Pages that link to "05000455/LER-2013-001"
Jump to navigation
Jump to search
The following pages link to 05000455/LER-2013-001:
Displayed 50 items.
- 05000455/LER-2012-001 (← links)
- 05000455/LER-2013-002 (← links)
- 05000455/LER-2013-003 (← links)
- 05000455/LER-2016-001 (← links)
- 05000455/LER-2011-002 (← links)
- 05000455/LER-2011-001 (← links)
- 05000455/LER-2010-001 (← links)
- 05000455/LER-2009-001 (← links)
- 05000455/LER-2008-001 (← links)
- 05000455/LER-2007-001 (← links)
- 05000455/LER-2005-001 (← links)
- 05000455/LER-2001-004 (← links)
- 05000455/LER-2001-003 (← links)
- 05000455/LER-2001-002 (← links)
- 05000455/LER-2001-001 (← links)
- ML13137A310 (redirect page) (← links)
- 05000455/LER-1993-005, Advises That LER 93-005 Will Not Be Used (← links)
- 05000455/LER-1991-001, Advises That LER 91-001-00 Will Not Be Used (← links)
- 05000455/LER-1987-019, Forwards Corrected LER 87-019-00.LER Originally Issued W/ Error in LER Number in Codified Field (Block 6) (← links)
- 05000455/LER-1986-001, Errata to LER 86-001-00,incorporating Page 4 Inadvertently Omitted from Original LER Re Crosby Relief Valve JO-25WR (← links)
- 05000455/LER-2022-001-01, Volumetric Examinations of Reactor Pressure Vessel Head Core Exit Thermocouple Penetration P-75 Identified an Indication Attributed to Primary Water Stress Corrosion Cracking (← links)
- 05000455/LER-2022-001, Volumetric Examinations of Reactor Pressure Vessel Head Core Exit Thermocouple Penetration P-75 Identified an Indication Attributed to Primary Water Stress Corrosion Cracking (← links)
- 05000455/LER-1989-003-06, :on 890304,undervoltage Condition Occurred When Line Bus Tie Breakers Opened Due to Fault in Line. Monitors Returned to Normal Operations After Voltage Transient Passed & Breakers Reclosed (← links)
- 05000455/LER-1998-003-04, :on 980416,high RCS Activity & ESF Actuation Occurred.Caused by Inadequate RCS Cleanup & Weak Administrative Controls.Posted Area Surrounding Refueling Cavity as High Radiation Area (← links)
- 05000455/LER-1998-004-04, :on 980419,FHB Rad Monitor ESF Actuation, Occurred.Caused by High Dose Water in Fuel Transfer Canal. Fhb Dose Rates Monitored (← links)
- 05000455/LER-1989-003-04, :on 890227,containment Ventilation Isolation Occurred Due to Radiator Monitor Failure of Checksource Test.Caused by Faulty Detector.Detector Replaced & Monitor Tested & Returned to Svc (← links)
- 05000455/LER-1989-002-07, :on 890220,boron Dilution Protection Sys Blocked for Greater than 1 H During Cold Shutdown.Caused by Lack of Administrative Tracking Tools Available to Operator. Timers W/Alarm Capability Made Available (← links)
- 05000455/LER-1989-001-12, :on 890211,safety Injection Actuation of Train a & B Equipment Occurred During Performance of Diesel Generator Operability Test.Caused by Inadequate Precautions in Surveillance Test.Procedures Revised (← links)
- 05000455/LER-1989-001-02, :on 890211,safety Injection Actuation of Trains a & B Equipment Occurred.Caused by Inadequate Precautions in Surveillance Procedure.Procedures Used for Diesel Generator Operability Test Will Be Revised (← links)
- 05000455/LER-1989-005-09, :on 890523,feedwater Isolation Occurred from Reactor Trip P-4 Signal Generated While Racking in Reactor Trip Breaker.Cause of Event Could Not Be Identified.Caution Placed on Reactor Trip Breaker Cubicle (← links)
- 05000455/LER-1987-006-01, :on 870427,reactor Tripped Due to Pressurizer Pressure Spiked Below Reactor Trip Setpoint.Caused by Failure of Pressurizer Pressure Transmitter & Nuclear Loop Power Supply on Channel 456 (← links)
- 05000455/LER-1987-007, :on 870504,reactor Tripped During Performance of Quarterly Power Range Calibr Surveillance on Channel NI-43(IG).Caused by Trip of Bus 211 Due to Failure of Wornout Capacitor.Inverter Repaired & Tested (← links)
- 05000455/LER-1987-011-08, :on 870725,reactor Tripped on Overtemp Delta T Condition.Caused by Inability of Plant Secondary Side to Remove Heat Generated by Primary Side & Controller Inability to Accept Large Load Reject in Valve Mode (← links)
- 05000455/LER-1987-012-07, :on 870730,2B Diesel Generator Failed to Reach Rated Speed within Required Time Limit.Caused by Instrument Drift of Pressure Indicator.Faulty Indicator & Turbocharger Replaced & Air Regulator Correctly Set (← links)
- 05000455/LER-1987-001-01, :on 870115,during Initial Criticality/Low Power Physics start-up Test Requiring Bistable Trip,Reactor Trip Occurred.Caused by Reactor Coolant Resistance Temp Detector Splice Failure.Splice Connection Corrected (← links)
- 05000455/LER-1987-009-08, :on 870629,manual Reactor Trip Initiated Due to 2C (Turbine Driven) Main Feedwater Pump Trip.Caused by Cold Solder Joint on Capacitor in Speed Control Feedback Loop. Solder Joint Repaired & Tested (← links)
- 05000455/LER-1987-010-07, :on 870701,manual Reactor Trip Occurred Due to Electrohydraulic Pump Manual Trip Necessitated by Fluid Leak.Caused by Vibration.Supply Line to Fullers Earth Filter Removed & Valve & Nipple Installed (← links)
- 05000455/LER-1987-016, :on 870831,during Surveillance Test,Inadvertent Train a Safety Injection Occurred.Caused by Personnel Communication Breakdown.Prof Program Will Be Covered W/ Operating Dept for 6 Wks (← links)
- 05000455/LER-1989-001-08, :on 890211,inadvertent Safety Injection Actuation of Trains a & B Equipment Occurred During Performance of Diesel Generator Operability Surveillance. Caused by Procedural Inadequacy (← links)
- 05000455/LER-1987-017-05, :on 870903,main Steam Isolation Bypass Valve Returned to Svc W/O Completing Required post-maint Testing. Caused by Cognitive Personnel Error.Training on Proper Completion of Checklist Will Be Given (← links)
- 05000455/LER-1987-015-07, :on 870829,feedwater Isolation Actuation on Steam Generator Level high-2 Occurred.Caused by Personnel Error.Personnel counseled.Color-coding of Instruments to Prevent Error Under Investigation (← links)
- 05000455/LER-1987-008-08, :on 870606,containment mini-purge Supply & Exhaust Ventilation Sys Simultaneously Put Into Operation. Caused by Personnel Error & Procedural Inadequacy.Personnel Involved Disciplined & Procedure Changed (← links)
- 05000455/LER-1987-014-06, :on 870824,primary Containment Type B Local Leakage Rate Tests of Equipment Hatch Airlock Door Gasket Interspaces Not Performed,Making Airlock Inoperable.Caused by Personnel Error.Surveillance Performed (← links)
- 05000455/LER-1987-013-07, :on 870819,deviation from FSAR Description Not Reported within One Month as Required by License Condition 2.C.3.Caused by Personnel Error.Memo Emphasizing Need for Notification of FSAR Deviations Issued (← links)
- 05000455/LER-1987-020-05, :on 871202,unanticipated Water Discharged Into Primary Sys When Safety Injection Accumulators Discharge Isolation Valves Opened.Caused by Defective Procedure. Procedure Revised to Include Precaution (← links)
- 05000455/LER-1998-002-03, :on 980312,channel 3 of Overtemperature Delta Temp (OTDT) Was Inoperable.Caused by Failure of 7300 Protection Sys lead-card in OTDT Channel 4.Failed Card Replaced (← links)
- 05000455/LER-1987-004-01, :on 870221,permission Given to Adjust Containment Isolation Valve 2PS9357A W/O Initiating Appropriate Limiting Condition for Action Requirement.Caused by Personnel Error.Shift Engineer Counseled (← links)
- 05000455/LER-1986-002-10, :on 861122,digital Rod Position Indication & Bank Demand Step Counters Differed by More than 12 Steps, Requiring Opening of Reactor Trip Breakers.Caused by Defective Detector Encoder Card.Card Replaced (← links)
- 05000455/LER-1987-007-06, :on 870504,reactor Tripped During Performance of Quarterly Power Range Calibr Surveillance.Cause of Capacitor Failure Undetermined But Attributable to Normal Wearout.Inverter 211 Replaced (← links)
- 05000455/LER-1987-006-06, :on 870427,reactor Trip Occurred When Pressurizer Pressure Spiked Below Reactor Trip Setpoint. Caused by Failure of Presssure Transmitter & Nuclear Loop Power Supply During Surveillance Performance (← links)