Pages that link to "05000529/LER-2012-001, Regarding Technical Specification LCO 3.1.7 Completion Time Exceeded"
Jump to navigation
Jump to search
The following pages link to 05000529/LER-2012-001, Regarding Technical Specification LCO 3.1.7 Completion Time Exceeded:
Displayed 11 items.
- 05000529/LER-2012-001 (redirect page) (← links)
- 05000529/LER-2015-001, Condition Prohibited by Technical Specification (TS) Limiting Condition for Operation (LCO) 3.3.5, Engineered Safety Features Actuation System (ESFAS) (← links)
- 05000529/LER-2007-004 (← links)
- 05000529/LER-2002-002 (← links)
- 05000529/LER-2001-002 (← links)
- 05000529/LER-2001-001 (← links)
- 05000529/LER-2000-009 (← links)
- 05000529/LER-2000-008 (← links)
- 05000529/LER-2000-007 (← links)
- 05000529/LER-2000-006 (← links)
- 05000529/LER-2000-005 (← links)
- 05000529/LER-2000-004 (← links)
- 05000529/LER-2000-003 (← links)
- 05000529/LER-2000-002 (← links)
- 05000529/LER-2000-001 (← links)
- 05000529/LER-1999-006 (← links)
- 05000529/LER-1999-001 (← links)
- 05000529/LER-1998-004 (← links)
- IR 05000528/2012003 (← links)
- TS-3.1.7 (← links)
- 05000529/LER-1986-008, Corrected Forwarding Ltr to LER 86-008-00,changing Identification Number from ANPP-86646-EEVB/PGN/98.05 to ANPP-36646-EEVB/PGN/98.05 (← links)
- 05000529/LER-2024-001, Valid Specified System Actuations of Unit 2 Train B Emergency Diesel Generator and Train B Auxiliary Feedwater (← links)
- 05000529/LER-2023-001-01, Unit 2 Automatic Reactor Trip on Low Steam Generator Water Level Due to Degraded Feedwater Flow (← links)
- 05000529/LER-2023-001, Regarding Unit 2 Automatic Reactor Trip on Low Steam Generator Water Level Due to Degraded Feedwater Flow (← links)
- 05000529/LER-2022-001, Emergency Diesel Generator Actuation on Loss of Offsite Power to Class 4.16 Kv Buses (← links)
- 05000529/LER-2021-002-01, Reactor Trip During Plant Protection System Surveillance Testing (← 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)
- 05000529/LER-2020-001-01, Reactor Trip on Low Steam Generator Level Signal (← links)
- 05000529/LER-1988-016-01, Has Been Canceled.Resolution of LERs Missing from Lertrk/Scss/Dcs Discussed (← links)
- 05000529/LER-1986-046-01, :on 860922,safety Injection Actuation Signal Automatically Actuated.Caused by Malfunctioning of Channel B Manual Actuation Handswitch.Faulty Handswitch Replaced (← links)
- 05000529/LER-1986-017-01, :on 860911,actuation of Reactor Protection Sys Initiated Automatic Reactor Trip.Caused by Effects of Reactor Coolant Pump Speed Transient on Core Protection Calculators (Cpc).Cpc Software Updated (← links)
- 05000529/LER-1986-031-01, :on 860826,hourly Fire Watch of 100 Ft Elevation in Auxiliary Bldg Not Performed.Caused by Potential High Noble Gas Concentration & Cognitive Personnel Error.Fire Watch Personnel Counseled (← links)
- 05000529/LER-1986-028-01, :on 860822,hourly Fire Watch Not Performed Per Tech Spec 3.7.12,Action Statement A.Caused by Cognitive Personnel Error.Fire Watch Established (← links)
- 05000529/LER-1986-026-01, :on 860825,reactor Trip Occurred,Initiated by Main Turbine Generator Trip.Caused by Loss of Generator Excitation Due to Transducer Calibr at Unnecessarily Low Value.Transducer Recalibr (← links)
- 05000529/LER-1986-033-01, :on 860828,main Generator Field Excitation Increased Causing Main Generator to Trip on Overexcitation. Caused by Reversal of Generator Current Transformer Polarity During Mfg.Current Transformer Wiring Changed (← links)
- 05000529/LER-1986-030-01, :on 860826,Train B Containment Purge Actuation Signal Generated by Esfas.Caused by Malfunction of Output Relay in Power Access Purge Area Monitor.Output Relay Replaced & Monitor Retested (← links)
- 05000529/LER-1986-021-01, :on 860806,discovered That Train B LPSI Pump Header Discharge Throttle Valve Not Adjusted to Proper Setting.Caused by Personnel Error on 860717 Due to Unclear Procedure.Separate Procedures in Effect (← links)
- 05000529/LER-1986-009, :on 860219,during Cold Shutdown,Train B Main Steam Isolation Signal Actuation Occurred,Actuating Esf. Caused by Incorrect Amperage fuse.Eight-amp Fuse Installed in Affected Path (← links)
- 05000529/LER-1986-032-01, :on 861013,discovered That Two Consecutive Hourly Fire Watch Rounds Not Performed on 861002.Caused by Personnel Error.Employee Removed from Further Fire Watch Duties (← links)
- 05000529/LER-1986-023-01, :on 861224,reactor Trip Initiated.Caused by Intermittent Ground on 125-volt Dc Bus.Ground Removed & Power Supply Replaced.Further Evaluations to Determine Root Cause of Degraded Voltage Condition Underway (← links)
- 05000529/LER-1987-001-01, :on 870208,control Room Ventilation Intake Noble Gas Monitors RU-29 & RU-30 Discovered Inoperable W/O Appropriate Action Statement Being Entered within Required Time Frame.Caused by Personnel Error (← links)
- 05000529/LER-1986-019-02, :on 860729,determined That Gas Grab Samples Not Taken & Analyzed within Required Time Limits Between 860721 & 860728.Caused by Personnel Miscommunication.Concurrent sign-offs Will Be Used (← links)
- 05000529/LER-1986-002, :on 860220,during Cold Shutdown,Train a Main Steam Isolation Signal Occurred,Actuating Esf.Caused by Incorrect Amperage fuse.Eight-amp Fuse Installed in Affected Path (← links)
- 05000529/LER-1986-041-01, :on 860701,unidentified Leakage Greater than 1 Gpm Detected in Rcs.Caused by Seal Leakage Due to Strainer Flushing Techniques Previously Employed.Flushing Procedure Modified (← links)
- 05000529/LER-1986-046, :on 860922,inadvertent Safety Injection Actuation Signal Automatically Actuated.Caused When One Channel of Manual Trip Path Test Actuated & Second Channel Handswitch Malfunctioned.Handswitch Replaced (← links)
- 05000529/LER-1986-024-01, :on 860514,determined That Several Steam Generator Snubbers Inoperable Since 860310 Due to Lack of Visual Exam.Caused by Personnel Error.Event Reviewed W/ Licensed Operators & Supervisors (← links)
- 05000529/LER-1986-039-01, :on 860903,control Room Essential Filtration Actuation Signal (CREFAS) Generated After CREFAS Module Removed from Bypass Before All Trip Inputs Cleared. Appropriate Disciplinary Action Taken (← links)
- 05000529/LER-1986-015-01, :on 860404,automatic Actuation of All Four Channels of Reactor Protection Sys Occurred Due to Low RCS Flow Through Steam Generator 2.Strainer Flushed & Seal Injection Flow Restored (← links)
- 05000529/LER-1986-022-01, :on 860814,discovered That HPSI Valve Declared Operable Based Upon Completion of Superseded Retest Utilizing Incorrect Acceptance Criteria.Caused by Personnel Error.Personnel Counseled (← links)
- 05000529/LER-1986-038-01, :on 861227,two MSIVs Declared Inoperable Due to Low Hydraulic Accumulator Pressure.Caused by Control Room Operator Using Wrong Handswitches to Open Valves.Personnel Counseled (← links)
- 05000529/LER-1986-037-01, :on 860626,main Steam Line Isolation Signal Actuated Due to Steam Generator 1 Level Swell.Caused by Cognitive Operator Error.Operator Counseled (← links)
- 05000529/LER-1986-036-01, :on 860620,part Length Control Element Assembly Dropped & Not Retrieved within Tech Spec 3.1.3.1 Time Constraints,Necessitating Plant Shutdown.Drop Caused by Faulty Timer Card.Card Replaced (← links)
- 05000529/LER-1986-042-01, :on 861126,during Routine Review of Active Surveillance Tests,Discovered That Max Surveillance Interval Exceeded for Portion of ESFAS Train a Subgroup Relay Monthly Functional Test.Caused by Personnel Error (← links)
- 05000529/LER-1986-047-01, :on 860725,reactor Trip Occurred Due to Core Protection Generated High Local Power Density Trip.Caused by Invalid Floating Point Fault in Core Protection Calculator Channel C.Resolution of Cause Continuing (← links)
- 05000529/LER-1986-027-01, :on 860531,turbine Trip Caused Actuation of Reactor Protection Sys,Initiating Reactor Trip.Caused by Personnel Error Due to Inadequate Procedures.Plant Operating Procedures Revised (← links)
- 05000529/LER-1986-045, :on 860715,Trains a & B of Control Room Essential Filtration Sys Actuated.Caused by Personnel Error. Operators Reminded of Importance of Proper Light Bulb Installation (← links)
- 05000529/LER-1986-025-02, :on 860525,automatic Reactor Trip Occurred Due to Low Level Condition in Steam Generator.Caused by Personnel Error.Temporary Mod Implemented to Reduce Refill Flow Demand Signal (← links)
- 05000529/LER-1999-002, :on 990318,discovered MSSV Lift Pressures That Were Outside of TS Limits.Caused by Valve Disc Bonding with Nozzle Seat or Setpoint Drift.Affected Valves Were Adjusted, retested,refurbished,re-certified &/Or Returned to Svc (← links)
- 05000529/LER-1986-048, :on 860717,safety Injection Tanks (SIT) Inoperable Due to Wide Range Level Exceeding High Level Limit.Caused by Personnel Error.Order Stating Importance of SIT Level Monitoring During Heatup Issued (← links)
- 05000529/LER-1986-018-01, :on 860718,Tech Spec 3.0.3 Entered Due to Three Inoperable Charging Pumps.Charging Pumps a & B Taken Out of Svc for Repairs,Causing Pump E Gas Binding.Operations & Preventive Maint Procedures Revised (← links)
- 05000529/LER-1986-043-01, :on 860706,inadvertent ESF Sys Actuation Occurred During Performance of Surveillance Test.Caused by Personnel Error.Technicians Counseled & Appropriate Disciplinary Action Taken (← links)
- 05000529/LER-1986-040-01, :on 860701,Limiting Condition for Operation 3.0.3 Entered When Both Containment Spray Pumps Rendered Inoperable Due to Lack of Required Surveillance Tests.Caused by Personnel Error.Test sign-off Modified (← links)
- 05000529/LER-1986-014, :on 860325,during Plant Protection Sys Monthly Functional Test,Main Steam Isolation Sys Actuation on Trains a & B Occurred.Caused by Technicians Not Adhering to Procedural Instructions.Technicians Counseled (← links)
- 05000529/LER-1986-013-01, :on 860324,no Initial Surveillance Testing Performed for Two Containment Penetration Conductor Overcurrent Protective Devices.Caused by Personnel Error. Devices Tested (← links)
- 05000529/LER-1986-035-01, :on 860611,Surveillance Test 42ST-2ZZ23 Not Performed within Time Interval Specified by Tech Spec. Caused by Personnel Error.Shift Supervisor Counseled.Change to Procedure Will Be Initiated (← links)
- 05000529/LER-1986-034-01, :on 860610,reactor Protection Sys Initiated Automatic Reactor Trip Due to High Pressurizer Pressure Following Unanticipated Main Turbine Trip.Caused by Momentary Drop in 24-volt Power Supply (← links)
- 05000529/LER-1986-007-01, :on 860227,discovered That Surveillance Test Procedure Not Performed within Required Time Interval.Caused by Inadequate Procedures.Form Notifying Control Room Personnel of Procedure Changes Put Into Effect (← links)
- 05000529/LER-1986-011-01, :on 860429,w/unit in Hot Standby,Both balance- of-plant/ESFAS Trains Determined Inoperable.Caused by Insufficient Length of Pins in ESFAS Module Pin Connectors. Pins Replaced (← links)
- 05000529/LER-1986-016-01, :on 860416,pressurized Heaters Operated in Condition Contrary to Tech Specs.Caused by Personnel & Procedural Error.Improper Amperage Calculation Formula Corrected (← links)
- 05000529/LER-1986-010-01, :on 860415,discovered That Local Leak Rate Test Not Performed on Containment Isolation Valve.Caused by Personnel Error.Local Leak Rate Test Performed on 860415 & Valve Declared Operable (← links)
- 05000529/LER-1986-049-01, :on 860923,automatic Reactor Protection Sys Actuation Initiated Reactor Trip Due to Low Level in Steam Generator 1.Caused by Inadequate Operating Procedure. Operating Procedures Revised (← links)
- 05000529/LER-1986-008-01, :on 860423,main Steam Isolation Sys Actuation Occurred in Trains a & B During Plant Protection Sys Monthly Functional Test.Caused by Personnel Failure to Follow Procedure.Technicians Counseled & Disciplined (← links)
- 05000529/LER-1986-002-01, :on 860220,during Cold Shutdown,Train a Main Steam Isolation Sys Actuation Occurred.Caused by Use of Undersized Fuse in 2-4 Logic Trip path.Eight-amp Fuse Installed in Affected Path (← links)
- 05000529/LER-1986-009-01, :on 860219,main Steam Isolation Sys Actuation Occurred.Caused by Application of Incorrect Amperage Fuse. Fuse Replaced.Investigation to Determine Why Wrong Fuse Installed Undertaken (← links)
- 05000529/LER-1986-003, :on 860122,logarithmic Power Level Channel Check Not Completed During Surveillance Test.Caused by Operator Error.Personnel Counseled on Following Procedures. Technical Advisors Now Reviewing Tests (← links)
- 05000529/LER-1986-004, :on 860124,inadvertent Actuation of Containment Purge Isolation Actuation Signal & Control Room Essential Filtration Actuation Signal Occurred.Caused by Personnel Error.Technicians Will Attend Briefing (← links)
- 05000529/LER-1985-006-01, :on 851231,while in Mode 6,containment Purge Isolation Signal & Control Room Emergency Filtration Actuation Signal Received on Both Channels.Caused by Improper Reset by Operator.Operator Counseled (← links)
- 05000529/LER-1986-006-01, :on 860208,containment Purge Isolation & Control Room Essential Filtration Actuation Signals Actuated on Both Channels.Caused by Failure of Technician to Fully Analyze Effects of Actions Prior to Beginning (← links)
- 05000529/LER-1986-005-01, :on 860130,control Room Essential Filtration Actuation Occurred Due to Train a Instrument & Control Power Failure.Caused by Inadequate Control of Mod to Vital Power Inverter.Inverters Inspected (← links)
- 05000529/LER-1986-001, :on 860103,source Range Monitor Channel Checks Not Performed within Max Allowable Time.Caused by Failure of Operator to Perform Test on Schedule.Step Added to Procedure to Initiate Test in Mode 6 (← links)
- 05000529/LER-1985-004-01, :on 851218,spurious Automatic ESF Actuation Initiated Due to Noise Spiking on Control Room Ventilation Intake Noble Gas Radiation Monitor.Caused by Noise from Unused Pair of Contacts on Radiation Monitor (← links)
- 05000529/LER-1985-001-01, :on 851219,spurious Automatic Actuation of ESF Initiated.Caused by Electrical Noise Spiking on Control Room Ventilation Intake Noble Gas Radiation Monitor.Hardware Changes Made to Monitors (← links)
- 05000529/LER-2020-001, Reactor Trip on Low Steam Generator Level Signal (← links)
- 05000529/LER-1990-003-01, Revised Page 7 to LER 90-003-01 (← links)
- 05000529/LER-2019-001, Automatic Actuation of the Reactor Protection System Resulting from a Loss of Reactor Coolant Pumps (← links)
- 05000529/LER-2018-001, Reactor Trip Due to Dropped Control Element Assembly (← links)
- 05000529/LER-1999-005, :on 990618,RT on Low DNBR Was Noted.Caused by Hardware Induced Calculation Error.Cr Operator Was Taken to Place Reactor in Stable Condition IAW Appropriate Operating Procedure (← links)
- 05000529/LER-1999-004, :on 990408,PSV Lift Pressures Were Outside of TS Limits.Caused by Lift Pressure Setpoint Drift.Psvs Have Been Tested,Disassembled,Inspected,Reassembled & Certified at Wyle Labs (← links)
- 05000529/LER-1999-001-01, :on 990103,TS Violation for Power Dependent Insertion Limit Alarm Being Inoperable.Caused by Personnel Error.Revised Procedure to Clarify How Computer Point Is to Be Returned to Scan Mode.With (← links)
- 05000529/LER-1998-003, :on 980113,discovered That One Channel of RWT Level Sys Had Failed High.Caused by Water Intrusion Into Electrical Termination Pull Box.Weep Holes Were Drilled Into Bottoms of Pull Boxes Nearest Level Transmitters (← links)
- 05000529/LER-1998-003-01, Forwards LER 98-003-01,per 10CFR50.73.Revised LER Provides Cause & Corrective Action for Delay in Bypassing Failed Instrument Used in PPS (← links)
- 05000529/LER-1998-004-01, :on 980630,personnel Discovered That Pressure Safety Valve Had Not Received Periodic Set Pressure Test for ASME Class 1 Pressure Safety Valve.Caused by Personnel Error.Pressure Safety Valve Reviewed (← links)
- 05000529/LER-1998-002, Forwards LER 98-002-00 Prepared & Submitted,Per 10CFR50.73. LER Repts TS Violation Due to Improperly Performed Shiftly Channel Checked for Core Protection Calculators Following CPC Data Link Failure (← links)
- 05000529/LER-1998-001-01, :on 980301,surveillance Test Deficiency Found During Qaa Leads to TS 3.0.3/4.0.3 Entry.Caused by Personnel Error.Personnel Responsible for Inadequately Performed SR Were Coached (← links)
- 05000529/LER-1998-001, Forwards LER 98-001-00,which Describes TS Violation Due to Exceeding Specified Surveillance Interval Including Maximum Allowable Extension of 25% as Specified in TS SR 4.0.2 for TS SR 4.5.2.d.3 (Trisodium Phosphate) (← links)
- 05000529/LER-1997-007, :on 971006,TS Violation Occurred Due to Inadequate Shutdown Cooling Flow During Modes 5 & 6 Operation.Independent Investigation of Event Was Conducted IAW APS CA Program (← links)
- 05000529/LER-1997-006, :on 971020,manual Reactor Trip Occurred Due to Vibration & Bearing Temp Increases in Reactor Coolant Pump. Caused by Failed Lower Journal Bearing.Bearing Assembly Was Disassembled,Inspected & Rebuilt (← links)
- 05000529/LER-1997-003-02, :on 970907,inadvertent Loss of Power & EDG Start Occurred Due to Procedural Error.Changed Train a & Train B Edg/Ist ST Procedures to Consistently Reflect Proper Pretest Staging Hand Switches (← links)
- 05000529/LER-1997-004, Forwards LER 97-004-00,reporting TS Violation Involving Missed Neutron Flux Power Daily Channel Checks Due to Procedural Deficiency (← links)
- 05000529/LER-1996-005, :on 960628,inadequate Procedural Controls Allows Equipment Qualification Boundary to Be Breached. Caused by Lack of Procedural Controls Placed on Use of Personnel Hatch.Personnel Hatch Closed (← links)
- 05000529/LER-1996-003, :on 960122,missed Surveillance for Logic Check of Logs 1 & 2 Safety Excore Bypasses.Caused by Procedural Error.Log Power Functional Test Revised to Check Logs 1 & 2 Bypasses Regardless of Power Level (← links)
- 05000529/LER-1996-002, :on 960401,inappropriate Work Practice Resulted in Esfa of Train B Edg.Night Order Was Issued to All Three Units Describing Event (← links)
- 05000529/LER-1995-005-01, :on 950717,RT on Low SG Water Level Was Result Following Degradation of MFW Flow.Completed Evaluation of Event (← links)
- 05000529/LER-1994-005-02, :on 941019,completed TS Required Shutdown Due to Expiration of LCO Time Limit.Design Change Options Identified & Will Be Reviewed to Determine If Valve &/Or Motor Operator Replacement or Mod Necessary (← links)
- 05000529/LER-1994-005, Forwards Suppl 1 to LER 94-005,providing Updated Info on Cause & Corrective Actions of TS Required Shutdown Due to Expiration of LCO Time Limit,Including Revised Energy Industry Identification Sys Codes (← links)
- 05000529/LER-1995-004-01, :on 950706,identified Four Occassions Between 950407 & 0630 When Conditional Surveillance in TS LCO 3.8.4.1 Action a Not Performed Due to Inattention to Detail. CR Copy of Temporary Procedure 40TP-9ZZ04 Corrected (← links)
- 05000529/LER-1995-003, :on 950613,TS LCO 3.0.3 Entered Following Loss of Both Trains of Essential Cw Sys & Both Hydrogen Recombiners.Caused by Spurious Actuations Due to Broken EDG Speed Probe Connector.Connector Replaced (← links)
- 05000529/LER-1995-001-02, :on 940817,containment Spray TS Violation Occurred Due to Unrecognized Valve Failed.Issued Night Order on 940831 to Alert CR Personnel to Problems Experienced W/Failed 2JSIAUV664 to Close 940817 (← links)
- 05000529/LER-1995-002-01, :on 950519,TS LCO 3.1.2.2 & LCO 3.1.2.4 Action Statements Not Met.Caused by an Unsatisfactory Swagelok Compression at Union of Flexible Tubing & Rigid Tubing. Pressure Transmitter Sensing Line Repaired (← links)
- 05000529/LER-1994-004, :on 941006,class 1E Batteries Found in Degraded Condition.Caused by Step Decline in Capacity Caused by Loss of Positive Active Matl.Ts LCO 3.8.2.2 Action Was Entered to Prevent Positive Reactivity Additions (← links)
- 05000529/LER-1994-007, Forwards LER 94-007-00 Re Momentary Entry Into TS LCO 3.03 Following Determination That Action Statement for TS LCO 3.7.7 Had Not Been Met W/Both Trains of CR Essential Filtration Sys Inoperable in Modes 1 Through 4 (← links)
- 05000529/LER-1994-006-02, :on 941029,reactor Tripped on Low DNBR Trip Signal Due to Erroneous Penalty Factor.Ceac 1 Processor Board Replaced & Equipment Root Cause Failure Analysis of Processor Board Being Performed (← links)
- 05000529/LER-1994-003-02, :on 940927,startup Channel High Neutron Flux Alarm Declared Inoperable.Caused by Personnel Error. Personnel Counseled (← links)
- 05000529/LER-1993-005, :on 931123,identified That SR 4.8.1.1.1.a Which Verifies Operability of Ac Offsite Sources Not Completed within Required Time (1 H) Due to Cognitive Personnel Error. Surveillance Completed W/No Problems on 931123 (← links)
- 05000529/LER-1993-005-01, :on 931123,identified That SR 4.8.1.1.1.a Had Not Been Completed within Required 1 H Timeframe.Caused by Personnel Error.Required Surveillance Completed Satisfactorily on 931123 (← links)
- 05000529/LER-1993-002, :on 930518,determined That 15 of 20 MSSV & 4 of 4 Pressurizer Safety Valves as-found Relief Settings Out of Tolerence Limits.Valves Exhibited Seat Wear.Efforts to Enhance MSSV Setpoint Repeatability Continuing (← links)
- 05000529/LER-1993-001, :on 930314,SG Tube Ruptured in SG 2.Caused by Iga/Isgcc Occurring as Result of Tube to Tube Crevice Formation.Implemented Changes to EOP (← links)
- 05000529/LER-1993-002-01, :on 930518,determined That 15 Out of 20 MSSV & Pressure Safety Valves Out of Tolerence Limit Specified in TS 3.7.1.1 & 3.4.2.2.Cause of Setpoint Drift Being Investigated.Valve Setpoints Readjusted (← links)
- 05000529/LER-1991-009, Forwards LER 91-009-00 Re Plant Operation W/Sg Tube Not Plugged Per TS 4.4.4.b,rendering SG 2 Administratively Inoperable During Cycle 4 Operation (← links)
- 05000529/LER-1986-018, :on 860718,TS 3.0.3 Entered Due to Three Inoperable Charging Pumps.Replaced Charging Pump a (← links)
- 05000529/LER-1993-001-03, :on 930314,reactor Manually Tripped Following Steam Generator Tube Rupture.Investigation Team Formed & Investigation Initiated Per Incident Investigation Program. Results Will Be Provided in Supplemental LER (← links)
- 05000529/LER-1992-005-01, Forwards LER 92-005-01 Re Failure to Perform ASME Code Class 2 Train B Charging Pump Testing within Max Allowable Surveillance Interval.Encl Discusses Root Cause Determination & Corrective Actions (← links)
- 05000529/LER-1990-009, :on 900911,determined That Fire Barrier Insp Criterion Not Met.Caused by Improper Installation During Construction.Review of Current Maint Programs Performed (← links)
- 05000529/LER-1992-004-01, :on 920619,Train a Loss of Power ESFAS Actuated Due to Fault Downstream of Startup Transformer. Startup Transformer NAN-X01 Quarantined & Senior Plant Mgt Informed (← links)
- 05000529/LER-1992-002, :on 920323,Unit 2 Reactor Tripped & Train a LOP ESFAS Actuation Occurred & Train B LOP ESFAS Actuation Occurred in Unit 3.Reactor Trip Caused by Component Failure. Failed Component Replaced (← links)
- 05000529/LER-1992-003-01, :on 920527,spurious Fuel Bldg Essential Ventilation Sys Actuation Occurred.Caused by age-related Degradation of Output Relay in Kaman Electronic Remote Indication & Control Unit (← links)
- 05000529/LER-1992-002-01, :on 920323,reactor Trip & Train a Loss of Power ESFAS Actuation Occurred.Caused by Fault on Startup Transformer Disconnect Switch.Disconnect Pole Assemblies on Disconnect Switch Replaced (← links)
- 05000529/LER-1992-001-01, :on 920109,reactor Tripped Due to Low Steam Generator Level.Caused by Failure of Wires Connected to a Switch Assembly.Plant Was Stabilized in Mode 3 at Normal Operating Temperature & Pressure (← links)
- 05000529/LER-1991-004, :on 910816,reactor Trip Occurred Due to High Pressurizer Pressure.Caused by Generator/Turbine Trip in Combination W/Coginitive Personnel Error.Generrex Ac/Dc Gate Board Was Replaced (← links)
- 05000529/LER-1991-007-02, :on 911205,discovered That Containment Isolation Valve Required to Be Closed During Core Alteration Was in Open Position.Caused by Procedure Inadequacy. Personnel Involved W/Actuator Briefed (← links)
- 05000529/LER-1991-005, :on 911009,determined That Main Steam Safety Valves Out of Tolerence,Per TS 3.7.1.1 & on 911104 & 05, Determined That Pressurizer Safety Valves Out of Tolerence. Caused by Setpoint Drift.Valves Adjusted (← links)
- 05000529/LER-1991-006-02, :on 911027,control Element Assemblies Withdrawn Approx 1 Ft Out of Core During Refueling Operations W/O Direct Communication W/Control Room.Caused by Personnel Errors.Personnel Involved Briefed (← links)
- 05000529/LER-1991-005-02, :on 911009,determined That 11 of 20 Main Steam Safety Valve as-found Relief Settings Out of Tolerance Specified in TS 3.7.1.1.Caused by Setpoint Drift.Valves Adjusted & Successfully Retested (← links)
- 05000529/LER-1991-002-01, :on 910619,daily Engineering Review of Reactor Coolant Pump (RCP) Vibration Data Missed Due to Personnel Error.Rcp Vibration Analysis Completed & Personnel Counseled.No Abnormalities Noted (← links)
- 05000529/LER-1990-010, Submits Results from Investigation Re Partial Welding of Jacket Water Header Supports on Three Engines,During Production of Ksv Nuclear Engines in 1979,per LER 90-010-00 (← links)
- 05000529/LER-1990-010-01, :on 901110,EDG Jacket Cooling Water Line Inadequately Supported (← links)
- 05000529/LER-1990-011, :on 901113,inadvertent Control Room Essential Filtration ESF Actuation Occurred (← links)
- 05000529/LER-1989-005, :on 890310,loss of Power to Alternate Plant Ventilation Effluent Radiation Monitor Occurred.Caused by Electrical Loads in Excess of Circuit Capacity.Power Restored to Alternate Sampling Sys (← links)
- 05000529/LER-1990-004, :on 900504,discovered That Pressurizer Code Safety Valves as-found Setpoints Out of Tolerance.Caused by Performance Limitation of Pressurizer Safety Valves.Valves Adjusted & Retested Satisfactorily (← links)
- 05000529/LER-1990-008-01, :on 900704,discovered That RCS Boron Concentration Not Determined within Frequency Required,Per Tech Spec 3.1.2.7 Action Requirements.Caused by Personnel Error.Personnel Counseled (← links)
- 05000529/LER-1988-015, :on 881203,chemistry Technician Discovered That New Fuel Area Radiation Monitor RU-19 Inoperable.Caused by Malfunction of Clock in Computer Internal to Monitor. Monitor Reset & Operated Properly (← links)
- 05000529/LER-1990-003-02, :on 900331,power Supply to Alternate Plant Ventilation Effluent Radiation Monitor Deenergized.Caused by Personnel Error.Design Mod Issued to Supply Dedicated Power to Loads (← links)
- 05000529/LER-1990-002-02, :on 900314,discovered That Monthly Valve Lineup for Train a Essential Auxiliary Feedwater Pump Not Performed within Required Interval.Caused by Personnel Error.Involved Individual Counseled (← links)
- 05000529/LER-1990-001-02, :on 900223,manual Reactor Trip Occurred During Planned Shutdown.Caused by Axial Shape Index Approaching Limit at End of Core Life Shutdown.Reactor Manually Tripped So That Channel Trip Setpoint Not Exceeded (← links)
- 05000529/LER-1989-005-02, :on 890310,loss of Power to Alternate Plant Ventilation Effluent Radiation Monitor Occurred.Caused by Electrical Loads in Excess of Circuit Capacity.Design Mod Issued to Supply Dedicated Power to Loads (← links)
- 05000529/LER-1989-003-01, :on 890216,feedwater Control Sys (FWCS) Malfunction Resulted in Reactor Trip Due to Low Level in Steam Generator 1.Caused by Malfunction of Steam Generator Valve.Pneumatic Relays in FWCS Replaced (← links)
- 05000529/LER-1989-009, :on 890712,reactor Trip Occurred on Calculated Low DNBR Due to Low Reactor Coolant Flow.On 890713,portion of Main Feedwater Sys Overpressurized.Caused by Failed Fuse in Potential Transformer.Fuse Replaced (← links)
- 05000529/LER-1989-008-01, :on 890509,calculational Error Identified in Surveillance Test That Would Have Resulted in Boron Diluted Alarm Channel 2 Being Inoperable.Caused by Personnel Error. Technicians Counseled & Test Procedure Revised (← links)
- 05000529/LER-1989-015, :on 881203,discovered New Fuel Area Radiation Monitor RU-19 Inoperable.Caused by Personnel Error.Radiation Monitoring Sys Surveillance Procedure Being Revised to Clarify Instructions (← links)
- 05000529/LER-1989-001, :on 890103,total Loss of Offsite Power to Class 1E 4.16 Kv Busses 2E-PBA-S03 & 2E-PBB-S04 Occurred.Caused by Reduced Impulse Withstand Voltage Rating Due to Rain.Failed Bushings on Each Transformer Replaced (← links)
- 05000529/LER-1989-002-02, :on 890610,main Steam Safety Valve Setpoints Discovered Out of Tolerance.Caused by Setpoint Drift.Valves Readjusted.Testing Will Continue on Refueling Schedule Until Satisfactory Performance Observed (← links)
- 05000529/LER-1989-008, :on 890509,calculational Error Identified in Surveillance Test That Would Have Resulted in Boron Dilution Alarm Channel 2 Being Inoperable.Caused by Personnel Error. Technician Counseled & Procedure Revised (← links)
- 05000529/LER-1988-015-01, :on 881203,new Fuel Area Radiation Monitor RU-19 Discovered Inoperable.Caused by Malfunction in Clock in Computer Internals to Monitor.Area Survey Conducted W/Negative Results & Night Order Issued (← links)
- 05000529/LER-1988-014-01, :on 881116,reactor Trip Occurred as Result of Low Steam Generator Water Level.Caused by Inadequate Feedwater Flow Due to Leakage of Packing.Procedural Changes Implemented & Evaluation Being Performed (← links)
- 05000529/LER-1988-006-01, :on 880726,B Train Loss of Power ESF Actuation Occurred.Caused by Inadequate Plant Design & Installation of Temporary Ventilation Trunk.Ventilation Trunk Removed from Transformer Leads W/O Incident (← links)
- 05000529/LER-1988-012-01, :on 880615,Channel D Linear Power Inoperable Due to Improper Landing of Leads to Plant Protection Sys Drawer.Caused by Personnel Error.Plant Protection Sys Channel D Linear Power Density Tripped (← links)
- 05000529/LER-1988-010, :on 880415,allowable Surveillance Test (ST) Interval for Plant Vent Sys Monitors (Pvsm) Exceeded.Caused by Personnel Error.Appropriate ST on Pvsm Completed & Terminology in ST 75ST-9ZZ07 Changed (← links)
- 05000529/LER-1988-011-01, :on 880522,decontamination Worker Received 2.607 Rem Whole Body Dose to Right Leg Resulting in Cumulative Whole Body Exposure for Quarter of 3.209 Rem. Caused by Incomplete Decontamination (← links)
- 05000529/LER-1987-021, :on 871202,post-accident Sampling Sys Declared Inoperable.Caused by Personnel Error.Appropriate Functional & Surveillance Tests Completed & Sys Decalred Operable.W/ (← links)
- 05000529/LER-1988-004, :on 880210,identified That Discharge Valve of Auxiliary Feedwater Pump Mispositioned in Closed Position. Caused by Personnel Errors.Event Will Be Reviewed by Operating Crews in All Three Units (← links)
- 05000529/LER-1988-005-01, :on 880221,inadvertent Safety Injection from Safety Injection Tanks (Bp)(Acc) Occurred.Caused by Personnel Error.Appropriate Disciplinary Measures Will Be Taken.Malfunctioning Fuse Replaced (← links)
- 05000529/LER-1987-015, :on 870816,control Room Essential Filtration Actuation Initiated on ESFAS Channels a & B.Caused by Voltage Spike on RU-30.Monitor Reset,Train B Returned to Svc & Procedural Change Initiated (← links)
- 05000529/LER-1987-018-01, :on 871004,ESF Signal Initiated on Train B & cross-tripped Train a as Designed.Caused by Spurious Signal Due to Voltage Spike Caused by Electronic Noise.Plant Change Package Initiated (← links)
- 05000529/LER-1987-014-01, :on 870605,discovered That Auxiliary Sample Cart in Svc as Backup to Fuel Bldg Ventilation Radiation Monitor Turned Off & Inoperable.Caused by Personnel Error. Radiation Protection Technician Terminated (← links)
- 05000529/LER-1987-017, :on 870608,discovered That 4-h Samples of Gaseous Radwaste Sys Had Not Been Taken as Required.Caused by Improper Communication Between Chemist & Control Room Operator.Night Order Initiated (← links)
- 05000529/LER-1987-013-01, :on 870510,shutdown Commenced Per Tech Spec 3.8.3.1 Due to Inoperable Inverter.Caused by Loose Silicon Controlled Rectifier (Scr).Loose SCR Replaced & Other SCRs Retorqued (← links)
- 05000529/LER-1987-006-01, :on 870307,during Surveillance Test,Limiting Condition for Operation 3.0.3 Entered When Tech Spec 3/4.6.3 Action Statements Could Not Be Met.Caused by Inoperability of Msivs.Tech Spec Change Request Submitted (← links)
- 05000529/LER-1987-005, :on 870305,fire Patrol for Control Diesel Generator & Main Steam Support Structure Performed Late. Caused by Malfunctioning Access Door to Main Steam Support Structure.Door Returned to Svc (← links)
- 05000529/LER-1999-003, Forwards LER 99-003-00,reporting Condition Prohibited by TS 3.7.17 Where Spent Fuel Assembly Was Stored in Inappropriate Region in Spent Fuel Pool (← links)
- 05000529/LER-1988-002, :on 880118,ASME Section XI Surveillance Test Interval Exceeded.Caused by Inadequate Administrative Controls Established for Tracking of Partially Completed Surveillance Tests.Controls Established (← links)
- 05000529/LER-1988-003-01, :on 880120,operability of Ac Offsite Sources Not Verified within 1 H After Declaring Diesel Generator Operable Following Preventative Maint.Caused by Personnel Error.Disciplinary Action Administered (← links)
- 05000529/LER-1987-019, :on 871122,reactor Trip Occurred Due to Core Axial Shape Index Out of Bounds.Caused by Deficient Procedure & Faulty Contact.Procedural Enhancements Initiated & Faulty Contact Replaced (← links)
- 05000529/LER-1986-044, :on 870515,discovered That Beginning on 860423- 25,both Independent Trains of Control Room Essential Filtration Sys Inoperable Due to Maint Activity.Caused by Inadequate Design.Change Request Initiated (← links)
- 05000529/LER-1987-012-01, :on 870716,discovered That Time Interval for Performance of Tech Spec Surveillance Requirement 4.6.1.3.b.1 Exceeded on 870102.Caused by Error in Approved Procedure.Procedure to Be Revised (← links)
- 05000529/LER-1987-016-01, :on 870718,contents of Chemical Waste Neutralization Tank Released to Onsite Evaporation Pond Exceeding Tech Spec 3.11.1.1 Limit for Mo-99.Caused by Personnel Error.Briefing Session Planned (← links)
- 05000529/LER-1987-007-01, :on 870423,time Interval for Sampling Concentration of Hydrogen & Oxygen in Gaseous Radwaste Sys Exceeded,Contrary to Tech Spec 3.3.3.9.Caused by Cognitive Personnel Error.New Form Used to Aid Personnel (← links)
- 05000529/LER-1987-004-01, :on 870416,reactor & Turbine Trip Occurred. Caused by High Local Power Density Trip Signals Generated by Core Protection Calculators.Effects of Cycling Each Breaker Will Be Incorporated Into Guidelines (← links)
- 05000529/LER-1987-002-01, :on 870320,Class 1E Train B Bank of Pressurizer Backup Heaters Could Not Be Energized from Control Room,Per Tech Spec Requirement.Caused by Malfunction of Heater Breaker & Personnel Error.Breaker Replaced (← links)
- 05000529/LER-2016-001, Regarding Main Steam Isolation Valve Actuator Train Inoperable Due to Low Nitrogen Pre-Charge Pressure (← links)
- 05000529/LER-2015-001, Regarding Condition Prohibited by Technical Specification (TS) Limiting Condition for Operation (LCO) 3.3.5, Engineered Safety Features Actuation System (ESFAS) (← links)
- 05000529/LER-2014-002, Regarding Technical Specification (TS) Required Plant Shutdown Due to a Dropped Control Element Assembly (← links)
- 05000529/LER-2014-001, Regarding Inoperable Essential Spray Pond Train Due to Corrosion on the Diesel Generator Fuel Oil Cooler Cover (← links)
- 05000529/LER-2013-002, Regarding Automatic Actuation of Unit 2 Reactor Protection System Resulting from Reactor Coolant Pump Motor Trip (← links)
- 05000529/LER-2013-001, Regarding Condition Prohibited by Technical Specifications Due to Emergency Diesel Generator Low Output Voltage (← links)
- 05000529/LER-2012-003, Regarding Entry Into Mode 3 with One Auxiliary Feedwater Train Inoperable (← links)
- 05000529/LER-2012-002, Regarding Condition Prohibited by Technical Specification Due to Low Pressure Safety Injection System Drain Pipe Leak (← links)
- 05000529/LER-2011-002-01, Inoperable Steam Generator Low Pressure Reactor Trip and Main Steam Isolation Signal Channels (← links)
- 05000529/LER-2012-001, Regarding Technical Specification LCO 3.1.7 Completion Time Exceeded (← links)
- 05000529/LER-2011-002, Regarding Inoperable Steam Generator Low Pressure Reactor Trip and Main Steam Isolation Signal Channels (← links)
- 05000529/LER-2011-001, For Palo Verde Unit 2, Irradiated Fuel Movement with Misaligned Control Room Essential Filtration System (← links)
- 05000529/LER-2010-002, For Palo Verde, Unit 2, Regarding Inoperable Emergency Diesel Generator Due to Fuel Oil Transfer Pump Failure (← links)
- 05000529/LER-2010-001, Essential Chiller B Inoperable Due to Incorrectly Positioned Head Pressure Control Bypass Valve (← links)
- 05000529/LER-2009-002, Regarding Condition Prohibited by Technical Specification 3.6.3 for Inoperable Containment Isolation Valves (← links)
- 05000529/LER-2009-001, Regarding Emergency Diesel Diesel Generator Fuel Oil Transfer Pump Failure (← links)
- 05000529/LER-2008-003, Technical Specification - Limiting Condition for Operation 3.0.3 for Greater than 1 Hour (← links)
- 05000529/LER-2007-005, Emergency Diesel Generator Inoperability Resulting from a Degraded Speed Control Actuator (← links)
- 05000529/LER-2008-002, Regarding Manual Reactor Trip During Low Power Physics Testing (← links)
- 05000529/LER-2008-001, Regarding Inoperable Boron Dilution Alarm Monitoring System (← links)
- 05000529/LER-2007-003, Manual Reactor Trip Due to Increased Steam Generator Sodium Levels from Failed Heat Exchanger Plug (← links)
- 05000529/LER-2005-006, Regarding Condition Prohibited by Technical Specifications Due to Partial Fouling of B Diesel Generator (EDG) Fuel Oil Strainer (← links)
- 05000529/LER-2007-001, Re Completion of a Shutdown Required by Technical Specification 3.5.3, Condition C (← links)
- 05000529/LER-2007-002, Regarding Condition Prohibited by Technical Specification - CEA Insertion Limit Exceeded (← links)
- 05000529/LER-2006-006, Regarding Technical Specification 3.7.7 Violation - Inoperable Essential Cooling Water Heat Exchanger (← links)
- 05000529/LER-2006-005, Re Reactor Head Vent Axial Indications Caused by Degraded Alloy 600 Component (← links)
- 05000529/LER-2006-004, Regarding Unit 2 Feedwater Isolation Valve Inoperability Results in Condition Prohibited by Technical Specification (← links)
- 05000529/LER-2006-003, For Palo Verde, Unit 2, Regarding Unit 2 Variable Overpower Reactor Trip During Main Turbine Control Valve Restoration (← links)
- 05000529/LER-2006-002, Regarding Two Independent Trains of Auxiliary Feedwater Inoperable Due to Single Cause (← links)
- 05000529/LER-2006-001, Re TS Required Reactor Shutdown on Failure to Complete Repairs on an AFW Valve within the 7 Day Completion Time (← links)
- 05000529/LER-2005-005, Regarding TS Required Reactor Shutdown - LCO 3.0.3 a Inoperable ECCS, Containment Spray & Refueling Water Tank (← links)
- 05000529/LER-2005-004, Re Technical Specification Required Shutdown Due to Core Protection Calculators Inoperable (← links)
- 05000529/LER-2005-003, Regarding Two Independent Trains of Auxiliary Feedwater Inoperable (← links)
- 05000529/LER-2005-002, Re Tis 3.0.4 Violation; Mode Change Made with One of Two Required LPSI Pumps Inoperable (← links)
- 05000529/LER-2005-001, Regarding Reactor Head Vent Axial Indications Caused by Degraded Alloy 600 Component (← links)
- 05000529/LER-2004-003, Regarding Actuation of Plant Emergency Diesel Generators (← links)
- 05000529/LER-2004-002, On 07/14/2004 Reactor Tripped on Low Departure from Nucleate Boiling Ratio (DNBR) (← links)
- 05000529/LER-2003-004, Mode 3 Entry with an Auxiliary Feed Water Pump Inoperable - Technical Specification Violation (← links)
- 05000529/LER-2004-001, Regarding Steam Generator Tube Leak (← links)
- 05000529/LER-2003-003, Corrected Copy of Letter for LER 03-003-00 for Palo Verde, Unit 2 (← links)
- 05000529/LER-2003-002, Regarding ESF Actuation - Unit 2 Emergency Diesel Generator Actuation (← links)
- 05000529/LER-2003-001, Regarding Reactor Trip with Loss of Forced Circulation Due to Failed Pressurizer Main Spray Valve (← links)
- 05000529/LER-2000-006-01, Safety Injection Tank Outlet Check Valve Back-Leakage Causes Degraded Safety Injection Flow (← links)
- 05000529/LER-2002-001, Re Main Steam Safety Valve As-Found Lift Pressures Outside of Technical Specification Limits (← links)
- ML12101A100 (redirect page) (← links)
- 05000528/LER-2012-006, For Palo Verde, Unit 1 Regarding Safety Injection System Check Valve Testing Could Have Resulted in Less than Required Injection Flow (← links)
- 05000528/LER-2012-005, Condition Prohibited by Technical Specifications Due to Remote Shutdown System Control Circuit Deficiencies (← links)
- 05000529/LER-2012-003, Regarding Entry Into Mode 3 with One Auxiliary Feedwater Train Inoperable (← links)
- 05000529/LER-2012-002, Regarding Condition Prohibited by Technical Specification Due to Low Pressure Safety Injection System Drain Pipe Leak (← links)
- 05000528/LER-2012-004, Regarding Essential Spray Pond Pump Actuation Due to a Control Room Essential Filtration Actuation Signal (← links)
- 05000528/LER-2012-003, Regarding Main Steam Isolation Valve Actuator Train Inoperable Due to Low Nitrogen Pre-Charge Pressure (← links)
- 05000528/LER-2012-002, Supported Systems Not Considered Inoperable with Support Equipment Inoperable (← links)
- 05000530/LER-2012-001, Regarding Manual Reactor Trip During Low Power Physics Testing (← links)
- 05000528/LER-2012-001, For Palo Verde, Unit 1, Regarding Technical Specification LCO 3.1.7 Incorrect Pdil Setpoint Values (← links)