Pages that link to "10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor"
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The following pages link to 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor:
Displayed 50 items.
- 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release (← links)
- 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor (← links)
- 10 CFR 20.2201(a)(1)(i) (← links)
- 10 CFR 73.71(b)(1), Safeguards Event (← links)
- 10 CFR 35.3045(a)(3) (← links)
- 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation (← links)
- 10 CFR 35.3045(a)(1) (← links)
- 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat (← links)
- 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident (← links)
- 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition (← links)
- 10 CFR 50.72(a)(1)(i), Emergency Class Declaration (← links)
- 10 CFR 50.72(b)(3)(iv)(A), System Actuation (← links)
- 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown (← links)
- 10 CFR 30.50(b)(2) (← links)
- 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness (← links)
- 10 CFR 20.2201(a)(1)(ii) (← links)
- 10 CFR 50.73(a)(1), Submit an LER (← links)
- 10 CFR 20.2202(b)(1) (← links)
- 10 CFR 40.35(f) (← links)
- 10 CFR 50.72(b)(3)(xii), Transport of a Contaminated Person Offsite (← links)
- 10 CFR 30.50(b)(1) (← links)
- 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge (← links)
- 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded (← links)
- 10 CFR 20.1906(d)(2) (← links)
- 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material (← links)
- 10 CFR 76.120(c)(2) (← links)
- 10 CFR 40.60(b)(2) (← links)
- 10 CFR 40.60(b)(3) (← links)
- 10 CFR 26.719, FFD Reporting requirements (← links)
- 10 CFR 21.21(d)(3)(i), Failure to Comply or Defect (← links)
- Agreement State (← links)
- NUREG-1022, Event Reporting Guidelines for 10 CFR 50.72 and 10 CFR 50.73 (← links)
- 10 CFR 50.73(a)(2)(iv)(A), System Actuation (← links)
- 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition (← links)
- 10 CFR 50.72(b)(3)(v), Loss of Safety Function (← links)
- 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat (← links)
- 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material (← links)
- 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident (← links)
- 10 CFR 50.73(a)(2)(v)(A) (redirect page) (← links)
- 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor (← links)
- Loss of Safety Function (← links)
- 05000296/LER-2015-001, High Pressure Coolant Injection and Reactor Core Isolation Cooling Inoperable Due To No Suction Source Aligned (← links)
- 05000482/LER-2015-002, Two Control Room Air Conditioning Trains Inoperable Due to Failure to Meet Surveillance Requirement (← links)
- 05000414/LER-2012-001 (← links)
- 05000410/LER-2001-003 (← links)
- 05000318/LER-2001-001 (← links)
- 05000282/LER-2001-004 (← links)
- 05000482/LER-2017-002 (← links)
- 05000029/LER-1985-007, Forwards LER 85-007-00 (← links)
- 05000265/LER-1997-006, Forwards LER 97-006-00 Re Cable in Unit 2 Being in Same Fire Area as Fire of Concern Due to Ineffective Implementation of Original Safe Shutdown Analysis.List of Commitments Provided (← links)
- 05000254/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee (← links)
- 05000333/LER-2024-001, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket (← links)
- 05000333/LER-2024-001-01, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket (← links)
- 05000341/LER-2024-001, Automatic RPS Scram on High RPV Pressure While Attempting to Lower Generator Output During RF-22 (← links)
- 05000414/LER-2024-001, Condition Prohibited by Technical Specifications and Loss of Safety Function Due to Failed Damper Controller for the 2A1 Emergency Diesel Generator Room Ventilation Fan (← links)
- 05000220/LER-2023-002, Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 12 (← links)
- 05000333/LER-2023-004, For James A. Ftizpatrick Nuclear Power Plant, Misaligned Spacer Prevented Tie Breaker Closing Coil Armature Operation on a Magne-Blast for EDG a Subsystem (← links)
- 05000458/LER-2023-002-01, Division I and II Diesel Generators Inoperable Due to Exceeding Load Sequence Times (← links)
- 05000412/LER-2023-004, Condition Prohibited by Technical Specification and Loss of Safety Function Due to Emergency Diesel Generator Lube Oil Contamination by Fuel Oil (← links)
- 05000458/LER-2023-002, Division I and II Diesel Generators Inoperable Due to Exceeding Load Sequence Times (← links)
- 05000341/LER-2023-001-01, Loss of Mechanical Draft Cooling Tower Fan Brakes During High Speeds Leads to Loss of Safety Function and Inoperability (← links)
- 05000333/LER-2023-003, Emergency Diesel Generator Fuel Oil Supply Procedure Error B Subsystem (← links)
- 05000250/LER-2023-001, RCS Pressure Boundary Degraded (← links)
- 05000443/LER-2023-001, Automatic Actuation of B Emergency Diesel Generator Emergency Power Sequencer (← links)
- 05000374/LER-2021-002-02, Supplement to Reactor Protection System Half Scram Due to Motor Generator Set Output Breaker Trip (← links)
- 05000458/LER-2023-001, Ultimate Heat Sink Inoperable Due to Boundary Valve Leakage (← links)
- 05000341/LER-2023-001, Loss of Mechanical Draft Cooling Tower Fan Brakes During High Speeds Leads to Loss of Safety Function and Inoperability (← links)
- 05000382/LER-2022-001-01, On Non-Compliance with Technical Specifications Due to Incorrect Procedural Guidance for Radiation Monitors (← links)
- 05000373/LER-2022-004, Both Trains of Main Control Room and Auxiliary Electric Room HVAC Declared Inoperable Due to Compressor Trips (← links)
- 05000373/LER-2022-003-02, Supplement to Main Control Room and Auxiliary Electric Room HVAC Declared Inoperable Due to Multiple Component Failures (← links)
- 05000483/LER-2022-003, Submittal of Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications (← links)
- 05000416/LER-2021-001-01, Primary Containment Outer Airlock Door Inoperable Due to Unacceptable Leak Rate (← links)
- 05000382/LER-2022-006, Non-Compliance with Technical Specifications Due to Incorrect Conversion Factors in Plant Stack and Fuel Handling Building Radiation Monitors (← links)
- 05000335/LER-2022-002, Condition Prohibited by Technical Specifications (← links)
- 05000412/LER-2022-001, Operation or Condition Prohibited by Technical Specification and Loss of Safety Function Due to Emergency Diesel Generator Fuel Oil Intrusion Into Lube Oil (← links)
- 05000458/LER-2022-003, Division 1 Standby Diesel Generator Speed Sensor Power Supply Failure (← links)
- 05000416/LER-2022-001, For Grand Gulf Nuclear Station, Unit 1, Manual Reactor Trip Due to the Loss of Balance of Plant Transformer 23 (← links)
- 05000287/LER-2022-002, Automatic Actuation of Emergency Feedwater System Due to Malfunctioning Startup Feedwater Control Valve (← links)
- 05000374/LER-2022-002, Turbine Stop Valve Limit Switch Failure Due to Lubricant Degradation (← links)
- 05000270/LER-2022-003, Manual Reactor Trip Due to Main Feedwater Control Valve Positioner Malfunction (← links)
- 05000270/LER-2022-001, Regarding Automatic Reactor Trip Due to Loss of Power to Reactor Coolant Pumps (← links)
- 05000287/LER-2022-001, Response Actions Resulted in Brief Inoperability of Both Onsite and Offsite Emergency AC Power Paths (← links)
- 05000389/LER-2022-001, Reactor Shutdown Required by Technical Specifications Due to a Misaligned Control Element Assembly (← links)
- 05000270/LER-2021-005, Automatic Reactor Trip Due to Spurious Trip Signal Concurrent with System Testing (← links)
- 05000270/LER-2021-004, More than One Axial Power Shaping Rod Not Aligned within Technical Specification Limits (← links)
- 05000270/LER-2021-003, Conditions Prohibited by Technical Specifications Due to Ssf and Psw Inoperability (← links)
- 05000335/LER-2021-001, Manual Reactor Trip Due to Insufficient Feed Flow to Steam Generators (← links)
- 05000270/LER-2021-002, Actuation of the Keowee Hydroelectric Station Due to Loss of AC Power to the Unit 2 Main Feeder Buses (← links)
- 05000389/LER-2021-002, Foreign Material Exclusion Device Found in Containment Spray System (← links)
- 05000266/LER-2021-001, Main Feedwater Pump Trip Results in Manual Reactor Trip (← links)
- 05000416/LER-2020-006-02, Primary Water Tank Low Level Causing Turbine Trip and Subsequent Reactor Scram (← links)
- 05000416/LER-2020-005-02, Primarv Water Svstem Flow Lowered Causinc Turbine Trio and Subseauent Reactor Scram (← links)
- 05000416/LER-2020-003-01, Manual Reactor Scram Due to Turbine High Pressure Control Valve Malfunction and Automatic Reactor Water Level Scram (← links)
- 05000416/LER-2020-002-02, Reactor Scram Due to Main Turbine Trip (← links)
- 05000327/LER-2021-001, Sequoya Nuclear Plant, Unit 1, Reactor Trip on High Neutron Flux Rate Due to Dropped Control Rods (← links)
- 05000277/LER-2021-001, High Pressure Coolant Injection System Declared Inoperable Due to Instrument Power Inverter Failure (← links)
- 05000456/LER-2021-001, Train a and B Source Range Neutron Flux Trip Functions Bypassed During Plant Startup (← links)
- 05000440/LER-2020-002-01, Standby Liquid Control System Rendered Inoperable Due to Valve Misposition (← links)
- 05000318/LER-2021-001, Calvert Cliff Nuclear Power Plant Unit No. 2, Pressure Heater Sleeve Weld Pressure Boundary Leakage Caused by Primary Water Stress Corrosion Cracking (← links)
- 05000483/LER-2021-001, Manual Actuation of Essential Service Water System (← links)
- 05000389/LER-2021-001, Automatic Reactor Trip Due to a Breaker Failure on the 2B2 480V Motor Control Center (← links)
- 05000317/LER-2020-001, Regarding Undervoltage Condition on 4.16kV Electrical Bus 11 Resulted in Actuation of Emergency Diesel Generator 1 a (← links)
- 05000298/LER-2020-004, Secondary Containment Differential Pressure Perturbation Could Have Prevented Fulfillment of a Safety Function (← links)
- 05000266/LER-2020-001, Re Reactor Coolant System Pressure Boundary Leak on Steam Generator Bowl Drain Line Results in Operation Prohibited by Technical Specifications (← links)
- 05000334/LER-2020-001, Intake Structure Interconnecting Flood Door Found Open Resulting in a Loss of Train Separation for the Reactor Plant River Water System (← links)
- 05000316/LER-2020-003, Manual Reactor Trip and Automatic Safety Injection Due to Failed Open Pressurizer Spray Valve (← links)
- 05000410/LER-2020-002-01, Failure to Meet Technical Specification MSIV Stroke Times (← links)
- 05000267/LER-1989-019, :on 890906,steam Entered Instrument Air Header a During Startup of Outside Auxiliary Boiler.Caused by Failure of Check Valve Which Allowed Steam to Flow Into Svc Air Line.Air Header Blown Down & Dried Out (← links)
- 05000267/LER-1989-015, :on 890817,Region 19 CRD Pair Failed to Properly Insert During Weekly Partial Scram Test.Caused by Failed Clevis Bolt Head That Became Logged Between Control Rod Absorber Strings & Guide Tube (← links)
- 05000352/LER-1989-023, :on 890405,determined That in Event of Fire, Lack of Protected Suppression Pool Level & Temp Indication to Support Safe Shutdown of Plant Could Have Adversely Impacted Operator to Assess Conditions (← links)
- 05000352/LER-1989-047, :on 890720,identified That Svc Water Sys Unavailable to Provide Cooling Water to ECCS & RCIC Sys Due to Valve Position.Caused by Inadequate Emergency Procedures. Valve Reopened & Procedure T-103 Revised (← links)
- 05000317/LER-1989-009, :on 890515,preliminary Evaluation Concluded That Util May Not Have Adequate Assurance to Bring Down Unit to Cold Shutdown Condition,Per App R Requirements. Caused by Inadequate Procedure (← links)
- 05000312/LER-1988-021, :on 880615,potential Loss of Equipment Necessary to Mitigate Consequences of Accident Due to Postulated Implosion of Junction Boxed Noted.Caused by Failure to Apply Changes.Weepholes Installed (← links)
- 05000245/LER-1987-032-01, :on 870811,first Stage Bypass Switches Failed to Meet Tech Spec Requirements.Caused by Setpoint Drift from Extended Periods of Depressurization.Switches Recalibrated to Conform to Tech Specs (← links)
- 05000352/LER-1989-012, :on 890215,identified That Fire in Certain Areas of Plant Could Result in Unavailability of RCIC Sys Due to Insufficient Protection of Control Cables.Evaluation Underway.Procedure GP-2 Will Be Revised (← links)
- 05000312/LER-1987-042, :on 870912,technician Detected Electrical Problems W/Amphenol Blue Ribbon Connectors.Caused by Coating of Residue from Solder Flux,Organic Matls & Plasticizers. Nonconforming Rept Procedure Revised (← links)
- 05000272/LER-1986-018-01, :on 860806,Limitorque Motor Valve Operators W/O Environ Qualified Wires Discovered.Caused by Insufficient Control of Wiring During Operator Assembly. Wiring Replaced.Stored Wires Will Be Inspected (← links)
- 05000339/LER-1987-001-02, :on 870203,load Limit Setting on Emergency Diesel Generator 2H Determined to Be Incorrect.On 870206, Emergency Diesel Generator 2J Load Setting Also Incorrect. Caused by Failure to Follow Procedure (← links)
- 05000413/LER-2020-002, Re Unacceptable Indication Identified During Reactor Pressure Vessel Head Nozzle Penetration Inspection (← links)
- 05000219/LER-1987-008, :on 870202,reactor Recirculation Flow Converter Scram Setpoint Found to Be Above Limiting Safety Sys Setpoint Listed in Tech Specs.Caused by Instrument Drift. Flow Converter Scram Setpoint Adjusted (← links)
- 05000266/LER-1997-020-01, Forwards LER 97-020-01,describing Plant Conditions in Which Ability to Achieve & Maintain Safe Shutdown in Event of Postulated Fire May Have Been Adversely Affected (← links)
- 05000461/LER-1997-018, :on 970823,inadequate Preventive Maint Led to Possible Failure of Westinghouse Dhp Circuit Breakers to Open on Demand.Performed Corrective Maint Tasks on Dhp Circuit Breakers (← links)
- 05000219/LER-1986-020, :on 860811,during Insp of Discs in Control Rod Hydraulic Control Unit (HCU) Manual Inlet & Outlet Isolation Valves,Valve V-102 for HCU 18-15 Found W/One Ear Broken from Wedge on Disc.Disc Replaced (← links)
- 05000443/LER-2020-001, Manual Reactor Trips Due to Control Rod Bank Unexpectedly Inserting (← links)
- 05000369/LER-1987-005-02, :on 870224,battery Charger Room Fire Walls Declared Inoperable Due to Walls Not Meeting NRC Commitment Re Boundary Specs.Caused by Improper Const of Walls.Const & QA Requirements Established (← links)
- 05000338/LER-1997-008, :on 971027,both EDGs Inoperable During Testing. Caused by TS Surveillance Requirement to Demonstrate Operability of Remaining EDG When One Inoperable.Required TS Actions Cleared Following 1J EDG Testing (← links)
- 05000391/LER-2020-001, Control Room Emergency Ventilation System Inoperable Due to Main Control Room Door Being Left Open (← links)
- 05000390/LER-2020-002, Automatic Start of the Emergency Diesel Generators Due to an Equipment Failure During Transfer of Power Source for the 1B-B Shutdown Board (← links)
- 05000321/LER-1988-015-02, :on 881026,informed That Automatic Depressurization Sys Design Was Such That Single Failure (Battery) Could Cause Sys to Be Unable to Perform Safety Function.Caused by Inadequate Design Review (← links)
- 05000413/LER-2020-002-01, Unacceptable Indication Identified During Reactor Pressure Vessel Head Nozzle Penetration Inspection (← links)
- 05000220/LER-2020-001, Control Room Air Treatment System Inoperable (← links)
- 05000296/LER-2020-002, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints (← links)
- 05000482/LER-2020-001-01, Plant Shutdown Due to Inoperable Containment Purge Isolation Valves (← links)
- 05000316/LER-2020-002, Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Leakage (← links)
- 05000272/LER-2020-002, Unit 2 RHR Availability for Emergency Core Cooling in Mode 4 (← links)
- 05000400/LER-2020-001-01, Automatic Reactor Trip During Turbine Control System Digital Electro-Hydraulic System Maintenance (← links)
- 05000250/LER-2020-001, Technical Specification Action Not Taken for Unrecognized Inoperable Reactor Protection System (RPS) and Engineered Safety Feature Actuation System (ESFAS) Instrument Channel Functional Units (← links)
- 05000346/LER-2020-002, Manual Reactor Trip on Trip of Reactor Coolant Pumps Due to Loss of 13.8 Kv Bus Potential Transformer Fuse (← links)
- 05000483/LER-2020-002, Reactor Trip and AFW Actuation Following Spurious MFRV Closure (← links)
- 05000254/LER-1988-003-01, :on 880125,valve Mo 1-1301-48 Failed to Open During Testing.Caused by Electrical Equipment Being Out of Adjustment.Torque Switch Bypass Adjusted Under Work Request Q63784 Using New Criteria (← links)
- 05000265/LER-2020-002, Electromatic Relief Valve 3D Did Not Actuate Due to Out of Specification Plunger (← links)
- 05000423/LER-2020-002, 3, Automatic Reactor Trip Due to Main Generator Ground Fault (← links)
- 05000245/LER-1990-018-01, :on 901212,discovered That Condenser Vacuum Switches Out of Tolerance Due to Instrument Drift.Barksdale Condenser Low Vacuum Scram Pressure Switches Replaced W/ Static O-Ring Pressure Switches (← links)
- 05000272/LER-2020-001, Station, Unit 1, Manual Reactor Trip and Auxiliary Feed Water System Actuation (← links)
- 05000498/LER-2020-001, Automatic Actuation of Emergency Diesel Generators Due to Lockout of Switchyard Electrical Bus (← links)
- 05000400/LER-2020-001, Automatic Reactor Trip During Turbine Control System Digital Electro-Hydraulic System Maintenance (← links)
- 05000325/LER-2020-001, Manual Reactor Scram During Startup Due to All Bypass Valves Fully Opening (← links)
- 05000266/LER-1997-022, :on 970507,discovered That Postulated Control Room Fire May Cause Electrical Hot Short That Disables Limit or Torque Switches for Certain Movs.Mods Initiated to Remedy Condition (← links)
- 05000265/LER-2020-001, Loss of Both Divisions of Residual Heat Removal Low Pressure Coolant Injection Due to Swing Bus Failure to Transfer (← links)
- 05000325/LER-2020-002, Technical Specification Required Shutdown Due to Unidentified Leakage (← links)
- 05000423/LER-1997-007, :on 970123,non-conservative Assumptions Used in TSs Shutdown Margin Curve Identified.Caused by Lack of Procedures for Generation & Documentation of Reactor Operational Info.Engineering Procedure Will Be Revised (← links)
- 05000331/LER-1996-006, :on 961026,non-conservative APRM 15% Scram Setpoint Occurred Due to Inadequate Procedures.Oss Immediately Halted Core Alterations & Verified That All CR Were Fully Inserted (← links)
- 05000245/LER-1996-031, :on 960425,incorrect Fuses Caused Automatic Depressurization Sys to Be Inoperable.Cause Has Not Been Determined.All DC Circuits within Fuse Control Program Will Have Fuses W/Properly Certified DC Rating (← links)
- 05000346/LER-2020-001, Three Main Steam Safety Valves Failed Inservice Test Program As-Found Lift Acceptance Criteria (← links)
- 05000410/LER-2020-001, Manual Scram Due to an Electro Hydraulic Control Fluid Leak on the Turbine Control System (← links)
- 05000410/LER-2020-002, Failure to Meet Technical Specification MSIV Stroke Times (← links)
- 05000338/LER-1996-008, :on 960926,identified Component Cooling Water Surge Tank Not Seismically Qualified When Tank Level Full. Caused by Personnel Error.Issued Justification for Continued Operation & Completed Design Mods (← links)
- 05000382/LER-2020-001, (Waterford 3), Violation of Technical Specification 3.3.3.7.3.a (Broad Range Gas Detection) Due to Operators and Maintenance Technicians Not Performing Procedure Step as Intended (← links)
- 05000333/LER-1992-050, :on 921111,discoverd Inadequate Testing of Emergency Diesel Generators.Caused by Procedural Deficiencies.Permanent Procedures Will Be Developed to Incorporate Deficiencies Identified (← links)
- 05000296/LER-2020-001, Automatic Actuation of Emergency Diesel Generators Due to an Offsite Lightning Strike (← links)
- 05000338/LER-2020-001-01, For North Anna Power Station, Unit 1, Degraded Upper Cylinder Piston Pin Bushing Discovered During Maintenance Activities on Emergency Diesel Generator (← links)
- 05000530/LER-2020-001, Condition Prohibited by Technical Specifications Due to Inoperable Spray Pond Pump (← links)
- 05000327/LER-2019-003-01, 1 for Sequoyah Nuclear Plant, Unit 1, Automatic Reactor Trio Due to Negative Rate Trip as a Result of a Dropped Control Rod (← links)
- 05000440/LER-1992-019, :on 921009,valve Positioning Error Resulted in Inoperability of Both SLCS Trains.Caused by Personnel Error. Operator Responsible for Valve Positioning Error Counseled Re Event (← links)
- 05000341/LER-2020-001, Secondary Containment Inoperable Due to Both Airlock Doors Open (← links)
- 05000389/LER-2020-001, Turbine Loss of Load Trip Found Outside Technical Specification Allowable Range Due to Unspecified Legacy M&TE or Calibration Deficiencies (← links)
- 05000285/LER-1996-004, :on 960315,discovered Adequate Shutdown Margin Was Not Maintained.Caused by Inadequate Technical Review by Plant Personnel Involved in Reviewing Procedure Change. Appropriate Personnel Trained on Incident (← links)
- 05000483/LER-2020-001, Emergency Exhaust Train Inoperable Due to Fan Belt Degradation and Failure (← links)
- 05000390/LER-2020-001, Manual Reactor Trip Due to Lowering Steam Generator Level Caused by a Hand Station Failure (← links)
- 05000440/LER-2020-001, Combustible Gas Mixing Compressor Was Declared Inoperable Due to Degraded Thermal Overloads Resulting in Technical Specification Violation (← links)
- 05000366/LER-1984-023, :on 840811,LOCA Loading Timers Reset Clutch Coils for 2F,2E & 2G Emergency Busses Burned Out.Caused by LOCA Timer Failure to Reset Automatically.Coils Replaced & Returned to Svc (← links)
- 05000382/LER-2019-005-01, Automatic Reactor Scram Due to Steam Generator 1 High Level Resulting from a Main Turbine Trip and Subsequent Reactor Power Cutback Due to Failed Diode Modules with the Main Exciter (← links)
- 05000265/LER-1995-004, :on 950726,switches 2-503-A/B/C/D Setpoints Found to Be Out of Tech Specs Limits.Caused by High Humidity Which Affected Switch Performance.Qcis 500-1,quarterly Low Condenser Vacuum Scram Calibr & Function Revised (← links)
- 05000265/LER-1995-004-01, Forwards LER 95-004-01 Re Condenser Vacuum Scram Switches Found Out of TS Limits Due to Apparent Setpoint Drift (← links)
- 05000482/LER-2020-001, Shutdown Due to Inoperable Containment Purge Isolation Valves (← links)
- 05000366/LER-1984-005, :on 840525,standby Liquid Control Sys Prvs Lifted at Lower than Expected Pressure When Bench Tested. Design Change Initiated to Replace Existing Prvs W/Prvs of Different Model.One Prv Replaced Thus Far (← links)
- 05000265/LER-1995-004-08, :on 950726,condenser Vacuum Scram Switches Found Out of TS Limits Due to Apparent Setpoint Drift. Switches Replaced & Setpoints Changed to Higher Value for Added Margin of Safety (← links)
- 05000373/LER-1991-016-01, :on 911024,division 3 125 Volt Dc Battery Inoperable Due to Loose Connection.Cause Unknown.Battery Cable Connection Retorqued & Resistance Measurements Verified (← links)
- 05000336/LER-1995-023, :on 950516,degradation of Boric Acid Sys Piping & Fittings Occurred Due to Periodic Boric Acid Leaks from Relief & Other Valves.Initiated Repairs & Replaced All Degraded Fittings & Pipe within Boric Acid Sys (← links)
- 05000440/LER-1995-003, :on 950323,loss of Safety Sys Function Occurred.Caused by Inoperable RHR Snubbers.Installed Pool Swell Shields on Three RHR Snubbers During RFO4 (← links)
- 05000373/LER-1995-002-05, :on 950208,Unit 1 Reactor Shutdown Commenced Due to Inability to Isolate Inboard Steam Supply to Rcic. PCIS Valve 1E51-F063 Declared Inoperable & Outboard Isolation Valve 1E51-F007 Closed & Deactivated (← links)
- 05000254/LER-1994-011-05, :on 940829,CRD L-11 Failed to Scram When Given Signal Due to Pipe Plug Inserted Into Solenoid Valve Due to Personnel Not Adhering to Procedure.Crd Inserted to Position 00 & Insps Conducted for Similar Obstructions (← links)
- 05000353/LER-1989-010-01, :on 891013,HPIC Sys Declared Inoperable.Caused by Personnel Error Resulting in Condensate Accumulating Inside Hpic Turbine Exhaust Pipe.Immediately Following Event Hpic Removed from Svc (← links)
- 05000336/LER-1991-003-01, :on 910212,loss of DC Switchgear Cooling During Loss of Instrument Air Due to Design Inadequacy.Loss of Air, Revised to Warn Operator of Loss of Normal Chill Water Flow to DC Switchgear Coolers & Vital Water Supply (← links)
- 05000446/LER-2020-001, Manual Reactor Trip Due to Trip of Both Main Feedwater Pumps (← links)
- 05000331/LER-1994-008, :on 940517,determined That Testing Had Not Been Performed at Required Surveillance Frequency for Reactor High Pressure Scram Pressure Switch.Caused by Inadequate Tracking.Appropriate Half Scram Inserted (← links)
- 05000331/LER-1994-001, :on 940107,determined That Test of APRM High Flux Scram Trip Setpoint Inadequate Due to Lack of Awareness.Surveillance Test Procedure for Testing Flow Biased APRM Scram Trip Setpoint Revised (← links)
- 05000374/LER-1993-005-06, :on 930802,2A DG Declared Inoperable.Caused by Equipment Failure of 2A DG Discharge Relief Valve.Work Request Written to Replace 2A DG Relief Valve (← links)
- 05000416/LER-1993-003, :on 930324,SSW C Sys Pump Motor Failed Due to Movement of Motor Stator End Windings During Motor star-ups.SSW C Pump Replaced & Failed Motor Refurbished by GE & Being receipt-inspected (← links)
- 05000213/LER-1990-007, :on 900626,determined That Postulated Heating Steam Sys Could Affect safety-related Equipment.Caused by Incorrect Conclusion Drawn from High Energy Line Break Study in 1973.Heating Steam Sys Piping Modified (← links)
- 05000344/LER-1990-017, :on 900531,determined That Undervoltage & Underfrequency Reactor Trip Circuitry Inside 12 Kv Switchgear Did Not Meet FSAR Separation Criteria.Caused by Lack of Design Interface.Fsar Will Be Revised (← links)
- 05000457/LER-1990-005-08, :on 900416,diesel Generator 2A Speed Oscillations Occurred Due to Defective Resistor.Caused by Failure of One Dropping Resistor in Governor Unit.Resistors Replaced (← links)
- 05000280/LER-2019-002, Items Non-Conforming to Design for Tornado Missile Protection (← links)
- 05000341/LER-2019-006, Secondary Containment Pressure Exceeded Technical Specification Due to Reactor Building HVAC Damper Malfunction (← links)
- 05000327/LER-2019-004, Automatic Actuation of Emergency Diesel Generators Due to Loss of Power to 6.9kV Shutdown Board (← links)
- 05000254/LER-1990-012-02, :on 900612,control Room Ventilation Emergency Air Filtration Unit Declared Inoperable.Caused by Heater Malfunction.Work Request Initiated (← links)
- 05000336/LER-1990-005-02, :on 900503,identified Potential for High Energy Line Break in Auxiliary Steam Sys That Could Degrade Plant Areas Determined as Mild Environs.Probably Caused by Incorrect Conclusions from Analysis in 1973 (← links)
- 05000298/LER-2019-003, Division 2 Service Water Discharge Blockage Resulting in Unplanned Service Water Inoperability (← links)
- 05000457/LER-1990-004-08, :on 900416,diesel Generator 2A Speed Oscillated Prior to Maint Teardown.Caused by Component Failure.Resistors Replaced & Placed on 3-yr Replacement Frequency (← links)
- 05000483/LER-2019-005-01, Violation of Technical Specification 3.7.10 Due to Control Room Emergency Ventilation System Train B Inoperability (← links)
- 05000328/LER-2019-002, Loss of Heater Drain Tank Flow Causes Turbine Runback and Manual Reactor Trip (← links)
- 05000461/LER-2019-004-01, Safety Relief Valve Wiring Issue Results in Condition Prohibited by Technical Specifications (← links)
- 05000265/LER-1991-004, :on 910211,standby Liquid Control Sys of Unit 1 & 2 Inoperable.Caused by Inadequate Mod Testing.Engineering Dept Evaluating Data & Temporary Procedure 6589 Generated (← links)
- 05000281/LER-2019-002, Auxiliary Feedwater System Loss of Safety Function Due to Check Valve Failure to Close (← links)
- 05000295/LER-1991-005-04, :on 910421,instrument Inverter 111 Experienced Interruption in Output Power & Declared Inoperable.Caused by Unknown Factor.Extensive Troubleshooting & Testing Performed on Inverter 111 & Maint Performed (← links)
- 05000395/LER-2019-004, 4-00 for Virgil C. Summer Nuclear Station (Vcsns), Unit 1, Condition Prohibited by Technical Specification 3.6.1.1 (← links)
- 05000410/LER-2019-001, High Pressure Core Spray Declared Inoperable (← links)
- 05000316/LER-2020-001, Failure of Source Range Nuclear Instrumentation Resulting in a Condition Prohibited by Technical Specifications (← links)
- 05000390/LER-2019-004, Control Room Emergency Ventilation System Inoperable Due to Main Control Room Door Being Left Open (← links)
- 05000354/LER-2019-002, Safety Relief Valve (SRV) As-found Set-point Failures (← links)
- 05000395/LER-2019-003, Completion of a Technical Specification Required Plant Shutdown (← links)
- 05000334/LER-2019-002, Manual Reactor Trip at 15% Power Due to Lifting of the 1A Main Steam Safety Valve (← links)
- 05000458/LER-2019-004, For River Bend Station, Unit 1, Potential Loss of Safety Function for All ADS, (Automatic Depressurization System) Valves (← links)
- 05000278/LER-2019-001, Failure of Reactor Mode Switch Results in Condition Prohibited by Technical Specifications (← links)
- 05000499/LER-2019-002, 0 for South Texas Project Unit 2, Incorrect Sequencer Part Replacement Leads to Undervoltage Signal and Valid Actuation of Emergency Diesel Generator (← links)
- 05000260/LER-2019-001-01, Traversing In-core Probe Purge Header Check Valve Leak Rate in Excess of Technical Specifications Limits (← links)
- 05000400/LER-2019-003, Both Source Range Nuclear Instruments Inoperable (← links)
- 05000387/LER-2019-001-01, Loss of Both Control Structure Chillers Due to Misaligned Breaker Stab (← links)
- 05000348/LER-2019-001, Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift (← links)
- 05000260/LER-2019-003, Automatic Reactor Scram During Startup Due to Intermediate Range Monitor Noise (← links)
- 05000353/LER-1989-010-02, :on 891013,HPCI Sys Declared Inoperable Due to Condensate Accumulation Inside HPCI Turbine Exhaust Pipe. Caused by Drain Pipe Flow Orifice Blockage Due to Debris in Exhaust Pipe.Condensate Drained (← links)
- 05000341/LER-2019-005, Secondary Containment Pressure Exceeded Technical Specification Due to Reactor Building HVAC Damper Malfunction (← links)
- 05000353/LER-1989-008-02, :on 890922,discovered That Normally Open Manual Emergency Svc Water Isolation Valve Found to Be in Closed Position.Exact Cause Not Determined.Valve Promptly Opened. Administrative Procedure A-8 Revised (← links)
- 05000483/LER-2019-001-01, Unplanned Loss of Switchyard Bus B Results in System Actuation (← links)
- 05000346/LER-2019-003, Anticipatory Reactor Trip System Actuated During Turbine Stop Valve Testing Due to the Closure of a Main Turbine Stop Valve (← links)
- 05000259/LER-2019-001-01, High Pressure Coolant Injection System Declared Inoperable Due to Steam Supply Isolation (← links)
- 05000440/LER-2019-004-01, Loss of Feedwater Heating Results in Loss of Safety Function (← links)
- 05000499/LER-2019-001, Equipment Clearance Order Error Leads to Loss of Primary Containment Integrity (← links)
- 05000335/LER-2019-003, Inoperability of Emergency Diesel Generator Due to Cracked Crankshaft (← links)
- 05000416/LER-2019-004, Loss of High Pressure Core Spray Due to Instrument Inverter Failure (← links)
- 05000254/LER-2019-002, Phase to Ground Fault in Isolated Phase Bus Duct Led to Generator Trip and an Automatic Scram (← links)
- 05000482/LER-2019-002, Emergency Diesel Generator Inoperable Due to Temperature Control Valve Failure (← links)
- 05000483/LER-2019-006, Unrecognized Inoperability of Boron Dilution Mitigation System (Bdms) Train B (← links)
- 05000390/LER-2019-003, Manual Reactor Trip Due to Main Feedwater Regulating Valve Failing Closed (← links)
- 05000414/LER-2019-004, Condition Prohibited by Technical Specification and Loss of Safety Function Due to Refueling Water Storage Tank Volume Below the Minimum Requirement (← links)
- 05000395/LER-2019-002, Regarding Condition Prohibited by Technical Specification 3.6.4 (← links)
- 05000311/LER-2019-002, Manual Reactor Trip and Auxiliary Feed Water System Actuation (← links)
- 05000346/LER-2019-001, Emergency Ventilation System Train Inoperable Due to Non-specific Test Description of Damper Operation (← links)
- 05000446/LER-2018-001-01, For Comanche Peak Nuclear Power Plant, Unit 2, Automatic Reactor Trip Due to Turbine Trip (← links)
- 05000220/LER-2019-004, Average Power Range Monitors Declared Inoperable (← links)
- 05000440/LER-2019-004, Loss of Feedwater Heating Results in Loss of Safety Function (← links)
- 05000354/LER-2019-001, Manual Scram and Manual Actuation of Reactor Core Isolation Cooling (← links)
- 05000498/LER-2019-002, Condition Prohibited by Technical Specifications and Loss of Safety Function Due to Inoperable Reactor Head Vent Throttle Valves (← links)
- 05000382/LER-2019-007, (Waterford 3), Plant Shutdown Required by Technical Specifications Due to Charging Pump Suction Line Flaw (← links)
- 05000400/LER-2019-002, B Train Chiller for the Essential Services Chilled Water System Tripped on High Compressor Oil Temperature (← links)
- 05000400/LER-2019-001-01, Turbine Control System Auto-Stop Trip Solenoid Operated Valves Response Times Impacted (← links)
- 05000483/LER-2019-005, Inoperability of CREVS B Train (← links)
- 05000413/LER-2019-002-01, Condition Prohibited by Technical Specifications and Loss of Safety Function Due to Auxiliary Feedwater Sump Pump Conditions (← links)
- 05000259/LER-2019-001, High Pressure Coolant Injection System Declared Inoperable Due to Steam Supply Isolation (← links)
- 05000414/LER-2019-003, Component Cooling Water System Alignment Led to Both Trains of Component Cooling Water Inoperable (← links)
- 05000425/LER-2019-002, Microswitch Failure Causes Closure of Main Steam Isolation Valve and Subsequent Automatic Reactor Trip (← links)
- 05000313/LER-2018-004-01, Reactor Trip Due to the Loss of a Non-Vital 4160 Volt Bus (← links)
- 05000382/LER-2019-006, (Waterford 3), Unplanned Loss of Both Trains of Broad Range Gas Monitors Results in a Condition That Could Have Prevented Fulfillment of a Safety Function (← links)
- 05000416/LER-2019-001-01, Automatic Reactor Shutdown Due to Activation of Generator Lockout (← links)
- 05000269/LER-2019-001, Standby Shutdown Facility Reactor Coolant Makeup Pump Oil Suction Tubing Failure (← links)
- 05000416/LER-2018-001-01, Grand Gulf. Nuclear Station, Unit 1, Reactor Manual Shutdown Due to Turbine Pressure Control Valve Position Changes (← links)
- 05000390/LER-2019-002, Loss of Control Room Emergency Air Temperature Control System Due to Air Filter Failure (← links)
- 05000220/LER-2019-003-01, Manual Reactor Scram Due to Pressure and-Power Oscillations (← links)
- 05000353/LER-2019-001, Regarding Valid Actuation of the Reactor Protection System Due to a Trip of D214-24 Load Center (← links)
- 05000324/LER-2019-003, High Pressure Coolant Injection (HPCI) Inoperable (← links)
- 05000220/LER-2019-001-01, Automatic Reactor Scram Due to High Reactor Pressure (← links)
- 05000255/LER-2018-003-01, Indications Identified in Reactor Pressure Vessel Head Nozzle Penetrations (← links)
- 05000341/LER-2019-003, Secondary Containment Declared Inoperable Due to Opening Both Airlock Doors (← links)
- 05000220/LER-2019-003, Manual Reactor Scram Due to Pressure and Power Oscillations (← links)
- 05000461/LER-2019-001, Main Feed Breaker Failed to Close During Bus Shift (← links)
- 05000220/LER-2019-002, Condition Prohibited by Technical Specification Due to Vacuum Breaker Not Locked Closed (← links)
- 05000260/LER-2019-002, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints (← links)
- 05000440/LER-2019-002, Loss of Safety Function Due to Low Pressure Core Spray Inoperability (← links)
- 05000391/LER-2019-001, Regarding Manual Reactor Trip Due to Main Feedwater Regulating Valve Failing Closed (← links)
- 05000387/LER-2019-001, Loss of Both Control Structure Chillers (← links)
- 05000483/LER-2019-004, Security Force Positions Evacuated Due to Severe Weather Announcement (← links)
- 05000382/LER-2019-005, Automatic Reactor Scram Due to Steam Generator 1 High Level Resulting from a Main Turbine Trip and Subsequent Reactor Power Cutback Due to Failed Diode Modules within the the Main Exciter (← links)
- 05000483/LER-2019-003, Reactor Trip Due to Source Range Hi-Flux (← links)
- 05000483/LER-2019-002, Mode 4 Entry with Inoperable Auxiliary Building Pressure Boundary (← links)
- 05000237/LER-2019-002, Scram Due to Main Turbine Low Oil Pressure Trip (← links)
- 05000364/LER-2019-002, Manual Reactor Trip Due to Misaligned Rod During Low Power Physics Testing (← links)
- 05000373/LER-2019-002, Turbine Stop Valve Limit Switch Failure Due to Insufficient Lubrication (← links)
- 05000335/LER-2019-001, Automatic Reactor Trip Caused by Main Generator Ground Resulting in Generator Lockout/Loss of Load (← links)
- 05000455/LER-2019-001, Manual Actuation of Auxiliary Feedwater Due to High Inboard Motor Bearing Temperature on Startup Feedwater Pump (← links)
- 05000220/LER-2019-001, Automatic Reactor Scram Due to High Reactor Pressure (← links)
- 05000400/LER-2019-001, Turbine Control System Auto-Stop Trip Solenoid Operated Valves Response Times Impacted (← links)
- 05000293/LER-2019-004, Manual Reactor Scram Due to Degrading Condenser Vacuum (← links)
- 05000293/LER-2019-003, Condition Prohibited by Technical Specifications Involving the Mechanical Vacuum Pump (← links)
- 05000364/LER-2019-001, Inoperable Containment Isolation Valve Due to Design Control Error (← links)
- 05000483/LER-2019-001, Unplanned Loss of Switchyard Bus B Results in System Actuation (← links)
- 05000498/LER-2019-001-01, Condition Prohibited by Technical Specifications Due to Inoperable Essential Cooling Water Pump (← links)
- 05000324/LER-2019-002, Manual Reactor Protection System Actuation and Specified System Actuation (← links)
- 05000425/LER-2019-001, Spurious Closure of Main Steam Isolation Valve Results in Manual Reactor Trip (← links)
- 05000339/LER-2019-001, Manual Reactor Trip on Degrading Condenser Vacuum Due to a Failed Weld (← links)
- 05000315/LER-2019-001, Two Main Steam Safety Valve Setpoints Found Outside Technical Specification Limits (← links)
- 05000324/LER-2019-001, Automatic Actuation of the Primary Containment Isolation System (← links)
- 05000498/LER-2019-001, Condition Prohibited by Technical Specifications Due to Inoperable Essential Cooling Water Pump (← links)
- 05000374/LER-2019-001, Safety Related Electrical Bus Undervoltage Results in Valid Actuation of the Common Emergency Diesel Generator (← links)
- 05000461/LER-2018-005-02, Unplanned Reactor Scram During Maintenance Outage Due to High Intermediate Range Monitor Flux (← links)
- 05000265/LER-2018-001-01, Two Main Steam Isolation Valves (Msivs) Closure Times Exceeded (← links)
- 05000341/LER-2019-002, Secondary Containment Airlock Doors Opened at the Same Time Resulting in a Condition Prohibited by Technical Specifications (← links)
- 05000416/LER-2019-001, Automatic Reactor Shutdown Due to Activation of Generator Lockout (← links)
- 05000277/LER-2019-001, Regarding Emergency Bus Breaker Relay Failure Results in Loss of Safety Function (← links)
- 05000323/LER-2018-001-01, Automatic Reactor Trip of Unit 2 Following a Load Rejection (← links)
- 05000254/LER-2019-001, HPCI System Inoperable Due to Blown Fuse in the Motor Speed Changer Circuit (← links)
- 05000237/LER-2019-001, Secondary Containment Differential Pressure Exceeded Technical Specification Due to Excess Ventilation Supply Flow (← links)
- 05000461/LER-2018-005-01, Unplanned Reactor Scram During Maintenance Outage Due to High Intermediate Range Monitor Flux (← links)
- 05000293/LER-2019-002, Failure of Main Steam Isolation Valve Limit Switch Results in a Condition Prohibited by Technical Specifications (← links)
- 05000482/LER-2018-002, Modification Activities Affected Control Room Envelope Boundary Causing a Condition Prohibited by Technical Specifications (← links)
- 05000293/LER-2019-001, Reactor Core Isolation Cooling System Declared Inoperable During Surveillance Testing (← links)
- 05000341/LER-2019-001, Unplanned Loss of Safety Function of Gland Seal Exhauster Trip During Planned Maintenance Due to Inadequate Procedure (← links)
- 05000254/LER-2018-004-01, Reactor Scram Due to Turbine-Generator Load Reject (← links)
- 05000313/LER-2018-004, Reactor Trip Due to the Loss of a Non-Vital 4160 Volt Bus (← links)
- 05000317/LER-2018-001-01, Pressurizer Safety Valve As-Found Settings Outside Technical Specification Limits Due to Damaged Internals (← links)
- 05000382/LER-2019-001, Past Inoperability of Effluent Accident Monitor Exceeds Allowed Outage Time Resulting in Condition Prohibited by Technical Specifications (← links)
- 05000259/LER-2018-007, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints (← links)
- 05000461/LER-2018-003-01, Load Driver Card Failure Resulting in High Pressure Core Spray Inoperability (← links)
- 05000341/LER-2018-007, Reactor Building to Suppression Chamber Vacuum Breaker Condition Prohibited by Technical Specifications (← links)
- 05000397/LER-2018-001-01, Automatic Reactor Scram Due to Main Transformer Trip (← links)
- 05000483/LER-2018-006, Inoperability of SSCs Due to Improper Environmental Qualification Classification (← links)
- 05000458/LER-2018-011, For River Bend Station, Unit 1, Condition Prohibited by Technical Specifications Due to Inadequate Design Change of Under Voltage Relay Trip Set Point Range (← links)
- 05000336/LER-2018-001, Regarding Loss of Both Trains of Control Room Emergency Ventilation Resulting in the Loss of Safety Function (← links)
- 05000280/LER-2018-003, Regarding Auto-Start of Emergency Diesel Generators Due to Pilot Wire Lockout on C Reserve Station Service Transformer (← links)
- 05000373/LER-2019-001, Turbine Stop Valve Limit Switch Failure Due to Lubricant Degradation (← links)
- 05000259/LER-2018-004-01, Hiqh Pressure Coolant Injection Declared Inoperable Due to Steam Supply Valve Isolation (← links)
- 05000374/LER-2018-001-01, Manual Reactor Scram Due to Main Condenser Vacuum Degradation (← links)
- 05000278/LER-2018-002-01, Reactor Coolant System Pressure Boundary Leakage Resulting in Technical Specification Required Shutdown (← links)
- 05000458/LER-2018-010, Reactor Scram Due to Turbine Control Valve Failure (← links)
- 05000255/LER-2018-003, Indications Identified in Reactor Pressure Vessel Head Nozzle Penetrations (← links)
- 05000269/LER-2018-002, Loss. of Condenser Vacuum Results in a Main Turbine Trip and a Manual Reactor Trip (← 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)
- 05000461/LER-2018-005, Unplanned Reactor Scram During Maintenance Outage Due to High Intermediate Range Monitor Flux (← links)
- 05000331/LER-2018-004, Regarding Automatic Reactor Scram Due to Feedwater Regulating Valve Failure (← links)
- 05000412/LER-2018-003, Unacceptable Indication Identified During Reactor Vessel Head Inspection (← links)
- 05000254/LER-2018-005, Loss of Safety Bus and Automatic Actuation of a Safety System During Undervoltage Relay Surveillance (← links)
- 05000387/LER-2018-006-01, Standby Liquid Control Valve Failed Surveillance Test (← links)
- 05000298/LER-2018-003, Safety Valve Failure Results in Loss of Safety Function (← links)
- 05000389/LER-2018-001-01, Pressurizer Instrument Nozzle Leak Due to Primary Water Stress Corrosion Cracking (← links)
- 05000341/LER-2018-006, Emergency Diesel Generator Load Sequencer Inhibits Automatic Start of Residual Heat Removal Pumps Under Certain Scenarios Due to Unrecognized Original Design Defect (← links)
- 05000317/LER-2018-001, For Calvert Cliffs Nuclear Power Plant, Units No. 1 and 2, Both Unit 2 Emergency Diesel Generators Inoperable Due to Depressurization in Common Air Start Headers (← links)
- 05000389/LER-2018-002, Automatic Reactor Trip Due to a Breaker Failure on the 2A1 6.9kV Bus (← links)
- 05000259/LER-2018-006, Standby Gas Treatment System Train C Inoperable Longer than Allowed by Tech (← links)
- 05000457/LER-2018-001, Reactor Coolant System Pressure Boundary Leak on a Steam Generator Bowl Drain Line Due to High Cycle Fatigue Cracking Initiated from Small Welding Defects (← links)
- 05000498/LER-2018-001, Main Steam Safety Valve as Left Settings Outside of Required Range Contrary to Technical Specifications Due to Inadequate Procedure (← links)
- 05000293/LER-2018-006, Automatic Reactor Scram Due to Feedwater Regulating Valve Malfunction (← links)
- 05000424/LER-2018-002, Manual Reactor Trip Due to Receiving Rod Control Urgent Failure Alarm During Low Power Physics Testing (← links)
- 05000440/LER-2018-003, Unanalyzed Condition Resulting from Unfused Alternating Current Control Circuits (← links)
- 05000278/LER-2018-004, Failure of a Main Steam Isolation Valve to Fully Close (← links)
- 05000278/LER-2018-003, Automatic Reactor Scram Due to Loss of Two Condensate Pumps (← links)
- 05000461/LER-2018-004, Undervoltage Condition Caused by an Offsite Ameren Transformer Bushing Failure Initiates an Automatic Start of an Emergency Diesel Generator (← links)
- 05000254/LER-2018-004, For Quad Cities Nuclear Power Station, Unit 1, Reactor Scram Due to Turbine-Generator Load Reject (← links)
- 05000387/LER-2018-006, Standby Liquid Control Valve Failed Surveillance Test (← links)
- 05000458/LER-2018-008, Potential Loss of Safety Function and Unanalyzed Cond It Ion Due to Legacy Design Deficiency in Control Building HVAC (← links)
- 05000341/LER-2018-004, Re Inoperability of Reactor Water Cleanup System Isolation Differential Flow-High Function (← links)
- 05000278/LER-2018-002, Reactor Coolant System Pressure Boundary Leakage Resulting in Technical Specification Required Shutdown (← links)
- 05000416/LER-2018-009, Reactor Manual Shutdown Due to Feedwater Level Control Changes (← links)
- 05000311/LER-2018-002, Automatic Reactor Trip Due to High 23 Steam Generator Water Level (← links)
- 05000286/LER-2018-002, Manual Reactor Shutdown Due to Weld Leak in Safety Injection System Tank (← links)
- 05000254/LER-2018-003-01, Two Reactor Protection System Channels Impacted by Single Main Stop Valve Limit Switch Failure (← links)
- 05000389/LER-2018-001, Pressurizer Instrument Nozzle Leak Due to Primary Water Stress Corrosion Cracking (← links)
- 05000287/LER-2018-002-01, Actuation of the Keowee Hydroelectric Station Due to Loss of AC Power to the Unit 3 Main Feeder Buses (← links)
- 05000410/LER-2018-002, Turbine Trip and Scram Due to Unit Differential Relay Trip (← links)
- 05000458/LER-2018-007, Manual Reactor Scram Due to Reactor Recirculation Pump Trip Caused by Transformer Failure (← links)
- 05000331/LER-2018-003, Regarding Combined Maximum Main Steam Line Pathway Leakage Exceeded Technical Specification Limit (← links)
- 05000338/LER-2018-002, 1J Emergency Diesel Generator Auto-Start (← links)
- 05000374/LER-2018-001, For LaSalle County Station, Unit 2, Manual Reactor Scram Due to Main Condenser Vacuum Degradation (← links)
- 05000482/LER-2018-001, Inappropriate Use of Blind Flange for Containment Isolation Valve Results in Condition Prohibited by Technical Specifications (← links)
- 05000317/LER-2018-003-01, Control Room Loss of Ventilation Due to Smoke Detector Failure Causing Common Supply Damper to Shut (← links)
- 05000354/LER-2018-002-01, Safety Relief Valve L (SRV) As-Found Setpoint Failure (← links)
- 05000341/LER-2018-005, Non-Functional Mechanical Draft Cooling Tower Fan Brakes Leads to HPCI Being Declared Inoperable and Loss of Safety Function (← links)
- 05000400/LER-2018-004, Independent Trains of the Emergency Core Cooling System Inoperable During Testing (← links)
- 05000306/LER-2018-001-01, Automatic Actuation of Emergency Diesel Generator D5 (← links)
- 05000293/LER-2018-005, Condition Prohibited by Technical Specifications Involving Standby Gas Treatment System Pneumatic Leakage Rate (← links)
- 05000259/LER-2018-005, Inoperability of Unit 1 and 2 Emergency Diesel Generators Results in Condition Prohibited by Technical Specifications (← links)
- 05000317/LER-2018-003, Control Room Loss of Ventilation Due to Smoke Detector Failure Causing Common Supply Damper to Shut (← links)
- 05000400/LER-2018-003, Turbine Control System Auto-Stop Trip Solenoid Operated Valves Response Times Impacted (← links)
- 05000455/LER-2018-001, Automatic Safety System Actuation Following a Trip of a Station Auxiliary Transformer and Subsequent Loss of Offsite Power (← links)
- 05000530/LER-2018-001, Reactor Trip on Low Steam Generator Level (← links)
- 05000528/LER-2018-004-01, Engineered Safety Feature Pump Room Exhaust Air Cleanup System Failure Resulting in a Condition Prohibited by Technical Specifications (← links)
- 05000461/LER-2018-003, Load Driver Card Failure Resulting in High Pressure Core Spray Lnoperability (← links)
- 05000331/LER-2018-002, Both Doors in Secondary Containment Airlock Opened Concurrently (← links)
- 05000414/LER-2018-002, Condition Prohibited by Technical Specifications (TS) Due to Failure of the 2A Diesel Generator (DG) (← links)
- 05000277/LER-2018-002, Unit 3, Emergency Diesel Generator Air Inlet Check Valve Failure Results in a Condition Prohibited by Technical Specifications (← links)
- 05000313/LER-2018-002, Leak in Class 1 Reactor Coolant System Pressure Boundary Piping Due to Cyclic Fatigue Failure on a High Pressure Injection Line Drain Tap Weld (← links)
- 05000325/LER-2018-003, Setpoint Drift in Main Steam Line Safety/Relief Valves Results in Two Valves Inoperable (← links)
- 05000353/LER-2017-004-01, Degraded Condition Due to RPV Instrument Nozzle Leakage (← links)
- 05000219/LER-2018-001, EMRV Pressure Sensor As-Found Setting Exceeded Limiting Safety System Settings (← links)
- 05000254/LER-2018-003, For Quad Cities Nuclear Power Station, Unit 1, Two Reactor Protection System Channels Impacted by Single Main Stop Valve Limit Switch Failure (← links)
- 05000272/LER-2018-001, Inadequate Protection from Tornado Missiles Due to Nonconforming Design Conditions (← links)
- 05000373/LER-2018-003-01, For LaSalle County Station, Unit 1, Two Main Steam Safety Relief Valves Failed Inservice Lift Inspection Pressure Test (← links)
- 05000306/LER-2018-002, RHR Flood Barriers Compensatory Measures (← links)
- 05000461/LER-2018-002, Division 2 Diesel Generator Inoperability Due to Air Receiver Remaining Isolated Following Clearance Removal Resulting in Unplanned Shutdown Risk Change (← links)
- 05000397/LER-2018-001, Automatic Reactor Scram Due to Main Transformer Trip (← links)
- 05000306/LER-2018-001, For Prairie Island Nuclear Generating Plant, Unit 2, Automatic Actuation of Emergency Diesel Generator D5 (← links)
- 05000296/LER-2018-004, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints (← links)
- 05000313/LER-2018-001, Automatic Reactor Trip Due to Loss of Main Feedwater Pump (← links)
- 05000410/LER-2018-001, For Nine Mile Point Unit 2, Auto Start of Division II Emergency Diesel Generator Due to Loss of Line 6 (← links)
- 05000416/LER-2018-008, Unplanned System Actuation (Diesel Generator) Caused by Inadvertently Opening the Wrong Fuse Drawer (← links)
- 05000316/LER-2018-003, Regarding Manual Reactor Trip Due to High-High Moisture Separator Drain Tank Level (← links)
- 05000458/LER-2018-004, Unanalyzed Condition Due to Inadequate Protection from Tornado Generated Missiles (← links)
- 05000483/LER-2018-002, Inadequate EOP Guidance for Asymmetric Natural Circulation Cooldown (← links)
- 05000416/LER-2018-007, Potential Loss of Safety Function (Residual Heat Removal) and System Actuation Caused by Inadvertent Valve Opening (← links)
- 05000499/LER-2018-001-01, Supplement to Unit 2 Condition Prohibited by Technical Specifications That Could Have Prevented the Fulfillment of a Safety Function Due to Two Inoperable Extended Range Monitors (← links)
- 05000247/LER-2018-002, Manual Reactor Trip Due to Trip of Both Main Boiler Feedwater Pumps (← links)
- 05000456/LER-2018-004, A Emergency Diesel Generator Output Breaker Opened During a Surveillance Which Resulted in Unplanned Actuations of Bus 141 Undervoltage Relay (← links)
- 05000458/LER-2018-003, Condition Prohibited by Technical Specifications Due to Untimely Recognition of Failed Laboratory Analysis of Ventilation Charcoal Sample (← links)
- 05000456/LER-2018-001, A Emergency Diesel Generator Lost Voltage During a Surveillance Due to a Failed Exciter Diode, Which Resulted in an Unplanned Actuation of Bus 141 Undervoltage Relay (← links)
- 05000352/LER-2018-003, High Pressure Coolant Injection (HPCI) Inoperability Due to Main Pump Inboard Seal Leak (← links)
- 05000354/LER-2018-001, Operations with a Potential to Drain the Reactor Vessel Without Secondary Containment (← links)
- 05000269/LER-2018-001, Manual Reactor Trip Due to Main Feedwater Flow Control Valve E/P Converter Failures (← links)
- 05000458/LER-2018-001, Potential Loss of Safety Function of Control Building HVAC Due to Legacy Design Flaw (← links)
- 05000341/LER-2018-002, Loss of Division 1 Offsite Power Causes Partial Loss of Feedwater Leading to ECCS Injection and Reactor Scram (← links)
- 05000317/LER-2018-002, Items Non-Conforming to Design for Tornado Missile Protection (← links)
- 05000316/LER-1918-002, Component Cooling Water System Inoperable Longer than Allowed by Technical Specifications (← links)
- 05000400/LER-2018-002, Reactor Pressure Vessel Closure Head Penetration Nozzle Indications Attributed to Primary Water Stress Corrosion Cracking (← links)
- 05000316/LER-2018-001, Valid Actuation of the Unit 2 Cd Emergency Diesel Generator During Testing (← links)
- 05000325/LER-2018-002, Automatic Reactor Trip During Stator Coolant System Realignment (← links)
- 05000400/LER-2018-001, Automatic Actuation of Auxiliary Feedwater System (← links)
- 05000315/LER-2018-001, East Essential Service Water Pump Inoperable Longer than Allowed by Technical Specifications (← links)
- 05000352/LER-2018-002, Primary Containment Isolation Valve Failed to Fully Close Resulting in Condition Prohibited by Technical Specifications (← links)
- 05000280/LER-1998-012, :on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With (← links)
- 05000293/LER-2018-004, Automatic Emergency Diesel Generator System Actuation Caused by Loss of Offsite Power (← links)
- 05000461/LER-2018-001, Degraded Personnel Airlock Interlock Results in Loss of Primary Containment (← links)
- 05000247/LER-2018-001, Re Penetration Indications Discovered During Reactor Pressure Vessel Head Inspection (← links)
- 05000416/LER-2018-006, Secondary Containment Roof Hatch Left Open Due to Inadequate Corrective Actions (← links)
- 05000499/LER-2018-001, Condition Prohibited by Technical Specifications That Could Have Prevented the Fulfillment of a Safety Function Due to Two Inoperable Extended Range Monitors (← links)
- 05000373/LER-2018-004, Technical Specification Required Shutdown Due to Reactor Pressure Boundary Leakage (← links)
- 05000414/LER-2018-001, Auxiliary Feedwater System Auto-Start Due to a Loss of Both Feedwater Pumps Signal (← links)
- 05000265/LER-2018-001, Two Main Steam Isolation Valves (Msivs) Closure Times Exceeded (← links)
- 05000259/LER-2018-002, Automatic Reactor Scram Due to an Unanticipated Electro-Hydraulic Control Logic Condition (← links)
- 05000338/LER-2018-001, SW-P-1B Failed to Trip During the 1J Blackout Test (← links)
- 05000277/LER-2018-001, Fire Safe Shutdown Requirements Not Met for Spurious Operation of Valves at a High-Low Pressure Interface (← links)
- 05000331/LER-2018-001, Regarding Loss of RPS Function During MSIV and TSV Channel Functional Testing Due to Use of a Test Box (← links)
- 05000395/LER-2018-001-01, Tor Virgil C. Summer, Unit 1, Valid Actuation of Emergency Diesel Generator (← links)
- 05000325/LER-2018-001, Implementation of Enforcement Guidance Memorandum (Egm) 11-003, Revision 3 (← links)
- 05000296/LER-2018-002, Inoperable 250V Shutdown Board Battery Charger Results in Condition Prohibited by Technical Specifications (← links)
- 05000254/LER-2018-002, Tornado Missile Protection Non-Conformance in Association with Egm 15-002 (← links)
- 05000416/LER-2018-003, Inoperable Reactor Protection Functions During Main Steam Isolation Valve and Turbine Stop Valve Channel Functional Tests Due to Use of a Test Box (← links)
- 05000395/LER-2016-001-02, (Vcsns), Unit 1 - Licensee Event Reports (2016-001-02, 2016-002-01, 2016-003-02) - Revision to Correct Typographical Errors (← links)
- 05000296/LER-2018-003, Misadjusted Switch Results in Condition Prohibited by Technical Specifications (← links)
- 05000528/LER-2018-001, Unit, Automatic Actuation of the Reactor Protection System Resulting from a Loss of Reactor Coolant Pumps (← links)
- 05000373/LER-2018-002, Damaged Bus Bar Identified Potentially Affecting High Pressure Core Spray System (← links)
- 05000272/LER-1995-010-01, :on 950615,RHR Pumps for long-term Flow Requirements for Both Units Declared Inoperable Due to RHR Flow Instrument Uncertainties.Evaluated EOPs (← links)
- 05000443/LER-2018-001, Re Pressurizer Safety Valve Outside of Technical Specification Limits Discovered During As-Found Set Point Testing (← links)
- 05000311/LER-1993-008, :on 930527,control Rod 1SA3 Withdrew to Approx 15 Steps from Fully Inserted in Response to Manual Insertion Command Due to Failure of Integrated Circuit Chips.Emergency License Amend Requested on 930617 (← links)
- 05000311/LER-1993-008-01, :on 930527,determined That Postulated Single Failure Concern Existed Where Failure of One Rod Control Sys Slave Cycler Decoder Card,In Conjunction W/Rod Motion Command Signal May Cause Rcca Withdrawal (← links)
- 05000272/LER-2016-006-01, Technical Specification for Containment Integrity Not Met (← links)
- 05000416/LER-2018-002, Both 208 Containment Air Lock Doors Simultaneously Inoperable (← links)
- 05000272/LER-1988-010-01, :on 880519,discovered That Diesel Generator Area Cardox Fire Suppression Sys PE Relay May Not Be Class 1E Seismically Qualified.Caused by Inadequate Design. Procedure Mods Made Re Resetting Relay (← links)
- 05000293/LER-2018-003, Target Rock Relief Valve Pilot Assembly Failed As-Found Lift Test, a Condition Prohibited by Plant Technical Specifications (← links)
- 05000272/LER-1987-006-02, :on 870525,observed Spring Charging Motor for Centrifugal Charging Pump 11 4 Kv Breaker Not Attached to Breaker Framework.Caused by Loosening of 4 Inch Bolts. Breakers Visually Examined for Loose Bolts (← links)
- 05000387/LER-2017-008, Core Spray Inoperable Due to Not Meeting Seismic Requirements as a Result of a Human Performance Error (← links)
- 05000254/LER-2018-001, Secondary Containment Differential Pressure Momentarily Lost Due to Fuel Pool Radiation Monitor Spike (← links)
- 05000333/LER-2017-004-01, Regarding Safety Relief Valves Out of Tolerance (← links)
- 05000440/LER-2018-001, Regarding Loss of Safety Function and Violation of Technical Specifications Due to Diode Failure (← links)
- 05000280/LER-2018-001, Loss of 4160 Volt Emergency Bus and Start of Emergency Diesel Generator Due to Opening Emergency Bus Potential Transformer Drawer (← links)
- 05000416/LER-2017-009, Regarding Reactor Core Isolation Cooling System Inoperability Due to Lockout Circuit Settings (← links)
- 05000321/LER-2018-002, Regarding Operations with the Potential to Drain the Reactor Vessel (Opdrvs) Without Secondary Containment (← links)
- 05000321/LER-2018-001, Regarding Condition Prohibited by Tech Specs Due to Secondary Containment Inoperability (← links)
- 05000293/LER-2018-001, Regarding Manual Reactor Scram Due to Loss of One Offsite Transmission Line (← links)
- 05000293/LER-2018-002, Diesel Generator a Inoperable, a Condition Prohibited by the Plant Technical Specifications (← links)
- 05000390/LER-2018-002, Regarding Shield Building Inoperability Due to Annulus Vacuum Transient (← links)
- 05000395/LER-2018-001, Valid Actuation of Emergency Diesel Generator (← links)
- 05000483/LER-2018-001, Violation of Technical Specification 3.6.3 Containment Isolation Manual Found in Open Position (← links)
- 05000282/LER-2018-001, Motor Driven Cooling Water Pump Auto Start Due to Smoking Packing on 11 Cooling Water Pump (← links)
- 05000255/LER-1995-008-01, Forwards LER 95-008-01,suppl Rept,Describing Final Results of Evaluation Performed to Determine Safety Significance of Disabled Containment High Pressure Trip Function (← links)
- 05000341/LER-2018-001, Regarding Secondary Containment Pressure Exceeded Technical Specification Due to Reactor Building HVAC System Manipulation (← links)
- 05000315/LER-2017-001, For Donald C. Cook Unit 1 Regarding Unit 1 Turbine Driven Auxiliary Feedwater Pump Inoperable Longer than Allowed by Technical Specifications (← links)
- 05000353/LER-2017-008-01, Eog Inoperable for Greater than 30 Days Resulting in Condition Prohibited by TS (← links)
- 05000237/LER-2017-002-01, Regarding Primary Containment Inboard and Outboard Feedwater Isolation Valves Exceed Leakage (← links)
- 05000382/LER-2018-001, For Waterford Unit 3 Regarding Failure to Enter Limiting Condition of Operation Action Statement Due to Lack of Procedure Guidance Results in a Condition Prohibited by Technical Specifications (← links)
- 05000387/LER-2017-009-01, Regarding Secondary Containment Declared Inoperable Due to Trip of Zone II Equipment Exhaust Fan (← links)
- 05000440/LER-2017-007, For Perry Nuclear Power Plant Regarding High Pressure Core Spray Inoperability Due to System Leak (← links)
- 05000461/LER-1917-010, Regarding Division 1 Transformer Failure Leads to Instrument Air Isolation to Containment Requiring a Manual Reactor Scram (← links)
- 05000353/LER-1918-001, HPCI Inoperability Due to Discharge Check Valve Failure to Close (← links)
- 05000260/LER-1994-004-02, :on 940415,Unit 2 Received a Full Scram from Full Power Due to RPS Trip Signal Generated by Low Scram Pilot Air Header Pressure Signal.Failed Module in Temp Detection Loop (← links)
- 05000289/LER-1917-004, Regarding Items Nonconforming to Design for Tornado Missile Protection (← links)
- 05000352/LER-1918-001, Regarding D12 EDG Inoperable for Greater than 30 Days Resulting in Condition Prohibited by TS (← links)
- 05000416/LER-1917-007, Regarding Engineered Safety Feature System Actuations Due to the Loss of Engineered Safety Features Transformer 11 (← links)
- 05000446/LER-1917-003, Regarding Manual Reactor Trip Due to Trip of Both Main Feedwater Pumps (← links)
- 05000293/LER-1917-013, Regarding Reportable Conditions Involving Standby Gas Treatment System and Secondary Containment Lnoperability Not Reported During the Previous Three Years (← links)
- 05000388/LER-1917-010, Regarding Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches (← links)
- 05000498/LER-1917-002, Regarding Condition Prohibited by Technical Specifications Due to Inoperable Control Room Envelope Makeup Filtration System Heating Coil (← links)
- 05000263/LER-1917-006, Regarding Loss of Reactor Protection System Scram Function During Main Steam Isolation Valve and Turbine Stop Valve Channel Functional Tests Due to Use of a Test Fixture (← links)
- 05000364/LER-1917-005, Regarding Power Range Nuclear Instrument Inoperable Due to Poor Connection of High Voltage Cable Connector (← links)
- 05000272/LER-1916-006, Regarding Technical Specification (TS) for Containment Integrity Not Met (← links)
- 05000306/LER-1917-003, Regarding Both Containment Spray Pump Control Switches in Pull-Out in Mode 4 (← links)
- 05000219/LER-1917-005, Regarding Failure of the Emergency Diesel Generator 2 During Surveillance Testing Due to a Broken Electrical Connector (← links)
- 05000390/LER-1917-015, Regarding Failure to Enter Limiting Condition of Operation Action Statement Results in a Condition Prohibited by Technical Specifications (← links)
- 05000272/LER-1917-001, Regarding Containment Integrity Inoperable for Longer than Allowed by Technical Specifications (← links)
- 05000334/LER-1917-003, Regarding Reactor Trip Due to Turbine Trip and Automatic Initiation of the Auxiliary Feedwater System (← links)
- 05000461/LER-1917-009, Regarding Trip of Emergency Reserve Auxiliary Transformer Static Var Compensator Causes Positive Secondary Containment Pressure Following Voltage Transient on 138 Kv Offsite Source (← links)
- 05000254/LER-1917-004, For Quad Cities Nuclear Power Station, Unit 1 Unit 1 HPCI Did Not Trip Due to Wear Debris in the Turbine Stop Valve Oil Resetting Solenoid (← links)
- 05000237/LER-1917-002, Regarding Primary Containment Inboard and Outboard Feedwater Isolation Valves Exceed Leakage Limits (← links)
- 05000296/LER-1917-002, Regarding 4kV Shutdown Board Potential Transformer Primary Fuses Do Not Coordinate with Secondary Fuses (← links)
- 05000286/LER-1917-004, Regarding Reactor Trip Due to Main Generator Loss of Field (← links)
- 05000395/LER-1917-005, V.C Summer, Unit 1, Regarding Automatic Reactor Trip Due to Main Turbine Trip (← links)
- 05000483/LER-1917-003, Regarding Violation of Technical Specification 3.6.3, Containment Isolation Check Valve Found in Open Position (← links)
- 05000278/LER-1917-001, Regarding Reactor Pressure Boundary Leakage Due to Weld Failure in One-Inch Diameter Instrument Line (← links)
- 05000364/LER-1917-003, Regarding Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits (← links)
- 05000364/LER-1917-002, Regarding Main Steam Safety Valve Lift Pressure Outside of Technical Specifications Limits (← links)
- 05000389/LER-1917-004, Regarding Automatic Reactor Trip Due to Turbine Control System Malfunction (← links)
- 05000389/LER-1917-003, Regarding Improper System Realignment Resulted in Loss of Steam Driven Auxiliary Feedwater Pump Flow Indication (← links)
- 05000395/LER-1917-006, Regarding Technical Specification Action Not Met for Inoperable Oxygen Monitor (← links)
- 05000266/LER-1917-003, Regarding Degraded Condition (← links)
- 05000266/LER-1917-002, Regarding Operation or Condition Prohibited by Technical Specifications (← links)
- 05000306/LER-1917-002, Regarding Reactor Coolant System Shutdown Communication Live Vent Through Wall Defect (← links)
- 05000352/LER-1917-004, Regarding Core Spray Pump Failed to Start Resulting in Condition Prohibited by TS (← links)
- 05000315/LER-1999-001, :on 990106,noted That GE Hfa Relays Installed in EDGs May Not Meet Seismic Qualification.Caused by Operating Experience Info Incorrectly Dispositioned in 1985. Updated LER Will Be Submitted by 990405 (← links)
- 05000440/LER-1917-006, Regarding Loss of Safety Function Due to the Inoperability of Both Trains of Motor Control Center Ventilation (← links)
- 05000397/LER-1917-007, Regarding Valve Closure Results in Momentary Increase in Secondary Containment Pressure (← links)
- 05000306/LER-1917-001, Regarding 23 Containment Fan Coil Unit Operability (← links)
- 05000346/LER-1917-002, For Davis-Besse Nuclear Power Station, Unit 1, Regarding Auxiliary Feed Water Pump Turbine Bearing Damaged Due to Improperly Marked Lubricating Oil Sight Glass (← links)
- 05000353/LER-1917-007, Regarding Reactor Mode Switch Change During RCIC Testing (← links)
- 05000220/LER-1917-003, Regarding Automatic Reactor Scram Due to Reactor Vessel Low Water Level (← links)
- 05000293/LER-1917-012, Regarding Start-Up Transformer Degraded Voltage Relay Found Outside Technical Specification Limit (← links)
- 05000254/LER-1917-003, Regarding Control Room Emergency Ventilation Air Conditioning Piping Refrigerant Leak Due to High Cycle Fatigue (← links)
- 05000266/LER-1917-001, Regarding Control Room Barrier Inadvertently Disabled (← links)
- 05000324/LER-1917-004, Regarding Emergency Diesel Generator and Primary Containment Isolation System Actuations (← links)
- 05000249/LER-1917-001, Regarding Standby Liquid Control System Inoperable Due to a Manufacturing Defect Causing a Piping Leak (← links)
- 05000387/LER-1917-009, Regarding Secondary Containment Declared Inoperable Due to Trip of Zone II Equipment Exhaust Fan (← links)
- 05000335/LER-1917-003, Regarding Inadequate Reactor Protection System Trip Process for Inoperable Channel Results in Operation in a Condition Prohibited by Technical Specifications (← links)
- 05000482/LER-1917-003, Regarding ARV and MSSV Tornado Missile Vulnerabilities Result in Unanalyzed Condition (← links)
- 05000395/LER-1917-004, Regarding Actuation of a Emergency Diesel Generator (← links)
- 05000397/LER-1917-006, For Condition Prohibited by Technical Specifications Due to Incomplete Action Statement (← links)
- 05000397/LER-1917-005, Regarding Valve Closure Results in Momentary Increase in Secondary Containment Pressure (← links)
- 05000251/LER-1917-001, Regarding Manual Reactor Trip Due to Lowering Steam Generator Level Caused by Loss of Flow Regulating Valve Positioner Control (← links)
- 05000289/LER-1917-003, Regarding Primary Containment Declared Inoperable Due to Both Airlock Doors Open Simultaneously (← links)
- 05000341/LER-1917-005, Regarding Non-Functional Mechanical Draft Cooling Tower Fan Brakes Leads to HPCI Being Declared Inoperable and Loss of Safety Function (← links)
- 05000296/LER-1917-001, Regarding Inoperable Residual Heat Removal Pump Results in Condition Prohibited by Technical Specifications (← links)
- 05000395/LER-1917-003, For Virgil C. Summer Nuclear Station, Unit 1, Regarding Failed Lightning Arrester on Main Transformer Causes Reactor Trip (← links)
- 05000410/LER-1917-001, Regarding Automatic Reactor Scram Due to High Reactor Pressure (← links)
- 05000397/LER-1917-004, Regarding Manual Reactor Scram Due to High Main Condenser Back Pressure (← links)
- 05000397/LER-1994-002, :on 940215,seals Conservatively Declared Inoperable,Following Completion of Preliminary Analysis of Seal Program.Caused by Original Const Inadequate in Some Initial Seal.Fire Watch Established (← links)
- 05000397/LER-1992-034, :on 920713,determined That Nonwater Tight Penetration Seals in ECCS Pump Rooms Could Result in Common Mode Failure from Flooding.Inadequate Penetration Seals in ECCS Pump Rooms Except for Door Seals Reworked (← links)
- 05000446/LER-1917-001, Regarding Auxiliary Feedwater System Actuation During Unit 2 Turbine Trip (← links)
- 05000397/LER-1993-004, :on 930127,determined That Two Inadequately Installed Fuses Could Have Caused Loss of RHR Capability During Seismic Event.Caused by Improper Installation of Fuses.Fuse Deficiencies Will Be Evaluated (← links)
- 05000397/LER-1992-005, :on 920219,thermal Overloads Prevented Motors from Performing Safety Functions.Caused by Misapplication of Design Inputs.Motors Replaced (← links)
- 05000483/LER-1917-002, Regarding Inadequate Protection from Tornado Missiles Identified Due to Nonconforming Design (← links)
- 05000416/LER-1917-006, Regarding Completion of Grand Gulf Nuclear Station Shutdown Required by Technical Specifications Because of an Inoperable a Residual Heat Removal Pump (← links)
- 05000387/LER-1917-007, Regarding Secondary Containment Declared Inoperable Due to Supply Air Flow (← links)
- 05000341/LER-1917-004, Regarding Inadequate Procedural Guidance for Residual Heat Removal Complex Ventilation Systems Leads to Condition Prohibited by Technical Specifications and Loss of Safety Function (← links)
- 05000440/LER-1917-005, Regarding Controller Malfunction Results in Momentary Degradation of Secondary Containment Pressure (← links)
- 05000440/LER-1917-004, Re Loss of Safety Function for High Pressure Core Spray Suppression Pool Level Instrumentation (← links)
- 10 CFR 50.73(a)(2)(v), Loss of Safety Function (← links)
- 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability (← links)
- Licensee Event Report (← links)
- 05000296/LER-2015-001, High Pressure Coolant Injection and Reactor Core Isolation Cooling Inoperable Due To No Suction Source Aligned (← links)
- 10 CFR 50.73(a)(2)(iv), System Actuation (← links)
- 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications (← links)
- 05000482/LER-2015-001, Personnel Error Causes Two Inoperable Residual Heat Removal Trains (← links)
- 05000482/LER-2015-002, Two Control Room Air Conditioning Trains Inoperable Due to Failure to Meet Surveillance Requirement (← links)
- 05000482/LER-2015-003, Manual Reactor Trip due to High Steam Generator Level Transient at Low Power (← links)
- 05000482/LER-2015-004, Incorrect Decision Results in Two Containment Isolation Valves being in a Condition Prohibited by Technical Specifications (← links)
- 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded (← links)