Pages that link to "05000388/LER-2020-001, Manual Reactor Scram Due to Rising Main Condenser Backpressure"
Jump to navigation
Jump to search
The following pages link to 05000388/LER-2020-001, Manual Reactor Scram Due to Rising Main Condenser Backpressure:
Displayed 6 items.
- 05000388/LER-2020-002-01, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch Caused by Lack of Requirements for Acclimation of the Instrument to the Operating Environment (← links)
- 05000387/LER-2020-002-01, Inoperability of Unit 1 B Residual Heat Removal Service Water Pump Due to the Circuit Breaker Spring Charging Motor Contact Actuator Being Out of Adjustment (← links)
- 05000387/LER-2020-003, Condition Prohibited by Technical Specifications Due to Inoperable Turbine Stop Valve and Turbine Control Valve Instrumentation (← links)
- 05000388/LER-2020-001-01, Manual Scram Due to Rising Main Condenser Backpressure Caused by Failure of an Offgas Recombiner Inlet Valve (← links)
- ML20098F706 (redirect page) (← links)
- 05000388/LER-2020-001 (redirect page) (← links)
- 05000388/LER-2014-001 (← links)
- 05000388/LER-2015-001 (← links)
- 05000388/LER-2015-002 (← links)
- 05000388/LER-2015-006 (← links)
- 05000388/LER-2016-006 (← links)
- 05000388/LER-2016-004 (← links)
- 05000388/LER-2016-003 (← links)
- 05000388/LER-2016-002 (← links)
- 05000388/LER-2016-001 (← links)
- 05000388/LER-2001-005 (← links)
- 05000388/LER-2001-004 (← links)
- 05000388/LER-2001-003 (← links)
- 05000388/LER-2001-002 (← links)
- 05000388/LER-2001-001 (← links)
- 05000388/LER-2017-009 (← links)
- 05000388/LER-2017-007 (← links)
- 05000388/LER-2017-006 (← links)
- 05000388/LER-2017-005 (← links)
- 05000388/LER-2017-004 (← links)
- 05000388/LER-2017-003 (← links)
- 05000388/LER-2017-001 (← links)
- ENS 54525 (← links)
- 05000388/LER-1984-013, Attachments to LER 84-013-00 (← links)
- IR 05000387/2020002 (← links)
- IR 05000387/2021003 (← links)
- 05000388/LER-2023-001, Secondary Containment Bypass Leakage Limit Exceeded Due Inadequate Procedure Guidance Resulting in Failure of the Inboard Containment Isolation Valve to Close and Pressurize (← links)
- 05000388/LER-2022-001, Re Inadequate Performance of Loss of Safety Determination Resulting in Both Divisions of Core Spray Being Inoperable (← links)
- 05000388/LER-2021-004-01, From Susquehanna Steam Electric Station, Unit 2 Main Turbine Pressure Regulator Inoperable for Longer than Allowed by Technical Specifications Due to Inadequate Valve Modification (← links)
- 05000388/LER-2021-005-01, Condition Prohibited by Technical Specification Due to Setpoint Drift Attributed to Age Related Degradation (← links)
- 05000388/LER-2021-003-01, Automatic Reactor Scram Due to Main Turbine Trip Caused by Inadvertent Trip of the Main Generator Output Breakers (← links)
- 05000388/LER-2021-001-01, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch (← links)
- 05000388/LER-2021-005, Condition Prohibited by Technical Specification Due to Setpoint Drift (← links)
- 05000388/LER-2021-002-01, Loss of Secondary Containment Due to Failed Differential Pressure Transmitter (← links)
- 05000388/LER-2021-002, Re Loss of Secondary Containment (← links)
- 05000388/LER-2021-001, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch (← links)
- 05000388/LER-2020-002-01, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch Caused by Lack of Requirements for Acclimation of the Instrument to the Operating Environment (← links)
- 05000388/LER-2020-001-01, Manual Scram Due to Rising Main Condenser Backpressure Caused by Failure of an Offgas Recombiner Inlet Valve (← links)
- 05000388/LER-1986-034, :on 860927-30,sampling of RHR Svc Water Not Completed.Caused by Communication Problems During Period When RHR Svc Water Monitors Out of Svc.Administrative Controls Will Be Implemented (← links)
- 05000388/LER-1986-013-01, :on 860919,full Reactor Protection Sys Scram Occurred When Intermediate Range Monitors C & G Spiked Upscale.Caused by Noise Due to Faulty Primary Containment Penetration Connectors.Cables Rebuilt (← links)
- 05000388/LER-1986-017-01, :on 861101,unplanned ESF Actuation Occurred & RWCU Sys Isolated in High Sys Flow.Caused by Instantaneous Flow Spike Induced by Cracking Open Bypass Valve.Design Changes Initiated.Sys Returned to Svc (← links)
- 05000388/LER-1986-011-01, :on 860717,limiting Condition for Operation Not Entered When Primary Containment Isolation Valve Inoperable. Caused by Smoking Electrical Components from Transversing in-core Probe Machine C (← links)
- 05000388/LER-1986-016-01, :on 861024,DX Unit Valve a Discovered Mispositioned.Caused by Procedure Incorrectly Stating That Valve a Be Placed at Zero Position.Procedure Revised to Reflect Correct Repositioning (← links)
- 05000388/LER-1986-015-01, :on 861012,valve F008 Isolated Twice,Due to Spurious High Flow Signal & Water Hammer,Respectively. Water Hammer Caused by Partial Draindown of Sys.Personnel Will Review Event (← links)
- 05000388/LER-1986-019-01, :on 861218,22 & 25,facility Entered Limiting Condition for Operation 3.0.3 Three Times to Sample Wetwell. Caused by Off Normal Valve Lineup of Containment Radiation Monitoring Sys.Operating Strategy Reviewed (← links)
- 05000388/LER-1986-009-01, :on 860708,Limiting Condition for Operation 3.0.3 Entered Twice.Caused by Surveillance Procedure SI-280-305 Being Performed While RCIC Sys Inoperable.W/ (← links)
- 05000388/LER-1985-018, :on 850529,circuit Breaker 8B in Reactor Protection Sys Distribution Panel 2Y201B Tripped.Caused by Loose Load Side Connection Leading to Overheating of Terminal Lug.Breaker Replaced (← links)
- 05000388/LER-1987-001, :on 870110,Limiting Condition for Operation 3.6.3.a Entered When Reactor Bldg Chilled Water Sys Inboard Isolation Valve Failed.Possibly Caused by Valve Failing to Stroke.Solenoid Valve Replaced (← links)
- 05000388/LER-1986-014, :on 860927-30,sampling of RHR Svc Water Effluent Not Completed as Required by Tech Specs.Caused by Communication Problems.Administrative Controls Implemented to Correct Communication Deficiencies (← links)
- 05000388/LER-1987-002-01, :on 870214,HPCI Sys Isolated.Caused by Cognitive Error Made by Technician.Test Signal Removed & Containment Isolation Valve Reopened.Mod Will Install States Links (← links)
- 05000388/LER-1986-018-01, :on 861219,125-volt Dc Battery Charger 1D613 Inoperable.Unit 1 Supervisor Failed to Inform Unit 2 Supervisor of Equipment Failure,Resulting in Violation of Tech Spec.Battery Replaced (← links)
- 05000388/LER-1986-015, :on 861012,primary Containment Isolation Valve Closed Twice Due to Spurious High Flow Signal.Caused by Waterhammer Due to Opening of Valve F008.Operations Personnel Will Review Event (← links)
- 05000388/LER-1986-003, :on 860124,Tech Spec Motherhood Clause Entered Due to Malfunctioning Which Provides ECCS Initiation Signals.Caused by Broken Adjustment Locking Screw Replaced (← links)
- 05000388/LER-1986-001-01, :on 860121,during Startup,Reactor Scrammed When Vessel Water Level Dropped to Plus 13 Inches.Caused by Operator Failing to Notice Turbine Bypass Valves Opened. Procedures Revised.Alarms Will Be Installed (← links)
- 05000388/LER-1985-012, :on 850316,power Supply to Standby Gas Treatment Sys Exhaust Vent Process Radiation Monitor Momentarily Shortened When Component Removed During Calibr. Caused by Malfunctioning Dampers (← links)
- 05000388/LER-1986-010-01, :on 860717,reactor Manually Shut Down Due to Excessive Unidentified Drywell Leakage.Caused by Leaking RHR Loop B Injection Testable Check Valve HV-251-F050B.Valve Repacked & Returned to Svc (← links)
- 05000388/LER-1986-008-01, :on 860619,HPCI Sys Failed to Attain Required Flow Rate & Declared Inoperable.Caused by Broken Control Valve.Valve Repaired & Procedure SO-252-002 Reperformed.W/ (← links)
- 05000388/LER-1986-007-01, :on 860609,as-found Leakage Exceeded Tech Spec 3.6.1.2 Criteria During Integrated Leak Rate Test.Cause Unstated.Isolation Valves Reworked (← links)
- 05000388/LER-1985-025-01, :on 851005,phase-to-ground Fault Occurred on 500 Kv Transmission Lines Due to Lightning Strike.Failure of Auxiliary Relay Resulted in Isolation of Generator.Caused by Stuck Relay.Relay Repaired (← links)
- 05000388/LER-1986-006-01, :on 860413,inboard Containment Isolation Valve Closed & RWCU Pumps Tripped.Caused by Isolation of RWCU During High Differential Flow as RWCU Filter/Demineralizer Being Returned to Svc.No Action Planned (← links)
- 05000388/LER-1986-004-01, :on 860115,reactor Manually Scrammed Due to Overheating of Phase Main Transformer B.Caused by Improper Alignment of Knife Switches to Transformer Cooling Loops. Knife Switches Corrected (← links)
- 05000388/LER-1986-002, :on 860122,HPCI Sys Shut Down During Quarterly Flow Surveillance Test.Caused by Leak of Approx 5 Gpm in Pressure Control Valve 2F035 Due to Tear in Main Diaphragm. Diaphragm Replaced.Test Completed (← links)
- 05000388/LER-1985-023-01, :on 850805,unit Scrammed Due to Turbine Control Valve Fast Closure Trip.Caused by Technician Error.Rcic Manually Initiated to Maintain Vessel Level.Special Rept to Be Filed Per Tech Spec 4.7.3d (← links)
- 05000388/LER-1984-022, :on 841010,HPCI Sys Declared Inoperable Due to High Vibration Identified During Maint Check.Hpci Booster & Main Pumps & Turbine Realigned & Rerun.Eccs & RCIC Sys Declared Inoperable on 841013 for Routine Test (← links)
- 05000388/LER-1985-024-01, :on 850807,reactor Water Cleanup Containment (RWCU) Inboard Isolation Valve Closed on High Sys Flow Signal.Caused by Fast Opening of Filter/Demineralizer Inlet Valve.Rwcu Operating Procedure Revised (← links)
- 05000388/LER-1985-022-01, :on 850703,instrumentation & Controls Technician Inadvertently Connected Test Equipment to Electronics Module for Reactor Water Cleanup Sys.Technician Counseled.Rear Input Wires Labeled (← links)
- 05000388/LER-1985-021-01, :on 850630,neutral Overvoltage Occurred in Main Generator,Causing Primary Lockout.Caused by Failure of Phase C Main Transformer Low Voltage Bushing.Bushing Replaced W/Spare Component (← links)
- 05000388/LER-1985-016-01, :on 850427,water Hammer Caused Reactor Water Level Transient.Caused by Rapid Filling of Partially Drained RHR Piping from Reactor Vessel.Operating Procedure for RHR Being Revised (← links)
- 05000388/LER-1985-015-01, :on 850421,spray Pond Bypass Valve HV-01222A Did Not Automatically Open When Emergency Svc Water Pump a Started.Caused by Two Open Sliding States Link Terminal Blocks in Relay Panel.Links Evaluated (← links)
- 05000388/LER-1985-020-01, :on 850531,lightning Strike Caused Voltage Transient.Caused by Loss of Motive or Control Power. Malfunctioning Damper Actuator Replaced (← links)
- 05000388/LER-1985-017-01, :on 850530,drywell Sump Inleakage of About 10 Gpm Caused Reactor Shutdown.Shutdown Completed on 850531. Caused by Severe Packing Leak in Reactor Recirculation Pump Discharge Bypass Valve A.Valve Repaired (← links)
- 05000388/LER-1985-019-01, :on 850524,Limiting Condition for Operation 3.0.3, Motherhood Clause, Declared & Standby Gas Treatment Sys Suction Ductwork Access Doors Opened.Entry Required to Perform Fire Damper Surveillance (← links)
- 05000388/LER-1985-018-01, :on 850529,three ESF Actuations Occurred Due to Tripping of Reactor Protection Sys Power Supply Breaker W/Unit at 100% Power.First Two Events Caused by Loose Connection.New Breaker Installed (← links)
- 05000388/LER-1985-014, :on 850417,RCIC Sys Inboard Steam Supply Valve Isolated on Equipment Area High Temp.Caused by Malfunction of Temp Indicating Switch E51-N600B.Switch Replaced on 850418 & Isolation Signal Cleared (← links)
- 05000388/LER-1985-013, :on 850327,standby Liquid Control Pump a Failed 92-day Flow Verification Surveillance Test.Caused by Faulty Suction & Discharge Valves Internal to Positive Displacement Pump.Repairs Completed (← links)
- 05000388/LER-1985-011, :on 850310,damper in Standby Gas Treatment Sys Train a Malfunctioned.Caused by Damaged Damper Actuator. Actuator Replaced & Damper Operation Verified to Be Correct on 850312 (← links)
- 05000388/LER-1984-015, :on 840802,reactor Water Cleanup Sys Isolated on High Flow.Caused by Instrument Drift.Switch PDIS-G33-2NO44A Recalibr (← links)
- 05000388/LER-1984-023-01, :on 841206,fire Watch Discontinued Following Completion of One of Two Independent Work Activities.Caused by Failure to Ref Two Work Activities in Fire Watch Log. Evaluation Being Conducted (← links)
- 05000388/LER-1984-027, :on 841026,fire Watch Not Provided for Inoperable Fire Barriers Per Tech Specs.Caused by Administrative Errors.Affected Fire Barriers Restored. Incident Discussed W/Unit Supervisor (← links)
- 05000388/LER-1984-010, :on 840627,pressure Drop Occurred on HPCI Pump Suction Piping During Heatup Plateau Review.Caused by Blockage in Startup Strainer.Strainers Removed (← links)
- 05000388/LER-1985-007, :on 850129,RHR Sys Shutdown Cooling Suction Valve Closed Unexpectedly.Cause Not Stated.Pressure Switch Checked & Shutdown Cooling Established.Switch May Be Replaced Pending Evaluation (← links)
- 05000388/LER-1984-021-01, :on 840930,reactor Scrammed Due to Turbine Trip on Moisture Separator B Drain Tank High Level.Task Team Established to Evaluate Drain Tank Level Control Sys (← links)
- 05000388/LER-1984-020-01, :on 840929,unplanned ESF Actuation Occurred During Calibr of Differential Pressure Instrument Resulting in Isolation of Reactor Water Cleanup Sys.Caused by Closure of Containment Isolation Valve (← links)
- 05000388/LER-1985-003, :on 850119,reactor Scrammed on Turbine Control Valve Fast Closure.Caused by Main Turbine Trip on High Vibration During Turbine Control Valve Testing.Vibration Reduced After Rebalancing (← links)
- 05000388/LER-1985-005, :on 850119,following Reactor Scram Due to Turbine High Vibration,Suppression Chamber Vacuum Breaker Surveillance Test Completed After Tech Spec Time Limit. Caused by Cognitive Error (← links)
- 05000388/LER-1985-001, :on 850112,HPCI Turbine Failed to Trip During Hot Functional Test HF-252-011.Caused by Broken Stop Valve Actuator Shaft.Actuator Shaft Replaced (← links)
- 05000388/LER-1985-002, :on 850112,nonlicensed,nonutility Electrician Caused Reactor Protection Sys Motor Generator M-G Set to Trip When Wrench Came in Contact W/Energized Conductor. Caused by Failure to Isolate Equipment (← links)
- 05000388/LER-1984-021, :on 840930,reactor Scrammed Due to Turbine Trip on Moisture Separator B Drain Tank High Level During Performance of Startup Test to Determine Max Feedwater Pump Runout Capabilities.Check Valve Installed (← links)
- 05000388/LER-1984-026-01, :on 841029,during Installation of Mod,Open Penetration Found in Fire Barrier.Caused by Penetration Not Being Sealed During Const.Surveillance Procedure Revised to Clarify Insp Criteria (← links)
- 05000388/LER-1984-023, :on 841206,fire Watch Required for Two Independent Work Activities.Caused by Fire Watch Log Not Referencing Activities.Addl Guidelines for Tracking Fire Protection Activities & Separate Log Developed (← links)
- 05000388/LER-1985-010, :on 850223,ESF Actuation Occurred.Caused by Tripped Reactor Protection Sys Power Supply Breaker.Breaker Reset & Affected Sys Restored (← links)
- 05000388/LER-1985-009, :on 850212,setpoints for Three Reactor Water Level Switches Found to Be Outside Acceptance Criteria During Performance of Scheduled Surveillance.Caused by Instrument Drift.Instruments Recalibr (← links)
- 05000388/LER-1985-008, :on 850216,logic Power Lost to HPCI & Loop B of Core Spray.Caused by Broken Lug on Negative Terminal.Lug Replaced.Power Restored (← links)
- 05000388/LER-1984-024-01, :on 841016,total Amount of Boron in Sodium Pentaborate Solution of Standby Liquid Control Sys Found Below Tech Spec Requirements.Chemicals Added & Proper Boration Attained.Surveillance Test Revised (← links)
- 05000388/LER-1985-006, :on 850129,w/unit in Hot Shutdown,Rhr Sys Shutdown Cooling Suction Inboard Isolation Valve Closed Unexpectedly.Possibly Caused by Faulty Pressure Switch. Switch May Be Replaced Pending Evaluation (← links)
- 05000388/LER-1985-007-01, :on 850130,during Purge of Containment,One Train of Standby Gas Treatment Sys Became Inoperable.Caused by Annunciation of Standby Gas Treatment Sys B Heater Failure Alarm.Event Reviewed W/Operators (← links)
- 05000388/LER-1984-022-01, :on 841010,HPCI Sys Declared Inoperable Due to High Vibration Detected During Maint Check of HPCI Bearings. Caused by Misalignment Between Booster Pump Reduction Gear Unit & Main Pump & Turbine.Pumps Realigned (← links)
- 05000388/LER-2020-001, Manual Reactor Scram Due to Rising Main Condenser Backpressure (← links)
- 05000388/LER-1984-016-01, :on 840809,31-day Surveillance Test Completed Late.Caused by Verbal Miscommunication Between Instrumentation & Controls (I&C) Assistant Foreman & Scheduler.I&C Shop Instruction Implemented (← links)
- 05000388/LER-1984-015-01, :on 840802,reactor Water Cleanup Sys Isolated on High Flow.No Pipe Break Identified.Caused by PDIS-G33-2N044A Out of Calibr Due to Instrument Drift. Instrument Recalibr & Returned to Svc (← links)
- 05000388/LER-1984-014-01, :on 840723,reactor Water Cleanup Inlet Outboard Board Isolation Valve (2F004) Closed Due to High Temp in Filter Demineralizer Room.Caused by Problems W/Reactor Bldg Chilled Water Sys (← links)
- 05000388/LER-1984-013-01, :on 840726,during Scram Due to Turbine Control Valve Fast Closure & Deenergization of 13.8 Kv & 14.16 Kv Buses,Control Rods Did Not Fully Insert.Caused by Failure of Diesel Generators to Start Automatically (← links)
- 05000388/LER-1984-012-01, :840709,core Spray Logic Control Power Fuses Removed Since Fuses Thought to Be Possible Blocking Point for Personnel Protection.Removal Affected Listed Equipment. Fuses Reinstalled (← links)
- 05000388/LER-1984-011-01, :on 840705 & 06,four Spurious Actuations of Standby Gas Treatment Sys & Control Room Emergency Outside Air Supply Sys Experienced.Caused by Malfunctioning Output Breaker.Breaker Replaced (← links)
- 05000388/LER-1984-010-01, :on 840627,HPCI Sys Declared Inoperable for 22 H to Facilitate Removal of Startup Strainer.Caused by Blockage in Startup During Heatup Plateau Review.Startup Strainer Removed & Ring Spacer Installed (← links)
- 05000388/LER-1984-019-01, :on 840919,RHR Pump D Declared Inoperable Due to Failure to Start on Manual Initiation Signal on 840918. HPCI Sys Inoperable Due to Lube Oil Changeout.Rhr Problem Due to Misoperation of Relay Contacts (← links)
- 05000388/LER-1984-018-01, :on 840908,turbine Control Valve Fast Closure Signal Generated from False Power Load Unbalance Signal. Caused by Zero Shift Pressure Transmitter PT-20107. Transmitter Recalibr (← links)
- 05000388/LER-1984-008-01, :on 840527,turbine Bypass Valve 1 Failed to Close Below Open Position,Resulting in Reactor Protection Sys Manual Scram.Caused by Chipping Hammer Wedged Between Bypass Valve Seat & Valve Disc.Disc Replaced (← links)
- 05000388/LER-1984-006-01, :on 840521,LPCI Valve HV-2F015B Closed & de-energized Following Dual Indication on Testable Check Valve HV-2F05B.Reactor Shut Down on 840528.Caused by Loose Plate Connector on Valve HV-2F122B (← links)
- 05000388/LER-1984-007-01, :on 840525,reactor Water Cleanup Differential Pressure Switch Jumpered Out for Calibr Check.Caused by Personnel Oversight.Shift Supervision Counseled on Occurrence (← links)
- 05000388/LER-1984-005-01, :on 840515,during Monthly Functional Test of Reactor Water Cleanup Sys Area Ventilation Differential Temp Controls Test,Personnel Caused Inadvertent Closure of Primary Containment Isolation Valve (← links)
- 05000388/LER-1984-004-01, :on 840501,during Shutdown W/Nonirradiated Fuel,Esf Actuations Occurred While Installing Test Equipment in Div 11 Primary Containment Isolation Sys Circuitry.Caused by Grounded Leads (← links)
- 05000388/LER-1984-009-01, :on 840611,dual Position Indication Received for One Suppression Chamber Drywell Vacuum Breaker & Containment Vacuum Breaker Div 1 Open Alarm Received.Caused by Loose Locking Nut.Actuating Bolts Adjusted (← links)
- 05000388/LER-1984-003-01, :on 840409,six Scrams Occurred within Approx 1 H.No Upscale Trip Lamps for Associated Nuclear Instrumentation Channels Lit.Scrams Caused by Intermittent Fault in Inoperative Trip Circuits (← links)
- 05000388/LER-1984-001-01, :on 840405,unit Experienced Reactor Protection Sys Actuation on Spurious Signal from Intermediate Range Monitor Channel D.Caused by Defective Cabinet.Channel Voltage Preamplifier Replaced (← links)
- 05000388/LER-1989-010, :on 890920,determined That Estimated Leakage for Main Steam Line Containment Penetrations a & B Exceeded Tech Spec Limit During Local Leak Rate Testing.Cause Not Determined.Msiv Poppet Seats & Discs Lapped (← links)
- 05000388/LER-2017-010-01, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches (← links)
- 05000388/LER-1986-005-01, :on 860321 Differential Pressure Condition Detected,Causing Supply Dampers to Oscillate.Caused by Open Plenum Door & Exhaust Damper Linkage Binding.Linkage Reworked & Lubricated (← links)
- 05000388/LER-2019-002, Valid Actuation of the Primary Containment Isolation System Due to a Trip of Reactor Protection System Bus 2B (← links)
- 05000388/LER-2019-001-01, Main Steam Isolation Valve Leakage (← links)
- 05000388/LER-1917-010, Regarding Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches (← links)
- 05000388/LER-1990-007, :on 900705,primary Power Supply to RPS a Power Distribution Panel Lost When One Electrical Protection Assembly (EPA) Breaker Tripped.Epa Logic Cards Reviewed & RPS Power Supply Will Be Redesigned (← links)
- 05000388/LER-1995-008-01, :on 950609,shift Average Licensed Core Thermal Power Was Exceeded.Caused by Failed Instrumentation Drift. Repaired & Recalibrated Subject Instrumentation (← links)
- 05000388/LER-1991-010, :on 910628,RWCU Isolated on Two Occassions Due to Actuations of Steam Leak Detection Instrumentation. Caused by Design Deficiency & Elevated Ambient Penetration Room Temps.Temp Modules Replaced (← links)
- 05000388/LER-1917-008, Regarding Condition Prohibited by Technical Specifications Due to a Loose Terminal Block Associated with a Primary Containment Isolation Valve (← links)
- 05000388/LER-1991-009, :on 910624,RWCU Steam Leak Detection Instrumentation Discovered to Be Inadvertently Actuated During Routine Functional Testing.Caused by Adequate Verbal Communication.Technicians Briefed (← links)
- 05000388/LER-1997-007-01, Forwards LER 97-007-01,per 10CFR50.73(a)(2)(i)(B).Revised LER Submitted to Modify Previous Position W/Regards to Entry Into TS 3.0.3 for Event (← links)
- 05000388/LER-1998-002-01, :on 980301,Unit 2 Turbine Bldg Discharge Vent Gaseous Effluent Monitor Declared Inoperable,Per Tech Specs 3.3.7.11.Caused by Design Uses Tubing Connectors,Do Not Clamp Tubing in Place.Tubing in All Vent Monitors Replaced (← links)
- 05000388/LER-1998-002, Forwards LER 98-002-00 Re Loss of Continuous Vent Sampling for Unit 2 Turbine Bldg (← links)
- 05000388/LER-1997-007, Forwards LER 97-007-00 Re TS 3.0.3 Entry Voluntarily Made, Per Guidance of NUREG-1022.Operability Testing Completed in Timely Manner,Rod Block Monitor Restored to Operable Status & LCO Cleared (← links)
- 05000388/LER-1995-008, Forwards LER 95-008 Shift Average Thermal Power Level for Unit 2 Was Exceeded by Up to 4 Mwt During Unit 2 Cycle 7 Operation as Result of Instrumentation Problems (← links)
- 05000388/LER-1917-002, Regarding Implementation of Enforcement Guidance Memorandum (Egm) 11-003, Revision 3 During Unit 2 Refueling (← links)
- 05000388/LER-2016-005, Regarding HPCI Manually Overridden Prior to a Manual Scram During a Plant Transient (← links)
- 05000388/LER-2015-015, Regarding Loss of Safety Function Due to Inoperability of Both Trains of the Control Room Emergency Outside Air Supply (Creoas) System (← links)
- 05000388/LER-2015-007, Regarding Primary Containment Isolation Failure Due to Sticking/Sluggish Solenoid Valve (← links)
- 05000388/LER-2015-004, Regarding Degraded Condition Due to Reactor Coolant Pressure Boundary Leakage Caused by Vibration and Stiff Pipe Connection (← links)
- 05000388/LER-2015-005, Regarding Condition Prohibited by Technical Specifications Due to Implementation of Enforcement Guidance Memorandum (EGM) 11-003 (← links)
- 05000388/LER-2015-003, Regarding Automatic Reactor Scram Caused by Main Turbine Trip Due to Loss of Main Condenser Vacuum (← links)
- 05000388/LER-2013-003, Manual Reactor Scram Due to Loss of Reactor Feedwater Pumps (← links)
- 05000388/LER-2013-004, Regarding RHR Pump Room Flooding (← links)
- 05000388/LER-2011-005, Core Flow Mis-calibrated Resulting in Core Flow Above 108 Mlb/Hr (← links)
- 05000388/LER-2013-002, Regarding Valve Internal Misalignment Resulting in Multiple Inoperable Main Steam Safety Relief Valves (← links)
- 05000388/LER-2013-001, Regarding Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 1 (← links)
- 05000388/LER-2012-004, Regarding Automatic Scram Due to Low Reactor Pressure Vessel Level (← links)
- 05000388/LER-2012-003, Regarding Unit 2, Automatic Reactor Scram While Performing Turbine Control Value Surveillance Testing (← links)
- 05000388/LER-2012-002, Regarding Manual Scram Due to Loss of the Integrated Control System (← links)
- 05000388/LER-2012-001, For Susquehanna, Unit 2, Regarding Two Control Room Floor Cooling Systems Inoperable (← links)
- 05000388/LER-2011-002-01, Regarding Condition Prohibited by Technical Specification Due to Unknown RCIC Inoperablitliy (← links)
- 05000388/LER-2011-004, Regarding Unit 2 HPCI Inoperability (← links)
- 05000388/LER-2011-003, For Susquehanna Unit 2, Scram Due to Main Turbine Trip During ICS Surveillance Testing (← links)
- 05000388/LER-2011-002, Regarding Condition Prohibited by Technical Specification Due to Unknown RCIC Inoperability (← links)
- 05000388/LER-2011-001, Regarding Multiple Inoperable Main Steam Safety Relief Valves (← links)
- 05000388/LER-2009-002, Emergency Service Water Cooling Valves Found Closed Resulting in the Unit 2 C Residual Heat Removal Pump Being Inoperable for Approximately 4 Months (← links)
- 05000388/LER-2009-001, Multiple Test Failures of Main Steam Safety Relief Valves (← links)
- 05000388/LER-2007-001, Regarding U2 Secondary Containment Bypass Leakage Exceeded (← links)
- 05000388/LER-2006-002, Regarding Missed Technical Specification LCO 3.8.1 Entry for Unit 2 During Unit 1 Ess Bus Testing (← links)
- 05000388/LER-2006-001, Re Tech Specs Not Met for Inoperable ADS Pressure Switches (← links)
- 05000388/LER-2005-005, Regarding Reactor Automatic Scram Due to a Main Generator Lockout (← links)
- 05000388/LER-2005-004, Re Common Mode Failure of Inboard a and B Loop RHR Shutdown Cooling Testable Check Valves Due to Vibration-Induced Seat Damage (← links)
- 05000388/LER-2005-003, Regarding Reactor Manual Scram Due to Loss of Main Transformer Cooling (← links)
- 05000388/LER-2005-002, Re Degraded 125 Vdc Battery Charger Results in Technical Specification Required Shutdown (← links)
- 05000388/LER-2005-001, Regarding Degradation of Primary Coolant Pressure Boundary Due to Recirculation Pump Discharge Valve Bonnet Vent Connection Weld Flaw (← links)
- 05000388/LER-2000-005-01, From Susquehanna, Unit 2 Regarding ESF Actuations Due to RPS EPA Breaker Trip (← links)
- 05000388/LER-2002-006, Operations Prohibited by Technical Specifications Due to Inoperable Reactor Core Isolation Cooling Check Valve (← links)
- 05000388/LER-2002-004, Regarding Unplanned RPS Actuation - Loss of Condenser Vacuum & Reactor Scram (← links)
- 05000388/LER-2002-005, Operations Prohibited by TS Due to Inoperable Main Steam Isolation Valve (← links)
- 05000388/LER-2002-002, Re Loss of Control Structure Chiller Safety Function When 4.16 Kv Breakers Found Racked-Out (← links)
- 05000388/LER-2002-003, Re Low Service Water Flow Causes Temporary Loss of Control Structure Chillers (← links)
- 05000388/LER-2002-001, Operation Prohibited by Technical Specifications Due to Mispositioned 125 Vdc Transfer Switches (← links)