Pages that link to "05000244/LER-1980-001, Forwards LER 80-001/03L-0"
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The following pages link to 05000244/LER-1980-001, Forwards LER 80-001/03L-0:
Displayed 6 items.
- ML17256A352 (← links)
- ML17250A526 (← links)
- ML17249A709 (redirect page) (← links)
- ML17261A175 (← links)
- ML17249A710 (← links)
- 05000244/LER-1980-001-03, /03L-0:on 800118,while Performing PT-12.1, Emergency Generator 1A Would Not Accept Nameplate Steady Load Rating.Caused by Adjusting Governor Setting to Incorrect Value Indicated on Dynotape Sticker Setting Mod (← links)
- 05000244/LER-1980-001, Forwards LER 80-001/03L-0 (← links)
- 05000244/LER-1980-005, Forwards LER 80-005/01T-0 (← links)
- 05000244/LER-1980-002, Forwards LER 80-002/03L-0 (← links)
- 05000244/LER-1980-001 (redirect page) (← links)
- 05000244/LER-2011-003 (← links)
- 05000244/LER-2011-002 (← links)
- 05000244/LER-2011-001 (← links)
- 05000244/LER-2010-002 (← links)
- 05000244/LER-2010-001 (← links)
- 05000244/LER-2008-001 (← links)
- 05000244/LER-2007-002 (← links)
- 05000244/LER-2007-001 (← links)
- 05000244/LER-2006-008 (← links)
- 05000244/LER-2006-007 (← links)
- 05000244/LER-2006-006 (← links)
- 05000244/LER-2006-005 (← links)
- 05000244/LER-2006-004 (← links)
- 05000244/LER-2006-003 (← links)
- 05000244/LER-2006-002 (← links)
- 05000244/LER-2006-001 (← links)
- 05000244/LER-2005-003 (← links)
- 05000244/LER-2005-002 (← links)
- 05000244/LER-2005-001 (← links)
- 05000244/LER-2004-002 (← links)
- 05000244/LER-2004-001 (← links)
- 05000244/LER-2003-006 (← links)
- 05000244/LER-2003-005 (← links)
- 05000244/LER-2003-004 (← links)
- 05000244/LER-2003-003 (← links)
- 05000244/LER-2003-001 (← links)
- 05000244/LER-2002-002 (← links)
- 05000244/LER-2002-001 (← links)
- 05000244/LER-1982-012, Forwards LER 82-012/03L-0 (← links)
- 05000244/LER-1982-010, Forwards LER 82-010/01T-0 (← links)
- 05000244/LER-1982-021, Forwards LER 82-021/03L-0 (← links)
- 05000244/LER-1983-001, Forwards LER 83-001/03L-0 (← links)
- 05000244/LER-1983-004, Forwards LER 83-004/03L-0 (← links)
- 05000244/LER-1983-006, Forwards LER 83-006/01T-0 (← links)
- 05000244/LER-1982-019, Forwards LER 82-019/03L-0 (← links)
- 05000244/LER-1982-020, Forwards LER 82-020/03L-0 (← links)
- 05000244/LER-1982-018, Forwards LER 82-018/03L-0 (← links)
- 05000244/LER-1982-017, Forwards LER 82-017/03L-0 (← links)
- 05000244/LER-1982-016, Forwards LER 82-016/03L-0 (← links)
- 05000244/LER-1983-009, Forwards LER 83-009/03L-0 (← links)
- 05000244/LER-1983-007, Forwards LER 83-007/03L-0 (← links)
- 05000244/LER-1983-005, Forwards LER 83-005/03L-0 (← links)
- 05000244/LER-1983-008, Forwards LER 83-008/01T-0 (← links)
- 05000244/LER-1983-003, Forwards LER 83-003/03L-0 (← links)
- 05000244/LER-1982-022, Forwards LER 82-022/01T-0 (← links)
- 05000244/LER-1982-026, Forwards LER 82-026/03L-0 (← links)
- 05000244/LER-1982-023, Forwards LER 82-023/03L-0 (← links)
- 05000244/LER-1976-014, Updated LER 76-014/03O-1:on 760412,N44 Power Range Detector High Voltage Power Supply Failed.Caused by Defective Modular Block Part IV-101.Power Supply Recalibr (← links)
- 05000244/LER-1976-024, Updated LER 76-024/01O-1:on 761008,accumulation of Borated Water Found Near Valve in Safety Injection Sys Piping Between Boric Acid Tanks & Safety Injection Pumps.Caused by Chloride Stress Corrosion Cracking (← links)
- 05000244/LER-1976-027, Updated LER 76-027/03O-1:on 761216,liquid Noticed Coming Through Insulation on 2-inch Letdown Diversion Line.Caused by Pinhole Leak in Socket Weld Between Pipe & Elbow.Section Line Replaced (← links)
- 05000244/LER-1976-007, Revised LER 76-07/30:on 760207,relays for Train a Containment Isolation & Ventilation Isolation Failed to Latch.Caused by MG-6 Relays Having Improper Latch Screw Factory Adjustment (← links)
- 05000244/LER-1983-014, Forwards LER 83-014/03L-0 (← links)
- 05000244/LER-1983-002, Forwards LER 83-002/03L-0 (← links)
- 05000244/LER-1983-015, Forwards LER 83-015/03L-0 (← links)
- 05000244/LER-1983-012, Forwards LER 83-012/03L-1 (← links)
- 05000244/LER-1983-013, Forwards LER 83-013/01T-0 (← links)
- 05000244/LER-1983-011, Forwards LER 83-011/03L-0 (← links)
- 05000244/LER-1983-010, Forwards LER 83-010/03L-0 (← links)
- 05000244/LER-1982-015, Forwards LER 82-015/03L-0 (← links)
- 05000244/LER-1982-014, Forwards LER 82-014/03L-0 (← links)
- 05000244/LER-1982-009, Forwards LER 82-009/03L-0 (← links)
- 05000244/LER-1986-009, Forwards Rev 1 to LER-86-009,changing Word, Indicators to Indication & Correcting Certain Numbers in Safety Assessment Section Due to Use of Incorrect Rod Position Indicator Number (← links)
- 05000244/LER-2023-003-01, Re. Ginna Nuclear Power Plant, Manual Reactor Trip Due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation Due to Low Steam (← links)
- 05000244/LER-2023-003, Manual Reactor Trip Due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation Due to Low Steam Generator Level (← links)
- 05000244/LER-2023-002, Overtemperature Delta Temperature Reactor Protection System and Auxiliary Feedwater System Actuations on Due to 100% Load Rejection Caused by Turbine Overspeed Circuit Card Failure (← links)
- 05000244/LER-2023-001, Vital Bus 17 Failed to Load Onto Emergency Diesel Generator B During Load / Safeguard Sequence Testing; Corroded Breaker Shunt Trip Attachment Plunger Found Which Indicated an Earlier Violation of Technical Specification 3.8.1 (← links)
- 05000244/LER-2021-002, Valid Auxiliary Feedwater System Actuation on Lowered Steam Generator Level Due to Failure to Control Main Feed Water Flow and Delay in Closing Main Steam Isolation Valves (← links)
- 05000244/LER-2021-001, Service Water Pump a Declared Inoperable Due to Winding Failure Following Replacement Resulting in Violation of Technical Specifications LCO 3.7.8.A (One Service Water Pump Inoperable Greater (← links)
- 05000244/LER-1989-006, :on 890616,operators Observed That Radiation Monitoring Sys R-10A,R-11 & R-12 Monitors Selected to Sample Ambient Air Instead of Required Containment Air.Caused by Personnel Error.Procedures Changed (← links)
- 05000244/LER-1986-006, :on 860816,boric Acid Transfer Pump Inoperable. Caused by Valve V-331 Misalignment.Valves V-331 & V-345 on Transfer Pumps a & B Locked Open.Technician Reminded to Receive Permission (← links)
- 05000244/LER-1986-009, :on 861026,control Room Operator Noticed That Control Rod Position Differed from Demand Position by Amount Greater than Allowed by Tech Specs.Caused by Procedural Inadequacy.Rod Position Indicator Adjusted (← links)
- 05000244/LER-1986-008, :on 861023,automatic Reactor Trip Occurred from Pressurizer High Pressure Due to Turbine Load Runback.Caused by Personnel Error.Module Replacement Procedure Written & Control & Protective Devices Checked & Tested (← links)
- 05000244/LER-1986-005, :on 860730,reactor Tripped Automatically Due to intermediate-range Reactor Trip 1/2 of 25% Power.Caused by Faulty Relays in intermediate-range Blocking Circuit Train A.Relays Replaced & Tested Satisfactorily (← links)
- 05000244/LER-1986-004, :on 860729,reactor Tripped Manually When Large Steam Leak Discovered in Turbine Bldg.Caused by Leak in Pipe Elbow on Moisture Separator Reheater Drain Line 2A.Elbow Replaced & Tested Satisfactorily (← links)
- 05000244/LER-1986-010, :on 861108,unit Found to Have Bypassed All Sample Points,Including Inservice Gas Decay Tank,For 12 H. Caused by Human Error in Shutting Off Oxygen Analyzer Strip Chart Recorder.Recorder Turned on (← links)
- 05000244/LER-1986-011, :on 861128,MSIV Inadvertently Closed,Causing Pressurizer High Pressure Reactor Trip.Caused by Personnel Error.Event Discussed W/Personnel (← links)
- 05000244/LER-1987-001, :on 870220,low Fuel Oil Condition to Day Tank B Occurred Due to Offsite Power Supply Scheduled Maint.Caused by Partial Plugging of Suction Strainers.Tanks Drained & Inspected (← links)
- 05000244/LER-1986-003, :on 860311,cutter Hose for Halon Bottle 1 Found Broken Off at Cutter Assembly Resulting in Inoperable Relay Room Fire Suppression Sys.Caused by Personnel Error.Broken Streetell Replaced (← links)
- 05000244/LER-1986-007, :on 860922,review of 1986 Surveillance Testing Schedule Identified Fire Detection Surveillance Interval Exceeded.Caused by Personnel Error.Comprehensive Review of Testing Schedule Conducted (← links)
- 05000244/LER-1986-001, :on 860118,containment Pressure ESP Actuation Channel Inoperable When Pressure Transmitters Isolated from Containment.Caused by Inadequate Surveillance Procedure. Procedure Revised (← links)
- 05000244/LER-1985-019, :on 851125,condenser Circulating Water Pump 1B Tripped,Resulting in Reactor Trip.Caused by Power Factor Relay Trip Setpoint Drift.Trip Setpoint Readjusted & Relay Tested Satisfactorily (← links)
- 05000244/LER-1986-002, :on 860216,two Motor Operated Valves Required to Be Operable for Refueling Discovered Inoperable Due to 480-volt Bus 14 Outage.Caused by Lack of Tech Spec Clarity. Procedures Reviewed & Modified (← links)
- 05000244/LER-1985-018, :on 850928,turbine & Reactor Tripped Manually Due to Electrohydraulic Sys Failure.Caused by Water Entering Electrohydraulic Fluid Through Tube Leak in Fluid Cooler. Tube Leak Repaired.Fluid Replaced (← links)
- 05000244/LER-1985-017, :on 850916,rod Control Sys on Bank D Switch Allowed Only Two Rods in Each of Banks B & D to Move, Causing Control Rod Insertion & Bank Overlap Violations. Caused by Faulty Firing Card.Card Replaced (← links)
- 05000244/LER-1985-016, :on 850915,control Rod Deviation Alarm Occurred.Caused by Intermittent Fluctuation in RPI & Change in Reactor Coolant Temp.On 850916,control Rod Indication Sys Made Inoperable to Replace Power Supplies (← links)
- 05000244/LER-1985-011, :on 850411,reactor Trip Occurred During Attempts to Trip Main Turbine Manually.Caused by Low Condenser Vacuum & Reactor Power Being Above P-7.Inquiry Re Reactor Trip Train Design Undertaken (← links)
- 05000244/LER-1985-015, :on 850620,for 45 S,Two Flow Paths from Boric Acid Storage Tank to RCS Unavailable.Caused by Nonlicensed Primary Auxiliary Operator Error.Low Level Logic in Boric Acid Tank Reset (← links)
- 05000244/LER-1985-013, :on 850531,one Emergency Diesel Generator Started Per Adverse Weather Emergency Plan Due to Notification of Tornado Warning.Generator Removed from Svc When Tornado Warning Rescinded (← links)
- 05000244/LER-1985-014, :on 850606,automatic Reactor & Turbine Trips Occurred When Overpower Delta Temp Reactor Trip Actuated. Reactor Stabilized at Hot Shutdown Conditions.Caused by Grounding of Wire During Repairs (← links)
- 05000244/LER-1985-009, :on 850408,during Secondary Sys Pressure Transient,Condensate Bypass Valve Automatically Opened Causing Turbine to Trip.Caused by Condensate Bypass Valve Switch in Automatic Position (← links)
- 05000244/LER-1985-010, :on 850408,during Operational Test of Nuclear Instrumentation Intermediate Range Channel N-35,reactor Trip Breaker B Opened W/No Annunciation of Reactor Trip First Out.Caused by Faulty Coil.Relay Replaced (← links)
- 05000244/LER-1985-012, :on 850506,two Containment Charcoal Filters & Fan Coolers Discovered Inoperable Under Large Break LOCA Conditions.Caused by Flood Following Refueling Water Storage Tank Emptying Into Containment (← links)
- 05000244/LER-1984-011, :on 840928 & 1011,control Rod Position Indication Sys Made Inoperable for Corrective Maint of +13 Vdc Power Circuit.Insp Revealed Loose Supply Socket.Wiring & Connectors Replaced (← links)
- 05000244/LER-1985-007, :on 850406,reactor Tripped & Turbine Failed to Automatically Trip.Caused by Steam Generator Level B Reducing Below 17% Narrow Range Level.Caused by Mechanical Binding of 20ET Trip Solenoid (← links)
- 05000244/LER-1985-008, :on 850407,reactor Tripped on Low Steam Generator Level.Caused by Operations Personnel Inability to Maintain Steam Generator Levels Above Trip Setpoints While Transferring Level Control (← links)
- 05000244/LER-1985-006-01, :on 850406,during Startup from Refueling Outage,Reactor Trip & Turbine Trip Occurred.Caused by Steam Generator B Level Below 30% W/Tripped Feedwater Flow Less than Steam Flow Bistable,Per Procedure CP-477 (← links)
- 05000244/LER-1985-005, :on 850405,leads of Resistance Temp Detector in Channel 4 Opened,Resulting in Reactor Trip Signal During Hot Shutdown.Only Actuation Was Automatic Opening of Reactor Trip Breakers.Caused by Personnel Error (← links)
- 05000244/LER-1985-004, :on 850326,safety Injection Actuation Signal Generated Twice.First Event Caused by Deficiency in Maint Procedure M-48.14.Second Event Caused by Momentary Loss of Power (← links)
- 05000244/LER-1984-012, :on 841005,insp of Auxiliary Bldg Exhaust Fan 1c Ductwork Revealed Discharge Damper Not Cycling W/Actuator Arm.Cause Not Stated.Stopwork for All Fuel Handling Issued Until Damper Repaired (← links)
- 05000244/LER-1985-002, :on 850121,control Room Notified That Low Frequency of 59.9 Hertz Existed.Caused by Ny Power Pools Imbalance Between Load Demand & Electrical Generation Due to Cold Weather.Diesel Generator Operation Begun (← links)
- 05000244/LER-1985-001, :on 850116,series of Blown Fuses in Computer Resulted in Actuation of 90 Alarms on Computer Alarm Typewriter at Time I&C Technicians Removing & Restoring Foxboro Channels.Caused by Personnel Error (← links)
- 05000244/LER-1984-009, :on 840817,diesel Generator a Started Upon Placing Safeguard Bus 18 Switches S5 & S6 in Test Position for Procedure PT-9.1.Caused by Intermittent Voltage from TBD-1 States Deck to Control Logic Board (← links)
- 05000244/LER-1996-004, :on 960309,decrease in Steam Generator Level Occurred.Caused by Failed Open Atmospheric Relief Valves. Booster Relay Replaced (← links)
- 05000244/LER-1985-003, :on 850309,cable Tunnel Smoke Detection Sys Auto Deluge Inadvertently Removed from Svc.Caused by Personnel Error of Misreading Zone to Be Deactivated. Procedure Reviewed (← links)
- 05000244/LER-1984-013, :on 841015,review of 841011 Surveillance Test Revealed Control Rod in Shutdown Bank Failed to Demonstrate Movement of at Least 10 Steps in Any Direction.Caused by Transposing Error.Control Rods Retested (← links)
- 05000244/LER-1984-008, :on 840725,isolation Valves Left in Closed Position & Firewatch Removed Violating Tech Specs Which Requires Continuous Firewatch When Suppression Sys Inoperable.Caused by Miscommunication (← links)
- 05000244/LER-1984-010, :on 840831,while Disconnecting Fire Protection Sys S-15 & Z-22,alarm Off Button on Fire Detection Panel Discovered in Off Position.Caused by Operator Error.Event Discussed W/Shift Supervisor & Personnel (← links)
- 05000244/LER-1984-007, :on 840530,electrical Generator Trip Occurred, Causing Trip of Turbine W/Subsequent Reactor Trip.Caused by Neoprene Sponge Rubber Gasket Being Sucked in Airflow Path & Lodged Into Rectifier Area of Exciter (← links)
- 05000244/LER-1984-006, :on 840522,during RCS Heatup to Hot Shutdown from Cold Shutdown,Automatic Safety Injection Actuated Due to Low Steam Line Pressure While Primary Sys Pressure at 2,000 Psig.Caused by Operator Error (← links)
- 05000244/LER-1984-005, :on 840514,RHR Suction Valve MOV-700 Failed to Stroke to Open Position When Actuated from Control Room. Caused by Packing Gland Flange Shifting Out of Vertical Position.Valve Stroked Manually (← links)
- 05000244/LER-1984-004, :on 840423,radiation Protection Technician Found Waste Gas Sys Oxygen Analyzer Inoperable.Caused by Personnel Error.Personnel Reinstructed on Importance of Following Procedure Requirements (← links)
- 05000244/LER-1984-001, :on 840218 & 19,accumulator Pressure Decreased to Below Tech Spec Limit.Safety Injection Accumulator B Declared Inoperable.Caused by Valve Leaking Nitrogen by Seat.Manual Valve Downstream Closed (← links)
- 05000244/LER-1976-024-01, /01T-0:on 761008,accumulation of Borated Water Found Near Valve in Safety Injection Sys Piping Between Boric Acid Tanks & Safety Injection Pumps.Caused by Chloride Stress Corrosion Cracking (← links)
- 05000244/LER-1976-009-03, /03L-0:on 760227,bus 18 Breaker from Emergency Generator a Tripped Prematurely.Caused by Phase C Overcurrent Trip Relay Actuating Earlier than Desired.Relay Replaced (← links)
- 05000244/LER-1976-010-03, /03L-0:on 760228,excessive Leakage Observed from Valve Inside Purge Supply Control Valve.Caused by Excessive Friction Between Spring Cylinder Assembly Piston Shaft & Guide Bushing.Assembly Sent to Vendor for Insp (← links)
- 05000244/LER-1976-012-03, /03L-0:on 760331,excessive Leakage Observed from Outer Door Handwheel Shaft Packing.Caused by Repeated Door Operation During Concentrated Maint Efforts.Corrective Action Under Investigation (← links)
- 05000244/LER-1976-013-03, /03L-0:on 760416,B Bank Group 2 Rod Cluster Controls G5 & 6 Dropped.Cause Under Investigation (← links)
- 05000244/LER-1976-014-03, /03L-0:on 760412,N44 Power Range Detector High Voltage Power Supply Failed.Cause Under Investigation (← links)
- 05000244/LER-1976-015-03, /03L-0:on 760424,air Ejector & Blowdown Radiation Monitors Alarmed Due to Iodine Leak from Steam Generator Tubes.Cause Under Investigation.Steam Generator Tubes Above Tube Sheet Plugged (← links)
- 05000244/LER-1976-016-03, /03L-0:on 760520,rod Position Deviation Channel Found Inoperable.Caused by Failure in Computer to Correctly Monitor Rod Position Deviation.Program Reinitialized (← links)
- 05000244/LER-1976-017-03, /03L-0:on 760618,A Accumulator Level Noted Below Tech Spec Limit.Caused by Procedure S-16.11 Not Providing Precautions Re Operator Remaining at Valve Controls During Lowering level.S-16.11 Changed (← links)
- 05000244/LER-1976-018-03, /03L-0:on 760704,B Bank Group 2 Rod Cluster Controls G-5 & 9 Dropped.Replacement of Fuses,Capacitors & Resistors in B Bank Group 2 Stationary Circuitry Recommended (← links)
- 05000244/LER-1976-020-01, /01T-0:on 760709,diesel Generator 1A Supply Breaker Overcurrent Trip Alarm Failed to Clear Following Attempt to Electrically Reset Breaker.Caused by Wear on Hunt Trip Alarm Switch Linkage (← links)
- 05000244/LER-1976-023-03, /03L-0:on 760819,piping Installed in Safety Injection Test Line Determined to Be 3/4-inch Schedule 40 Rather than Specified Schedule 80.Caused by Inadequate Administrative Controls (← links)
- 05000244/LER-1976-025-03, /03L-0:on 761010,during Operation of RHR Sys,Leak at Weldolet to Nipple Weld on 3/4 Inch Vent on RHR Return Line Discovered.Caused by Improper Fitup of Nipple to Socket.New Nipple Installed (← links)
- 05000244/LER-1976-026-03, /03L-0:on 761116,controller Output for Control Valve Spray Sodium Hydroxide Valve 836A Fell Below Limit. Caused by Poor Cold Soldered Potentiometer Wire.Joint Resoldered (← links)
- 05000244/LER-1976-027-03, /03L-0:on 761216,liquid Noticed Coming Through Insulation on 2-inch Letdown Diversion Line.Caused by Pinhole Leak in Socket Weld Between Pipe & Elbow.Section Line to Be Replaced (← links)
- 05000244/LER-1976-028-03, /03L-0:on 761217,during Reduced Load Operation, Control Rod F-12 Dropped Into Core.Caused by Open Circuit Point at Reactor Head Assembly Plug Connection.Complete Plug & Cable Assembly Replaced (← links)
- 05000244/LER-1976-029-03, /03L-0:on 761217,core Quadrant Power Tilt Ratio Calculation in Excess of Limit.Caused by Insertion of Control Rod F-12 W/Reactor at 48% Power (← links)
- 05000244/LER-1976-030-03, /03L-0:on 761217,during Normal Rounds,Liquid Discovered Leaking from Mixed Bed Demineralizer a Inlet Pipe.Caused by Pinhole Leak in Weld Between Pipe & Elbow. Hole Repaired (← links)
- 05000244/LER-1977-001-03, /03L-0:on 770103,during Testing,Safety Injection Pump C Failed to Start Manually from Bus Breaker 14.Caused by Weak Spring in Secondary Contact Assembly.Assembly Replaced (← links)
- 05000244/LER-1977-002-01, /01T-0:on 770217,Westinghouse Notified That Reactivity Insertion Curve Used for Safety Analyses Not Sufficiently Conservative.Caused by Westinghouse Error (← links)
- 05000244/LER-1975-001-03, /03L:on 750305,during Core Boring of Floor Above Rod Control Cabinets,Turbine Runback to 70% Occurred.Caused by Water Hose for Boring Machine Breaking at Coupling & Grounding Out Grippers for Control Rods G5/G9 (← links)
- 05000244/LER-1975-006-01, /01T:on 750321,during Steps to Provide Addl Purification of Reactor Coolant,Boron Concentration Inadvertently Reduced from 2068 to 1,975 Ppm.Caused by Deborating Demineralizer Being Valved Out (← links)
- 05000244/LER-1975-007-01, /01T:on 750325,during Eddy Current Insp of Steam Generator tubes,10 a & 12 B Steam Generator Hot Leg Tubes Had Wall Thinning at 50% or Greater.Caused by Buildup of Phosphate Residue (← links)
- 05000244/LER-1975-008-01, /01T:on 750408,post-accident Filter Charcoal Samples Showed Filter a Efficiency of 99.4% While B Above Criteria of 99.9%.Caused by Charcoal Aging.Tech Spec Change Considered to Replace Criteria of 99.9% (← links)
- 05000244/LER-1975-009-01, /01T:on 750410,visual Insp of Caps on Control Rod Drive Rod Travel Housings Revealed Powder Deposit on Cap K-7.Caused by Insufficient Torque Down of Cap.Cap Replaced (← links)
- 05000244/LER-1975-002-03, /03L:on 750418,small Leak Found on Letdown Drain Line Reducer Weld.Caused by Weak Point in Weld Due to Const. Leak Repaired (← links)
- 05000244/LER-1975-003-03, /03L:on 750623,MSIVs Closed W/O Operation of Solenoid Valves.Caused by Sufficient Rotation of Valve Disk to Allow Flow Stream to Force Valves Closed (← links)
- 05000244/LER-1975-010-01, /01T:on 750611,during Safeguards Valve Surveillance Testing,C Safety Injection Pump Discharge MOV 8714 & B Found Closed.Caused by Operator Error During Monthly Surveillance Testing.Procedure Reviewed (← links)
- 05000244/LER-1975-011-01, /01T:on 750617,during Normal Power Escalation After Shutdown,Rcs Gross Activity Increased to 10.6% of Limit. Caused by Not Realizing That Steady State Had Been Reached Based on Degrossed Activity Analysis (← links)
- 05000244/LER-1975-013-01, /01T:on 750815,flow Path from Refueling Water Storage Tank to Containment Sump B Inadvertently Established & Containment Integrity Requirement Violated.Caused by Personnel Error (← links)
- 05000244/LER-1975-004-03, /03L:on 750813,while Performing Reactor Protection Periodic Test PT-5.10 on Protection Channel I,Overpower Delta T Trip Bistable TC-405A Setpoint Found Off in Nonconservative Direction.Caused by Failed Zenerdiode (← links)
- 05000244/LER-1975-012-01, /01T:on 750722,during Surveillance Testing of Undervoltage Relays,Undervoltage Device 273/11B Failed to Drop to de-energized Position After Signal Simulated.Caused by Bushing Deposit Buildup on Plunger Shaft (← links)
- 05000244/LER-1975-005-03, /03L:on 750822,bus 16 Breaker from Emergency Generator 1B Failed to Close Manually on 3 Attempts.Cause Not Known.Increased Weekly Surveillance to Bus 16 Until Next Scheduled Outage Recommended (← links)
- 05000244/LER-1975-006-03, /03L:on 750902,during Performance of Measure to Eliminate Erratic Steam Generator Level Indication & Control Signal to Feedwater Control,Level Signal Input Transferred from LT-461 to LT-462 (← links)
- 05000244/LER-1975-007-03, /03L:on 750908,operator Noted Discrepancy Between Rod Position Indicators & Bank Counters.Caused by Lack of Administrative & Procedural Coverage & Malfunction of Plant Computer (← links)
- 05000244/LER-1975-008-03, /03L:on 750917,during Performance of PT-1 Rod Control Sys,Rpi Indicated Rod G-5 in Bank B Not Moving W/Bank.Caused by Open Circuit in Cable (← links)
- 05000244/LER-1975-009-03, /03L:on 751012,I-131 Equivalent Activity Reported to Be at 5.43 Mci/G.Caused by Partial Cooldown & Subsequent Heatup & Accompanying Depressurizing & Pressurizing of Fuel (← links)
- 05000244/LER-1975-010-03, /03L:on 751106,emergency Generator 1 Wattmeter Indicated No Response to Operation of Governor Control Switch.Cause Not Stated.All Connections on Emergency Generator Metering Wiring Checked & Tightened (← links)
- 05000244/LER-1975-011-03, /03L:on 751120,pinhole Noted in 3/4-inch Socket Weld of Charging Pump B Discharge Drain Line.Caused by Formation of Small Void During Tig Welding.Leak Repaired (← links)
- 05000244/LER-1975-012-03, /03L:on 751214,pinhole Noted in 1/2-inch Socket Weld on Charging Pump B Discharge Drain Line.Caused by Faulty Weld.Affected Drain Piping Section Removed & Refabricated W/New Piping (← links)
- 05000244/LER-1976-001-03, /03L:on 760111,during Surveillance Test Prior to Heatup,Cv Supply & Exhaust Valves Leaked Excessively. Possibly Caused by Low Ambient Temp During Shutdown. Investigation for Replacement Seat Matl Begun (← links)
- 05000244/LER-1976-002-03, /03L:on 760112,operator Noticed Component Cooling Pump B Noisy.Caused by Failure of Coupling Bolts.Coupling Repaired & Motor Realigned (← links)
- 05000244/LER-1976-003-03, /03L:on 760115,during Routine 105 Psig Hydro Test of RHR Suction Piping from Cv Sump B to Reactor Coolant Drawn Tank Pumps,Leaking Observed at Pump a Suction Flange. Caused by Loose Flange Bolts (← links)
- 05000244/LER-1976-004-03, /03L:on 760129,during Load Decrease for Shutdown, Both Control Power Fuses Blew for N42 Power Range Channel. Caused by Component Failure.Capacitor Replaced (← links)
- 05000244/LER-1976-006-03, /03L:on 760206,undervoltage Device 274/11B Failed to Drop to de-energized Position After Undervoltage Signal Simulated.Caused by Buildup of Bushing Deposits on Plunger Shaft.New Relays to Be Installed (← links)
- 05000244/LER-1976-007-03, /03L:on 760227,sump a Discharge AOV Not Closed. Caused by Westinghouse Type MG-6 Relays Having Improper Latch Screw Factory Adjustment.Relays Replaced (← links)
- 05000244/LER-1976-008-01, /01T:on 760227,during Planned Current Insp of Steam Generator tubes,39 Tubes in Steam Generator Inlet a & 2 Tubes in Steam Generator Inlet B Showed Defects Above Wastage Limit.Caused by Corrosion (← links)
- 05000244/LER-1976-011-01, /01T:on 760308,during Flow Test of Control Room Ventilation Sys,Zero Flow Indicated for Cleanup Path Designed for 25% Total Sys Flow.Caused by Drive Piston Being Improperly Mounted During const.W/7760319 Ltr (← links)
- 05000244/LER-1984-003, :on 840307,valves MOV-851A & B Mistakenly Opened Prior to Shutting Valve MOV-850A,resulting in Draining Water from RCS Loop to Sump B.Caused by Human Error.Minor Rev to Procedure O-2.2 Initiated (← links)
- 05000244/LER-1984-002, :on 840303,while Cooling Down RCS to Cold Shutdown Condition,Valve MOV-700 Failed to Stroke to Open Position When Actuated from Control Room.Caused by Dry Valve Stem or Light Torque Switch Setting (← links)
- 05000244/LER-1983-029-03, /03L-0:on 831116,found Unreliable Feedwater Temp Data Used in Heat Balance Calorimetrics,Resulting in Nuclear Power Ranges Not Calibr Per Tech Specs.Caused by Omitting Resistance Temp Device Data Points from Scan (← links)
- 05000244/LER-1983-028-03, /03L-0:on 830916,small Leak Discovered in Weld on Outlet Side of Boric Acid to FCV-110A Manual Shutoff Valve V-354.Caused by Lack of Fusion in Weld at Point Where Weld Pass Overlapped.Area Ground Out & Rewelded (← links)
- 05000244/LER-1983-030-03, /03L-0:on 831216,actual Setpoint for Permissive Circuit P-10 Found Low at 8% Rather than 10% Full Power. Caused by Conflicting Tech Spec Requirements.Rev Proposed (← links)
- 05000244/LER-1983-014-03, /03L-0:on 830329,during Refueling Calibr,Certain Steam Generator Level Transmitter Outputs Shifted Low by 2 to 2.5% of Span.Caused by Instrument Drift.Transmitters Recalibr (← links)
- 05000244/LER-1983-002-03, /03L-0:on 830105,during Performance of ISI-7, Main Steam Snubber 160 Identified as Inoperable.Caused by Piston Rod Detachment from Piston.Snubber Replaced (← links)
- 05000244/LER-1983-026-01, /01T-0:on 830915,boric Acid Storage Tank Solution Concentration Less than Tech Spec Requirements.Caused by Leakage of Reactor Makeup Water Through Valve FCV-110A & Check Valve 355.Sampling Increased (← links)
- 05000244/LER-1983-027-03, /03L-0:on 830916,while Reducing Power,Trip Occurred from 17% Power Resulting in Violations of Tech Specs 3.1.1.1a & C.Caused by low-low Steam Generator Level in Loop B.Operator Counseled (← links)
- 05000244/LER-1983-022-03, /03L-0:on 830725,while Performing Procedure S-16.2 Nitrogen Makeup to Accumulators,Containment Isolation Valve AOV-846 for Nitrogen Supply to Containment Seized in Mid Position.Caused by Galling Plug (← links)
- 05000244/LER-1983-025-03, /03L-0:on 830620,small Leak Found in 3/8-inch Diameter Swag Lock Compression Fitting Connection Upstream of Pressurizer Liquid Sample Manual Isolation Valve V-956E. Caused by Thermal Stress (← links)
- 05000244/LER-1983-024-03, /03L-0:on 830621,Foxboro Model N-E11DM Steam Generator Steam Flow Transmitter FT-464 Found Out of Tolerance.Caused by Pressure Static Shift.Transmitter Adjusted (← links)
- 05000244/LER-1983-021-03, /03L-0:on 830618,pressurizer Water Level Dropped Below 12%.Caused by RCS Cooldown After Reactor Trips.Level Restored by Increasing Charging Flow (← links)
- 05000244/LER-1983-023-03, /03L-0:on 830619,following Manual Turbine Trip Due to Loss of electro-hydraulic Turbine Control,Block Valve MOV 516 Closed Due to Indicated Leakage Through Pressurizer PORV-430.Caused by High Pressurizer Pressure (← links)
- 05000244/LER-1983-020-03, /03L-0:on 830613,during Startup from Refueling Outage,Rcs Chloride Concentration Exceeded 15 Ppm at Greater than 250 F.Caused by Increased Chloride Solubility Due to Increasing RCS Temp & Contamination (← links)
- 05000244/LER-1983-019-03, /03L-0:on 830613,while Changing from Cold to Hot Shutdown,Containment Spray Pumps Found in pull-stop Position at 207 F.Caused by Changes in Tech Spec Interpretation. Pumps Placed in Auto (← links)
- 05000244/LER-1983-015-03, /03L-0:on 830412,RHR Pump Manually Tripped Following Loss of RHR on Hot Leg of Loop.Caused by Leak in Steam Generator a Temporary Cold Leg Nozzle Isolation Device,Allowing Air in RCS & RHR Suction Line (← links)
- 05000244/LER-1983-013-01, /01T-0:results of multi-frequency Eddy Current Exam of Steam Generator a Inlet & Outlet Revealed No Tubes W/Indications Above Plugging limit.Twenty-three Tubes W/ Intergranular Attack Indications Found in Generator B (← links)
- 05000244/LER-1983-012-03, /03L-1:on 830323,individual Doors for Personnel Hatch Had Higher Leak Rate than Allowed.Caused by Incorrect Maint Procedure on 821007 Requiring Only Door Seal Leak Testing.Procedure Revised.Other Procedures Reviewed (← links)
- 05000244/LER-1983-012-01, /01T-0:on 830323,during Scheduled Local Leak Testing of Containment Personnel Hatch,Audible Exterior Door Shaft Leak Found.Caused by Improper Testing of Packing Area Following Maint.Maint Procedure Revised (← links)
- 05000244/LER-1983-011-03, /03L-0:on 830311,battery Charger Breaker Found Open.Caused by QC Inspector Accidentally Bumping Breaker While Climbing Ladder to Inspect Penetrations.Breaker Closed.Qc Inspector Cautioned (← links)
- 05000244/LER-1983-010-03, /03L-0:on 830224,rod Position Indicator for Control Rod Bank SD Group 1 Position C09 Deviated from Control Bank SD by 12 Steps.Caused by Signal Error for Rod Position Indicator.Signal Adjusted to Correct Drift (← links)
- 05000244/LER-1983-017-03, /03L-0:on 830501,RHR Pumps a & B Took Suction from Refueling Water Storage Tank (Rust) for Filling Reactor Refueling Cavity.Rhr Pump Stopped & Flow Dropped to Zero. Caused by Power Failure to MCC D Circuit (← links)
- 05000244/LER-1982-015-03, /03L-0:on 820622,at steady-state 100% Operation, Periodic Test Identified Faulty Sealing of Containment Gas Radiation Monitor Return Line Check Valve.Caused by Dirt Deposits from Veins of Monitor Pump (← links)
- 05000244/LER-1982-014-03, /03L-0:on 820624,discharge Check Valve 862B on Containment Spray Pump Failed to Close at Required Differential Pressure.Caused by Wear on Pin & Swing Arm. Parts Will Be Replaced During Next Outage (← links)
- 05000244/LER-1982-009-03, /03L-0:on 820320,safeguard Bus 17 Was Out of Svc for More than 7 Days Due to Installation of New Undervoltage Sys on Buses 16 & 17.Buses Returned to Svc on 820326 & Motor Driven Fire Pump Returned to Operable Status (← links)
- 05000244/LER-1983-009-03, /03L-0:on 830119,boric Acid Transfer Pump B Tripped Immediately After Start.Caused by Failed Control Power Fuses.Fuses Replaced (← links)
- 05000244/LER-1983-007-03, /03L-0:on 830117,water Level in Pressurizer Dropped Below 12% Level.Caused by RCS Cooldown Following Trip.Level Returned to 19.5% within 15 Minutes (← links)
- 05000244/LER-1983-005-03, /03L-0:on 830117,I-131 Spike Occurred in RCS After Unit Tripped from 100% Power.Caused Not stated.I-131 Concentration Returned to Normal Levels by Normal Letdown (← links)
- 05000244/LER-1983-008-01, /01T-0:on 830125,emergency Diesel Generator 1A Start Relay Indicating lights,R-1 & R-2,found Off,Causing Loss of Permissive Start Relays.Caused by Personnel Failure to Follow Procedures.Shift Supervisors Addressed on Subj (← links)
- 05000244/LER-1983-003-03, /03L-0:on 830108,containment Vessel Sump a Isolation Valve AOV-1728 Failed to Close on Command.Cause Unknown.Valve Diaphragm Replaced & Leak Tests PT-23.23 & PT-2.5 Performed Satisfactorily (← links)
- 05000244/LER-1982-026-03, /03L-0:on 821026,during Performance of PT-3, Containment Spray Sys Periodic Test,Check Valve 862B Failed to Close Promptly.Cause Not Stated.Maint Performed on Valve & Retest Indicated Acceptable Performance (← links)
- 05000244/LER-1982-023-03, /03L-0:on 821016,nipple to Discharge Pipe of 1B Component Cooling Water Pump Broke Off While Investigating Leakage.Caused by Personnel Error.Failed Pipe Replaced W/ Steel Schedule 80 Nipple (← links)
- 05000244/LER-1982-021-03, /03L-0:on 820923,containment Spray Pumps & Sodium Hydroxide Additive Sys,Check Valve 862 B Failed to Promptly Close.Valve Repairs Consisted of Machining Seat & Disc Assembly (← links)
- 05000244/LER-1982-022-01, /01T:on 821001,one Tube of a Steam Generator Inlet Found W/Crevice Intergranular Attack Indication Above Plugging Limit.B Steam Generator Inlet Had 28 Tubes Above Plugging Limit & 2 W/Stress Corrosion.Rept Follows (← links)
- 05000244/LER-1983-001-03, /03L-0:on 830104,valve 9626A Found Mispositioned in Closed Position.Possible Causes Include Human Error & Deliberate Tampering.No Positive Conclusion Reached Even After Exhaustive Investigation (← links)
- 05000244/LER-1983-004-03, /03L-0:on 830114,check Valve 862B Declared Inoperable After Failing to Close Promptly During Test of Containment Spray Sys.Maint Performed on Valve.Valve Retested Satisfactorily.Revised Test Method Developed (← links)
- 05000244/LER-1983-006-01, /01T-0:on 830120,screen House Suction Bay Water Level Dropped Below Suction of Motor Driven & Diesel Driven Fire Pumps,Rendering Fire Suppression Sys Inoperable.Caused by Frazil Ice in Circulating Water Pump Suction (← links)
- 05000244/LER-1982-019-03, /03L-0:on 820901,while Performing PT-2.9, Containment Particulate/Gas Radiation Monitor R11/12 Return Line Isolation Check Valve CV-1599 Found Leaking Excessively.Caused by Graphite in Valve & Valve Disc Wear (← links)
- 05000244/LER-1982-020-03, /03L-0:on 820712,review of New Fire Sys Tech Specs Revealed That Many Surveillance Requirements Overdue.New Fire Sys Test Procedures Still in Development Stage at Time of Discovery.All Requirements Will Be Met by 821130 (← links)
- 05000244/LER-1982-018-03, /03L-0:on 820730,computer Alarm Received, Indicating RPI for Control Rod Bank a Group 2 Position HO2 Deviated from Control Rod Bank a by 12 Steps.Caused by Instrument Drift.Rpi Adjusted to Correct Drift (← links)
- 05000244/LER-1982-017-03, /03L-0:on 820803,during Surveillance Testing of RHR Pump B at 100% steady-state Power,Leakage from Mechanical Seal Exceeded Tech Spec Limit,Rendering Pump Inoperable.Caused by Degradation of Seal Due to Normal Wear (← links)
- 05000244/LER-1982-016-03, /03L-0:on 820722,containment Spray Pump B Discharge Check Valve Failed to Seat at Required Differential Pressure.Caused by Wear on Pin & Swing Arm of Swing Check Valve.Delivery of Replacement Parts Delayed (← links)
- 05000244/LER-1982-011-03, /03L-0:on 820423,while Performing Local Leak Rate Testing on Containment Penetration Isolation Valves, Containment Gas Radiation Monitor Return Line Check Valve Was Leaking Excessively.Possibly Caused by Dirt (← links)
- 05000244/LER-1982-011, Forwards LER 82-011/03L-0 (← links)
- 05000244/LER-1982-013-01, /01T-0:on 820518,while Performing Safety Injection Functional Test,Satelite Station a for Fire Detection Sys Lost Ac Power.Condition Existed for More than 1-h W/O Fire Watch Patrols in Inoperable Fire Detection Zone Areas (← links)
- 05000244/LER-1982-008-01, /01T-0:on 820303,emergency Cooldown Occurred. Caused by Cooldown/Depressurization of Primary Sys Following Rupture of Tube B Steam Generator Resulting in Calculated Delta T of Approx 280 F.No Action Neccessary (← links)
- 05000244/LER-1982-008, Forwards LER 82-008/01T-0 (← links)
- 05000244/LER-1982-007-01, /01T-0:on 820223,evaluation of Thermal Transient Performed for Followup of 820125 Event Where B Steam Generator Experienced Tube Failure Leading to RCS Cooldown Rate Greater than 100 F Per Hour.Cause Not Stated (← links)
- 05000244/LER-1982-007, Forwards LER 82-007/01T-0 (← links)
- 05000244/LER-1982-003, Ro:On 820125,event Described in LER 82-003 Resulted in Calculated Temp Difference Across Tube Sheet of B Steam Generator of Approx 280 F.Addl Info Will Be Submitted W/ 14-day Written Rept (← links)
- 05000244/LER-1982-005-03, /03L-0:on 820125,while Opening Pressurizer PORV for Fourth Time to Reduce Pressure,Porv Stuck Open.Caused by Environmentally Qualified Asco NP-1 Which Can Not Have Restricted Vent.Restricted Vent Removed & Replaced (← links)
- 05000244/LER-1982-005, Forwards LER 82-005/03L-0 (← links)
- 05000244/LER-1982-006-01, /01T-0:on 820203,during Filling of Secondary Side B Steam Generator,Reduction of Reactor Coolant Boric Acid Concentration Occurred.Caused by Procedure Not Requiring Both Ends of Tube to Be Plugged.Procedure Changed (← links)
- 05000244/LER-1982-006, Forwards LER 82-006/01T-0 (← links)
- 05000244/LER-1982-004-01, /01T-0:on 820125,fire Watches Posed as Result of Eight Inoperable Fire Detection Zones (← links)
- 05000244/LER-1982-004, Forwards LER 82-004/01T-0 (← links)
- 05000244/LER-1982-003-01, /01T-0:on 820125,B Generator Experienced Tube Failure.Caused by Axial Burst Rupture of Tube Due to Mechanical Loading Mechanism on Tube 1 Between First Support Plate Tube Sheet.Tube Will Be Plugged (← links)
- 05000244/LER-1982-002-03, /03L-0:on 820113,two Pinhole Leaks from Weld in Suction for Reactor Coolant Drain Tank Pump Noticed During Normal Operations.Cause Not Stated.Defective Area on 6-inch Scheduled 10 Stainless Steel Pipe Ground Out & Repaired (← links)
- 05000244/LER-1982-002, Forwards LER 82-002/03L-0 (← links)
- 05000244/LER-1982-001-03, /03L-0:on 820107,leak Identified on Containment Primary Isolation Valve for 3/8-inch Pressurizer Liquid Sample.Valve Isolated & Repaired.Sys Returned to Svc W/O Performing Necessary Leak Test.Cause Not Stated (← links)
- 05000244/LER-1982-001, Forwards LER 82-001/03L-0 (← links)
- 05000244/LER-1981-021-03, /03L-0:on 811222,while at steady-state 100% Operation,Periodic Test Identified Containment Gas Radiation Monitor Return Line Check Valve Not Sealing Tight.Caused by Dirt on Seat of Rockwell 1-inch 1500 Psi Valve (← links)
- 05000244/LER-1981-021, Forwards LER 81-021/03L-0 (← links)
- 05000244/LER-1981-022-01, /01T-0:on 811221,error Discovered in Data Supplied for Containment for Coolers in LOCA-ECCS Analysis.Cause Not Given.Calculations Will Be Performed Prior to Start of Cycle XII (← links)
- 05000244/LER-1981-022, Forwards LER 81-022/01T-0 (← links)
- 05000244/LER-1981-018-03, /03L-0:on 811202,zones S03,S04 & S05 of Fire Suppression Sys Had Been Isolated for 14 Days.Caused by Inadvertent Operation of Fire Suppression Sys on 811114.Fire Watches Established & Protection Sys to Be Installed (← links)
- 05000244/LER-1981-018, Forwards LER 81-018/03L-0 (← links)
- 05000244/LER-1981-020-03, /03L-0:on 811119,two Fire Seals from a Battery Room Found Not Installed.Caused by Personnel Failure to Fill Seals W/Fire Barrier Foam.Improved Training & Supervision Instituted (← links)
- 05000244/LER-1981-020, Forwards LER 81-020/03L-0 (← links)
- 05000244/LER-1981-019-03, /03L-0:on 811114,two Full Length Rods Misaligned from Group Step Counter Demand Position by More than 12 Steps.Caused by Inadvertent Actuation of Fire Suppression Sys Due to Personnel Procedural Error (← links)
- 05000244/LER-1981-016-03, /03L-0:on 811105,during Test C,Si Pump Did Not Start W/Bus 16 Breaker.Caused by Closing Circuit Malfunction,Due to Weak Lockout Coil.Qualified Replacement Installed & Tested (← links)
- 05000244/LER-1981-016, Forwards LER 81-016/03L-0 (← links)
- 05000244/LER-1981-017-03, /03L-0:on 811110,several Fire Suppression Sys Had Exceeded 14-day out-of-svc Limit.Caused by Sys Removal from Svc to Perform Mods Required by 10CFR50,App R.Sys to Be Returned to Svc by 811117 (← links)
- 05000244/LER-1981-017, Forwards LER 81-017/03L-0 (← links)
- 05000244/LER-1981-015-01, During Containment Atmosphere Sampling & Analysis,Nonautomatic Primary Containment Isolation Valve Opened.Caused by Procedure Inadequacy.Procedure PC-23.2 Revised (← links)
- 05000244/LER-1981-015, Forwards Updated LER 81-015/01X-1 (← links)
- 05000244/LER-1981-014-03, /03L-0:on 810720,halon Fire Suppression Sys Was Inoperable for More than 14-day Limit.Caused by Lack of Info Re Tech Spec Requirement in Procedures.Procedures Changed to Restore Operability of Sys While Mod Continued (← links)
- 05000244/LER-1981-014, Forwards LER 81-014/03L-0 (← links)
- 05000244/LER-1982-025-03, /03L-0:on 821007,cable Tunnel Spray/Sprinkler Fire Protection Sys Taken Out of Svc to Perform Sys Mod.On 821021,sys Declared Operable When Mods Complete.Personnel Instructed to Perform Mods in Less than 14 Days (← links)
- 05000244/LER-1982-025, Forwards LER 82-025/03L-0 (← links)
- 05000244/LER-1982-024-03, /03L-0:on 821021,RPI for Control Rod K-7 Declared Inoperable.Rpi Repaired Indicator Replaced,Connection in Main Control Board Replaced & RPI Returned to Svc (← links)
- 05000244/LER-1982-024, Forwards LER 82-024/03L-0 (← links)
- 05000244/LER-1982-027-03, /03L-0:on 821011,leak Identified on Boric Acid Transfer Pump 1A Discharge Piping.Caused by Intergranular Stress Corrosion Cracking.Cracking Section of Pipe & Fitting Replaced (← links)
- 05000244/LER-1982-027, Forwards LER 82-027/03L-0 (← links)
- 05000244/LER-1983-018-03, /03L-0:on 820126,RCS Average Temp Reduced to Less than 350 F & Both Reactor Coolant Pumps Inoperable.Caused by Personnel Failure to Incorporate Tech Specs (← links)
- 05000244/LER-1982-028-03, /03L-0:on 821219,while Performing Nitrogen Makeup to Accumulator & Charging RCS Overpressurization Sys Nitrogen,Containment Isolation Valve AOV-846 Opened & Closed Sluggishly.Caused by Matl in Plug.Seat Replaced (← links)
- 05000244/LER-1982-028, Forwards LER 82-028/03L-0 (← links)
- 05000244/LER-1983-016-03, /03L-0:on 830418,during Maint,Pinhole Leak Discovered on Boric Acid Transfer Sys Branch Connection Off Boric Acid Filter Outlet.Caused by Intergranular Attack Due to Stress Corrosion Cracking.Piping Will Be Replaced (← links)
- 05000244/LER-1983-016, Forwards LER 83-016/03L-0 (← links)
- 05000244/LER-1981-013-03, /03L-0:on 810714,pipe Leakage Noted in Charging Pump Suction Line from Immediate Borate Sys.Probably Caused by Stress Corrosion Cracking.No Exam Possible Until Replacement Completed Next Cold Shutdown (← links)
- 05000244/LER-1981-013, Forwards LER 81-013/03L-0 (← links)
- 05000244/LER-1981-010-03, /03L-0:on 810420,leaking Relief Valve Was Found on Letdown Sys.Caused by Cracked Bellows Due to Increasing Differential Pressure as Result of Crud Buildup.Valve Repaired & Reinstalled (← links)
- 05000244/LER-1981-010, Forwards LER 81-010/03L-0 (← links)
- 05000244/LER-1981-008, Forwards LER 81-008/03L-0 (← links)
- 05000244/LER-1981-009, Forwards LER 81-009/01T-0 (← links)
- 05000244/LER-1980-011, Forwards LER 80-011/03L-0 (← links)
- 05000244/LER-2018-002, Loss of Offsite Power to Vital Bus Due to Human Error Causes Automatic Actuation of Emergency Diesel Generator a (← links)
- 05000244/LER-2075-006, Transfer of a Steam Generator Level Control Input Signal from Level Transmitter LT-461 to Level Transmitter LT-462 on 9/2/75 (← links)
- 05000244/LER-2077-006, C Charging Pump Varidrive on 6/19/1977 (← links)
- 05000244/LER-2076-006, Malfunction of Undervoltage Relay During Surveillance Test on 2/6/1976 (← links)
- 05000244/LER-2075-003, R. E. Ginna, Failure of 1C Safety Injection Pump to Start Manually from Buss 16 (← links)
- 05000244/LER-2075-002, For R. E. Ginna, Failure of the 1C Safety Injection Pump to Start Manually from Bus 16 Ginna Station (← links)
- 05000244/LER-2075-004, For R. E. Ginna, Failure of the Main Steam Line Isolation (Msli) Valves Solenoid Valves to Operate Properly at Ginna Station (← links)
- 05000244/LER-2075-005, For R. E. Ginna, Failure of the IC Safety Injection Pump to Start Manually from Bus 16 at Ginna Station (← links)
- 05000244/LER-2075-008, For R. E. Ginna, Control Rod G-5 Lift Coil Open Circuit (← links)
- 05000244/LER-2075-009, For R. E. Ginna, Reactor Coolant Iodine-131 Equivalent Activity (← links)
- 05000244/LER-2075-010, For R. E. Ginna, Unresponsive Emergency Generator Governor Control Switch (← links)
- 05000244/LER-2075-011, For R. E. Ginna, (30-Day Report), Charging Pump Disclosure Drain Line Pinhole Leak (← links)
- 05000244/LER-2075-012, For R. E. Ginna, (30-Day Report), Charging Pump Discharge Drain Line Pinhole Leak (← links)
- 05000244/LER-2075-013, For R. E. Ginna, 30 Day, B Steam Generator Tube Degradation (← links)
- 05000244/LER-2076-003, For R. E. Ginna, Residual Heat Removal System Low Pressure Piping Excessive Leakage (← links)
- 05000244/LER-2075-001, For R. E. Ginna, Drop of Two Control Rods (← links)
- 05000244/LER-2075-007, For R. E. Ginna, Abnormal Degradation of Steam Generator Tubes (← links)
- 05000244/LER-2076-014, N44 Power Range Detector High Voltage Power Supply Failure (← links)
- 05000244/LER-2076-013, Drop of Two Control Rods (← links)
- 05000244/LER-2076-015, Air Ejector and Blowdown Radiation Monitors Alarmed (← links)
- 05000244/LER-2076-016, Rod Position Deviation Channel Was Found to Be Inoperable (← links)
- 05000244/LER-2076-010, R. E. Ginna - Supplemental Report on LER 1976-10-00, R. E. Ginna Plant, Containment Purge Supply Valve Having Excessive Leakage During Testing (← links)
- 05000244/LER-2076-020, For R.E. Ginna, a Accumulator Level Below Technical Specification Limit (← links)
- 05000244/LER-2076-019, For R. E. Ginna, Release of Liquid Radioactive Waste Without Continuous Operation of a Gross Activity Monitor. for R. E. Ginna, Release of Liquid Radioactive Waste Without Continuous Operation of a Gross Activity Monitor (← links)
- 05000244/LER-2076-021, R. E. Ginna, Unit 1, D Bank Group 2 RCCs G-3 and G-11 Partially Dropped Into Core (← links)
- 05000244/LER-2076-022, R. E. Ginna, Unit 1, Error in Westinghouse Safety Analysis Methods (← links)
- 05000244/LER-2076-023, R. E. Ginna, Unit 1, Incorrect Piping Installation for Modification SM 75-9.21 (← links)
- 05000244/LER-2076-024, R. E. Ginna, Unit 1, Accumulation of Borated Water Near Valve in Safety Injection System Piping Between Boric Acid Tanks and Safety Injection Pumps (← links)
- 05000244/LER-2076-025, R. E. Ginna, Unit 1, Leak at Residual Heat Removal System Return Pipe Vent (← links)
- 05000244/LER-2076-026, R. E. Ginna, Unit 1, Controller Output for Cv Spray Naoh Valve 836A Was Less than 10 Ma (← links)
- 05000244/LER-2076-027, R. E. Ginna, Unit 1, Liquid Leak Through Insulation on 2 Letdown Diversion Line (← links)
- 05000244/LER-2076-029, R. E. Ginna, Unit 1, Core Quadrant Power Tilt Ratio Calculation in Excess of Limit During Dropped Rod Condition (← links)
- 05000244/LER-2076-028, R. E. Ginna, Unit 1, on Control Rod F-12 Dropping Into Core During Operation at Reduced Load for Condenser Work (← links)
- 05000244/LER-2076-030, A Mixed Bed Demineralizer Inlet Piping Leak (← links)
- 05000244/LER-2077-001, R. E. Ginna, Bus 14 Circuit Breaker for C Safety Injection Pump (← links)
- 05000244/LER-2077-003, Abnormal Degradation of Steam Generator Tubes (← links)
- 05000244/LER-2076-030-03, Leak in Letdown Diversion Line on 12/16/1976, and LER 1976-030-03 a Mixed Bed Demineralizer Inlet Piping Leak (← links)
- 05000244/LER-2077-008, B Steam Generator Tube Leak (← links)
- 05000244/LER-2077-007, Bus 14 Breaker for C Safety Injection Pump (← links)
- 05000244/LER-2078-003, B Steam Generator Tube Leak (← links)
- 05000244/LER-2078-002, R. E. Ginna, Power Range Low Range Trip Set Point Test (← links)
- 05000244/LER-1977-023, Letter Forwarding Update Report LER 77-023/1X-1, Supplemental Report on Reportable Occurrence 77-023/1T, Control Rod Urgent Failure Rod Stop (← links)
- 05000244/LER-2078-005, For R. E. Ginna, Unplanned Reactivity Insertion of More than 0.5% K/K While Subcritical (← links)
- 05000244/LER-2078-004, For R. E. Ginna, Motor Control Center 1C Circuit Breaker to Motor Control Center 1H Trip (← links)
- 05000244/LER-2076-007, For R. E. Ginna, Concerning Relay for Train a Containment Isolation and Containment Ventilation Isolation Failure to Latch (← links)
- 05000244/LER-2076-008, For R. E. Ginna, Abnormal Degradation of Steam Generator Tubes (← links)
- 05000244/LER-2078-009, For R. E. Ginna, Bus 18 Breaker from a Emergency Generator Overcurrent Relay (← links)
- 05000244/LER-2076-011, Zero Flow Indicated for Cleanup Filtering Path in Charcoal Filter in Control Room Ventilation System (← links)
- 05000244/LER-2076-012, Containment Personnel Airlock Handwheel Shaft Seal Excessive Leakage During Testing (← links)
- 05000244/LER-2078-007-01, Bus 14 Breaker for C Safety Injection Pump (← links)
- 05000244/LER-2078-006, R. E. Ginna, Main Steam Line Snubbers, Positions MS146 Top and Bottom (← links)
- 05000244/LER-2078-007, For R. E. Ginna, Bus 16 Circuit Breaker for B Emergency Generator (← links)
- 05000244/LER-2018-001, R.E. Gina Nuclear Power Plant Regarding Leakage in Reactor Coolant System Pressure Boundary Through an Existing Weld in Original Installation Equipment Due to Orifice Wear/Erosion Resulting in Progressively Increasing System (← links)
- 05000244/LER-1999-008, :on 990427,overtemperature Delta T Reactor Trip Occurred Due to Faulted Bistable During Calibr of Redundant Channel.Plant Was Stabilized in Mode 3 & Faulted Bistable Was Subsequently Replaced.With (← links)
- 05000244/LER-1981-012-03, /03L-0:on 810504,pressurizer Pressure Transmitter PT-431 Found High.Caused by Transmitter Drift.Transmitter Recalibr (← links)
- 05000244/LER-1981-009-01, /01T-0:on 810515,fifteen Tubes in Steam Generator B Showed Indications.Caused by Concentration of Caustics in Crevices Leading to Intergranular Attack & Wedge Area Defect in One Indication.Tubes Welded or Mechanically Plugge (← links)
- 05000244/LER-1981-011-03, /03L-0:on 810426,small Leak in Fitting of RHR Pump Seal 1B Discovered.Caused by Worn Fitting Threads. Fitting Replaced (← links)
- 05000244/LER-1981-007-03, /03L-0:on 810418,loss of 34.5-kV Supply to Transformer 12 Occurred,Creating Loss of Offsite Power. Caused by Fault in B Phase Vacuum Breaker Switch Which Supplies Spare Transformer 12B (← links)
- 05000244/LER-1981-008-03, /03L-0:on 810402,radiation Monitors R-11 & R-12 Were Inoperative & Monitor R-10A Was Not Placed in Operation.Caused by Seized Bearing in Pump Supplying Air Sample to R-11 & R-12.Procedure Modified to Put 10A in Svc (← links)
- 05000244/LER-1981-006-03, /03L-0:on 810323,immediate Borate Valve Outlet Piping Found Leaking.Probably Caused by Stress Corrosion Cracking.Investigation Underway (← links)
- 05000244/LER-1981-005-03, /03L-0:on 810302,safety Injection Pump Did Not Start W/Westinghouse DB-50 Air Circuit Breaker 16 During Test C.Caused by Closing Circuit Malfunction.Breaker Replaced & Tested.Investigation Continuing (← links)
- 05000244/LER-1981-005, Forwards LER 81-005/03L-0 & Updated LER 81-002/03X-1 (← links)
- 05000244/LER-1981-004-03, /03L-0:on 810211,containment Fan Cooler Unit C Condensate Dumps & Sump a Pumping Rate Increased During Normal Steady State Operation.Probably Caused by Galvanic Reaction of Carbon Steel Plug in Copper Motor Cooler (← links)
- 05000244/LER-1981-003-03, /03L-0:on 810115,during Normal Reactor Coolant Boration,Absence of Boric Acid Flow from a Boric Acid Pump Observed.A Pump Declared Inoperable.Caused by Valve Not Fully Open After Sampling.Valves Will Be Locked Open (← links)
- 05000244/LER-1981-002-03, /03L-0:on 810109,safety Injection Pump C Did Not Start W/Bus Breaker 16.Probable Cause Due to Breaker in off-set Position.Personnel to Be Instructed in Proper Breaker Alignment (← links)
- 05000244/LER-1981-001-03, /03L-0:on 810105,leak Noted on Diesel Emergency Generator B Jacket Cooling Water Return Line to Expansion Tank.Caused by Broken Bushing Due to Possible Lack of Support Connection.Bushing Replaced (← links)
- 05000244/LER-1980-010-03, /03L-0:on 801125,pinhole Leak Found in Weld on RHR Thermowell.Caused by Poor Quality Weld.Weld Repaired (← links)
- 05000244/LER-1980-009-03, /03L-0:on 801003,during Performance of PT-12.1 to Verify Operability of 1A Emergency Generator,Part from Barring Device Seen to Fly Out.Caused by Bearings Not Designed to Withstand Operation W/Generator Running (← links)
- 05000244/LER-1980-008-03, /03L-0:on 800910,during PT-12.2 Test for B Emergency Generator,Bus 16 Breaker Did Not Close.Caused by Guide Pin Split End Opening & Binding Control Relay Antipump Release Lever.Split End Closed (← links)
- 05000244/LER-1999-011, :on 990823,small Tears Were Discovered in Flexible Duct Work Connector at Inlet of CR HVAC Sys Return Air Fan (AKF08).Caused by in-leakage Greater than That Assumed.Implemented Temporary Mod 99-029.With (← links)
- 05000244/LER-1999-004, :on 990412,discovered That Containment Recirculation Fan Chevron Separator Vanes Were Installed Backwards.Caused by Improper Assembly by Mfg.Moisture Separator Vanes Were Dismantled & Correctly re-installed (← links)
- 05000244/LER-1999-004-01, Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded (← links)
- 05000244/LER-1999-007, :on 990423,reactor Trip Occurred Due to Instrument & Control Technicians Inadvertently Pulling Fuses from Wrong Nuclear Instrument Channel.Setpoint Adjustments Were Completed by Different Crew of Technicians (← links)
- 05000244/LER-1999-007-01, Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions (← links)
- 05000244/LER-1998-003, :on 980904,actuations of CR Emergency Air Treatment Sys Was Noted Due to Invalid Causes.Caused by Various Degraded Components in CR RM Sys.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored (← links)
- 05000244/LER-1998-003-02, Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations (← links)
- 05000244/LER-1999-010, :on 990615,ventilation Isolation of Auxiliary Bldg Occurred When Auxiliary Bldg Gas Radiation Monitor R-14 Reached High Alarm Setpoint.Cr Operators Rest Auxiliary Bldg Ventilation Isolation Signal.With (← links)
- 05000244/LER-1999-001, :on 990222,deficiencies in NSSS Vendor steam- Line Brake Mass & Energy Release Analysis Results in Plant Being Outside Design Bases Occurred.Caused by Deficiencies in W.Temporary Administrative Replaced.With (← links)
- 05000244/LER-1999-009, :on 990503,instrumentation Declared Inoperable in Multiple Channels Resulted in Condition Prohibited by Ts. Caused by Unanticipated High Frequency AC Voltage Ripple. Entered TS LCO 3.0.3.With (← links)
- 05000244/LER-1999-006, :on 990421,start of turbine-driven Auxiliary Feedwater Pump Was Noted.Caused by MOV Being Left in Open Position.Closed Manual Isolation Valve to Secure Steam to Pump.With (← links)
- 05000244/LER-1999-005, :on 990413,undervoltage Signal of Safeguards Bus During Testing Resulted in Automatic Start of B Edg. Caused by Personnel Error.Blown Fuse Was Replaced & Offsite Power Was Restored to Safeguards Bus 17.With (← links)
- 05000244/LER-1999-003, :on 990301,two Main Steam non-return Check Valves Were Declared Inoperable Due to Exceedance of Acceptance Criteria.Caused by Changes in Methodology & Matls.Packing Gland Torque Will Be Adjusted.With (← links)
- 05000244/LER-1999-002, :on 990227,discovered That Surveillance Had Not Been Performed at Frequency,Per Ts.Caused by Personnel Error.Procedure O-6.13 Will Be Evaluated for Enhancement Documentation of Completion of ITS Srs.With (← links)
- 05000244/LER-1998-005, :on 981120,loss of 34.5 Kv Offsite Power Circuit 751,resulted in Automatic Start of B Edg.Caused by Faulted Cable Splice.Performed Appropriate Actions of Abnormal Procedure AP-ELEC.1.With (← links)
- 05000244/LER-1998-004, :on 971030,determined That Improperly Performed Surveillance Resulted in Condition Prohibited by Ts.Caused by Procedure non-adherence.Appropriate Calibr Procedures Were Properly Performed with 24 H of Condition Discovery (← links)
- 05000244/LER-1998-003-01, Forwards LER 98-003-01 Re Event or Condition That Resulted in Manual or Automatic Actuation of Esf,Including Rps,Per 10CFR50.73.Rev 1 Addresses Root Cause of Actuations of CR Emergency Air Treatment Sys (← links)
- 05000244/LER-1998-002, :on 971019,CR Emergency Air Treatment Sys Actuating Function Was Not Operable.Caused by Mispositioned Switch.Revised Procedure CPI-MON-R37 (← links)
- 05000244/LER-1998-001, :on 980209,discovered That Boraflex Degradation in SPF Was Greater than Was Assumed.Caused by Dissolution of Boron on Boraflex Matrix,Per 10CFR50.21.Removed Spent Fuel Assemblies from Selected Degraded Storage Rack Cells (← links)
- 05000244/LER-1997-007, :on 971117,reactor Engineer Recognized That Neutron Flux Low Range Trip Circuitry for Channel Was Not in Tripped Condition as Required.Caused by Technical Inadequacies.Channel Defeat Will Be Identified (← links)
- 05000244/LER-1997-007-01, Forwards LER 97-007-01,re RT Instrumentation Which Would Have Been in Condition Prohibited by Ts.Rev 1 Corrects Typo on Page 6 & Clarifies Content of Training Which Will Be Conducted (← links)
- 05000244/LER-1997-006, :on 971103,verification of B Concentration Was Not Performed Due to Misinterpretation of Event Sequence. Audible Count Rate Function Was Restored to Operable Status (← links)
- 05000244/LER-1997-006-01, Forwards LER 97-006-01,re Verification of B Concentration Which Was Not Performed Due to Misinterpretation of Event Sequence.Rev Clarifies Role of Operations as Part of Cause & Includes Addl CAs That Address Cause (← links)
- 05000244/LER-1997-005, :on 971031,undetected Unblocking of SI Actuation Signal Occurred at Low Pressure Condition,Due to Faulty Bistable Which Resulted in Inadvertent SI Actuation Signal.Sias,Ci & CVI Signals Were Reset (← links)
- 05000244/LER-1997-055, Forwards LER 97-055-00 Re Undetected Unblocking of SI Actuation Signal Occurrence While at Low Pressure Condition Due to Faulty Bistable Which Resulted in Inadvertent Safety Injection Actuation (← links)
- 05000244/LER-1997-004, :on 971024,radiation Monitor Alarm Were Noted Due to Higher than Normal Radioactive Gas Concentration Resulted in Cvi.New R-12 Alarm Setpoint Was Maintained for Duration of Refueling Outage (← links)
- 05000244/LER-1997-003, :on 970730,bistable Instrument Trip Setpoint Could Have Exceeded Allowable Value.Caused by Insufficient Existing Margin Between Trip Setpoint & Allowable Value. Held Switches in Tripped Configuration (← links)
- 05000244/LER-1997-002, :on 970720,34.5 Kv Offsite Power Circuit 751 Was Lost.Caused by Automatic Actuation of B Emergency DG Due to Undervoltage on Safeguards Buses 16 & 17.Offsite Power Restored to Safeguards Buses 16 & 17 (← links)
- 05000244/LER-1996-009, :on 960723,determined That Leak Rate Outside Containment Was Greater than Program Limit.Caused by Weld Defect.Isolated Leak & Cut Out & Replaced Leaking Pipe (← links)
- 05000244/LER-1996-009-02, Forwards LER 96-009-02 Re Leak Outside Containment Due to Weld Defect.Further Assessment Determined That Leak Rate Is within Design Basis & Entry Into TS LCO 3.0.3 Was Not Required (← links)
- 05000244/LER-1997-001, :on 970131,discovered Service Water Temp Was Less than Specified Value.Caused by non-representative Method of Monitoring.Increased Water Temp in Screenhouse Bay to Greater than 35 Degrees F (← links)
- 05000244/LER-1996-015, :on 961223,discovered Thermally Induced Overpressure Transient Could Occur.Caused by Thermal Expansion of Fluid During Design Basis Accident Condition. Installed Relief Valve on Affected Line (← links)
- 05000244/LER-1996-013, :on 961029,circuit Breakers Closed While in Mode 3 & Resulted in Condition Prohibited by TS Due to Personnel Error.Circuit Breakers for MOV-878B & MOV-878D Were re-opened (← links)
- 05000244/LER-1996-012, :on 960820,feedwater Transient Occurred,Due to Closure of Feedwater Regulating Valve,Causing Lo Lo Steam Generator Level Reactor Trip.Sgs Were Restored & Missing Screw in 1/P-476 Was Replaced (← links)
- 05000244/LER-1996-010, :on 960806,latching of Main Turbine While in Mode 4 Occurred,Due to Defective Procedure,Resulting in Automatic Start of Auxiliary Feedwater Pump.Caused by Defective Maint Procedure.Procedure Revised (← links)
- 05000244/LER-1996-011, :on 960807,improper Configuration of Circuit Breaker Occurred,Due to Undetected Internal Interference, Resulting in Automatic Start of Both Auxiliary Feedwater Pumps.Running AFW Pumps Were Secured (← links)
- 05000244/LER-1996-008, :on 960707,main Feedwater Pump Breakers Opened. Caused by Change in Seal Water Differential Pressure Occurred During Sys Realignment.Afw Flow Controlled as Desired to Maintain S/G Level (← links)
- 05000244/LER-1996-007, :on 960612,CR Operators Identified Control Rods Misaligned & Not Moving in Proper Sequence.Caused by Faulty Firing Circuit Card in Rod Control Sys.Faulty Firing Circuit Card in 1BD Power Cabinet Replaced (← links)
- 05000244/LER-1996-006, :on 960521,discovered Containment Penetration Not in Required Status.Caused by Personnel Error.Installed Flange Inside Containment Penetration 2 (← links)
- 05000244/LER-1996-005, :on 960516,PORC Determined Deficient Procedures Do Not Meet SRs for Testing safety-related Logic Circuits. Caused by Inadequancies in Individual Testing Procedures. Procedures Re Improved TSs Revised (← links)
- 05000244/LER-1996-003, Forwards LER 96-003,Rev 1.HPES Completed,Root Cause Analysis Completed & Corrective Actions Identified (← links)
- 05000244/LER-1996-002, :on 960307,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump.C/As: Thermography Performed (← links)
- 05000244/LER-1996-001, :on 950504,inservice Test Not Performed During Refueling Outage.Caused by Inadequate Tracking of Surveillance Frequency.Valve Test Performed & Disassembled (← links)
- 05000244/LER-1995-009, :on 950817,surveillance Was Not Performed Due to Improper Application of TS Requirements Resulting in TS Violation.Testing of MOV-515 Was Performed on 951115.W/ (← links)
- 05000244/LER-1995-008, :on 950825,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump That Resulted in Manual Rt.Returned S/G Levels to Normal Operating Levels (← links)
- 05000244/LER-1995-007, :on 950803,lost Power from 34.5 Kv Offsite Power Circuit 751 Due to Offsite Electrical Storm,Resulting in Automatic Start of EDG B.Offsite Power Restored,Edg B Stopped & Realigned & Circuit 751 Cleared (← links)
- 05000244/LER-1995-006, :on 950630,34.5 Kv Offsite Power Circuit 751 Was Lost Due to Offsite Lightning Strike & Resulted in Automatic Start of a Edg.Performed Appropriate Actions of Abnormal Procedure AP-ELEC.1 to Stabilize Plant (← links)
- 05000244/LER-1995-005, :on 950607,FW Isolation on High SG Level Occurred.Caused by Decrease in Instrument Air Pressure Due to an Air Leak in Containment.Fw Flow Switched to Manual Control (← links)
- 05000244/LER-1995-003, :on 950407,inadvertent Automatic SI Actuation Occurred When Technician Unblocked SIAS Due to Misleading Procedural Direction.Pressurizer Pressure Channel P-431 Bistable Proving Switch Reinstated (← links)
- 05000244/LER-1995-004, :on 950407,SG Tube Degradation Occurred Due to Iga/Scc That Caused QA Manual Reportable Limits to Be Reached.Sleeved or Plugged Affected Tubes W/Accepted Industry Repair Methods (← links)
- 05000244/LER-1995-002, :on 950212,concurrent Indication of Individual CR Position Briefly Unavailable.Caused by Short Circuit. Repair of Short Circuit Completed (← links)
- 05000244/LER-1995-001, :on 950203,pressurizer Safety Valves Lift Settings Found Above TS Tolerance During post-svc Test,Due to Setpoint Shifts That Resulted in Independent Trains Being Considered Inoperable (← links)
- 05000244/LER-1994-012, :on 940921,approx 1032 Edst W/Reactor at Approx 98% Steady State Power,Power from Circuit 751 Was Lost. Caused by Automatic Actuation of B Emergency D/G Was Due to Undervoltage.Safeguards Buses Were Restored (← links)
- 05000244/LER-1994-011, :on 940917,indicating Lamp on B Train Safeguards Initiation Cabinet Failed.Caused by Loss of 125 Vdc Control Power.Burned Out Indicating Lamp & Blown Fuse Replaced (← links)
- 05000244/LER-1994-010, :on 940916,volt Bus 12B Inadvertenly Tripped. Caused by Defective Procedure.Normal Power Supplies Restored & B Emergency Diesel Generator Stopped & Aligned for Auto Standby (← links)
- 05000244/LER-1994-009, :on 940809,SI Pumps Declared Inoperable Due to Leak at Socket Weld in Common Recirculation Line for SI Pumps.Affected Weld Inspected & Removed & Maint Procedure for Overhaul of SI Pumps Will Be Upgraded (← links)
- 05000244/LER-1994-008, :on 940613,B Safety Injection Pump Was Declared Inoperable During Monthly Surveillance Test.Caused by Broken Motor Rotor Bar.B SI Pump Motor Rotor Bars Were Replaced & B SI Pump Motor Was Reassembled (← links)
- 05000244/LER-1994-007, :on 940427,feedwater Transient Occurred Due to Loss of Ability to Control Feedwater Regulating Valve, Causing Lo Lo SG Level Reactor Trip.Caused by Improperly Secured Stroke Adjust Set Screw (← links)
- 05000244/LER-1994-002, :on 940202,containment Pressure Channels P-947 & P-948 Were Inoperable.Caused by Water Being Trapped in Low Point of Line.Corrective Action:Iron Oxide Scale Was Removed & Sensing Line restored.W/940506 Revised Ltr (← links)
- 05000244/LER-1994-022, :on 940202,determined That Containment Pressure Channels P-947 & P-948 Were Inoperable.Caused by Obstruction of Common Pressure Sensing Line.Corrective Action:Iron Oxide Scale Was Removed & Channels Declared Operable (← links)
- 05000244/LER-1994-006, :on 940323,SG Tube Degradation Due to Iga/Scc, Caused QA Manual Reportable Limits to Be Reached.Caused by Pwscc.Tubes Repaired (← links)
- 05000244/LER-1994-005, :on 940217,turbine Runback Occurred Due to Lost Offsite Power Circuit 751 Causing Low Voltage on Safeguard Busses 14 & 18.Circuit 751 Restored by Automatic Reclosure of Transformer Breaker (← links)
- 05000244/LER-1994-004, :on 940214,four Surveillance Tests Missed Due to Lack of Clearly Defined Interpretations of Ts. Intermediate Range Bistable Circuits Reviewed to Verify Trip Signal Would Deenergize Reactor Trip Relay (← links)
- 05000244/LER-1994-003, :on 940208,open Instrument Tube Resulted in Loss of Containment Integrity.Caused by Personnel Error. Swagelok Plug Installed on Open Tube (← links)
- 05000244/LER-1994-001, :on 940119,Radition Monitor R-32 Declared Inoperable Due to Low Output by One Decade.Correct Value of Calibr Constant for R-32 Determined & Edited Into R-32 Control Terminal (← links)
- 05000244/LER-1993-007, :on 931122,RT Occurred Due to High Source Range Flux Level During Reactor Startup.Caused by Failure of Personnel Focusing on RT Setpoint.Replaced Status Lights & Corrected PPCS Alarm Message (← links)
- 05000244/LER-1993-006, :on 931110,feedwater Transient Occurred,Due to Loss of Ability to Control Feedwater Regulating Valve.Caused by low-low SG Level Reactor Trip.New Screw & Nut Installed in Linkage Arm (← links)
- 05000244/LER-1993-005, :on 931011,due to Misinterpretation of TS 4.6.1.e.3.(a) Requirements,Verification of Load Shedding Capability of Safeguards Loads Not Adequately Performed. Testing Completed to Verify Capability (← links)
- 05000244/LER-1993-001, Provides Status of Source Range Detector Action Plan Per LER 93-001 Re Loss of Source Range Detector Indication During Energization (← links)
- 05000244/LER-1993-004, :on 930707,Main Feedwater Isolations Occurred Due to Secondary Side & Condensate Feedwater Pressure Transient.Returned Feedwater Regulating Valves to pre-event Controls Configuration (← links)
- 05000244/LER-1992-006, :on 920518,main FW Isolations Occurred on SG a Due to Overfeeding SG a While in Manual Control.Caused by Heater Drain Tank Level Control Sys Problem.Administrative Controls Instituted to Ensure Valve Not Open (← links)
- 05000244/LER-1993-003, :on 930328,discovered Failures of Safeguard Svc Water Sys During Planned Maint.Caused by Design & Operating Environ.Replaced Affected Valves W/Qualified Spares.W/ (← links)
- 05000244/LER-1993-002, :on 930404,during 1993 SG Eddy Current Exam, Determined 1% of Total Tubes in SG a & B Degraded.Caused by Iga & IGSCC within Tube Sheet Crevice Region.Tubes Welded Using Tube Sheet Sleeve (← links)
- 05000244/LER-1992-007, :on 921224,turbine Runback Occurred & a EDG Started & Tied Into Safeguard Buses 14 & 18.Caused by Loss of Power to Safeguards.Restored Normal Power to Safeguards Buses 14 & 18 (← links)
- 05000244/LER-1992-001, :on 920105,containment Ventilation Isolation Occurred Due to Actuation Signal from Containment Particulate Radiation Monitor R-11.Root Cause Undetermined. Radiation Monitor Reset & Drawer Replaced (← links)
- 05000244/LER-1992-005, :on 920420,determined That 242 Tubes in a SG & 216 Tubes in B SG Required Corrective Action Due to Tube Degradation.Affected Tubes Either Sleeved or Plugged.W/ (← links)
- 05000244/LER-1992-003, :on 920229,reactor Trip Occurred Due to Lo Lo Level in Steam Generator B.Caused by Plugged Instrument Tubing for Feedwater Pump a Seal Injection Differential Pressure Switch.Turbine Flushed (← links)
- 05000244/LER-1992-002, :on 920203,reactor Trip Occurred W/Reactor at Approx 23% Full Power Just Subsequent to Turbine Trip While at 47% Power.Caused by Lo Lo Level in SG a Due to Design Perturbations.New Setting Calculated (← links)
- 05000244/LER-1991-010, :on 911230,during Operator Review of Plant Process Computer Logs,Util Discovered That Invalid Data Had Been Used for Calculation.Caused by Invalid Input from Lefm.Lefm HP-85B Computer Was Reinitialized (← links)
- 05000244/LER-1991-009, :on 911111,steam Generator Feedwater Isolations Occurred on Both Steam Generators.Caused by Perturbations of Advanced Digital Feedwater Control Sys.Feedwater Regulating Valves Manually Controlled (← links)
- 05000244/LER-1991-006, :on 910629,EDG a Started Automatically Due to Apparent Undervoltage Signal from Bus 14 Undervoltage Monitoring Sys.Root Cause Not Determined.Bus 14 Energized & EDG Declared Operable (← links)
- 05000244/LER-1991-005, :on 910414,steam Generator Tube Degradation Occurred Due to Iga/Scc & Primary Water Stress Corrosion Cracking Attack on Steam Generator Tubing.Affected Tubes Sleeved or Plugged (← links)
- 05000244/LER-1991-004, :on 910328,emergency Generator B Started Due to Potential for Severe Weather While Operating W/Rcs in Reduced Inventory Condition.Generator Removed from Svc & Realigned for Auto Standby (← links)
- 05000244/LER-1991-003, :on 910314,fire Sprinkler Sys S-04 Rendered Inoperable W/O Firewatch W/Backup Fire Suppression Equipment Being Established.Due Inadequate Adherence to Procedures. Site Contingency Procedure SC-3.16.2.4 Revised (← links)
- 05000244/LER-1990-010, :on 900609,reactor Trip Occurred from Steam Generator a Low Level Coincident W/Steam Flow/Feed Flow Mismatch.Caused by Faulty Feedwater Flow Controller. Controller Replaced (← links)
- 05000244/LER-1991-002, :on 910304,loss of Offsite Power Circuit 751 Occurred Due to Ice Storm,Resulting in Automatic Actuation of EDG & Turbine Runback.Buses Restored to Normal Power & EDG Realigned (← links)
- 05000244/LER-1991-001, :on 910215,loss of Safeguards Bus Occurred During Emergency Diesel Generator Monthly Load Test.Caused by Supply Breakers Tripping.Bus 18,emergency Diesel Generator 1A & Output Breaker Inspected (← links)
- 05000244/LER-1990-017, :on 901212,two DC Switches Opened Causing Disabling of Manual Automatic Actuation of Safeguards Sequence Initiation.Caused by Inadequate Procedures. Procedures Revised (← links)
- 05000244/LER-1990-018, :on 901220,dropped Control Rod/Turbine Runback Occurred During Rod Control Exercises.Caused by Degraded Power Bridge Thyristor Suppression Filter Capacitors. Capacitors Replaced (← links)
- 05000244/LER-1990-019, :on 901221,reactor Tripped Due to Lo Lo Level in Steam Generator A.Caused by Main Feedwater Pump a Tripping Due to Feed Pump Seal Water Low Differential Pressure.Procedures Will Be Revised (← links)
- 05000244/LER-1990-016, :on 901212,reactor Trip Occurred from Inadvertent Intermediate Range Trip.Caused by de- Energization of One Out of Two Intermediate Range Nuclear Instrument Sys High Flux Trip Bistable (← links)
- 05000244/LER-1990-015, :on 901212,automatic Start of EDG a Occurred Due to Initiation Signal from Bus 14 Undervoltage Monitoring Sys.Caused by Failure of Solid State Switch Printed Circuit Board.Circuit Board Replaced (← links)
- 05000244/LER-1990-014, :on 901206,potential Technical Inoperability of Pressurizer PORV Discovered During Certain Procedures. Caused by Procedural Inadequacy.Periodic Test Procedures PT-5.10 & PT5.30 Changed (← links)
- 05000244/LER-1990-013, :on 901211,turbine Trip W/Subsequent Reactor Trip Occurred.Caused by Inadvertent ATWS Mitigation Sys Actuation Circuitry (AMSAC) Actuation.Jumper,Omitted in AMSAC Circuit Design,Installed (← links)
- 05000244/LER-1990-012, :on 900926,turbine Trip Relay Actuation Due to Dropped Flashlight in Relay Rack (← links)
- 05000244/LER-1990-008, :on 900524,safeguards Buses Degraded Voltage Relays Miscalibrated.Caused by Wrong Setpoint Tolerance Being Specified in Calibr Procedure.Degraded Voltage Relays Calibr to Conservative Tolerance Setpoint (← links)
- 05000244/LER-1990-011, :on 900619,fire Damper Found Missing During Surveillance Test PT-13.26 Due to Lack of Installation. Caused by Inadequate Design Info.Hourly Fire Watch Established (← links)
- 05000244/LER-1990-009, :on 900609,emergency Diesel Generator a Started Automatically & Tied Into Safeguards Buses 14 & 18 Due to Undervoltage.Caused by Inadvertent Closure of 4 Kv Bus 11A Normal Feed Breaker.Breaker Reopened (← links)
- 05000244/LER-1989-016, :on 891117,discovered Potential Problem W/ Safety Injection Block/Unblock Switch.On 891220,determined That Single Failure of Switch Could Render Both Trains of Safety Injection Inoperable.Also Reported Per Part 21 (← links)
- 05000244/LER-1989-016-02, Forwards LER 89-016-02 Re 891117 Failure of Safety Injection Block/Unblock Switch Which Could Render Both Trains of Safety Injection Sys Inoperable.Also Reported Per Part 21 (← links)
- 05000244/LER-1990-007, :on 900510,reactor Trip Occurred from Steam Generator a Low Level Coincident W/Feed Flow/Steam Flow Mismatch.Caused by Shorting of Two High Gain Ac Amplifier Transistors.Plant Stablized in Hot Shutdown (← links)
- 05000244/LER-1990-003, :on 900323,higher than Normal Count Rate Noted on source-range Nuclear Instrumentation Sys,Resulting in Reactor Trip During Reenergization.Caused by Low Internal Resistance on Detector.Detector changed-out (← links)
- 05000244/LER-1990-002, :on 900226,fire Watch Patrol Hourly Patrol Performed in Wrong Areas.Caused by Personnel Error.Card Issued to Each Individual Performing Tech Spec Fire Watch Commitment (← links)
- 05000244/LER-1990-001, :on 900225,determined That Security Tours Did Not Necessarily Result in Entry to Areas Once Per Hour,As Required by Tech Specs.Caused by Improper Interpretation of Security Touring Policy (← links)
- 05000244/LER-1988-010, :on 881211,two Steam Generator 1B Pressure Channels Began Drifting High.Caused by Freezing of Affected Pressure Transmitter Sensing Lines.Affected Lines Thawed & Calibr (← links)
- 05000244/LER-1987-008, :on 871223,failure of Safeguards Circuit Breakers Occurred Due to Zero Clearance Between Ampector Actuator Arm & Breaker Trip Bar.Caused by Inadequate Design Info from Vendor.Clearance Reset (← links)
- 05000244/LER-1987-007, :on 871218,during Review of Westinghouse Ltr Re Operating Plant Feedback,Potential for Loss of Cooling During High Head Recirculation Phase Discovered.Caused by Design Flaw.Affected Valve Repositioned (← links)
- 05000244/LER-1987-006, :on 871130,standby Auxiliary Feedwater Pump 1D Deemed Inoperable Beyond Tech Spec Limit.Caused by Cooling Unit 1B Ac Electrical Breaker Found in Off Position Due to Unaware Operator.Breaker Turned to on Position (← links)
- 05000244/LER-1987-005, :on 870514,containment Ventilation Isolation Occurred Due to Spurious Signal from Containment Particulate Radiation Monitor (R-11).Caused by Frayed Input Signal Bnc Connector.Connector Resoldered (← links)
- 05000244/LER-1987-004, :on 870424,during Full Power,Train B Containment Isolation Occurred.Caused by Personnel Accidentally Bumping Relay in Safeguards Cabinet During Electrical Wire Checkout.Personnel Counseled (← links)
- 05000244/LER-1987-003, :on 870316,major Portion of Fire Sys Detection & Auto Suppression Found Inoperable.Caused by Operator Failure to Follow Procedural Direction During Fire Sys Disconnect Procedure.Procedure Updated (← links)
- 05000244/LER-1987-002, :on 870306,RCS Oxygen Analysis Indicated That Steady State Requirements of Tech Spec 3.1.6.2 Had Been Exceeded.Caused by Personnel Error & Procedural Inadequacy. Procedural Guidance Being Developed (← links)
- 05000244/LER-1980-007-03, /03L-0:on 800829,controller TC-402R for Channel II Did Not Respond to Change in Input.Caused by Faulty Main Amplifier Bridge Assembly & Low Limit Transmitter.Controller Replaced & Calibr (← links)
- 05000244/LER-1979-015-01, During Piping Sys Insp Per IE Bulletin 79-14,found Pipe Supports Not Installed Per Tech Specs.Caused by Lack of Documented Approvals for Field Changes.Pipe Supports Reworked to Establish Acceptability (← links)
- 05000244/LER-1979-023-01, During Inservice Insp, Liquid Penetrant Examination of Pressurizer nozzle-to-safe- End Weld Showed Linear Indications.Caused by Inadequate Delta Ferrite Content & Geometric Discontinuity (← links)
- 05000244/LER-1980-006-01, /01T-0:on 800711,during Routine Analysis of Boric Acid Tank Samples,Concentration Exceeded Tech Spec Limit on Three Occasions.Caused by Entry of Ascarite Into Tank. Reagent Check Now Performed W/Sampling (← links)
- 05000244/LER-1980-005-01, /01T-0:on 800603,during Performance of Monthly Verification Procedure,Loop a Accumulator Injection Circuit Breaker Found in on Position.Cause Not Stated.Breaker Returned to Off Position (← links)
- 05000244/LER-1980-004-01, /01T-0:on 800506,during post-installation Test of Reactor Vessel Head Vent,Dc Power Switches for Both Trains of Low Temp Overpressurization Protection Found in Off Position W/No RCS Vent Open.Cause Unknown (← links)
- 05000244/LER-1980-003-01, /01T-0:on 800414,during Steam Generator Inservice Insp,One Tube in a Steam Generator & 34 Tubes in B Generator Showed Pluggable Indications.Probably Caused by Concentration of Caustics in Crevices (← links)
- 05000244/LER-1980-002-03, /03L-0:on 800331,during Review of Special Instructions,Discovered That Time from Previous Boron Concentration Sample Exceeded 75 Days.Caused by Inadequate Guidance for Bimonthly Sampling Schedule.Schedule Changed (← links)
- 05000244/LER-1980-001-03, /03L-0:on 800118,while Performing PT-12.1, Emergency Generator 1A Would Not Accept Nameplate Steady Load Rating.Caused by Adjusting Governor Setting to Incorrect Value Indicated on Dynotape Sticker Setting Mod (← links)
- 05000244/LER-1979-024-01, Samples of Boric Acid Storage Tank Concentrations Found Below Min Limits.Caused by Backflow of Refueling Water Through Boric Acid Tank Outlet Motor Operated Valve (← links)
- 05000244/LER-1979-025-03, /03L-0:on 791223,containment Entry Was Made But Personnel Air Lock Not Tested Until 791226,exceeding 48-h Tech Spec Requirement.Caused by Existing Procedural Inadequacy (← links)
- 05000244/LER-1979-022-01, /01T-0:on 791201,during Normal Operations,Found Two Leaking Tubes & Eleven Other Tubes W/Pluggable Defects. Caused by Possible Thermal,Hydraulic & Mechanical Loading in Wedge Area & by Possible Residual Caustics Concentratio (← links)
- 05000244/LER-1979-022, Forwards LER 79-022/01T-0 (← links)
- 05000244/LER-1979-021-03, /03L-0:on 791018,Tech Spec Requirement 4.8.5 Re Stroking Crossover Valves Omitted from Procedure for Testing Standby Auxiliary Feedwater Pumps.Caused by Personnel Error. Test Personnel Briefed & Performed Tests (← links)
- 05000244/LER-1979-020-03, /03L-0:on 791009,during Snubber Insp,Snubber in Position MS146 Found W/No Accumulator Level.Caused by Movement of Pipe Resulting in Wear on Accumulator & Eventual Failure of Shaft Seal.Unit Replaced W/Spare (← links)
- 05000244/LER-1979-019-03, /03L-0:on 790919,loose Nuts on Anchor Bolts Were Found on Pipe Supports & on Svc Water Piping to Standby Auxiliary Feedwater Pump.Caused by Nuts Working Loose During Sys Operation.Nuts Were Torqued to Current Requirement (← links)
- 05000244/LER-1979-017-01, /01T-0:on 790831,analysis of Boric Acid Storage Tank Samples Revealed Concentrations Above 13% Limits. Possibly Due to Evaporation,Redissolution of Crystals or Sampling Error.Load Reduction Begun & Levels Restored (← links)
- 05000244/LER-1979-008-03, /03X-1 on 790406:during Maint on Boric Acid Flow Control Valve,Leaks Noted on Valve Outlet 1-inch Nipple. Caused by External Caustic Pitting.Actions to Minimize Caustics & Chlorides Are Being Taken (← links)
- 05000244/LER-1979-016-01, /01T-0 on 790804:14-h Interval of Reactor Operation Lapsed Prior to Trip During Trip Testing Following Maint Outage & Restoration of Criticality.Caused by Unclear Checkoff procedure.On-shift Training Held (← links)
- 05000244/LER-1979-014-03, /03L-0 on 790709:during RCS Cooldown,Operator Noted Channel P-452 Overpressurization Alarm Not in Correct State.Caused by Bistable Setpoint Drift.Alarm Unit Replaced (← links)
- 05000244/LER-1979-013-01, /01T-0 on 790707:during Ultrasonic & Radiographic Examination of Steam Generator Feedwater nozzle-to-elbow Welds,Small Linear Indications in Elbows Were Found.Cause Not Identified.Elbows Replaced (← links)
- 05000244/LER-1979-012-01, /01X-1 on 790327:several Anchor Bolts Identified as Not Being in Accordance W/Drawing During Inservice Insp. Caused by Inadequate Control of Const Installation.Anchor Bolts Corrected (← links)
- 05000244/LER-1979-011-01, /01T-0 on 790511:notified by Manufacturer of Pressurizer Power Operated Relief Valve That Template Used to Fabricate Valve Internals Not within Specs.Caused by Error in Tracer Lathe Template (← links)
- 05000244/LER-1979-010-01, /01T-0 on 790420:routine Sample of Boric Acid Storage Tanks Showed Less than 12%.Reactor Power Reduction Started.Caused by Possible Backflow of Makeup Water.Check Valve Replaced (← links)
- 05000244/LER-1979-009-01, /01T-0 on 790416:routine Sample of Boron Boric Acid Tank Showed 11.8%.Reactor Power Reduction Started. Caused by Possible Backflow of Makeup Water.Check Valve Replaced (← links)
- 05000244/LER-1979-007-03, /03L-0 on 790402:surveillance Requirement for Nuclear Intermediate Range Channel Test within Seven Days Was Not Performed for Two Training Criticalities.Caused by Unclear Training Procedures (← links)
- 05000244/LER-1979-006-01, /01T-0 on 790321:degradation in 6 Tubes of Steam Generator B.Caused by Localized Residual Caustics Erosion at Support Plates & Stress Corrosion Mechanism Re Deformation at Tube Sheet & Operationsl Stresses (← links)
- 05000244/LER-1979-004-03, /03L-0 on 790206:fuel Pressure Lost & Generator Tripped During Diesel Generator Testing.Caused by Operator Error.Operator Reinstructed & Precautionary Note Added to Procedure to Emphasize Importance of Proper Sequence (← links)
- 05000244/LER-1979-005-03, /03L-0 on 790206:containment Recirculation Sump Failed to Reopen After Hydro Testing.Caused by Flexibility of Long Extension Rod Between Limitorque SMB-00 Operator & Valve.Valve Stroked Monthly & Timed Quarterly (← links)
- 05000244/LER-1979-001, Forwards LER 79-001/03L-0 (← links)
- 05000244/LER-1979-002-03, /03L-0 on 790104:during Steady State Power a Charging Pump Leaked & Found to Be Cracked.Caused by Fatigue Cracking Due to High Loop Stresses Generated in Compression Stroke of Piston in Cylinder (← links)
- 05000244/LER-1979-003-03, /03L-0 on 790104:B Charging Pump Speed Control Operated Improperly W/Sticking Lower Varidrive Disc & Belt Slippage at Min Speed.Operation at 1 Speed Caused Local Lubrication Problems (← links)
- 05000244/LER-1978-009-01, /01T-0 on 781226:during Surveillance of Repair on Halon Sys for Relay Room & Computer Room,Noted That Fire Watch Was Adjacent To,But Not In,Unprotected Area.Caused by Failure to Communicate Proper Assignment to Personnel (← links)
- 05000244/LER-1981-012, Forwards LER 81-012/03L-0 (← links)
- 05000244/LER-1981-011, Forwards LER 81-011/03L-0 (← links)
- 05000244/LER-1981-007, Forwards LER 81-007/03L-0 (← links)
- 05000244/LER-1981-006, Forwards LER 81-006/03L-0 (← links)
- 05000244/LER-1981-004, Forwards LER 81-004/03L-0 (← links)
- 05000244/LER-1981-003, Forwards LER 81-003/03L-0 (← links)
- 05000244/LER-1981-002, Forwards LER 81-002/03L-0 (← links)
- 05000244/LER-1981-001, Forwards LER 81-001/03L-0 (← links)
- 05000244/LER-1981-019, Responds to NRC Re Violations Noted in IE Insp Rept 50-244/81-24.Corrective actions:LER-81-019 Submitted Reporting 811114 Event Re Inadvertent Actuation of Fire Suppression Sys (← links)
- 05000244/LER-1988-004, :on 880314,tube Leak Detected in Steam Generator B.Caused by Missed Call from Recent Steam Generator Eddy Current Insp Program.Eddy Current Data Analysis Procedures Updated (← links)
- 05000244/LER-1988-003, :on 880310,reactor Trip Occurred Due to Low Steam Generator a Level Coincident W/Steam Flow Feedwater Flow Mismatch.Caused by Unanticipated RCS Temp Control Problems.Plant Stabilized (← links)
- 05000244/LER-1988-002, :on 880308,level of Boric Acid Storage Tank Less than 2,000 Gallons in Violation of Tech Specs.Caused by Partial Plugging of Level Sensing Lines.Sensing Lines Cleaned Prior to Declaring Tank Operable (← links)
- 05000244/LER-1988-001, :on 880205,reactor Trip Occurred.Caused by Higher than Normal Count Rate on Source Range (SR) Nuclear Instrumentation Sys Due to Faulty Connectors at Detectors. SR Detectors Replaced (← links)
- 05000244/LER-1989-003, :on 890518,inadvertent Safety Injection Occurred.Caused by Procedural Inadequacy.Safety Injection & Containment Isolation Signals Reset & Equipment Restored to pre-event Condition (← links)
- 05000244/LER-1989-002, :on 890506,safeguards 480 Volt Bus 14 Tripped During Offsite Power Mod Relay Testing.Caused by Typo in Mod Test Procedure That Called for Wrong Terminal Block to Be Opened.Error Corrected (← links)
- 05000244/LER-1989-001, :on 890412,steam Generator Tube Degradation Occurred Due to Intergranular Attack/Stress Corrosion Cracking.Caused by Tube Degradation in Excess of QA Manual Reportability Limits.Affected Tubes Plugged (← links)
- 05000244/LER-1988-009, :on 880930,two 6-inch Diameter Pipes Found to Have Degraded Blocks Around Pipe Sleeves & Improper Fire Barrier Fill.Caused by Inadequate Fire Barrier Insp Procedures.Procedure Will Be Upgraded (← links)
- 05000244/LER-1988-008, :on 880903,emergency Diesel Generator B Automatically Started Due Inadvertent Initiation Signal from Bus 16.Caused by Failed Solid State Switchboard.Switchboard Replaced W/Qualified Spare (← links)
- 05000244/LER-1988-007, :on 880804,containment Particulate Radiation Monitor de-energized Due to Open AC Fuse Inadvertently Causing Containment Ventilation Isolation.Caused by Internal Bridge Rectifier Power Supply Failure (← links)
- 05000244/LER-1988-006, :on 880716,emergency Diesel Generator Started Automatically.Caused by Failed Bushing on Main Electrical Substation 115 Kv Oil Circuit Breakers.Bushing Replaced & Sent to Lapp Insulator Co for Evaluation (← links)
- 05000244/LER-1988-005, :on 880601,reactor Trip Occurred Followed by Safety Injection Initiation from Pressurizer Low Presssure. Caused by Blown Fuse in Steam Generator B & RCS Cooldown. Plant Stabilized Per Emergency Procedures (← links)
- 05000244/LER-1991-008, :on 910805,failure of One of Two Trains of Undervoltage Protection Discovered on Safeguards Bus 14 Due to Temp Related Failure of Solid State Switch Printed Circuit Card.Circuit Card Replaced (← links)
- 05000244/LER-1991-007, :on 910731,B Emergency Diesel Generator Started Automatically Due to Initiation Signal from Bus 16 & 17 Undervoltage Monitoring/Protection Sys.Caused by Temp Related Switch Failure.Switch Replaced (← links)
- 05000244/LER-1990-006, :on 900505,isolation of Wrong Pressurizer Pressure Transmitter Occurred,Resulting in Inadvertent Safety Injection Actuation During Maint.Caused by Personnel Error.Plant Stabilized & Closed Valve Opened (← links)
- 05000244/LER-1990-005, :on 900425,emergency Diesel Generator a Started Automatically Due to Initiation Signal from Bus 14 or 18 Undervoltage Monitoring Sys.Caused by Single Relay Dropping Out on Both Buses.Generator Realigned (← links)
- 05000244/LER-1990-004, :on 900416,steam Generator Tube Degradation Noted on 75 Steam Generator a Tubes & 211 Steam Generator B Tubes.Caused by Intergranular Attack/Stress Corrosion Cracking.Tubes Sleeved or Plugged (← links)
- 05000244/LER-1989-015, :on 891119 & 22,turbine Runbacks to Approx 99% Full Power Occurred.Caused by Overtemp Delta T &/Or Overpressure Delta T Circuitry Due to Malfunction of Channel TI-401.Dual Current Source Replaced W/Spare (← links)
- 05000244/LER-1989-013, :on 891020,containment Ventilation Isolation Occurred Due to Containment Gas Radiation Monitor R-12 Reaching Alarm Setpoint.Caused by Flow/Pressure Fluctuations at Monitor Skid.Signal Reset (← links)
- 05000244/LER-1989-014, :on 891023,containment Ventilation Isolation Occurred Due to Containment Gas Radiation Monitor R-12 Reaching Alarm Setpoint.Caused by Flow/Pressure Fluctuations.Isolation Signal Reset (← links)