Percent Power Change Evolutions.Caused by Inadequate Procedure/ Procedure Review.Changed Procedure (← links)
- 05000397/LER-1991-018, :on 910712,control Room Emergency Filtration & Standby Gas Treatment Sys Carbon Absorber Surveillances Not Performed Per TS 4.7.2 Requirements.Caused by Inadequate Procedures.Carbon Replaced (← links)
- 05000397/LER-1991-020, :on 910716,discovered That RHR Valve B Capability to Shutdown in Event of Fire Could Be Jeopardized Due to Hot Short in Control Circuits.Caused by Design Deficiency.Wiring Changes Implemented.W/Undated Ltr (← links)
- 05000397/LER-1991-016, :on 910707,ESF Actuation Occurred.Caused by Blown Rupture Disk.Corrective Actions Taken to Replace Blown Rupture Disk & to Test Relief Valves for Proper Operating Pressure (← links)
- 05000397/LER-1990-023, :on 901004,pressure Loss Occurred in Containment Instrument Air Sys When Relief Valve CIA-RV-2 Opened Prematurely.Caused by Inadequate Mgt Programs & Work Practices.Sys Requirements Reviewed (← links)
- 05000397/LER-1991-015, :on 910602,high HPCS Sys Pump Suction Switchover from Condensate Storage Tanks to Suppression Pool Occurred.Caused by Personnel Error.Operator Involved Ack & Reset Alarm (← links)
- 05000397/LER-1991-014, :on 910510,RHR Shutdown Cooling Isolation Occurred Due to Less than Adequate Design Drawing Info. Affected Drawings Revised & Tagging Sys to Indicate Sys Interrelationship Updated (← links)
- 05000397/LER-1991-012, :on 910506,manual Initiation of Reactor Protection Sys Occurred Due to Low Scram Air Header Pressure.Caused by Hose Failure.Hose Replaced (← links)
- 05000397/LER-1991-011, :on 910429,ESF Actuation Occurred as Wire in Control Room Panel Inadvertently Cut.Caused by Equipment/ Design Deficiency.Operators Replaced Blown Fuse & Reset Isolation Logic Signal (← links)
- 05000397/LER-1989-043, :on 891121,HPCS Sys Immediately Declared Inoperable.Caused by Equipment Failure.Failure Analysis & Determination of Root Cause of HPCS-V-23 Failure Performed & HPCS Operability Surveillance Revised (← links)
- 05000397/LER-1991-007, :on 910415,reactor Scram & Shutdown Cooling Insulation Occurred Causing Automatic Actuation.Caused by Inadequate Work Instruments.Plant Control Room Operators Reset Scram Signal (← links)
- 05000397/LER-1991-009, :on 910417,ESF Actuation & RWCU Isolation Occurred When Electricians Cut Wires to Plug of Wind Direction Recorder,Causing Voltage Drop.Caused by Equipment Installation Error.Wires Reversed (← links)
- 05000397/LER-1991-008, :on 910416,reactor Declared in Mode 5 (Refueling) W/Average Reactor Coolant Temp of 140 F.Caused by Less than Adequate Procedures.Temp Reduced & Upper Temp Limits Incorporated Into Plant Procedures (← links)
- 05000397/LER-1991-004, :on 910328,two Deficiencies Noted in Thermolog Application on Critical Cable Tray Running Through Div 1 Area.Caused by Inadequate Installation of Thermolog.Fire Tour of Cable Spreading Room Retained (← links)
- 05000397/LER-1990-022, :on 900930,pressure Decrease Occurred in Containment Instrument Air Sys When Nitrogen Cryogenic Tank Was Inadvertently Depleted.Containment Nitrogen Inerting Procedures PPM 2.3.1 & 2.3.7 Revised (← links)
- 05000397/LER-1990-030, :on 901117,discovered That Outboard RCIC Turbine Steam Supply Isolation valve,RCIC-V-8 Returned to Svc W/Unacceptable Stroke Time Due to Inadequate Procedures. Valve RCIC-V-8 Stroke Time Changed (← links)
- 05000397/LER-1991-001, :on 910108,RCIC Turbine & Equipment Area Temp Alarms Received & Outboard Isolation Valve Automatically Closed.Caused by Failure of Electronic Component Re Printed Circuit Input Card.Circuit Card Replace (← links)
- 05000397/LER-1991-002, :on 910110,reactor Recirculation Sys Jet Pump Operability Surveillance Testing Did Not Meet Literal Compliance W/Tech Specs.Caused by Inadequate Procedure. Procedure Revised (← links)
- 05000397/LER-1990-031, :on 901207,reactor Scram Occurred Due to Actuation of Reactor Protection Sys Logic.Caused by Shorted Transformer Output Line.Damaged Insulator Stack Replaced (← links)
- 05000397/LER-1990-032, :on 901211,plant Sys Engineer Discovered Cross Connection Between Reactor Bldg Exhaust Air Sys & Sanitary Drain Sys in Reactor Bldg.Caused by Design Deficiency. Mechanical Seal Installed (← links)
- 05000397/LER-1990-028, :on 901023,degradation of Primary Containment Pressure Boundary Caused Plant Shutdown,Due to Cracks on HPCS Small Bore Piping (← links)
- 05000397/LER-1990-029, :on 901108,inadequate Containment Penetration Testing Associated W/Wetwell Hatch Pressure Warning Devices Discovered (← links)
- 05000397/LER-1990-026, :on 901024,inadequate Electrical Power Supply Separation Discovered in Two Control Room Panels Due to Design Error (← links)
- 05000397/LER-1990-024, :on 900907,diesel Generator Started on Undervoltage Due to Voltage Disturbances (← links)
- 05000397/LER-1990-027, :on 901030,diesel Fuel Oil Not Tested for Sulfur Content & Water in Accordance W/Tech Specs (← links)
- 05000397/LER-1990-021, :on 900925,operators Manually Scrammed Reactor After Experiencing Main Turbine Hydraulic Control Oil Pressure Problems (← links)
- 05000397/LER-1990-020, :on 900917,util Determined Overheating of Control Cabinet Could Cause Diesel Generator Failure (← links)
- 05000397/LER-1990-018, :on 900904,ESF Actuation of Containment Instrument Air Sys Occurred as Result of Inadvertent Manual Relief Valve Blowdown.Manual Actuator Removed & Lighting Fixture Secured (← links)
- 05000397/LER-1990-016, :on 900806,steam Supply Line Isolation Valve for RCIC Sys Turbine Discovered to Have Unacceptable Closing Time.Caused by Personnel Error.Personnel Counseled & Trained on ASME Test Program & Generic Ltr 89-04 (← links)
- 05000397/LER-1990-015, :on 900806,diesel Fuel Oil Analysis Tech Spec Surveillance Verification Time Requirement Exceeded.Caused by Inadequate Procedure & Work Practices.Temporary Procedure for Diesel Generator Fuel Sampling Cancelled (← links)
- 05000397/LER-1989-011, :on 890502,determined That Eight Valve Motors Did Not Meet Plant Commitment Made in Response to IE Circular 81-13.Caused by Less than Adequate Design Basis Documentation.Plant Mod Request Revised (← links)
- 05000397/LER-1990-012, :on 900527,failure of Diesel Generator Slip Ring End Bearing Resulted in Fire in Bearing Area.Caused by Mfg Error,Design Deficiency & Personnel Error.Emergency Operating Procedures Used to Deal W/Fire (← links)
- 05000397/LER-1989-010-01, :on 890501,experienced Momentary Loss of 120-volt Ac Power to Bus & on 890503,bus Suffered Sustained Loss of 120-volt Ac Power.Caused by Nameplate Falling Into Reactor Protection Sys Bus a Supply Circuitry (← links)
- 05000397/LER-1990-014, :on 900703,HPCS Sys Pump Suction Switchover from Condensate Storage Tanks to Suppression Pool Occurred Due to Suppression Pool High Water Level Condition.Caused by Procedural Inadequacy.Procedures Modified (← links)
- 05000397/LER-1990-013, :on 900610,ESF Isolations & Actuations Occurred Due to Breaker Trip.Cause of Event Not Determined.Power Restored to E-MC-7A & Isolations Restored (← links)
- 05000397/LER-1990-011, :on 900521,HPCS Sys Pump Suction Valve Switchover Actuation Occurred During Annual Maint.Cause Unknown.Plant Procedure 7.4.3.3.1.58 Completed on 900603 (← links)
- 05000397/LER-1989-040, :on 890919,determined That Under Certain Meteorological Conditions Situation Would Be Created Not within Licensing Basis Consideration for Secondary Containment Performance (← links)
- 05000397/LER-1990-010, :on 900517,secondary Containment Isolation Occurred During Reactor Refueling Outage.Caused by Inadequate Work Control.Work Control Procedures Will Be Reviewed to Determine If Addl Steps Needed (← links)
- 05000397/LER-1990-008, :on 900416,seismic Monitoring Instrumentation Determined Inadequate.Caused by Inadequate Procedures.Vendor Requested to Provide Proper Calibr of Instrument.Plant Procedures Revised to Reflect Calibr (← links)
- 05000397/LER-1988-037, :on 881130,plant Shutdown Initiated Due to Containment Supply Purge Valve Air Vol Leak Exceeding Tech Spec Limits.Caused by Damaged CSP-V-9 Rubber Seat.Damaged Seat Replaced W/New Seat Matl (← links)
- 05000397/LER-1990-007, :on 900314,review of Plant Procedures Associated W/Diesel Generator Fuel Oil Testing Showed No Requirement to Check for Water in Day Tanks.Caused by Less than Adequate Procedure Preparation (← links)
- 05000397/LER-1990-006, :on 900308,10CFR50 App R Cable Fire Protection Review Identified 12 New Cables in Fire Areas Vulnerable to Design Basis Fire.Caused by Equipment Design Deficiency. Items Placed on Hourly Fire Watch (← links)
- 05000397/LER-1990-005, :on 900209,nonsafety-related Circuit Breaker on Power Panel Tripped,Resulting in ESF Actuation.Caused by Equipment Mfg Error Involving Defect in Circuit Breaker Tripping Mechanism.Defective Breaker Replaced (← links)
- 05000397/LER-1990-004, :on 900208,HPCS Diesel Generator Declared Inoperable for Performance of Corrective Maint to Investigate Previous Trip of Output Circuit Breaker Which Occurred on 900204.New Droop Switch Installed (← links)
- 05000397/LER-1989-038, :on 890121,two 3/8-inch Drain Line Valves Associated W/Standby Liquid Control Flow Transmitter Not Labeled & Not Contained in Checklist.Caused by Inadequate Procedures.Walkdown Will Be Conducted (← links)
- 05000397/LER-1989-033, :on 890811,RWCU Isolation Occurred When Fuse in Power Supply to Leak Detection Monitor Blew,Giving False High Alarm Signal to Isolation Logic.Cause Unknown.Fuse Replaced & RWCU Sys Restored to Operation (← links)
- 05000397/LER-1990-003, :on 900126,HPCS Sys Pump Suction Valve Switchover Occurred During Performance of Procedure for Draining Ref Leg.Caused by Plant Configuration.Sys Restored to pre-event Lineup Status (← links)
- 05000397/LER-1990-002, :on 900118,discovered That Main Steam Solenoid Pilot Valves Inoperable from June 1986 to June 1989.Caused by Personnel Error Due to Installation of Unqualified Power Connector.Connector Replaced (← links)
- 05000397/LER-1990-001, :on 900103,diesel Generator Sys Declared Inoperable Due to Failed Diesel Fuel Tech Spec Surveillance. Caused by Fuel Oil Sampling Method.Independent Consultant Hired to Assess Diesel Fuel Program (← links)
- 05000397/LER-1989-045, :on 891201,two 3/4-inch Test Connection Valves Located Between Containment & Outboard Isolation Valve on Primary Coolant Sample Line Not Included in Surveillance. Caused by Personnel Error.Instruction Added (← links)
- 05000397/LER-1989-044, :on 891128,discovered Six Incorrectly Sized Thermal Overload Heaters That Could Have Prevented HPCS from Performing Safety Function.Caused by Inadequate Design. Procedures Revised (← links)
- 05000397/LER-1989-010, :on 890501,power Lost to Reactor Protection Sys 120-volt Instrument Bus a Twice,Causing ESF Actuations. Caused by Metal Nameplate Falling Into Power Supply Circuitry.Nameplates Removed from Panels (← links)
- 05000397/LER-1989-042, :on 891106,pressure Switch,Which Provides Input to Logic Calibr,Outside Tech Spec Limits.Caused by Inadequate Procedures W/Ambiguous Instructions.Surveillance Procedures Revised (← links)
- 05000397/LER-1989-041, :on 891103,determined That Motor for Valve Operator Associated W/Rhr Sys Valve Does Not Provide Sufficient Starting Torque at Degraded Voltage Conditions. Cause Indeterminate (← links)
- 05000397/LER-1989-039, :on 890914,discovered Three Discrepancies W/ Current Configuration of Reactor Bldg Exhaust Air Radiation Monitoring Sys That Do Not Satisfy Design Basis Requirements (← links)
- 05000397/LER-1989-036, :on 890905,discovered That Present Surveillance Procedures Do Not Provide for Independent Measurement of Two Values.Caused by Less than Adequate Surveillance Procedures on Response Time Testing of APRM Sys (← links)
- 05000397/LER-1989-037, :on 890830,differential Pressure Indicating Switch RHR-DPIS-12B Discovered Isolated & Equalized.Cause Not Determined.Instrumentation & Control Work Practices Manual Developed & Training Provided (← links)
- 05000397/LER-1989-035, :on 890817,reactor Scram Occurred During Surveillance Testing of Reactor Level Instrument Associated W/Automatic Depressurization Sys.Caused by Personnel Error. Training Improved & Visibility Increased (← links)
- 05000397/LER-1989-031, :on 890806,low Reactor Pressure Vessel Level Reactor Scram Initiated by Reactor Protective Sys in Response to Actual Low Water Level Condition Caused Unplanned Trip of Reactor Feedwater Pump 1B (← links)
- 05000397/LER-1989-034, :on 890811,six Class 1E 480 Volt Ac Motor Control Ctrs Declared Inoperable Due to Design Deficiency. Caused by Exclusion of Fault Tripping Coordination. Distribution Sys to Be Evaluated (← links)
- 05000397/LER-1989-032, :on 890810,discovered That non-Class 1E 120 Volt Ac Electrical Power Supply Branch Circuit Violated Electrical Separation Criteria.Caused by Equipment/Design Deficiency/Spec Less than Adequate (← links)
- 05000397/LER-1989-027, :on 890630,determined That Two Seismic Supports Missing on PASS Containment Isolation Valves.Caused by Inadequate Work Practices & Training of Project Personnel. Tech Spec Action Statement 3.6.1 Entered (← links)
- 05000397/LER-1989-030, :on 890210,HPCS Suction Valve from Suppression Pool Failed to Fully Open During Surveillance Procedure. Caused by Motor Operator HPCS-MO-15 Mfg Design Defect.Tech Spec Action Statements Entered & Valve Closed (← links)
- ML071420042 (redirect page) (← links)
- GO2-14-049, Relief Request for the Columbia Generating Station Fourth Ten-Year Interval Inservice Testing Program (← links)
- GO2-15-055, Submittal of Fourth 10-Year Inservice Testing (IST) Program Plan (← links)
- 05000397/LER-2007-005, Regarding Inoperable Diesel Generator Due to Inadequate Procedure That Caused Potential Transformer Fuses to Clear During Shut Down of the Diesel (← links)
- 05000397/LER-2007-004, Re Reactor Scram Due to Tripped Condensate Booster Pump (← links)
- 05000397/LER-2007-003, Re Technical Specification Required Shutdown Due to Inoperable AC Electrical Power Subsystem (← links)
- 05000397/LER-2007-002, Re Discrepancy in Special Nuclear Material Inventory (← links)