Pages that link to "05000323/LER-2013-001, Regarding Valid EDG 2-1 Start Signal Caused by a Loss of 4KV Class 1E Bus G"

The following pages link to 05000323/LER-2013-001, Regarding Valid EDG 2-1 Start Signal Caused by a Loss of 4KV Class 1E Bus G:

Displayed 25 items.

• 05000323/LER-2013-001 (redirect page) ‎ (← links)
  • ENS 48796 ‎ (← links)
  • 05000323/LER-2010-002 ‎ (← links)
  • 05000323/LER-2010-001 ‎ (← links)
  • 05000323/LER-2002-001 ‎ (← links)
  • 05000323/LER-2001-004 ‎ (← links)
  • 05000323/LER-2001-003 ‎ (← links)
  • 05000323/LER-2001-002 ‎ (← links)
  • 05000323/LER-2001-001 ‎ (← links)
  • DCL-13-047, LER 13-001-00 for Diablo Canyon Power Plant, Unit 2, Regarding Valid EDG 2-1 Start Signal Caused by a Loss of 4KV Class 1E Bus G (redirect page) ‎ (← links)
    • DCL-13-047 (redirect page) ‎ (← links)
  • 05000323/LER-1985-027, Forwards LER 85-027-00 Re Missed Surveillance on Valve FCV-678 Due to Preventive Maint & Test Schedular Sys File Being Updated in Error.Util Reviewed Surveillance Program Improvement Action Plan at 860425 Mgt Meeting W/Nrc ‎ (← links)
  • 05000323/LER-2024-001, LCO 3.0.3 Completion Time Limits ‎ (← links)
  • 05000323/LER-2022-001, Reactor Coolant System Pressure Boundary Degradation ‎ (← links)
  • 05000323/LER-2021-002, Manual Reactor Trip Due to Increased Water Level in a Feedwater Heater ‎ (← links)
  • 05000323/LER-2021-001, Emergency Diesel Generator Declared Inoperable Due to Low Frequency Condition Discovery During Routine Surveillance ‎ (← links)
  • 05000323/LER-2020-002, Manual Reactor Trip Due to Increased Main Generator Hydrogen Usage ‎ (← links)
  • 05000323/LER-1989-001, :on 890117,action B of Tech Spec 3.7.1.2, Auxiliary Feedwater Sys, Was Exceeded.Caused by Personnel Misunderstanding of Design Basis Operability Requirements of Steam Driven Pump.Operations Summary Issued ‎ (← links)
  • 05000323/LER-1986-025, :on 861002,diesel Generator 2-2 Automatically Started.Caused When Electrician Inadvertently Grounded Terminal in Component Cooling Water Pump Breaker Cubicle. Event Will Be Reviewed W/Personnel ‎ (← links)
  • 05000323/LER-1986-024, :on 860918,reactor Trip Breaker a Opened W/O Reactor Trip Signal.Caused by Electrician Unintentionally Jarring Another Relay or Tripping Feature in Trip Breaker Cubicle.Wire Lug Replaced ‎ (← links)
  • 05000323/LER-1986-023, :on 860918,automatic Reactor Trip & Subsequent Turbine Trip Occurred.Caused by Main Feedwater Pump 2-2 Reducing to Min Speed While Plant Technicians Made Adjustments to Lovejoy Controller ‎ (← links)
  • 05000323/LER-1986-002-01, :on 860117,instrument Ac Panel Py 2-1 Inadvertently Transferred to Backup Power.Caused by Unlicensed Operator Error.Operator Counseled & Procedures Revised ‎ (← links)
  • 05000323/LER-1986-021, :on 860709,automatic Reactor Trip & Subsequent Turbine Trip Occurred Due to Low Steam Generator Level Coincident W/Steam Flow Mismatch.Caused by Overspeed Trip of Pump.New Speed Control Sys Installed ‎ (← links)
  • 05000323/LER-1986-019, :on 860703,while Separating Unit from Transmission Sys for Testing,Rapid Loss of Main Condenser Vacuum Occurred Causing Reactor Trip.Caused by Improperly Positioned Valves.Valves Repositioned ‎ (← links)
  • 05000323/LER-1985-026, :on 850507 & 860210,Mode 6 Entered W/O Performing Required Surveillance Test & Discovered That Test Line Not Included in Procedures,Respectively.Caused by Inadequate Procedure Review ‎ (← links)
  • 05000323/LER-1986-014, :on 860506,while in Mode 1,diesel Generator 2-1 Started on Bus Undervoltage & Abnormally Loaded Onto 4 Kv Bus G.Caused by Jumper Incorrectly Terminating in 4 Kv Bus G Auto Transfer Scheme ‎ (← links)
  • 05000323/LER-1986-006, :on 860220 & 26,w/axial Flux Difference (Afd) Monitor Alarm Out of Svc,Indicated Afd of Operable ex-core Channel Not Monitored & Logged Per Tech Spec Requirement 4.2.1.2.1.Caused by Personnel Error ‎ (← links)
  • 05000323/LER-1986-026, :on 861124,allowed Outage Time for Auxiliary Feedwater Flow Transmitter Exceeded Tech Specs.On 861128, Discovered That Flow Transmitter Inoperative on 861122. Caused by Personnel Error.Summaries Issued ‎ (← links)
  • 05000323/LER-1986-022, :on 860824,axial Flux Difference (Afd) Outside Target Band for Greater than 15 Minutes,Violating Tech Spec 3.2.1.1,Action A.Caused by Personnel Error.Afd Back on Target Band at Time of Discovery ‎ (← links)
  • 05000323/LER-1985-027-01, :on 851106,surveillance Test Interval of Tech Specs 4.0.5,4.6.3.3 & 4.0.2 Exceeded When Full Stroke Test Not Performed on Valve FCV-678.Caused by Personnel Error. Personnel Counseled ‎ (← links)
  • 05000323/LER-1986-020, :on 860705,reactor & Turbine Trip Occurred. Caused by hi-hi Water Level in Steam Generator SG 2-1 & Inability of Operators to Respond Quickly to Feedwater Flow ‎ (← links)
  • 05000323/LER-1986-018, :on 860627,reactor Trip Breakers Actuated When Power Fuse Removed from Intermediate nuclear-range Instrument.Caused by Technician Performing Procedural Step Out of Sequence.Technician Counseled ‎ (← links)
  • 05000323/LER-1986-027, :on 861213,time Limit of Tech Spec 4.11.2.1.2, Table 4.11-2,Item 4 (Continuous Particulate Sample),Exceeded for Plant Vent Particulate Sample.Caused by Personnel Error. Personnel Counseled & Tailboard Meeting Held ‎ (← links)
  • 05000323/LER-1986-011-03, :on 860330,manual Unit Trip Initiated Due to Condenser Tube Failure.Caused by Condenser Steam Dump Valve Malfunctioning Due to Mechanical Problem Bending Positioner Linkage on Valve.Valve Repair Underway ‎ (← links)
  • 05000323/LER-1986-017, :on 860627,diesel Generators 1-3 & 2-1 Autostarted on Bus Undervoltage During Switching of Auxiliary Power Sys for Maint.Caused by Failure to Update Electrical Switching Procedures ‎ (← links)
  • 05000323/LER-1986-007, :on 860305,nuclear Instrumentation Sys Negative Rate Reactor Trip Occurred Due to Two Dropped Rods.Caused by Faulty Logic Module in Rod Control Circuitry.Faulty Module Replaced & Plant Stabilized ‎ (← links)
  • 05000323/LER-1985-018, :on 851202,digital Rod Position Indication Sys Experienced Data a Failure & General Warning on Each Control Rod,Resulting in Reactor Trip.Caused by Faulty Dc Logic Power Supply.Power Supply Repaired ‎ (← links)
  • 05000323/LER-1986-015, :on 860502,discovered That 860214 Transition from Mode 5 to Mode 4 Made W/O Current Channel Functional Test on Radiation Monitor.Caused by Personnel Error. Individual Counseled ‎ (← links)
  • 05000323/LER-1986-013, :on 860418,limiting Condition for Operation & Action Statement 2.C of Tech Spec 3.3.1,Table 3.3-1 Not Met When Quadrant Power Tilt Ratio Determination Could Not Be Performed in Time ‎ (← links)
  • 05000323/LER-1986-012, :on 860409,automatic Reactor & Turbine Trip Occurred Due to Low Steam Generator Level Coincident W/Steam Flow/Feed Flow Mismatch.Caused by Failure of Thrust Bearing Detector Probe.Probe Replaced ‎ (← links)
  • 05000323/LER-1986-008, :on 860311,automatic Reactor & Subsequent Turbine Trips Occurred.Caused by Nuclear Instrumentation Sys (Nis) Trip Signal Exceeding Trip Setpoint.Nis Reset in Accordance W/Westinghouse Recommendation ‎ (← links)
  • 05000323/LER-1986-003, :on 860131 & 0209,spreading Room Carbon Dioxide Sys Taken Out of Svc for Maint Activities W/O Posting Continuous Fire Watch.Caused by Personnel Error.Special Training Conducted for Const Personnel ‎ (← links)
  • 05000323/LER-1985-025-01, :on 860113,discovered Sample Line Vent Valves to Containment Hydrogen Analyzer Cell 82 Open & Lines Uncapped.Valves Verified Closed & Lines Capped on 851004. Cause Undetermined.Lines Capped ‎ (← links)
  • 05000323/LER-1985-026-01, :on 850507,plant Entered Mode 6 for First Time W/O Performing Tech Spec Requirement 4.9.4 for Spare Instrument Test Line.Caused by Inadequate Procedure. Procedure Revised ‎ (← links)
  • 05000323/LER-1985-014-01, :on 851005,unit Entered Mode 2 (Hot Shutdown) W/Steam Generator Main Feedwater Isolation Valve FCV-439 Inoperable.Caused by Incorrect Wiring Terminations in Control Sys.Maint Bulletin Issued ‎ (← links)
  • 05000323/LER-1985-011-01, :on 851025,auxiliary Feedwater Steam Supply Line Snubber Inoperability Not Determined Before Exceeding Limiting Condition for Operation.Caused by Miscommunication Between Technician & Engineer.Snubber Replaced ‎ (← links)
  • 05000323/LER-1986-004, :on 860206,inadvertent ESF Actuation of Fuel Handling Bldg Ventilation Sys Occurred.Caused by Improperly Secured Radiation Monitor Connector.Socket Connectors W/ Locking Devices Installed ‎ (← links)
  • 05000323/LER-1986-010, :on 860314,automatic Isolation of Containment Ventilation Sys Occurred.Caused by Momentary Alarm Signal from Gaseous Radiation Monitors.Event Being Studied by Noise Reduction Task Force ‎ (← links)
  • 05000323/LER-1985-019, 0l:on 851127,blown Fuse Discovered on Solenoid Valve SV-306 During post-safety Injection Review.Caused by Incorrect Wiring Change & Personnel Error.Wiring Corrected ‎ (← links)
  • 05000323/LER-1985-017-01, :on 851128,reactor Trip Occurred Due to Steam Flow/Feed Flow Mismatch.Caused by Leak in Condensing Pot of Steam Generator Water Level Transmitter Ref Leg.Exhaustive Testing of Reactor Trip Breaker B Performed ‎ (← links)
  • 05000323/LER-1986-002, :on 860117,RHR Valve 8702 Closed & RHR Pump 2-1 Secured in Response to Ensuing loss-of-flow Alarm.Caused by Unlicensed Operator Error.Valve Reopened.Pump Restarted, Observed for Seal Damage & Declared Operable ‎ (← links)
  • 05000323/LER-1986-005-01, :on 860222,main Turbine & Subsequent Reactor Trip Occurred Due to Generator Loss of Electrical Field Relay Actuation.Caused by Incorrect Polarity.Min Excitation Leads Reversed & Voltage Regulator Passed Test ‎ (← links)
  • 05000323/LER-1985-024-01, :on 851225,automatic Reactor & Turbine Trips Occurred During Full Load Rejection Test.Caused by Slow Response of Steam Dump Control Sys.Sys Modified to Improve Steam Dump Valve Response Time ‎ (← links)
  • 05000323/LER-1985-023-01, :on 850725,unit Entered Hot Shutdown W/O Necessary Surveillance on Some ECCS & Associated Containment Spray Motor Operated Valves.Caused by Personnel Error. Procedure STP V-7B Satisfactorily Performed ‎ (← links)
  • 05000323/LER-1985-022-01, :on 851221,automatic Reactor & Turbine Trips Occurred.Caused by Loose Wiring to Feedwater Regulating Valve Solenoid & Personnel Error Causing Momentary Opening of Connection.Connection Properly Terminated ‎ (← links)
  • 05000323/LER-1985-020-01, :on 851116,discovered That Plant Vent Particulate & Iodine Monitor RE-24 Sample Collection Pump Deenergized.Caused by Switching Off of RE-24 Power Switch. Protective Cover Installed Over Switch ‎ (← links)
  • 05000323/LER-1985-015-01, :on 851109,P-14 signal,hi-hi Steam Generator Level Resulted in Turbine Trip & Subsequent Reactor Trip. Caused by Personnel Error.Addl Training Being Provided to Applicable Operations Personnel ‎ (← links)
  • 05000323/LER-1985-013, :on 851106,during Startup Procedure 43.7, Reactor Tripped on lo-lo Steam Generator Level.Caused by Turbine Interceptor Valves Opening Too slowly.Electro- Hydraulic Control Sys Modified ‎ (← links)
  • 05000323/LER-1985-008-01, :on 850913,while Unit in Cold Shutdown, Automatic Isolation of Containment Ventilation Sys Occurred. Investigation Continuing.Alarm Reset & Gaseous Radiation Monitor Isolation Valves Returned to Position ‎ (← links)
  • 05000323/LER-1985-007-01, :on 850829,reactor Trip on Low Steam Generator Level Coincident W/Steam Flow/Feed Flow Mismatch Occurred. Caused by Personnel Error.Operator Counseled on Significance of Understanding Abnormal Plant Conditions ‎ (← links)
  • 05000323/LER-1985-010-01, :on 851024,turbine & Reactor Tripped Due to High Water Level in Steam Generator.Caused by Inadequate Procedures.Procedures for Operation of Condensate Booster Pumps During Unusual Plant Conditions Revised ‎ (← links)
  • 05000323/LER-1985-006-01, :on 850824,during Startup,Random Failure of Rod Drive Motor Generator Set Relays Resulted in Rod Insertion & Manual Reactor Trip.Caused by Burned Out Coil on Auxiliary Relay & Relay Drift.Relays Replaced ‎ (← links)
  • 05000323/LER-1986-001-01, :on 860102,automatic Reactor & Turbine Trip Occurred Due to lo-lo Steam Generator Water Level.Caused by Main Feedwater Pump Trip During Full Load Rejection Startup Test.Pump Control Oil Sys Flushed ‎ (← links)
  • 05000323/LER-1985-003-02, :on 850809,automatic Isolation of Containment Ventilation Sys Occurred.Caused by Switching of Radiation Monitor Mode Switch to Reset & Back During Troubleshooting. Events Under Study ‎ (← links)
  • 05000323/LER-1985-009-01, :on 851022,generator & Reactor Trip Occurred. Caused by Technician Inadvertently Actuating Current Test Block of Main Generator Differential Relay.Technician Counseled & Instructions Installed on Panel ‎ (← links)
  • 05000323/LER-1985-012-01, :on 851017,review of Completed Surveillance Test Procedure Data Sheet Determined Three Feedwater Control Valves Had Exceeded Closure Time Requirements of Tech Spec Table 3.3-5.Caused by Personnel Error ‎ (← links)
  • 05000323/LER-1985-021-01, :on 851204,spurious Safety Injection Occurred. Caused by Safety Injection Signal Received on Train a of Solid State Protection Sys While Preparing to Investigate 851202 Event.No Corrective Action Required ‎ (← links)
  • 05000323/LER-1985-018-02, :on 851202,spurious Safety Injection Occurred After Initiation of Manual Reactor Trip in Response to Digital Rod Position Indication Sys Data a Failure.Exact Cause Under Investigation ‎ (← links)
  • 05000323/LER-1985-019-01, :on 851127,blown Fuse Discovered on Solenoid Valve SV-306 During post-safety Injection Review.Caused by Wiring Error.Short Cause of Previous Fuse Failures on 850814 & 29.Wiring Error Corrected ‎ (← links)
  • 05000323/LER-1985-016-01, :on 851126 & 1201,automatic Reactor Trips Occurred During 50% Load Rejection Startup Testing.Caused by Steam Dump Control Sys & Feedwater Control Sys Settings Inadequately Adjusted,Respectively ‎ (← links)
  • 05000323/LER-1985-004-02, :on 850816,containment Purge Supply & Exhaust Valves Not Maintained Closed When Solid State Protection Sys Train a Removed from Svc.Caused by Technician & Operator Errors.Procedure Revised ‎ (← links)
  • 05000323/LER-1985-005-02, :on 850815,automatic Isolation of Containment Ventilation Sys Occurred.Caused by Spurious Spike in Containment Gaseous Radiation Monitor RM11.Noise Reduction Task Force Will Investigate Spurious Signals ‎ (← links)
  • 05000323/LER-1985-001-02, :on 850705,automatic Isolation of Containment Ventilation Sys Occurred W/Unit in Mode 5.Caused by Spurious Spike in Vent Gaseous Radiation Monitor RM14A.Alarm Reset. No Corrective Action Identified ‎ (← links)
  • 05000323/LER-2020-001, Shutdown Required by Technical Specifications ‎ (← links)
  • 05000323/LER-1981-002, Interim Deficiency Rept Re Inadequate Design of Sys Contained in Annulus Area of Containment Bldg,Initially Reported 811105.Further Info of Progress Is Identified in Suppls to LER 81-002 ‎ (← links)
  • 05000323/LER-2019-001, Containment Spray Inoperable in Mode 4 ‎ (← links)
  • 05000323/LER-1979-028, Forwards LER 79-028/03L-0 ‎ (← links)
  • 05000323/LER-1979-035, Forwards LER 79-035/03L-0 ‎ (← links)
  • 05000323/LER-2018-001-01, Automatic Reactor Trip of Unit 2 Following a Load Rejection ‎ (← links)
  • 05000323/LER-2018-001, Automatic Reactor Trip of Unit 2 Following a Load Rejection ‎ (← links)
  • 05000323/LER-1917-001, Regarding Relief Valve Leakage Resulting in Inoperable Pressurizer Power Operated Relief Valve ‎ (← links)
  • 05000323/LER-2016-001, Regarding Reactor Trip Breakers Manually Opened During Shutdown Due to a Control Rod Movable Gripper Fuse Failure ‎ (← links)
  • 05000323/LER-2014-002-01, Regarding Unit 2 Plant Shutdown Required by Technical Specifications ‎ (← links)
  • 05000323/LER-2014-001, Regarding Lightning Arrester Failure Resulting in Reactor Trip ‎ (← links)
  • 05000323/LER-2013-005, Regarding Unit 2 Reactor Trip Due to Lightning Arrester Flashover ‎ (← links)
  • 05000323/LER-2013-004, Regarding Technical Specification 3.8.1 Not Met Due to Failed Wire Lug on Emergency Diesel Generator 2-3 ‎ (← links)
  • 05000323/LER-2013-002, Both Source Range Nuclear Instruments Inoperable While in Mode 6 ‎ (← links)
  • 05000323/LER-2013-001, Regarding Valid EDG 2-1 Start Signal Caused by a Loss of 4KV Class 1E Bus G ‎ (← links)
  • 05000323/LER-2012-002, Regarding Coupling Capacitor Voltage Transformer Bushing Failure Causes Reactor Trip ‎ (← links)
  • 05000323/LER-2012-001, Regarding Failure to Meet Emergency Diesel Generator Technical Specifications ‎ (← links)
  • 05000323/LER-2011-001, For Diablo Canyon Regarding Unit 2 Reactor Trip from Loss of Main Feedwater Pump 2-1 ‎ (← links)
  • 05000323/LER-2009-003, Re Containment Sump Recirculation Valve Position Interlock Failure Due to Inadequate Testing ‎ (← links)
  • 05000323/LER-2009-002, Technical Specification 3.7.1 Violation Due to Cracked Valve Spring ‎ (← links)
  • 05000323/LER-2009-001, Regarding Technical Specification 3.0.3 One Hour Exceeded Due to Failure of Group Step Counters ‎ (← links)
  • 05000323/LER-2008-002, Regarding Manual Reactor Trip Due to Pacific Ocean Circulating Water System Debris ‎ (← links)
  • 05000323/LER-2008-001, Regarding Reactor Trip Due to Main Electrical Transformer Failure ‎ (← links)
  • 05000323/LER-2006-004, Regarding Automatic Reactor Trip Due to Circulating Water Pump Surge Capacitor Failure ‎ (← links)
  • 05000323/LER-2006-003, Re Manual Reactor Trip Due to Reactor Coolant Pump High Temperature Indication ‎ (← links)
  • 05000323/LER-2006-002, Re Steam Generator Tube Plugging Due to Stress Corrosion Cracking ‎ (← links)
  • 05000323/LER-2006-001, CFR 21 Notification of a Defective Residual Heat Removal Check Valve ‎ (← links)
  • 05000323/LER-2005-002, Unplanned Emergency Diesel Generator Auto-Start During Testing Due to Personnel Error in Relay Testing ‎ (← links)
  • 05000323/LER-2005-001, TS 3.4.10 Not Met During Pressurizer Safety Valve Surveillance Testing Due to Random Lift Spread ‎ (← links)
  • 05000323/LER-2004-001, Regarding Unplanned Valid Emergency Diesel Generator Auto-start During Phase Sequence Check Due to Personnel Error in Configuring Test Equipment Setup ‎ (← links)
  • 05000323/LER-2003-006, Re Unit 2 Auxiliary Feedwater System Actuation Due to Personnel Error ‎ (← links)
  • 05000323/LER-2003-005, For Diablo Canyon Unit 2, Technical Specification 3.7.5.C Required Shutdown Due to Personnel Error ‎ (← links)
  • 05000323/LER-2003-004, Manual Reactor Trip Due to a Single Random Fuse Failure ‎ (← links)
  • 05000323/LER-2003-003, Technical Specification 3.4.12 Not Met Due to Personnel Error ‎ (← links)
  • 05000323/LER-2003-002, Unanalyzed Condition in Unit Component Cooling Water System Due to Valve Liner Failure ‎ (← links)
  • 05000323/LER-2003-001, From Diablo Canyon Unit 2 Regarding Steam Generator Tube Plugging Due to Stress Corrosion Cracking ‎ (← links)
  • 05000323/LER-2002-004, From Diablo Canyon Regarding Manual Start of Unit 2 AFW Pumps Due to Ocean Debris & High Swells ‎ (← links)
  • 05000323/LER-2002-003, Regarding TS 3.7.7 Not Met Due to Cable Fault ‎ (← links)
  • 05000323/LER-2002-002, Re Manual Reactor Trip Due to Loss of Main Feedwater to Steam Generator ‎ (← links)
• ML17018A440 ‎ (← links)
• ML16341C057 ‎ (← links)
• ML15070A607 ‎ (← links)
• ML13192A354 ‎ (← links)
• ML13120A268 (redirect page) ‎ (← links)
• ML13074A818 ‎ (← links)
• ML13022A013 ‎ (← links)
• DCL-12-124, 10 CFR 54.21 (B) Annual Update to the Diablo Canyon Power Plant License Renewal Application and License Renewal Application Amendment Number 46 ‎ (← links)
• DCL-12-129, Request for Approval of an Alternative to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI Pressure Test Requirements for Class 1 Reactor Vessel Flange Leakoff Lines ‎ (← links)
• 05000275/LER-2013-009-01, Regarding Unanalyzed Condition Affecting Unit 1 Emergency Diesel Generators ‎ (← links)
• 05000275/LER-2013-010, Regarding Two Emergency Diesel Generators Inoperable Due to Operator Error ‎ (← links)
• 05000275/LER-2013-009, Regarding Unanalyzed Condition Affecting Unit 1 Emergency Diesel Generators ‎ (← links)
• 05000275/LER-2013-006-01, Regarding Emergency Diesel Generators Valid Start Signal Due to Loss of Startup Power ‎ (← links)
• 05000275/LER-2013-008, Regarding Technical Specification 3.3.4 Not Met Due to Inoperable Remote Shutdown System Function ‎ (← links)
• 05000275/LER-2013-003-01, Regarding Actuation of Six Emergency Diesel Generators Due to Loss of Offsite Power ‎ (← links)
• 05000275/LER-2013-006, Regarding Emergency Diesel Generators Valid Start Signal Due to Loss of Startup Power ‎ (← links)
• 05000323/LER-2013-005, Regarding Unit 2 Reactor Trip Due to Lightning Arrester Flashover ‎ (← links)
• 05000275/LER-2013-004, Regarding All Three Unit 1 Emergency Diesel Generators Momentarily Inoperable ‎ (← links)
• 05000275/LER-2013-005, Both Trains of Residual Heat Removal Inoperable Due to Circumferential Crack on a Socket Weld ‎ (← links)
• 05000275/LER-2013-003, Regarding Actuation of Six Emergency Diesel Generators Due to Loss of Offsite Power ‎ (← links)
• 05000323/LER-2013-004, Regarding Technical Specification 3.8.1 Not Met Due to Failed Wire Lug on Emergency Diesel Generator 2-3 ‎ (← links)
• 05000323/LER-2013-002, Both Source Range Nuclear Instruments Inoperable While in Mode 6 ‎ (← links)
• DCL-13-046, Response to NRC Request for Additional Information Regarding Request for Approval of an Alternative to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI Pressure Test. ‎ (← links)
• 05000275/LER-2013-001, Noncompliance with TS 3.4.12, Low Temperature Overpressure Protection System Due to Human Error ‎ (← links)