Pages that link to "05000410/LER-2024-001, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum"

The following pages link to 05000410/LER-2024-001, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum:

Displaying 39 items.

• 10 CFR 50.73(a)(2)(iv)(A), System Actuation (← links)
• ML18207A406 (← links)
• ML103050559 (← links)
• ML102800415 (← links)
• ML102090608 (← links)
• ML101600452 (← links)
• ML101470493 (← links)
• ML101300683 (← links)
• ML093580130 (← links)
• ML093020116 (← links)
• ML021370019 (← links)
• ML021350457 (← links)
• ML021340214 (← links)
• ML021330263 (← links)
• ML021080912 (← links)
• ML020940164 (← links)
• ML020930011 (← links)
• ML020870203 (← links)
• ML020810012 (← links)
• ML020720326 (← links)
• ML020670385 (← links)
• ML020520218 (← links)
• ML020440429 (← links)
• ML020440419 (← links)
• ML020440253 (← links)
• ML020310427 (← links)
• ML020240003 (← links)
• ML020180359 (← links)
• ML020100071 (← links)
• ML20105A176 (← links)
• ML20100F682 (← links)
• ML20094K422 (← links)
• ML20115E362 (← links)
• ML20241A190 (← links)
• NMP2L2880, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum (redirect page) (← links)
  • NMP2L2880 (redirect page) (← links)
• ML24136A202 (redirect page) (← links)
  • IR 05000410/2024003 (← links)
• 05000410/LER-2024-001 (redirect page) (← links)
  • 05000410/LER-2002-006 (← links)
  • 05000410/LER-2001-004 (← links)
  • 05000410/LER-2001-003 (← links)
  • 05000410/LER-2001-002 (← links)
  • 05000410/LER-1986-016, Informs That Condition Reported in LER 86-016 Re Incorrect Location of Flow Switches in Standby Gas Treatment Sys Could Create Substantial Safety Hazard & Also Reportable Per 10CFR21 (← links)
  • 05000410/LER-1987-045, Corrected LER 87-045-00:on 870729,two Separate ESF Actuations Occurred.Caused by Lack of Administrative Controls & Personnel Error.Surveillance Procedures Revised to Prohibit Concurrent Performance (← links)
  • 05000410/LER-1989-003, Forwards Corrected Copy of LER 89-003-00 Submitted on 890320.Typo Identified on Page 5 of 7 Corrected (← links)
  • ENS 57004 (← links)
  • 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater (← links)
  • 05000410/LER-2024-001, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum (← links)
  • 05000410/LER-2022-002-01, Reactor Protection System Actuation While Shutdown (← links)
  • 05000410/LER-2022-002, Reactor Protection System Actuation While Shutdown (← links)
  • 05000410/LER-2022-001, Regarding Automatic Reactor Scram Due to Low Reactor Water Level During Maintenance (← links)
  • IR 05000410/2024003 (← links)
  • 05000410/LER-2020-002-01, Failure to Meet Technical Specification MSIV Stroke Times (← links)
  • 05000410/LER-1986-008-01, :on 861117,discovered Potential Breaches in Fire Barriers During Control Rod Testing.Caused by Failure to Seal Penetrations.Fire Watches Established & Penetrations Sealed (← links)
  • 05000410/LER-1986-007-01, :on 861120,two Electrical Protection Assemblies Spuriously Tripped,Resulting in Loss of Power to safety- Related Control Circuit.Root Cause Evaluation Will Be Performed (← links)
  • 05000410/LER-1986-004-01, :on 861109,unit Experienced Two Full Scrams W/Mode Switch in Refuel.Caused by Faulty Circuit Card.Root Cause Unknown But Random Infant Mortality Suspected.Circuit Card Replaced (← links)
  • 05000410/LER-1986-003-01, :on 861108,partial Loss of Secondary Containment Isolation Actuation Instrumentation Occurred. Caused by Personnel Error.Training Mod Recommendation Initiated (← links)
  • 05000410/LER-1986-002-01, :on 861104,four Source Range Monitors (Srms) Downscale Channels Placed in Bypassed State When Jumpers Installed to Clear SRM Downscale Rod Blocks.Caused by Human Error & Procedure Deficiency.Procedure Revised (← links)
  • 05000410/LER-1986-001-01, :on 861105,two Reactor Scrams Occurred During Initial Fuel Loading.Caused by Spike on Intermediate Range Monitor D & High Level Scram Discharge Trip.Operator Training Mod Submitted (← links)
  • 05000410/LER-1986-005-01, :on 861105,source Range Monitor Channel C Erroneously Left in Bypass Position Following Surveillance Check.Caused by Failure of Operator to Adhere to Procedure. Procedure Revised & Staff Counseled (← links)
  • 05000410/LER-1987-013, :on 870209,automatic Actuation of ESF Sys Occurred Due to Loss of Power to Class 1E Bus.Caused by Personnel Error.Training Mod Recommendation Submitted to Remind Operators to Assess Plant Conditions (← links)
  • 05000410/LER-1987-012, :on 870208,MSIV Closure Occurred on Low Condenser Vacuum Signal.Caused by Unusual & Complicated Set of Conditions That Precluded Running Surveillance Test W/O Adverse Consequences.Test Procedure Revised (← links)
  • 05000410/LER-1987-011, :on 870207,while at 0% Power,All Rods Experienced Reactor Scram.Caused by Bumping Piece of Steel Tubing Between Reactor & Water Level Instrumentation. Design Change Will Eliminate Problem (← links)
  • 05000410/LER-1987-010, :on 870202,spurious Reactor Scram Signal Experienced Due to Low Reactor Water Level Signal.Caused by Opening of Instrument Valve on Differential Pressure Indicator. Hold-Out Tag Placed on Valve (← links)
  • 05000410/LER-1987-006, :on 870202,MSIVs Closed on Isolation Signal. Caused by Inadvertent Trip of Two safety-related Reactor Monitoring Devices.Surveillance Procedure N2-ISP-ISC-R001 Will Be Revised Prior to Next Scheduled Use (← links)
  • 05000410/LER-1986-016-01, :on 861207 & 08,during Surveillance Procedure, Filter Train Heaters Intermittently Deenergized on Low Flow Signal.Caused by Flow Switch Design Deficiency.Sensing Line Relocated (← links)
  • 05000410/LER-1987-014, :on 870129,inoperable Instrumentation in Radioactive Gaseous Effluent Monitoring Sys Utilized W/O Establishment of Required Compensatory Measures.Cause Under Investigation (← links)
  • 05000410/LER-1986-027-01, :on 861215,Agastat GP Series Relay Failed to Function During Preoperational Test.Caused by Improper Seating of Relays in Sockets.Relays Properly Seated & Maint Procedure Revised.Part 21 Related (← links)
  • 05000410/LER-1986-006-01, :on 861112,Tech Spec Hourly Fire Watch Patrol Surveillance Requirements Exceeded Twice.Caused by Cognitive Personnel Errors.Fire Dept Personnel Trained in Tech Spec Requirements & Patrol Methods Revised (← links)
  • 05000410/LER-1987-009, :on 870126,during Performance of Procedure N2-ISP-RPS-R102,full Isolation Occurred When Stop Valves SV-3 & -4 Limit Switches Calibr.Caused by Procedural Deficiency.Procedure to Be Revised (← links)
  • 05000410/LER-1986-026-01, :on 861229,discovered That Conduit Seals Inside Manhole 6 Did Not Meet Internal Flooding Criteria.Caused by Design Deficiency.Two Covers to Manhole 5 Redesigned.Part 21 Rept Issued on 8701223 (← links)
  • 05000410/LER-1987-008, :on 870127,violation of Limiting Condition for Operation Occurred During mark-up of Carbon Dioxide Fire Suppression Sys.Caused by Misinterpretation of Communication by Personnel.Signature for Actions Required (← links)
  • 05000410/LER-1987-003, :on 870116,single Jumper Fell Off & Shorted to Ground Causing Reactor Bldg Ventilation Exhaust Damper to Close.Caused by Difficulty in Obtaining Tight Grip W/Jumper Alligator Clip on Head of Termination Screw (← links)
  • 05000410/LER-1987-002, :on 870109,trains of Standby Gas Treatment Sys Automatically Initiated.Caused by Failure to Adequately Review Markup.Operators Cleared Red Markup & Restored Power to Inlet Dampers (← links)
  • 05000410/LER-1986-008, :on 861117,discovered Potential Breaches in safety-related Fire Barriers.Caused by Contractor Failure to Follow Established Procedures for Identifying Incomplete Const Work.Breaches Sealed (← links)
  • 05000410/LER-1986-024-01, :on 861231,visible Corrosion Observed on Div I & II Battery Bus Bars & Terminals.Caused by Naturally Occurring Leakage from Battery Seals.Corrosion Removed (← links)
  • 05000410/LER-1986-025-01, :on 861231,automatic Initiation of Standby Gas Treatment Sys Train B Occurred.Caused by Component Location Design Deficiency.Design Changed to Relocate Exterior Differential Pressure Primary Elements (← links)
  • 05000410/LER-1987-017, :on 870224,auto-initiation of Standby Gas Treatment Sys & Primary Containment Isolation Occurred. Caused by Breaker Being Opened on Reactor Protection Sys Power Supply While Performing Troubleshooting (← links)
  • 05000410/LER-1986-022-01, :on 861222,Div I-III Diesel Generators Declared Inoperable During Simultaneous Draining of Day Tank During Chemistry Surveillance Test.Caused by Procedure Deficiency. Procedure Revised.Personnel Counseled (← links)
  • 05000410/LER-1986-020-01, :on 861218,Div 1 ECCS Initiation Experienced Due to Spurious High Drywell Pressure Signal.Caused by Electricians Replacing Relay.Electrical Maint Training Initiated (← links)
  • 05000410/LER-1986-010, :on 861123,25% of Control Rods Received Full Scram Signal When Group 2 Control Rod Scram Solenoid Valves Deenergized.Cause Not Positively Determined.Training Mod Request Will Be Issued.Procedures Revised (← links)
  • 05000410/LER-1986-023-01, :on 861223,inoperable Fire Detector Discovered During Routine Insp.Caused by Personnel Removing Detector from Base Prior to Replacement,Per 861222 Work Request. Surveillance Procedure Will Be Developed (← links)
  • 05000410/LER-1986-019-01, :on 861215,reactor Scram Signal on Scram Discharge Vol Received Following Preplanned Scram.Caused by Operator Failure to Adhere to Scram Recovery Procedure. Procedure Revised.Training Mod Recommended (← links)
  • 05000410/LER-1986-018-01, :on 861216,while Testing Off Normal Status Sys Isolators,Electrician Placed Jumpers from 120-volt Dc Source to 120-volt Ac Line Source,Resulting in Blown Fuse.Caused by Test Engineer Error.Engineer Disciplined (← links)
  • 05000410/LER-1986-021-01, :on 861210 & 11,HPCS Sys Initiation Experienced Due to lo-lo Water Level Signal.Caused by Inadvertent Movement of 4 Ft Section of Flexible Steel Piping Creating Hydraulic Surges.Steel Plate Removed from Rack (← links)
  • 05000410/LER-1986-014-01, :on 861203,scram Experienced to one-quarter of Control Rods During Recovery from Earlier Scram & Containment Isolation.Caused by Personnel Error.Addl Licensed Operator Training Requested (← links)
  • 05000410/LER-1986-009, :on 861124,reactor Bldg Ventilation Exhaust Damper 2HVR*AOD9B Closed Initiating Standby Gas Treatment Train A.Caused by Jumper Which Fell & Shorted to Ground. Alternate Installation Methods Under Review (← links)
  • 05000410/LER-1986-011-01, :on 861127 & 1208,automatic Initiation of Standby Gas Treatment Sys Div I & II Occurred.Caused by Reactor Bldg Refuel Area Exhaust Ventilation Duct Radiation High Signal (← links)
  • 05000410/LER-1986-012-01, :on 861128 & 29,automatic Initiation of Standby Gas Treatment Sys Divs I & II & Emergency Recirculation Subsystem of Secondary Containment Ventilation Sys Occurred. Caused by Supply Fan Trip (← links)
  • 05000410/LER-1986-010-01, :on 861123,25% of Control Rods Received Full Scram Signal When All Group 2 Control Rod Solenoid Valves de-energized.Cause Undetermined.Investigation in Form of Supervisory Procedure S-SUP-1 Begun (← links)
  • 05000410/LER-1986-015-01, :on 861203,reactor Scram Occurred While in Shutdown Mode.Caused by Reactor Protection Sys Power Supplies Inadvertently Cross Connected,Resulting in Loss of Power.Design Change Built Into MSIV (← links)
  • 05000410/LER-1986-012, :on 861128 & 29,series of Related Automatic Initiations of Standby Gas Treatment Sys Occurred.Caused by Clogged Filters & Personnel Error.Approx 50% of First Stage Filters Replaced & Training Mod Initiated (← links)
  • 05000410/LER-1987-016, :on 870226,abandoned Penetration in Fire Wall Between Secondary Containment & Main Steam Tunnel Found Improperly Sealed.Caused by Personnel Error.Penetrations Reviewed & Fire Watch Established (← links)
  • 05000410/LER-1987-015, :on 870222,failure to Maintain Hourly Watch Patrol in Area W/Inoperable Fire Detection Sys Occurred. Caused by Change to Fire Watch Patrol Rover Schedule W/O Notifying Fire Chief.Personnel Counseled (← links)
  • 05000410/LER-1986-011, :on 861127 & 1208,automatic Initiation of Standby Gas Treatment Sys Divs I & II Occurred.Caused by Spurious Reactor Bldg Exhaust Ventilation Duct High Radiation Signals.Accumulator Added to Lines (← links)
  • 05000410/LER-1986-007, :on 861120,ESF Actuation Occurred.Caused by Two Electrical Protection Assemblies (Epas) Tripping Twice in 2 H Causing Loss of Power to Circuit Bus Due to Personnel Error During MSIV Testing.Epas Reset (← 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)
  • 05000410/LER-1992-008, :on 920327,Unit 2 Experienced ESF Actuations. Caused by Personnel Error.Technician Involved Counseled, Procedure Revised & Directive to Help Minimize Risk of Relay State Verification Methods Issued (← links)
  • 05000410/LER-1995-011, :on 951115,discovered That 100% of Rated Core Thermal Power Exceeded During Fuel Cycles 4 & 5 Due to Core Thermal Power Calculation Methodology Error.Reduced Power & Established Administrative Limit on Power (← links)
  • 05000410/LER-2019-001, High Pressure Core Spray Declared Inoperable (← links)
  • 05000410/LER-2024-002, Automatic Reactor Scram on Turbine Trip Due to Failed Breaker (← links)
  • 05000410/LER-2018-002, Turbine Trip and Scram Due to Unit Differential Relay Trip (← 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)
  • 05000410/LER-1998-017, :on 980602,control Room Ventilation Sys Was Declared Inoperable.Caused by Original Design Deficiency. Mod Designed,Tested & Implemented Prior to Startup from RF06 to Correct Design Deficiency (← links)
  • 05000410/LER-1998-004, :on 980302,TS Required LSFT of Level 8 Trip of Main Turbine Was Missed.Caused by Knowledge Deficiency of EHC Sys.Revised Applicable LSFT Procedures Prior to Refueling Outage 6 (← links)
  • 05000410/LER-1993-010, :on 931108,HPCS Was Inoperable Due to Equipment Deficiency,Inadequate Managerial Methods & Poor Work Practices.Replaced Deficient Contactors & Restored Tap Setting.Also Reportable Per Part 21 (← links)
  • 05000410/LER-1989-014, :on 890413,unit Reactor Experienced Reactor Scram Which Was Result of Turbine Trip Due to Actuation of Generator Protection Circuitry.Turbine Trip Caused by Disconnected Wire.Wire Relanded (← links)
  • 05000410/LER-1987-051, :on 870813,shutdown Cooling Sys Isolated & Tech Specs 3.4.9.2 Exceeded.Caused by Equipment Failure,Personnel Error & Procedural & Design Deficiencies.Shutdown Cooling Sys Manually Restored (← links)
  • 05000410/LER-1988-024, :on 880605,ESF Actuation Occurred Due to Resetting of Failed Radiation Monitor Microcomputer.Caused by Lack of Personnel Training.Defective Cards & Modules in RE14B Microcomputer & DRMS Panel Replaced (← links)
  • 05000410/LER-1988-014, :on 880313,reactor Scram & ESF Actuations Occurred.Caused by Equipment Failure Due to Design Deficiency.Transmitter Replaced W/Upgraded Model & Temporary Mod Performed to Bypass Logic for Valves (← links)
  • 05000410/LER-1988-001, :on 880120,reactor Scram Occurred Due to Actual Low Water Level Condition.Caused by Design & Personnel Errors.Operator Disciplined & Mod Addressed Inadvertent Feedwater Control Valve Lockup (← links)
  • 05000410/LER-1987-025, :on 870519,secondary Containment Isolation Signal Generated Due to Technician Relanding Lifted Lead Prematurely.Caused by Breakdown in Communications.Gaitronics Phone &/Or Headset Jack Installed (← links)
  • 05000410/LER-1999-010-01, For Nine Mile Point, Unit 2, Regarding Two Standby Liquid Control Valves Not Tested as Required by Technical Specification 4.0.5 and LER 99-010-01, Supplement 1, Unit 2 Reactor Trip Due to a Feedwater Master (← links)
  • 05000410/LER-1917-002, Regarding Secondary Containment Inoperable Due to Wind Conditions (← links)
  • 05000410/LER-1917-001, Regarding Automatic Reactor Scram Due to High Reactor Pressure (← links)
  • 05000410/LER-1999-001-01, :on 990212,NMP2 Was Outside Design Basis Due to Safe SD SW Pump Bay Unit Coolers Being Oos.Caused by Inadequate Managerial Methods.Interim ACs Were Set for Safe SD Equipment.With (← links)
  • 05000410/LER-1998-019, :on 980617,determined That Fire Proofing Was Missing from Beam.Caused by Failure of Contractor Personnel. Breach Permit Initiated & Compensatory Fire Patrols Were Established (← links)
  • 05000410/LER-1998-014, :on 980525,noted Differences Between Actual Valve Weights & Weights Shown on Engineering Drawings.Caused by Vendor Failing to Provide Accurate Valve Weights.Revised Valve Drawings & Associated Calculation,Per 10CFR21 (← links)
  • 05000410/LER-1993-011, :on 931119,reactor Scram & ESF Actuation Occurred.Caused by Poor Work Organization & Planning. Work Planning Guide Revised & Procedure Changes Will Be Evaluated (← links)
  • 05000410/LER-1990-021-01, :on 901026,TS Violation Re RHR Sys Valve Tests Not Included in Inservice Test Pump/Valve Program Plan Occurred (← links)
  • 05000410/LER-2016-001, Regarding Secondary Containment Inoperable Due to Simultaneous Opening of Airlock Doors (← links)
  • 05000410/LER-2015-003, Regarding Primary Containment Isolation Function for Some Valves Not Maintained During Surveillance Testing (← links)
  • 05000410/LER-2015-002, Regarding Manual Reactor Scram Due to Unexpected Reactor Water Level Change (← links)
  • 05000410/LER-2015-001, For Nine Mile Point, Unit 2, Regarding Secondary Containment Inoperable Due to Sustained High Winds (← links)
  • 05000410/LER-2014-008, Re Secondary Containment Inoperable Due to Reactor Building Exhaust Fan Trip (← links)
  • 05000410/LER-2014-007, Regarding Secondary Containment Inoperable Due to Simultaneous Opening of Airlock Doors (← links)
  • 05000410/LER-2014-006, Regarding Secondary Containment Inoperability Following Auxiliary Boiler Trip (← links)
  • 05000410/LER-2014-005, Regarding Secondary Containment Inoperable Due to Sustained High Winds (← links)
  • 05000410/LER-2014-004, Regarding Actuation of the Alternate Rod Insertion System and Subsequent Reactor Scram (← links)
  • 05000410/LER-2014-002, High Pressure Core Spray System Inoperability Due to Inoperable High Pressure Core Spray Diesel Generator (← links)
  • 05000410/LER-2014-003, Regarding Uninterruptible Power Supply Failure and Subsequent Manual Scram (← links)
  • 05000410/LER-2014-001, Regarding Emergency Diesel Generator Actuation Due to Loss of Offsite Power Source Line 5 (← links)
  • 05000410/LER-2013-005, Regarding Secondary Containment Inoperabilities Due to Differential Pressure Not Meeting Technical Specification Surveillance Requirement 3.6.4.1.1 (← links)
  • 05000410/LER-2013-004, Regarding Manual Reactor Protection System Actuation Due to Loss of Reactor Recirculation Flow (← links)
  • 05000410/LER-2013-003, Regarding Unanalyzed Condition Caused by Unfused Control Room DC Ammeters (← links)
  • 05000410/LER-2013-002, For Nine Mile Point Unit 2, Regarding Failure of High Pressure Core Spray System Pressure Pump Due to Motor Winding Failure (← links)
  • 05000410/LER-2013-001, Regarding Reactor Core Isolation Cooling System Isolation Due to a Temperature Switch Unit Failure (← links)
  • 05000410/LER-2012-005, Regarding Automatic Diesel Actuation Due to the Loss of a 115 Kv Offsite Power Source (← links)
  • 05000410/LER-2012-004, Regarding Manual Reactor Scram Due to a Loss of Main Turbine Gland Sealing Steam Resulting in Lowering Condenser Vacuum (← links)
  • 05000410/LER-2012-003, Regarding Suppression Pool Level Below Technical Specification Limit During Mode Change (← links)
  • 05000410/LER-2012-002, Regarding Loss of Isolation Function on RHR Shutdown Cooling Suction Line Due to Breaker Trip (← links)
  • 05000410/LER-2012-001, Forced Shutdown Due to an Increase in Drywell Leakage in Excess of Technical Specifications Limit (← links)
  • 05000410/LER-2011-004, Regarding Reactor Water Cleanup System Automatic Isolation Function Disabled During Troubleshooting (← links)
  • 05000410/LER-2011-003, Regarding Reactor Shutdown Due to an Unisolatable Leak on a Feedwater Pump Minimum Flow Line (← links)
  • 05000410/LER-2011-002, Regarding Reactor Shutdown Due to Reactor Coolant System Unidentified Leakage Above Technical Specification Limits (← links)
  • 05000410/LER-2011-001, Regarding As-Found Safety Relief Valve Lift Setpoints Exceed Technical Specification Allowable Values (← links)
  • 05000410/LER-2010-001, Regarding Reactor Scram Due to Inadvertent Actuation of the Redundant Reactivity Control System During Maintenance (← links)
  • 05000410/LER-2009-001, Regarding Momentary Loss of Control Power to High Pressure Core Spray Pump Due to Degraded Fuse Block Connection (← links)
  • 05000410/LER-2006-002, Regarding RCIC Exhaust Piping Vacuum Breakers Isolated Resulting in an Unanalyzed Condition (← links)
  • 05000410/LER-2006-001, Regarding Automatic Reactor Scram Due to a Loss of Main Turbine Gland Sealing Steam (← links)
  • 05000410/LER-2005-001, Regarding Both Standby Gas Treatment Subsystems Inoperable Due to an Original Design Deficiency (← links)
  • 05000410/LER-2004-001, Re Inoperability of a Control Room Envelope Filtration System Train Due to a Locked Closed Damper (← links)
  • 05000410/LER-2003-003, Regarding Oscillation Power Range Monitor Inoperable Due to Non-Conservative Settings for Adjustable Parameters (← links)
  • 05000410/LER-2003-002, Regarding Reactor Scram Due to Electric Grid Disturbance (← links)
  • 05000410/LER-2003-001, Regarding Oscillation Power Range Scram Due to a Power and Flow Perturbations Resulting from a Power Supply Failure (← links)
  • 05000410/LER-2002-004, Reactor Trip Due to Main Steam Isolation Valve Failure (← links)
  • 05000410/LER-2002-003, From Nine Mile Point, Unit 2 Regarding Open Door Between Control Building & Auxiliary Building Results in Breach of Control Room Envelope (← links)
  • 05000410/LER-2002-002, Reactor Water Cleanup System Differential Flow Isolation Signal Inoperable (← links)
  • 05000410/LER-2001-001-01, Reactor Scram Due to Relay Failure in Electro Hydraulic Control Systems (← links)
  • 05000410/LER-2002-001, Automatic Scram Signal During Refueling Outage Due to Inadequate Instrument Air Isolation Procedure (← links)
  • 05000410/LER-2001-007, Re Manual Reactor Scram Due to Unidentified Drywell Leakage (← links)
  • 05000410/LER-2001-006, Re Manual Scram Due to Feedwater Pump Motor Failure (← links)
  • 05000410/LER-2024-002-01, Supplement to NMP2 Licensee Event Report 2024-002-00, Automatic Reactor Scram on Turbine Trip Due to Failed Breaker (← links)
• 05000410/LER-2024-002, Automatic Reactor Scram on Turbine Trip Due to Failed Breaker (← links)
• 05000410/LER-2024-002-01, Supplement to NMP2 Licensee Event Report 2024-002-00, Automatic Reactor Scram on Turbine Trip Due to Failed Breaker (← links)