Pages that link to "05000530/LER-2021-001, Reactor Trip During Control Element Assembly Alignment Activities"
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The following pages link to 05000530/LER-2021-001, Reactor Trip During Control Element Assembly Alignment Activities:
Displayed 9 items.
- ML18194A800 (← links)
- 05000530/LER-2021-001-01, Reactor Trip During Control Element Assembly Alignment Activities (← links)
- 05000528/LER-2021-001-01, Unit 1 and 3 Emergency Diesel Generator Actuation on Loss of Offsite Power to Class 4.16 Kv Buses (← links)
- ML22034A997 (redirect page) (← links)
- 05000530/LER-2021-001 (redirect page) (← links)
- 05000530/LER-2015-002, Condition Prohibited by Technical Specification 3.0.4 Due to an Inoperable Atmospheric Dump Valve (ADV) (← links)
- 05000530/LER-2015-003, Damaged High Pressure Safety Injection Pump Motor Journal Bearing (← links)
- 05000530/LER-2015-004, Condition Prohibited by Technical Specifications 3.0.4 and 3.7.2 Due to an Inoperable Main Steam Isolation Valve (← links)
- 05000530/LER-2010-001 (← links)
- 05000530/LER-1998-001 (← links)
- 05000530/LER-1999-001 (← links)
- 05000530/LER-1996-001 (← links)
- 05000530/LER-1995-001 (← links)
- 05000530/LER-2001-002 (← links)
- 05000530/LER-2001-001 (← links)
- ENS 55626 (← links)
- IR 05000528/2022003 (← links)
- 05000530/LER-2024-001, Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation (← links)
- 05000530/LER-2024-001-01, Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation (← links)
- 05000530/LER-2024-002, Invalid Specified System Actuation of Train B Emergency Diesel Generator (← links)
- 05000530/LER-2021-001-01, Reactor Trip During Control Element Assembly Alignment Activities (← links)
- 05000530/LER-2021-001, Reactor Trip During Control Element Assembly Alignment Activities (← links)
- 05000530/LER-1989-008, :on 890630,maint Personnel Identified Sixth Trip Lever Arm on 10-ton Fuel Handling Crane Rails Instead of Only Five Trip Lever Arms for Crane Interlocks.Cause Under Investigation.Sixth Level Arm Removed (← links)
- 05000530/LER-1989-006-01, :on 890606,operations Personnel Discovered That Two Required Dayshift,Shiftly Surveillances Not Performed within Required Interval.Caused by Personnel Error. Personnel Counseled (← links)
- 05000530/LER-1987-002-02, :on 870615,control Room Essential Filtration Actuation Signals & Containment Purge Isolation Actuation Signals Received on Both Channels of balance-of-plant Esfas. Cause Under Investigation (← links)
- 05000530/LER-1997-001, :on 970306,initiated Manual Fuel Bldg Essential Ventilation Actuation.Caused by Loss of Spent Fuel Pool (SPF) Level.Restored Air Pressure to Gate Seal & SPF Level Proceeded to Increase (← links)
- 05000530/LER-2020-001, Condition Prohibited by Technical Specifications Due to Inoperable Spray Pond Pump (← links)
- 05000530/LER-2024-003, Violation of Technical Specifications 3.9.2 and 3.3.12 (← links)
- 05000530/LER-2018-001-01, Reactor Trip on Low Steam Generator Level (← links)
- 05000530/LER-2018-001, Reactor Trip on Low Steam Generator Level (← links)
- 05000530/LER-1998-003-02, :on 980902,discovered That MSSV as-found Lift Pressures Were Outside TS Limits.Caused by Bonding of Valve Disc to Nozzle Seat.Affected Valves Were Adjusted,Retested & Returned to Svc (← links)
- 05000530/LER-1998-003-01, Forwards LER 98-003-01 Re MSSV as-found Lift Pressures out- Side of TS Limits.Ler Suppl Provides Evaluation Findings from Unit 3 out-of-tolerance MSSVs Conditions Which Were Discovered During pre-outage Testing (← links)
- 05000530/LER-1998-002-01, Forwards LER 98-002-01,re Discovery & Correction of cross- Wired Power Supply Receptacle for B Train H Recombiner,Per 10CFR50.73 (← links)
- 05000530/LER-1998-004, Forwards LER 98-004-00 Prepared & Submitted Pursuant to 10CFR50.73.LER Reports TS Violation Due to non-compliance with TS 3.9.3 for Not Establishing Containment Penetration Isolation During Core Alterations (← links)
- 05000530/LER-1998-003, Forwards LER 98-003-00 Prepared & Submitted Per 10CFR50.73.LER Repts out-of-tolerance Condition of Several MSSV Which Were Discovered During pre-outage Testing (← links)
- 05000530/LER-1998-002-02, :on 980814,B Train H Recombiner Was Noted Inoperable Due to cross-wired Power Receptacle.Cause of Event Is Under investigation.Cross-wired Power Supply Receptacle for B Train H Recombiner Was re-wired (← links)
- 05000530/LER-1998-002, Forwards LER 98-002-00,re Discovery & Correction of cross- Wired Power Supply Receptacle for B Train H Recombiner. No New Commitments Made by Util (← links)
- 05000530/LER-1998-001-02, :on 980730,entered TS 3.0.3 Due to Safety Injection Flow Instruments Being Removed from Svc.Caused by Personnel Error.Transmitters Were Unisolated & Returned to Svc (← links)
- 05000530/LER-1993-005-02, :on 930309,CR Personnel Discovered Missed TS LCO Action & Subsequently Performed Surveillance Satisfactorily.Caused by Personnel Error.Appropriate Disciplinary Action Issued (← links)
- 05000530/LER-1997-003, :on 970215,seven Main Steam Safety Valves Were Found Out of Tolerance Prior to Refueling Outage.Safety Analysis Performed Based Upon as-found MSSV Data Which Demonstrated That MSSVs Would Perform Safety Functions (← links)
- 05000530/LER-1997-003-01, Forwards LER 97-003-01,reporting Test Results of Main Steam Safety Valve as-found Lift Settings That Were Out of Tolerance Limits Specified in TS Limiting Condition for Operation 3.7.1.1 (← links)
- 05000530/LER-1997-002-01, :on 970531,RT Occurred.Caused by Spurious Opening of All Four RT Switchgear Breakers.Independent Investigation of Event Being Conducted in Accordance W/Util Corrective Action Program (← links)
- 05000530/LER-1997-002, Forwards LER 97-002-00 Re Automatic Reactor Trip Following Spurious Opening of All Four RT Switchgear Breakers (← links)
- 05000530/LER-1996-001-02, :on 960621,inaccurate Gas Calculations for Post Accident Sampling Sys Occurred.Caused by Surveillance Test Worksheet Errors.Independent Investigation of Event Being Conducted (← links)
- 05000530/LER-1995-002-02, :on 950924,identified That Abnormal Blowdown Valves to Blowdown Flash Tank (Bft) Isolated,Resulting in Reactor Core Power Exceeding 3,800 Mwt Due to Personnel Error.Procedure for Aligning Blowdown to Bft Revised (← links)
- 05000530/LER-1995-002, Forwards LER 95-002-00 Re Condition Where Max Power Level of Facility OL Exceeded for Nine H.Highest Rolling 12 H Average 100.97 Percent Power (← links)
- 05000530/LER-1995-001-01, :on 950412,leak Identified Through Cracked Weld in Piping Near Charging Pump Suction Drain Valve.Caused by Defective Weld.Pump Weld Repaired & Returned to Svc (← links)
- 05000530/LER-1994-008, Forwards LER 94-008-00,eight Incore Instruments Found cross- Wired (← links)
- 05000530/LER-1994-007, :on 940830,reactor Trip Occurred When Steam Generator 2 Water Level Reached RPS Trip Setpoint.Caused by Component failure.FWCS-2 Master Controller Was Replaced (← links)
- 05000530/LER-1994-006, :on 940823,shutdown Cooling Loop Rendered Inoperable Due to Pump Breaker Racked Down & in Test Position.Training Provided to Licensed Operators on Procedure 40DP-9OP26, Operability. (← links)
- 05000530/LER-1994-005-01, :on 940819,reactor Trip Occurred Following Degradation of Mf Flow.Fwcs cabinets,SG-1 Economizer & MFW Pumps Quarantined & FWCS-1 Master Controller Replaced.W/ (← links)
- 05000530/LER-1994-002-01, :on 940318,13 of 20 MSSVs Setpoints Found to Be Out of Tolerance.Most Valves Exhibited Seat Wear.Valves Replaced w/pre-tested Spares & Approval to Amend TS LCO 3.7.1.1,MSSV Setpoints Received (← links)
- 05000530/LER-1994-004-01, :on 940530,LCO 3.0.3 Entered Following Determination That Secondary Pressure Boundary Leakage Existed.Caused by Defective Weld.Control Room Personnel Returned to Mode 5 & Exited LCO 3.0.3 (← links)
- 05000530/LER-1994-003, Corrected Ltr Forwarding LER 94-003-00,changing Ltr Number to 192-00892-JML/AKK/RKR.W/o LER (← links)
- 05000530/LER-1994-002, :on 940317,main Steam Safety Valve Setpoints Found Out of Tolerance.Valves Adjusted,Certified & Returned to Svc (← links)
- 05000530/LER-1993-004-01, :on 931103,reactor Manually Tripped After Recognizing That Subgroup 5 of CEA Regulating Group 4 Slipped Into Reactor Core During Reactor Power Reduction. CEA Regulating Group 4 Will Be Monitored (← links)
- 05000530/LER-1992-005-02, :on 921023,determined That 11 of 20 Main Steam Safety Valve as-found Relief Setpoints Out of TS 3.7.1.1 Tolerance from 921010-23.Possibly Caused by Setpoint Drift. Valves Will Be Removed & Shipped to Offsite Facility (← links)
- 05000530/LER-1992-005-01, Forwards LER 92-005-01 Re Main Steam Safety Valve as-found Relief Settings Out of Tolerance Limits in TS 3.7.1.1.Suppl Updates Valve Testing Schedule in Section Iii.B & Provides Main Steam & Pressurizer Safety Valve Test Res (← links)
- 05000530/LER-1993-001-02, :on 930204,reactor Trip Occurred Due to SG 2 Water Level Reaching RPS Trip Setpoint for Low SG Water Level Following Loss of Main Feedwater Pump A.Caused by Failure of Circuit Board.Investigation Underway (← links)
- 05000530/LER-1993-001, Forwards LER 93-001-00 Re Reactor Trip Which Occurred Following Failure of Main Feedwater Pump a & Resultant ESFAS Actuations.Ler Also Serves as Special Rept Describing Circumstances of ECCS Actuation (← links)
- 05000530/LER-1992-004-02, :on 921009,containment & Fuel Bldg Ventilation ESF Actuations Occurred Due to Personnel Error.Reactor Operator Disciplined (← links)
- 05000530/LER-1992-004, Forwards LER 92-004-00 Re 921009 Invalid Control Room, Containment & Fuel Bldg Ventilation ESF Actuations.Addl Info Provided Re 921014 Event (← links)
- 05000530/LER-1992-002-02, :on 920722,RCS Leakage Monitor Declared Inoperable to Investigate Sampling Discrepancy.Inleakage Due to Cracked Gasket Was Periodically Diluting Gaseous Sample. Monitor Repaired & Returned to Svc (← links)
- 05000530/LER-1992-001-02, :on 920124,reactor Trip Followed Manual Trip of Mfwp B,Following Receipt of Low Suction Pressure Trip Alarms for Both Mfwps.Caused by Inadequate Original Solder Joint. Instrument Air Valve Replaced and Resoldered (← links)
- 05000530/LER-1991-008-01, :on 911114,lighting Induced Electrical Fault on a Phase Main Transformer Caused Generator Trip,Turbine Trip & Reactor Power Cutback.Caused by Problem W/Calculator Software.Lightning Protection Sys Evaluated (← links)
- 05000530/LER-1991-010-01, :on 911115,mobile Crane Came in Contact W/ Energized 13.8 Kv Power Line,Resulting in Deenergization of Offsite Power.Caused by Personnel Error.Crane Operating Engineer Site Access Revoked (← links)
- 05000530/LER-1991-011-01, :on 911104,auxiliary Feedwater Flow Transmitters Equalizing Valve Found Improperly Aligned. Cause Not Determined.Valves Aligned Properly (← links)
- 05000530/LER-1991-003, :on 910619,spurious Containment Spray Sys Actuation Occurred During Performance of Monthly Esfs Surveillance Testing of Pps.Caused by Incorrect Assembly of Esfas.Pushbutton Test Switch Replaced (← links)
- 05000530/LER-1991-004-01, :on 910713,spurious Train a Containment Purge Isolation Actuation Signal Initiated on balance-of-plant Esfas,Resulting in Spike of Monitor RU-37.Caused by Failure of Detector Tube.Technicians Briefed (← links)
- 05000530/LER-1990-005-02, :on 900803,while Performing Root Cause Investigation of Failure of Economizer Feedwater Isolation Valve,Concluded That Anchor/Darling 4-way Valve Rebuild Kits Contained Nonqualified Backup Ring Matl (← links)
- 05000530/LER-1990-004, :on 900414,reactor Trip Occurred.Caused by Control Element Assembly Dropping Into Core Due to Optical Isolator Card Malfunction.Card Replaced & Retested (← links)
- 05000530/LER-1990-002, :on 900222,locked High Radiation Area Gate Found Open & Unguarded.Caused by Personnel Error.Radiation Protection Personnel Verified Room Unoccupied & Secured Gate Per Approved Procedure (← links)
- 05000530/LER-1989-012, Informs That LER 89-012 for Unit 3 Not Used,Per NUREG-1022 (← links)
- 05000530/LER-1990-001, :on 900127,spurious Train B Containment Purge Isolation Actuation Signal Initiated on Balance of Plant Esfas.Caused by Spiking of Radiation Monitor RU-38 Due to Malfunctioning Central Processing Unit (← links)
- 05000530/LER-1989-001, :on 890303,electrical Grid Disturbance Resulted in Main Generator Output Breakers Opening,Resulting in Reactor Power Cutback & Steam Bypass Control Sys Actuation. Caused by Malfunction in Subj Control Sys (← links)
- 05000530/LER-1989-004, :on 890104,exhaust Rocker Arm for Cylinder 8L Failed,Resulting in Emergency Diesel Generator Trip.Caused by Crack in Rocker Arm.On 890107,ESF Actuation Occurred.Also Reported Per Part 21.Rocker Arm Redesigned (← links)
- 05000530/LER-1989-013-01, :on 890926,control Room Operator Inadvertently Turned Wrong Handswitch During post-maint Testing Which Resulted in ESFAS Actuation.Caused by Personnel Error. Disciplinary Measures Taken (← links)
- 05000530/LER-1989-010-01, :on 890923,discovered That Surveillance Testing Interval for Radioactive Effluent Monitoring Sys Exceeded. Caused by Personnel Error.Human Performance Evaluation Sys Analysis of Error Initiated (← links)
- 05000530/LER-1989-005-01, :on 890628,sample Flow Rate for Vent low-range Radioactive Effluent Monitor Below Low Flow Alarm Setpoint, Rendering Monitor Inoperable.Caused by Loose Set Screw on Coupling.Set Screw on Sample Pump Tightened (← links)
- 05000530/LER-1989-001-01, :on 890303,electrical Grid Disturbance Resulted in Opening Main Generator Output Breakers,Low Pressure Reactor Trip & Turbine Trip.Caused by Steam Bypass Control Sys Malfunction.Plant Stabilized (← links)
- 05000530/LER-1989-003, :on 890218,control Room Essential Filtration Actuation Signal on Train B Actuated.Caused by Spurious Trip from Control Room Ventilation Intake Radiation Monitor RU-30 & Detector.Detector Replaced (← links)
- 05000530/LER-1989-009-01, :on 890728,inadvertent Train a Fuel Bldg Essential Ventilation Actuation Signal Initiated on Balance of Plant ESF Actuation Sys.Caused by Personnel Error. Individual Counseled (← links)
- 05000530/LER-1989-005-02, :on 890628,discovered That Sample Flow Rate for Plant Vent Low Range Radioactive Effluent Monitor Below Alarm Setpoint.Caused by Loose Set Coupling Screw. Pre-planned Alternate Sampling Program Begun (← links)
- 05000530/LER-1989-007, :on 890503,deficiencies Found During Installation of Relays Constituted Reportable Condition. Caused by Inadequate Methodology of Applying Epoxy Matl to Relay Coils.Relays Replaced.Part 21 Related (← links)
- 05000530/LER-1988-008, :on 890220,determined That Excessive Moisture Condensation Occasionally Discovered in Unit Resulting in Invalid Sample Results.Caused by Cooling of High Humidity Sample Stream.Resistance Heating Installed (← links)
- 05000530/LER-1989-002, :on 890203,discovered That Detector Bypass Valve Installed Backwards in Plant Vent Sys Low Range Radioactive Gaseous Effluent Monitor.Cause Not Determined. Valve Properly Installed & Monitors Inspected (← links)
- 05000530/LER-1989-001-02, :on 890303,electrical Grid Disturbance Resulted in Main Generator Output Breakers Opening.Caused by Malfunction in Steam Bypass Control Sys.Operations Personnel Stabilized Plant (← links)
- 05000530/LER-1988-008-02, :on 890220,determined That Excessive Moisture Condensation Occasionally Discovered in Unit Resulted in Invalid Sample Results.Caused by Cooling of High Humidity Sample Stream.Temporary Heat Trace Installed (← links)
- 05000530/LER-1988-005-01, :on 880908,technician Entered Locked High Radiation Area W/O Prior Approval of Radiation Protection Personnel.Caused by Personnel Error.Technician Denied Access to Controlled Area Pending Further Training (← links)
- 05000530/LER-1988-005-02, :on 880908,maint Dept Technician Reported Unauthorized Entry Into Locked High Radiation Area on 880912.Caused by Personnel Error.Technician Counseled, Disciplined & Provided W/Addl Training (← links)
- 05000530/LER-1988-002, :on 880109,ASME Surveillance Interval Exceeded for Containment Isolation Valve.Caused by Personnel Error. Individual Will Receive Appropriate Counseling &/Or Disciplinary Action (← links)
- 05000530/LER-1988-004-02, :on 880406,loss of Power Event Occurred Which Resulted in Train B ESF Load Sequencer Sys Actuation.Caused by Error in Work Document Being Utilized to Replace Current Transformer.Maint Testing Stopped (← links)
- 05000530/LER-1988-001-02, :on 880204,discovered Isolation Valve in Containment Pressure Transmitter Sensing Line Shut.Cause Not Determined.Pressure Transmitter Properly Aligned & Returned to Svc (← links)
- 05000530/LER-1987-004-02, :on 871217,w/reactor at 50% Test Plateau During Power Ascension Testing,Reactor Trip Occurred.Caused by Malfunctioning Logic Sequencer Card in Control Element Drive Mechanism Control Sys.Card Replaced (← links)
- 05000530/LER-1987-005-02, :on 871030,while Unit in Mode 3,main Steam Isolation Sys Automatically Actuated.Caused by Faulty Logic Card for MSIV-170.Faulty Logic Card Replaced (← links)
- 05000530/LER-1987-003-02, :on 870929,condition Identified That,If Not Corrected,Could Have Resulted in Improper Operation of Two Shutdown Cooling Isolation Valves in Redundant Trains.Caused by Vendor Error.Bolting Replaced (← links)
- 05000530/LER-1987-002, :on 870615,control Room Essential Filtration & Containment Purge Isolation Actuation Signals Received on Both Channels of Balance of Plant Esfas.Caused by Calibr of Static Transfer Switch.Switch Recalibr (← links)
- 05000530/LER-1989-011-01, :on 891206,discovered That Quarterly ASME Surveillance Testing on Train a of Air Start Sys Check Valve for Train B Emergency Diesel Generator Not Performed.Caused by Insufficient Controls.Procedure Revised (← links)
- 05000530/LER-1987-001-02, :on 870328,while Preparing to Enter Mode 6, Control Room Essential Filtration Actuation Signals & Containment Purge Isolation Actuation Signals Received.Cause Under Investigation (← links)
- 05000530/LER-1916-002-01, Regarding Emergency Diesel Generator Failure Resulting in a Condition Prohibited by Technical Specifications (← links)
- 05000530/LER-2015-001, Regarding Leakage from Reactor Coolant Pump 2A Suction Pipe Instrument Nozzle (← links)
- 05000530/LER-2016-001, Regarding Control Room Essential Filtration System Air Filtration Unit Failure Resulting in a Condition Prohibited by Technical Specifications (← links)
- 05000530/LER-2015-004, Regarding Condition Prohibited by Technical Specifications 3.0.4 and 3.7.2 Due to an Inoperable Main Steam Isolation Valve (← links)
- 05000530/LER-2015-003, Regarding Damaged High Pressure Safety Injection Pump Motor Journal Bearing (← links)
- 05000530/LER-2015-002, Regarding Condition Prohibited by Technical Specification 3.0.4 Due to an Inoperable Atmospheric Dump Valve (Adv) (← links)
- 05000530/LER-2013-002, Condition Prohibited by Technical Specifications During Dropped Control Element Assembly Recovery (← links)
- 05000530/LER-2013-001, Regarding Leakage on Reactor Vessel Bottom-Mounted Instrumentation Nozzle 3 (← links)
- 05000530/LER-2012-001, Regarding Manual Reactor Trip During Low Power Physics Testing (← links)
- 05000530/LER-2011-001, For Palo Verde, Unit 3, Regarding Reactor Trip Due to Failed Open Main Feedwater Pump a Minimum Flow Recirculation Valve (← links)
- 05000530/LER-2010-003, Regarding Essential Cooling Water System Train a Inoperable Due to Degraded Room Air Handling Unit (← links)
- 05000530/LER-2010-002, Condition Prohibited by Technical Specification Resulting from Containment Spray Nozzle Obstruction (← links)
- 05000530/LER-2009-001, Regarding Manual Reactor Trip Due to a Loss of Instrument Air to the Containment Building (← links)
- 05000530/LER-2008-002, Regarding Manual Reactor Trip Due to High Main Turbine Vibrations During Unit Shutdown (← links)
- 05000530/LER-2008-001, From Palo Verde, Unit 3, Regarding Manual Reactor Trip When Removing a Degraded CEDM MG Set from Service (← links)
- 05000530/LER-2007-001, Condition Prohibited by Technical Specification Resulting from Containment Spray Nozzle Blockage (← links)
- 05000530/LER-2006-007, Regarding Manual Reactor Trip Due to Degrading Condenser Vacuum and Condensate Flow (← links)
- 05000530/LER-2006-006, Regarding Voluntary LER for Failure of Emergency Diesel Generator to Attain Required Voltage Due to Relay Contactor (← links)
- 05000530/LER-2006-005, Re Manual Reactor Trip Due to Loss of Main Feedwater (← links)
- 05000530/LER-2006-004, Regarding Emergency Diesel Generator Actuation on Loss of Power to a Train 4.16KV Bus (← links)
- 05000530/LER-2006-003, Regarding Loss of Power to One Class Bus During Testing Due to Human Error (← links)
- 05000530/LER-2006-002, Regarding Automatic Reactor Protection System Actuation Due to an Invalid Control Element Assembly Calculator Penalty Factor (← links)
- 05000530/LER-2004-002-01, 1 for Palo Verde, Unit 3 Regarding Main Turbine Control System Malfunction Results in Automatic Reactor Trip on Low DNBR (← links)
- 05000530/LER-2006-001, Regarding Two Independent Trains of Auxiliary Feedwater Inoperable (← links)
- 05000530/LER-2004-002, Regarding an Automatic Reactor Trip on Low DNBR Following a Main Turbine Control System Malfunction (← links)
- 05000530/LER-2004-001, Re RCS Pressure Boundary Leakage Caused by Degraded Alloy 600 Component (← links)
- 05000530/LER-2003-004, Reactor Trip with Loss of Forced Circulation Due to an Electrical Grid Disturbance (← links)
- 05000530/LER-2003-003, Regarding Technical Specification Violation for Failure to Calibrate Nuclear Instrumentation (← links)
- 05000530/LER-2003-002, Re RCS Pressure Boundary Leakage Caused by Degraded Inconel Alloy 600 Components (← links)
- 05000530/LER-2003-001, Regarding Main Steam Safety Valve as Found Lift Pressures Outside of TS Limits (← links)
- 05000530/LER-2002-001, Re Technical Specification Violation Due to Incorrect Constant Entered in Core Operating Limit Supervisory System (← links)
- 05000529/LER-2021-002-01, Reactor Trip During Plant Protection System Surveillance Testing (← links)
- 05000528/LER-2021-001, Emergency Diesel Generator Actuation on Loss of Offsite Power to Class 4.16 Kv Bus (← links)
- 05000529/LER-2021-002, Reactor Trip During Plant Protection System Surveillance Testing (← links)
- 05000529/LER-2021-001, Automatic Actuation of the Reactor Protection System Resulting from a Loss of Reactor Coolant Pumps (← links)