Search by property

This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.

List of results

• 05000424/LER-1990-021-01, :Between 901202-03,special Condition Surveillance Not Performed When Rod Position Deviation Monitor Inoperable.Caused by Personnel Error.Future Training on Proteus Computer Planned  + ( :Between 901202-03,special Condition Surveillance Not Performed When Rod Position Deviation Monitor Inoperable.Caused by Personnel Error.Future Training on Proteus Computer Planned )
• 05000440/LER-1990-041, :Between 901212 & 28,inoperable Reactor Pressure Vessel Level Instrumentation Channels Resulted in HPCS Sys Being Inoperable & in Tech Spec Violation.Caused by Personnel Error.Memo Issued  + ( :Between 901212 & 28,inoperable Reactor Pressure Vessel Level Instrumentation Channels Resulted in HPCS Sys Being Inoperable & in Tech Spec Violation.Caused by Personnel Error.Memo Issued )
• 05000353/LER-1994-009-02, :Between 940829 & 0906,approved Clearance Incorrectly Specified Removal of Fuse from D21 EDG Breaker Auxiliary Control Power Circuit That Would Prevent a CS Sys Subsystem from Automatically Starting  + ( :Between 940829 & 0906,approved Clearance Incorrectly Specified Removal of Fuse from D21 EDG Breaker Auxiliary Control Power Circuit That Would Prevent a CS Sys Subsystem from Automatically Starting )
• 05000298/LER-1989-006, :Control Bldg HVAC Design Concerns Identified During NRC Insp on 870511-0619.Caused by Inadequate Design. Steps to Install Permanent Essential Equipment That Will Provide Acceptable Room Temps Being Pursued  + ( :Control Bldg HVAC Design Concerns Identified During NRC Insp on 870511-0619.Caused by Inadequate Design. Steps to Install Permanent Essential Equipment That Will Provide Acceptable Room Temps Being Pursued )
• 05000315/LER-1985-043, :Corrective Actions & Preventive Measures Taken Re Discrepancies in Process Sensor Calibr Completed,Per Confirmatory Action Ltr Issued on 850820  + ( :Corrective Actions & Preventive Measures Taken Re Discrepancies in Process Sensor Calibr Completed,Per Confirmatory Action Ltr Issued on 850820 )
• 05000301/LER-1987-004-01, :Degradation of Steam Generator Tubes Noted During Eddy Current Exam Conducted on 871008-22.One Tube Weld Repaired.Remaining Tubes Left as Found Due to Minimal Leakage Observed & Hazards Associated W/Repair  + ( :Degradation of Steam Generator Tubes Noted During Eddy Current Exam Conducted on 871008-22.One Tube Weld Repaired.Remaining Tubes Left as Found Due to Minimal Leakage Observed & Hazards Associated W/Repair )
• 05000298/LER-1989-010, :Diesel Generator Room Ambient Temp Control Inadequacies Identified During NRC Insp on 870511-0619. Caused by Error in Original Plant Design.Design Change 87-132 Provided Permanent Mod to Eliminate Deficiency  + ( :Diesel Generator Room Ambient Temp Control Inadequacies Identified During NRC Insp on 870511-0619. Caused by Error in Original Plant Design.Design Change 87-132 Provided Permanent Mod to Eliminate Deficiency )
• 05000219/LER-1984-006-01, :During 1983,blast Cleaning of Torus Structure Components Revealed Areas of Corrosion Pitting & Missing Fillet Welds on Ring Girders.All Irregularities Repaired  + ( :During 1983,blast Cleaning of Torus Structure Components Revealed Areas of Corrosion Pitting & Missing Fillet Welds on Ring Girders.All Irregularities Repaired )
• 05000333/LER-1987-004, :During 1987 Refuel Outage,Three of Six Target Rock Safety/Relief Valves Removed for Testing Found W/ Setpoint Values Outside Allowable Tolerance.Probable Cause Due to Sticking of Pilot Valve Disc  + ( :During 1987 Refuel Outage,Three of Six Target Rock Safety/Relief Valves Removed for Testing Found W/ Setpoint Values Outside Allowable Tolerance.Probable Cause Due to Sticking of Pilot Valve Disc )
• 05000271/LER-1984-008, :During 840612-17,air Particulate & Charcoal Cartridge Sampling Not Performed as Required by Tech Spec. Caused by Technician Leaving Off Air Sampling Station. Procedures Revised & Technicians Instructed  + ( :During 840612-17,air Particulate & Charcoal Cartridge Sampling Not Performed as Required by Tech Spec. Caused by Technician Leaving Off Air Sampling Station. Procedures Revised & Technicians Instructed )
• 05000219/LER-1985-004, :During 850102-30,power Shape Monitoring Sys Calculations Inadequate Due to Flux Peaking Outside of Instrument Calibr Range.Caused by Error in Acceptance Criteria.Core Thermal Power Reduced  + ( :During 850102-30,power Shape Monitoring Sys Calculations Inadequate Due to Flux Peaking Outside of Instrument Calibr Range.Caused by Error in Acceptance Criteria.Core Thermal Power Reduced )
• 05000361/LER-1986-034, :During 860107-1109,eight ESF Actuations Occurred During Performance of Maint Activities.Personnel Responded to Each Actuation in Accordance W/Approved Procedures.Circumstances Reviewed by Maint Personnel  + ( :During 860107-1109,eight ESF Actuations Occurred During Performance of Maint Activities.Personnel Responded to Each Actuation in Accordance W/Approved Procedures.Circumstances Reviewed by Maint Personnel )
• 05000361/LER-1986-035, :During 860316-870527,15 Spurious Actuations of Train a Containment Purge Isolation Sys Occurred.Caused by Electrical Noise Spikes by Operation of HPSI Sys Components. Detector Replaced & Proper Grounding Confirmed  + ( :During 860316-870527,15 Spurious Actuations of Train a Containment Purge Isolation Sys Occurred.Caused by Electrical Noise Spikes by Operation of HPSI Sys Components. Detector Replaced & Proper Grounding Confirmed )
• 05000361/LER-1986-032, :During 860508-870413,eleven Actuations of Toxic Gas Isolation Sys & Three Actuations of Control Room Isolation Sys Occurred.Caused by Power Deenergization. Operating Instruction on Power Transfer Evolutions Modified  + ( :During 860508-870413,eleven Actuations of Toxic Gas Isolation Sys & Three Actuations of Control Room Isolation Sys Occurred.Caused by Power Deenergization. Operating Instruction on Power Transfer Evolutions Modified )
• 05000316/LER-1986-027, :During 860802-29,backup Tritium Sample Sys Removed from Svc While Primary Sys Removed from Svc on 860806.Caused by Inadequate Procedural Guidance.Procedural Controls Adopted  + ( :During 860802-29,backup Tritium Sample Sys Removed from Svc While Primary Sys Removed from Svc on 860806.Caused by Inadequate Procedural Guidance.Procedural Controls Adopted )
• 05000271/LER-1987-011, :During 870818 & 20,requirements of Tech Spec 3.5.H.4 for Min Subsystems Required for Refueling Not Satisfied.Caused by Procedural Error.Required Equipment During Refueling & Operation Clarified  + ( :During 870818 & 20,requirements of Tech Spec 3.5.H.4 for Min Subsystems Required for Refueling Not Satisfied.Caused by Procedural Error.Required Equipment During Refueling & Operation Clarified )
• 05000336/LER-1984-007-01, :During Mar 1984,at 100% Power,Monthly Surveillance for Thermal Margin/Low Pressure Operability Check Missed.Caused by Personnel Lack of Communication. Surveillance Performed  + ( :During Mar 1984,at 100% Power,Monthly Surveillance for Thermal Margin/Low Pressure Operability Check Missed.Caused by Personnel Lack of Communication. Surveillance Performed )
• 05000416/LER-1986-027, :During NRC 860611-15 Insp,Hourly Fire Watches Found to Exceed Tech Spec 1 H Frequency.Caused by Administrative Deficiencies.Fire Watch Personnel Received Verbal & Written Instructions  + ( :During NRC 860611-15 Insp,Hourly Fire Watches Found to Exceed Tech Spec 1 H Frequency.Caused by Administrative Deficiencies.Fire Watch Personnel Received Verbal & Written Instructions )
• 05000272/LER-1995-012-01, :During Nov 1995,TDAFWP Encl Not Matching as- Built Conditions of 761211.Caused by Inadequate Verification of as-build Design Deficiency Calculations.Helb Calculations Reviewed  + ( :During Nov 1995,TDAFWP Encl Not Matching as- Built Conditions of 761211.Caused by Inadequate Verification of as-build Design Deficiency Calculations.Helb Calculations Reviewed )
• 05000364/LER-1990-005, :During Seventh Refueling outage,571 Tubes Found Defective & Classified as Category C-3.Caused by Defects in Tube Sheet Area & at Support Plates.All Tubes Plugged & Boric Acid Added  + ( :During Seventh Refueling outage,571 Tubes Found Defective & Classified as Category C-3.Caused by Defects in Tube Sheet Area & at Support Plates.All Tubes Plugged & Boric Acid Added )
• 05000269/LER-1987-002-04, :During Wk of 870127,determined That Operators May Not Be Able to Isolate Particular Letdown Flow Path. Caused by Design Deficiency.Power Removed from Breakers for Valves LP-1 & HP-2 on 870129  + ( :During Wk of 870127,determined That Operators May Not Be Able to Isolate Particular Letdown Flow Path. Caused by Design Deficiency.Power Removed from Breakers for Valves LP-1 & HP-2 on 870129 )
• 05000369/LER-1991-009-02, :During Wk of 910708,discovered That Gain Setting to Average Reactor Coolant Temp Input Would Cause Process Control Equipment to Reach Hardware Limit.Caused by Design Defect.Resistors Changed  + ( :During Wk of 910708,discovered That Gain Setting to Average Reactor Coolant Temp Input Would Cause Process Control Equipment to Reach Hardware Limit.Caused by Design Defect.Resistors Changed )
• 05000369/LER-1991-009-01, :During Wk of 910708,hardware Limits for Certain Process Control Equipment in Reactor Protection Sys Exceeded.Caused by Design Deficiency Due to Deficient Documentation.Resistors Changed  + ( :During Wk of 910708,hardware Limits for Certain Process Control Equipment in Reactor Protection Sys Exceeded.Caused by Design Deficiency Due to Deficient Documentation.Resistors Changed )
• 05000315/LER-1997-020, :Has Been Canceled  + ( :Has Been Canceled )
• 05000298/LER-1989-008, :Insufficient Operator Guidance to Assure Adequate Svc Water Flow During Design Basis LOCA Identified During NRC Insp on 870511-0619.Caused by Procedural Deficiency.Procedures Revised  + ( :Insufficient Operator Guidance to Assure Adequate Svc Water Flow During Design Basis LOCA Identified During NRC Insp on 870511-0619.Caused by Procedural Deficiency.Procedures Revised )
• ML12335A177  + ( :Licensee Documents ALION-CAL-STP for 12-10-12 Public Telecon GSI-191 )
• ML17208A767  + ( :NRC IE Bulletin 79-01B,Phase 1, Master List & Component Evaluation Sheets )
• 05000304/LER-1985-028, :Not Used  + ( :Not Used )

• 05000333/LER-1978-048, :Number Not Used  + ( :Number Not Used )
• ML19199A287  + ( :Number Not Used )
• 05000272/LER-1978-046, :Number Not Used  + ( :Number Not Used )
• ML19199A285  + ( :Number Not Used )
• ML19199A286  + ( :Number Not Used )
• ML19199A289  + ( :Number Not Used )

• 05000289/LER-1978-014, :Number Not in Use  + ( :Number Not in Use )
• 05000289/LER-1978-021, :Number Not in Use  + ( :Number Not in Use )
• 05000336/LER-1983-020, :Ongoing Eddy Current Exams Identified Number of Steam Generator Tubes W/Defects Which Required Both Steam Generators to Be Placed in C-3 Insp Category.Frequency of Occurrence Primarily on Cold Leg Side  + ( :Ongoing Eddy Current Exams Identified Number of Steam Generator Tubes W/Defects Which Required Both Steam Generators to Be Placed in C-3 Insp Category.Frequency of Occurrence Primarily on Cold Leg Side )
• 05000250/LER-1985-006, :Redundant Raw Water Tank II Installed,Which Holds 300,000 Gallons of Water Dedicated to Fire Suppression.New Raw Water Tank II Meets App R Iii.A Requirements Approved by NRC on 811109  + ( :Redundant Raw Water Tank II Installed,Which Holds 300,000 Gallons of Water Dedicated to Fire Suppression.New Raw Water Tank II Meets App R Iii.A Requirements Approved by NRC on 811109 )
• B12024, :Response to Info Requested Re Station Blackout, Technical Review  + ( :Response to Info Requested Re Station Blackout, Technical Review )
• ML18092B532  + ( :Revised SPDS Sar )
• 05000272/LER-1990-026-01, :Several Occurrences of ASME Code 3 Piping Leakage Occurred Starting on 900611.Caused by Equipment Failure.All Affected Components Repaired Per ASME Code  + ( :Several Occurrences of ASME Code 3 Piping Leakage Occurred Starting on 900611.Caused by Equipment Failure.All Affected Components Repaired Per ASME Code )
• 05000000/LER-1984-002, :Since 840107,several Instances of Reactor Protection Sys Bus Breaker Trips Resulted in Loss of Shutdown Cooling.Trip on 840119 Caused by Failure of Circuit Board  + ( :Since 840107,several Instances of Reactor Protection Sys Bus Breaker Trips Resulted in Loss of Shutdown Cooling.Trip on 840119 Caused by Failure of Circuit Board )
• 05000382/LER-1988-030, :Since 881110,number of Discrepancies Have Been Identified in fire-rated Assemblies at Plant.Cause of Events Appears to Be Inadequate Fire Seal Installation & Insp Program During Initial Plant Const  + ( :Since 881110,number of Discrepancies Have Been Identified in fire-rated Assemblies at Plant.Cause of Events Appears to Be Inadequate Fire Seal Installation & Insp Program During Initial Plant Const )
• 05000412/LER-1988-008-01, :Since Jul 1987,five Failures of Brown Boveri Ite 51 Overcurrent Relays Experienced.Caused by Short Circuiting of Output Silicon Control Rectifier Due to Impurities.Problem Also Reportable Per 10CFR21  + ( :Since Jul 1987,five Failures of Brown Boveri Ite 51 Overcurrent Relays Experienced.Caused by Short Circuiting of Output Silicon Control Rectifier Due to Impurities.Problem Also Reportable Per 10CFR21 )
• 05000425/LER-1990-001-03, :Surveillances Performed on 900103 & 0201 Failed to Meet Requirements of Tech Specs 4.6.1.1.a.Caused by Personnel Misled to Believe That Only 2 of 41 Items Verified.Sts Revised  + ( :Surveillances Performed on 900103 & 0201 Failed to Meet Requirements of Tech Specs 4.6.1.1.a.Caused by Personnel Misled to Believe That Only 2 of 41 Items Verified.Sts Revised )
• 05000298/LER-1989-009, :Svc Water Sys Inservice Testing Concerns Identified During NRC Insp on 870511-0619.Cause Not Stated.Inservice Testing Program Procedure for Pump Testing,Providing Specific Trending Guidance,Upgraded  + ( :Svc Water Sys Inservice Testing Concerns Identified During NRC Insp on 870511-0619.Cause Not Stated.Inservice Testing Program Procedure for Pump Testing,Providing Specific Trending Guidance,Upgraded )
• 05000483/LER-1986-003, :an 860224,firewatch Requirements Not Met When Grinding Caused Smoke & Dust to Set Off Alarm.Caused by Need to Obtain Keys from Key Room & Slow Response Time.Keys Now Provided on Firewatch Key Rings  + ( :an 860224,firewatch Requirements Not Met When Grinding Caused Smoke & Dust to Set Off Alarm.Caused by Need to Obtain Keys from Key Room & Slow Response Time.Keys Now Provided on Firewatch Key Rings )
• 05000338/LER-1984-013, :from 840910-25,liquid Radwaste Discharged W/O Treatment W/Projected Doses to Unrestricted Areas in Excess of Limits Specified in Tech Spec 3.11.1.3.Caused by Inadequate Checking of Demineralizers  + ( :from 840910-25,liquid Radwaste Discharged W/O Treatment W/Projected Doses to Unrestricted Areas in Excess of Limits Specified in Tech Spec 3.11.1.3.Caused by Inadequate Checking of Demineralizers )
• 05000454/LER-1985-038, :from 850117-0331,CO2 Fire Protection Sys Valve Alignment Not Verified Per Tech Specs.Caused by Surveillance Coordinator Error.Surveillance Coordinator Instructed to Check Failed Surveillances  + ( :from 850117-0331,CO2 Fire Protection Sys Valve Alignment Not Verified Per Tech Specs.Caused by Surveillance Coordinator Error.Surveillance Coordinator Instructed to Check Failed Surveillances )
• 05000369/LER-1985-012-01, :from 850214-0425,fire Doors Normally Locked Closed Were Unlocked & Not Verified Closed Daily Nor Was Fire Watch Posted.Caused by Administrative/Procedural Deficiency.Required Surveillance Implemented  + ( :from 850214-0425,fire Doors Normally Locked Closed Were Unlocked & Not Verified Closed Daily Nor Was Fire Watch Posted.Caused by Administrative/Procedural Deficiency.Required Surveillance Implemented )
• 05000528/LER-1985-016, :from 850323-0415,hourly Fire Patrols Not Conducted Per Tech Spec 3.7.12.Caused by Personnel Disregard for Responsibilities.Personnel Fired &/Or Replaced W/Station Staff & Logs & Monitoring Improved  + ( :from 850323-0415,hourly Fire Patrols Not Conducted Per Tech Spec 3.7.12.Caused by Personnel Disregard for Responsibilities.Personnel Fired &/Or Replaced W/Station Staff & Logs & Monitoring Improved )
• 05000325/LER-1985-060, :from 851031-1103 & on 851105,sampling of Main Condenser Offgas Treatment Sys & Explosive Gas Monitoring Sys Not Conducted.Caused by Personnel Failure.Caution Tags Affixed to Reactor Turbine Gauge Board  + ( :from 851031-1103 & on 851105,sampling of Main Condenser Offgas Treatment Sys & Explosive Gas Monitoring Sys Not Conducted.Caused by Personnel Failure.Caution Tags Affixed to Reactor Turbine Gauge Board )
• 05000413/LER-1989-011, :from 890131 to 890413,lower Containment Temp Monitoring Not Performed Per Tech Spec Compensatory Action. Caused by Not Notifying Personnel of Inoperable Smoke Detectors.Hourly Compensatory Action Initiated  + ( :from 890131 to 890413,lower Containment Temp Monitoring Not Performed Per Tech Spec Compensatory Action. Caused by Not Notifying Personnel of Inoperable Smoke Detectors.Hourly Compensatory Action Initiated )
• 05000295/LER-1989-016-03, :from 890919-21,fuel Handling Senior Reactor Operator Did Not Meet 10CFR55.53 Requirements.Caused by Lack of Administrative Control Re Operator Activity.Fuel Handling Instructions Changed  + ( :from 890919-21,fuel Handling Senior Reactor Operator Did Not Meet 10CFR55.53 Requirements.Caused by Lack of Administrative Control Re Operator Activity.Fuel Handling Instructions Changed )
• 05000354/LER-1989-022-01, :from 891016-27,scrams Experienced on Channel B Reactor Protection Sys Electric Assemblies & Nuclear Steam Supply Shutdown Sys Isolated,Resulting in Loss of Shutdown Cooling.Assemblies & Output Voltages Reset  + ( :from 891016-27,scrams Experienced on Channel B Reactor Protection Sys Electric Assemblies & Nuclear Steam Supply Shutdown Sys Isolated,Resulting in Loss of Shutdown Cooling.Assemblies & Output Voltages Reset )
• 05000364/LER-1989-014, :from 891115-16,Tech Spec 3.0.3 Entered Voluntarily to Repair Leaking Containment Purge Isolation Dampers.Caused by Need to Repair Dampers.Dampers Closed & Automatic Isolation Feature Restored  + ( :from 891115-16,Tech Spec 3.0.3 Entered Voluntarily to Repair Leaking Containment Purge Isolation Dampers.Caused by Need to Repair Dampers.Dampers Closed & Automatic Isolation Feature Restored )