Pages that link to "05000280/LER-1985-001"
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The following pages link to 05000280/LER-1985-001:
Displayed 50 items.
- 05000280/LER-1983-022-03, /03L-0:on 830505,w/unit at Cold Shutdown,Special Test Showed Flow Orifice Used During Control Room Leakage Test Would Not Simulate Emergency Bottle Air Pressurization. Orifice Modified (← links)
- 05000280/LER-1983-030-03, /03l-0:on 830707,at 100% Power,Breaker for Heat Tracing Circuit 26A on Panel 9 Found Open.Breaker Closed. Circuit Verified Operational (← links)
- 05000280/LER-1986-028, :on 860925,individual Rod Position Indicators for All Control Rods Moved Down Approx 25 Steps.Caused by Failed Normal Negative Power Supply.Two Negative Power Supplies Replaced & Calibr (← links)
- 05000280/LER-1986-002, :on 860108,unit Tripped from 97% Power & Specific Activity Sample of Reactor Coolant Exceeded Tech Spec Dose Equivalent I-131 Limit.Caused by Iodine Spike. Level Monitored Every 4 H (← links)
- 05000280/LER-1986-009, :on 860208,during Startup,Operating Main Feedwater Pump Tripped Due to High Level in Steam Generator C.Caused by Dust Accumulation in Pilot Relay Blocking Air to Valve Operator.Blockage Removed (← links)
- 05000280/LER-1986-008, :on 860213,unexpected Start of Auxiliary Feed Pump 2-FW-P-3B Occurred.Caused by Open Coil in Bfd Relay AFP-3XB.Relay Replaced & Tested Satisfactorily (← links)
- 05000280/LER-1986-005, :on 860124,unit Manually Tripped from 42% Power Due to Arcing on Isolated Phase Bus Duct A.Caused by Corrosion on Contact Surfaces of Lugs of Ground Straps. Damaged Section of Duct Replaced & Welded (← links)
- 05000280/LER-1986-002-01, :on 860119,at 100% Power,Excess Leakage of RCS Noted.Caused by Failed motor-operated Valve Packing & Failed Diesel Generator Diaphragm.Valve Will Be Repacked & Diaphragm Replaced During Next Suitable Outage (← links)
- 05000280/LER-1986-001-01, :on 860107,reactor Trip Occurred Due to Loss of Instrument Air.Caused by Hot Gas Bypass Valve in Dryer Improperly Adjusted to Maintain Air Temp Above Freezing. Operator Attempted to Gain Manual Control (← links)
- 05000280/LER-1986-011, :on 860227,instrumentation Accident Monitoring High Range Radiation Monitors Declared Inoperable.Caused by Design Deficiency in Computer Software.Effluents Monitored by Alternate Methods (← links)
- 05000280/LER-1986-007, :on 860107,two Bolting Studs in Valve Flange MOV-SI-1890B Failed.Caused by Intergranular Stress Corrosion of Bolting Matl.Insp Conducted & Stud Matl Replaced,As Necessary (← links)
- 05000280/LER-1984-017, :on 840620,control Rod B-6 Became Stuck at 56 Steps Withdrawn,Resulting in Quadrant Power Tilt of Greater than 2% for More than 24 H.Caused by Spring Clamp Separation.Fuel Assembly Removed from Svc (← links)
- 05000280/LER-1985-022-01, :on 851121,spurious auto-start of Auxiliary Vent Emergency Fans Occurred.Cause Not Determined.Steam Generator Pressure Returned to Normal & Letdown Trip Valve TV-1204 Opened (← links)
- 05000280/LER-1985-020, :on 850927,following Controlled Shutdown Due to Hurricane Gloria,Iodine Spike Discovered.Caused by Known Fuel Element Defects in Reactor Core.Level of Dose Equivalent I-131 Monitored Per Tech Spec Table 4.1-2B (← links)
- 05000280/LER-1985-019, :on 850927,individual Rod Position Indicator for Two Rods Inoperable.Spurious Incorrect Rod Position Indication Is Generic Westinghouse PWR Concern.Portion of Sys Outside Containment Tested & No Problems Found (← links)
- 05000280/LER-1985-021, :on 851114,unexpected Start of Auxiliary Feed Pump 2-FW-P-3A Occurred.Caused by Open Coil in Bfd Relay AFP-2XA.Relay Replaced & Tested Satisfactorily (← links)
- 05000280/LER-1986-010, :on 860207,reactor & Turbine Tripped on High Steam Generator Level.Caused by Failure to Adjust Feedback Cam Following Maint.Cam Adjusted & Maint Procedure Revised (← links)
- 05000280/LER-1986-004, :on 860119,following Manual Reactor Trip, Specific Activity Sample of Primary Coolant Sys Exceeded Dose Equivalent I-131 Level of 1.0 Uci/Cc.Caused by Fuel Element Defects in Reactor Core (← links)
- 05000280/LER-1985-018, :on 850911,turbine Trip/Reactor Trip Occurred Due to Low Condenser Vacuum Signal.Caused by Operation Error.Covers Placed on Inlet Valve Switches & Operator Reinstructed (← links)
- 05000280/LER-1985-013, :on 850721,containment Temp Exceeded 120 F for Approx 3 H.Caused by Loss of Component Cooling Chiller Unit. Component Restarted & Chiller Condenser Svc Water Tubes Cleaned (← links)
- 05000280/LER-1984-004-03, :on 840225,following Shutdown,Specific Activity Sample of Reactor Coolant Showed Peak Dose Equivalent I-131 Level of 1.77 Mci/Cc,Exceeding Tech Spec 3.1.D.2.Caused by Fuel Element Defects in Reactor Core (← links)
- 05000280/LER-1984-010-03, :on 840517,reanalysis Rept on Compliance to Design Requirements of 10CFR50,App R Received.Insp of Fire Protection Equipment Identified Five Areas of Deficiency. Caused by Changes in NRC Interpretation (← links)
- 05000280/LER-1984-011-03, :on 840518,operations Personnel Performing Sys Walkdown Following Maint Discovered Intended Heat Sink for Charging Pump Component Cooling Water Sys Isolated.Caused by Inadequate Procedures (← links)
- 05000280/LER-1984-020, :on 840926,reactor Trip Occurred Due to Reactor Coolant Pump (RCP) Motor C Trip.Caused by Complete Separation of Phase Main Load Connection Bus Bar A.All Bus Bars in RCP Replaced (← links)
- 05000280/LER-1985-013-01, :on 850721,containment Temp Exceeded 120 F for Approx 3 H.Caused by Loss of Component Cooling Chiller I-CD-REF-IA Due to Tube Fouling on Water Side Causing High Chiller Condenser Pressure (← links)
- 05000280/LER-1985-017-01, :on 850911,following Reactor trip,I-131 Level Exceeded Tech Spec Limit.Caused by Fuel Element Defects in Reactor Core.Dose Equivalent Monitored Until Less than 1.0 Uci/Cc (← links)
- 05000280/LER-1985-010, :on 850515,intermediate Range High Flux Trip Bistables NI-35 & NI-36 Tripped at 30% & 31% Power, Respectively.Apparently Caused by Lack of Experience in Developing Intermediate Setpoints (← links)
- 05000280/LER-1985-011, :on 850626,while Racking Charging Pump B Breaker 15J5 Out for Pump Maint,Normal Feeder Breaker 15H6 for Operating Charging Pump C Tripped Due to Electrical Interlock.Caused by Inadequate Precautions (← links)
- 05000280/LER-1983-036-03, /03L-0:on 830830,at 100% Power,Low Pressure Carbon Dioxide Sys & Fire Detection Sys Inoperable W/O Fire Watch. Caused by Personnel Error.Fire Watch Posted.Sys Returned to Svc (← links)
- 05000280/LER-1983-038-03, /03L-0:on 830829,at 100% Power,Svc Water Pumps 1-SW-P-10A & 1-SW-P-10B Failed to Develop Sufficient Discharge Pressure When Redundant Water Supply Header Isolated.Caused by Npsh.Pumps Vented (← links)
- 05000280/LER-1985-007, :on 850429,turbine/reactor Trip Occurred as Result of Main Feed Pump a Trip.Caused When Valve Open Signal Not Sent to Feed Pump Trip Logic.Valve Position Actuator Arm Modified (← links)
- 05000280/LER-1985-012, :on 850609,during Testing of Discharge Valves, Chemical Addition Tank Water Level Decreased.Caused by Failed Closed Contact,Resulting in Valve Reopening.Flow Path Isolated & Failed Contacts Replaced (← links)
- 05000280/LER-1985-009, :on 850512,PORV PCV-1455C Cycled Twice Due to Overpressure Condition.Caused by Failure of Normal Letdown Pressure Control Valve PCV-1145 Due to Positioner Misadjustment.Part Adjusted (← links)
- 05000280/LER-1985-005-01, :on 850403,operator Discovered Lockout of Automatic Initiation of CO2 for Fire Zone 7 W/O Required Fire Watch.Caused by Misunderstanding Between Personnel Re Fire Zone Tagging (← links)
- 05000280/LER-1984-001, :on 840106,reactor Trip Occurred W/Unit at 100% Power.Caused by Over Temp delta-t Signal.Feedwater to Steam Generator a Isolated & Source Range Channels Manually Reinstated (← links)
- 05000280/LER-1984-025, :on 841203,during Refueling Outage W/Plant in Cold Shutdown,Source Range & Intermediate Range Trip Signal Occurred.Caused by Voltage Transient Induced Upon Vital Bus 2 During Replacement of Key Switch (← links)
- 05000280/LER-1985-002-01, :on 850113,lo-lo Level in Steam Generator B Caused Reactor Scram.Caused by Failure of Personnel to Adequately Control Steam Generator Level.Feedwater Bypass Flow Indication Design Installed (← links)
- 05000280/LER-1985-006, :on 850128,reactor Trip Occurred Due to Differential Pressure anti-motoring Turbine Trip.Caused by Isolation of Exhaust Pressure Sensing Line Root Valve in anti-motoring Instrumentation.Plant Returned to Svc (← links)
- 05000280/LER-1985-004, :on 850127,reactor Tripped Due to Closing of Four Turbine Stop Valves.Caused by Insufficient Consideration of Steam Leakage Effect on Plant Parameters. Plant Parameters Returned to Stable Conditions (← links)
- 05000280/LER-1985-003, :on 850126,reactor Tripped Due to Voltage Transient Induced on Vital Bus I When Momentary Overload Condition Caused Circuit Breaker 13 to Trip Open.Cause Unknown.Plant Returned to Stable Condition (← links)
- 05000280/LER-1985-001, :on 850101,safe Signal Placed in Loop B Channel 2 of Overtemp Delta T W/O Cognizance of Operations or Instrumentation Staff.Caused by Lack of Administrative Controls.Event Will Be Reviewed (← links)
- 05000280/LER-1984-027, :on 841218,during Surveillance Testing of Emergency Diesel Generator 3,fire Occurred in Vicinity of Turbocharger.Caused by Leaking Fitting on Fuel Injector Line Which Allowed Fuel Oil to Leak Into Lube Oil (← links)
- 05000280/LER-1984-026-01, :on 841231,reactor Trip Occurred When Reactor Trip Breaker B Opened.Cause Undetermined.Reactor Trip Breaker B Inspected & Shunt Devices Tested.No Discrepancies Found (← links)
- 05000280/LER-1984-024, :on 841116,spurious Safety Injection Occurred When Returning Consequences Limiting Safeguards,High Phase (Equivalent to Containment Depressurization Actuation Sys) to Svc.Impact on Unit Minimal (← links)
- 05000280/LER-1984-023, :on 841113,spurious Safety Injection Received While Technicians Performing Calibr Procedure CAL-63.Caused by Electrical Transient in Instrument Loops (← links)
- 05000280/LER-1984-021, :on 841028,assigned Fire Watch Not Present at Cable Tunnel Area & Carbon Dioxide (CO2) Fire Sys Locked Out.Caused by Personnel error.CO2 Sys Restored & Personnel Counseled on Importance of Proper Fire Watch (← links)
- 05000280/LER-1984-018, :on 840823,operator Discovered Air Hose Blocking Open Fire Door Between Equipment Space 1 & Cable Spreading Room.Caused by Misinterpretation of End of Walkdown Procedures.Hose Removed (← links)
- 05000280/LER-1984-016, :on 840619,automatic Reactor Trip Resulted from Exceeding 10% Power on Two of Four Nuclear Power Channels, Ni 44 & Ni 41,w/turbine Unlatched.Caused by Isolation Valve Malfunction Due to Broken Gear Pin (← links)
- 05000280/LER-1984-019, :on 840905,control Room Area Emergency Ventilation Sys Technically Inoperable.Caused by post- Maint Testing Oversight.Flow Test Performed on Both Units Relay Room Emergency Ventilation Fans (← links)
- 05000280/LER-1984-013, :on 840601,w/RCS Solid,At 145 F & 325 Psig,Porv Cycled in Response to Overpressure Condition While Placing Charging Sys in Svc.Caused by Personnel Error (← links)