Pages that link to "05000440/LER-2025-001"
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The following pages link to 05000440/LER-2025-001:
Displaying 50 items.
- 05000440/LER-1987-057, :on 870813,reactor Protection Sys Actuation Occurred Due to Deficient Change to Surveillance Instructions.Caused by Inadequate Instruction for Flushing Sensing Lines.Surveillance Instructions Revised (← links)
- 05000440/LER-1987-056, :on 870812,RWCU Containment Inboard Isolation Valve Closed.Caused by Procedural Error of Wrong Terminal Identification.Surveillance Instruction Revised to Identify Correct Terminal Number (← links)
- 05000440/LER-1987-076, :on 871203,main Steam Drain Line Isolations Occurred.Caused by Inadequate Surveillance Instructions. Instructions Revised (← links)
- 05000440/LER-1987-054, :on 870722,discovered That Suppression Pool Swell Deflector Shields Required by Design Not Installed for Six Limitorque Operators.Shields Installed & as-built Drawings Completed to Reflect Installation (← links)
- 05000440/LER-1987-055, :on 870729,reactor Protection Sys Actuation Occurred Due to Trip Signal Generated by Neutron Monitoring Sys Aprm.Caused by Misposition of Switch S-3 on APRM Card. Failed APRM Card Replaced & Tested (← links)
- 05000440/LER-1987-053, :on 870714,discovered That Readings for Control Room Radiation & Source Range Neutron Monitors Not Recorded & Actions Required by Tech Specs 3.3.7.1 & 3.3.7.6 Not Taken on 870713.Caused by Personnel Error (← links)
- 05000440/LER-1987-075, :on 871114,Tech Spec Violated Due to Plant Exceeding 150 Psig W/Rcic Sys Inoperable.Caused by Personnel Error.Shift Supervisor Disciplined.Licensed Operator Will Be Formally Trained on Incident (← links)
- 05000440/LER-1987-074, :on 871114,RCWU Inboard Containment Isolation Occurred Due to High Differential Flow.Caused by Detector Low Flow Inaccuracies & Low Voltage Clip at Square Root Converters.Flow Design Will Be Evaluated & Changed (← links)
- 05000440/LER-1998-002-01, :on 980701,trip Unit Failure Initiated RCIC W/ Subsequent Reactor Scram.Caused by Design Application of Optical Isolator.Replaced Failed & Damaged Components & Verified Initiation Relay Contacts (← links)
- 05000440/LER-1987-073, :on 871029,three MSIVs Failed to Fast Close in Time Required by Tech Specs 3.4.7 & 3.6.4.On 871103,two MSIVs Failed to Close.Caused by Sticking of Fast Closure Dual Solenoid Air Pilot Valves.Elastomer Discs Replaced (← links)
- 05000440/LER-1987-072, :on 871027,following Improper Transfer of Station Loads,Reactor Scram Occurred Due to Reactor Water Level of Less than Level 3.Caused by Personnel Error. Engineering Design Change Will Be Implemented (← links)
- 05000440/LER-1987-071, :on 871027,RWCU Sys Containment Isolation Occurred.Caused by Faulty Temp Switch Module.Leak Detection Isolation Logic Bypass Switches Placed in Bypass Position When Performing Once Per Shift Channel Checks (← links)
- 05000440/LER-1987-070, :on 871024,loss of Reactor Protection Sys Bus Occurred Due to Overvoltage Trip of Electrical Protection Assembly.Cause Undetermined.Potential Cause Isolated to Voltage Regulator.Regulator Replaced (← links)
- 05000440/LER-1987-051, :on 870705,primary Containment Leakage Rate Through MSIV Lines A,B & D Exceeded Tech Spec 3.6.1.2.Caused by Worn MSIV Seats Due to Component Wear & Inadequate Mating & Sealing of Bonnet Pressure Seal Ring (← links)
- 05000440/LER-1987-027, :on 870413,manual Fast Reactor Shutdown Conducted Due to Loss of Condenser Vacuum & Steam Leak in Reactor Bldg.Vacuum Loss Caused by Hole in 24-inch Main Steam Drain Manifold.Manifold Replaced (← links)
- 05000440/LER-1986-040, :on 860728,main Steam Line Leak Detection Differential Pressure Trip Units Read Downscale.Caused by Misunderstanding of Tech Spec Action Statement.Operators Trained (← links)
- 05000440/LER-1987-052, :on 870703,04 & 05,operators Failed to Place Inoperable Intermediate Range Neutron Monitor (IRM) Channels in Tripped Condition.Caused by Personnel Error.Irm Detectors Replaced.Licensed Operators Will Be Counseled (← links)
- 05000440/LER-1987-050, :on 870704,unexpected Reactor Protection Sys Actuation Occurred Due to Upscale Trip of Neutron Monitoring Sys Intermediate Range Monitor.Caused by Grounding Deficiencies in Plant Ground Grid.Design Change Initiated (← links)
- 05000440/LER-1987-049, :on 870704,false High Pressure Signal Caused Closure of RHR Shutdown Cooling Suction Outboard Containment Isolation Valve.Caused by Procedure Deficiency in Plant Instructions.Instructions Revised & Plant Response Reviewed (← links)
- 05000440/LER-1987-048, :on 870703,containment Fire Hose Reel Inboard/ Outboard Supply Isolation Valves Discovered in Open Position Since 870622.Caused by Procedural Deficiency.Integrated Operating Instructions Will Be Reviewed & Revised (← links)
- 05000440/LER-1987-047, :on 870702,plant Operators Failed to Demonstrate Operability of Offsite Electrical Power Sources within 8 H.Caused by Personnel Error.Personnel Will Receive Training on Correct Tech Spec Interpretation (← links)
- 05000440/LER-1987-046, :on 870701,RWCU Sys Isolation Occurred Due to RWCU HX Room Leak Detection High Temp Signal.Caused by Technician Placing Air Sampler in Manner That Hot Air Blew Over Sensor.Technicians Counseled (← links)
- 05000440/LER-1987-069, :on 870930,unexpected Annulus Exhaust Gas Treatment Sys Train B Auto Start Following Transfer of Operating Trains.Cause Unknown.Repetitive Task Revised to Increase Frequency for Switching Trains to Twice Month (← links)
- 05000440/LER-1987-068, :on 870929,RHR Shutdown Cooling Inboard Isolation Occurred.Caused by Personnel Not Paying Sufficient Attention to Detail to Identify Any Drifting in Pressure Regulator During Performance of Test.Procedures Revised (← links)
- 05000440/LER-1987-045, :on 870630,manual Reactor Scrammed Due to Generator Bushing Failure & Resultant Increased Hydrogen Concentration.Caused by Bushing Sealing Compound Overheating & Melting.Bushings Replaced (← links)
- 05000440/LER-1987-066, :on 870926,Tech Spec 4.8.1.1.2.e.14.a Found Violated.Caused by Discovery of Inadequate Testing of All Divs 1 & 2 Standby Diesel Generator Lockout Features Due to Inadequate Procedures.Procedures Revised & Features Tested (← links)
- 05000440/LER-1987-044, :on 870624 & 28,RCIC Sys Automatically Isolated.Caused by Pressure Oscillations in Rcic/Leak Detection High Flow Instrument Process Lines.Leaking Transmitter Test Connection Repaired (← links)
- 05000440/LER-1987-043, :on 870622,during Annulus Exhaust Gas Treatment Sys (AEGTS) Operability Test,Aegts Exhaust Fan a Started Automatically.Caused by Instrument Drift of AEGTS Exhaust Fan B Differential Pressure Switch.Switch Setpoint Calibr (← links)
- 05000440/LER-1987-042, :on 870617,reactor Protection Sys Electrical Protection Assembly Breaker Tripped,Resulting in Deenergization of Bus A.Caused by Failure of Assembly Logic Card.Card Replaced (← links)
- 05000440/LER-1988-001, :on 880103,reactor Scram Occurred Due to Upscale Trip on intermediate-range Neutron Monitors.Caused by Excessive Feedwater Injection Into Reactor Vessel While Adjusting Potentiometer.Low Speed Stop Lowered (← links)
- 05000440/LER-1987-065, :on 870914,main Steam Drain Line Inboard Isolation Valve Closed Unexpectedly Due to Nssss Isolation Signal During Testing.Caused by Bad Connection in Channel C Isolation Logic (← links)
- 05000440/LER-1987-064, :on 870909,feedwater Pump Overspeed & Change in Feedwater Flow Control Signal Resulted in Reactor Scram,Hpcs Injection & RCIC Initiation.Caused by Procedural Error in Periodic Test Instruction (Pti).Pti Revised (← links)
- 05000440/LER-1987-063, :on 870906,RCIC Sys Isolation Occurred.Cause Undetermined.Engineering Design Change Initiated to Provide Indication of RCIC Trip Delay Status When Taking RCIC Ld Isolation Channels from Bypass to Normal (← links)
- 05000440/LER-1987-062, :on 870828,RHR Head Spray Containment Isolation Valve Energized in Violation of Tech Spec 3.6.4.Caused by Personnel Error.Operator Involved Counseled Re Need for Greater Attention to Detail (← links)
- 05000440/LER-1987-040, :on 870604,RCIC Sys Leak Detection High Steam Flow Trip Unit Noted to Be Reading Downscale.Caused by Steam Condensing in High Side Instrument Process Line of Associated Transmitter (← links)
- 05000440/LER-1987-061, :on 870830,Tech Specs Violated When Inner Air Lock Door Not Maintained Closed W/Outer Air Lock Door Inoperable.Caused by Bushing Failure.Bushing Replaced & Design Change for Air Lock Door Initiated (← links)
- 05000440/LER-1987-060, :on 870822,turbine Bldg/Heater Bay Vent Radiation Monitor Found to Have Been Inoperable for Approx 19 H.Caused by Personnel Error Due to Inattention to Detail. Tagging Error Corrected & Noble Gas Sample Drawn (← links)
- 05000440/LER-1987-059, :on 870821,RWCU Containment Isolation Occurred Due to Indicated High Differential Flow.Caused by Particulate Buildup in Flow Control Valve Positioner Air Flow Restriction Orifice (← links)
- 05000440/LER-1997-008, :on 970807,TS Limit for RCS Heatup/Cooldown Was Not Exceeded Due to Conservative Use of RPV Bottom Head Drain Temperature.Caused by Inadequate Transit Monitoring. Revised Reactor Scram off-normal Instruction (← links)
- 05000440/LER-1997-008-01, Forwards LER 97-008-01,TS Limit Not Exceeded Due to Conservative Use of Reactor Pressure Vessel Bottom Head Drain Temp as Indicator of RCS Heatup/Cooldown Rate.No TS Violation Occurred.Event 32737 Retracted for Listed Reason (← links)
- 05000440/LER-1997-012, :on 970923,reactor Protection Sys Actuation Occurred.Caused by Insufficient Procedural Guidance.Rps Sys Operating Instruction Revised to Include Table/Checklist of Reactor Mode Switch Positions & Effects on RPS Signals (← links)
- 05000440/LER-1997-010, :on 970911,loss of Electrical Power to Reactor Protection Sys Bus Occurred.Caused by Electrical Protective Assembly (EPA) Trip.Replaced EPA Logic Control Board & Associated Molded Case Circuit Breaker (← links)
- 05000440/LER-1997-010-01, Forwards LER 97-010-01 Re Loss of Electrical Power to Reactor Protection Sys Due to Electrical Protective Assembly Trip.Supplemental Rept Submitted to Correct Minor Technical Error in Original Rept (← links)
- 05000440/LER-1999-004, :on 990916,loss of Safety Function Resulted in TS 3.0.3 Entry.Caused by Design Deficiency in Control Complex Architectural Walls.Revised Storm Contingencies Instructions.With (← links)
- 05000440/LER-1987-035, :on 870524,reactor Protection Sys Manual Reactor Scram Initiated in Response to Leak in Condensate Sys.Caused by Excessive Vibration of Condensate Sys.Design Change Under Development (← links)
- 05000440/LER-1986-066, :on 861006,RCIC Sys Isolated During Performance of Main Steam Line Tunnel High Temp Channel Functional Surveillance Test.Cause Undetermined.Rcic Sys Restored to Standby Readiness (← links)
- 05000440/LER-1987-026, :on 870411,unexpected RWCU Containment Isolation Occurred.Caused by Inaccurate Differential Flow Indication at Low RWCU Flow & Low Reactor Pressure Conditions.Bias Signal to Flow Summer Changed (← links)
- 05000440/LER-1986-064, :on 860925,leak Detection Sys Isolation Logic Div 2 for Rwcu,Rcic & RHR Sys Inoperable for Period Exceeding Tech Spec Limit.Caused by Personnel Error. Personnel Counseled (← links)
- 05000440/LER-1986-063, :on 860923,discovered That on 860918,Unit 1 Div 3 125-volt Dc Distribution Bus ED-1-C Disconnected from Unit 1 Div 3 Battery & Normal Charger & cross-connected to Unit 2 Div 3 Battery & Charger.Procedure Revised (← links)
- 05000440/LER-1987-025, :on 870407,outboard Containment Isolation Valves for RHR Sys a Automatically Isolated.Caused by High Pressure Signals from Loose Signal Connection.Single Common Wire Properly Connected to Signal Common Bar (← links)