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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
- ML17331B305 +
- ML082480293 +
- 05000255/LER-1993-010, :on 930917,primary Coolant Sys Cooldown Rate as Defined in TS Exceeded.Caused by Combination of Personnel Error & Inadequate Procedures.Proper Temp Monitoring Techniques Verified +
- L-12-114, LER 12-S02-00, for Perry Nuclear Power Plant, Unit 1, Regarding Potential Vulnerability in a Safeguards Security System +
- ML19257B897 +
- ML051370177 +
- ENS 44036 +
- 05000272/LER-1982-048, Forwards LER 82-048/03L-0.Detailed Event Analysis Encl +
- ML031500474 +
- ML20080E781 +
- ML20106E576 +
- ML20090K591 +
- ML20071Q137 +
- ML20127M258 +
- IR 05000255/1985013 +
- ML20245G894 +
- NPL-97-0061, LER 97-S01-00:on 970204,compensatory Measures for Microwave Zones Had Not Been Implemented.Caused by Mgt Oversight of CAS & SAS Activities Was Inadequated.Addl Mgt Oversight of CAS & SAS Operations Has Been Implemented +
- 05000245/LER-1989-014, :on 890529,reactor Recirculation Pump Seal a Pressure Became Erratic & Containment Pressure Rapidly Increased.Caused by Seal Failure Due to Damage to Seal Internals.Investigation Into Causes Continuing +
- 05000346/LER-1998-005, :on 980601,both Low Pressure Injection/Dhr Pumps Were Rendered Inoperable During Testing.Caused by Inadequate Self Checking,Communication & Procedure Usage Work Practices.Operations Mgt Reviewed Expectations +
- 05000346/LER-1998-004, :on 980601,ductwork for Number 2 Control Room Humidifier Found Disconnected from Humidifier.Caused by Less than Adequate Connection at Humidifier Blower Housing. Ductwork Repaired +
- 05000461/LER-1987-058, :on 870930,failure to Perform Leak Test of Primary Containment Air Lock Door Seal Identified.Caused by Personnel Error Due to Misinterpretation of Tech Specs.Leak Test Completed & Containment Verified +
- 05000413/LER-1987-012, :on 870311,instrument Air Supplies for Three Pressurizer PORVs Discovered Incorrectly Connected.Caused by Design/Installation Deficiency & Personnel Error.Air Supplies Rerouted +
- 05000414/LER-1987-016-01, :on 870413,facility Shutdown Due to Unidentified Reactor Coolant Leakage Greater than 1.0 Gallon Per Minute.Caused by Nozzle & Disc of Valve 2NM434 Badly Pitted.Valve Repaired +
- 05000461/LER-1999-002, :on 990106,loss of Offsite Power to SR Electrical Buses Was Noted.Caused by Offsite Fault on in Service Offsite Electrical Supply Line.Repairs Were Made to Faulted Line & Leaning Support Structure.With +
- 05000266/LER-1985-001, :on 850405,during Refueling Shutdown W/Plant Proceeding Toward Cold Shutdown,Pressure on Steam Line a Decreased Causing Actuation of Safety Injection.Caused by Inadequate Precautions in Procedure OP-3C +
- 05000353/LER-1992-012-02, :on 921204,both Reactor Recirculation Pumps Tripped When end-of-cycle Recirculation Pump Trip Breakers Tripped Open.Root Cause Undetermined.Upcoming Continuing Training Programs Will Be Enhanced +
- 05000293/LER-1996-005, :on 960419,automatic Scram Occurred Due to Turbine Vibration During Planned Power Reduction.Turbine Vibration Trip Setting That Initiates Trip of Turbine Due to High Vibration Changed +
- ML20095A761 +
- 05000261/LER-1983-021-03, /03L-0:on 830818,w/unit at 79% Power,Pressurizer Level Channel I (LC-459A) Failed Low.Caused by Inadvertent Deenergization of LC-459A During Routine Calibr of Other Instruments in Same rack.LC-459A Reenergized +
- 05000498/LER-1994-018, :on 941102,required 0.125 Inches Water Gauge Could Not Be Demonstrated on Trains of CR Envelope HVAC Due to Less than Adequate Surveillance Test Procedure.Electrical Auxiliary Bldg HVAC Airflows Adjusted +
- 05000498/LER-1994-018-01, :on 941102,failure to Fully Meet Requirements of TS Re CR Envelope HVAC Sys Boundary.Caused by Less than Adequate Surveillance Test Procedure.Development of Detailed Testing Method Initiated +
- 05000272/LER-1982-048-03, /03L-0:on 820724,inner Door Seal Leakage of 100 Ft Elevation Containment Air Lock Door Greater than Tech Spec. Caused by Personnel Closing Door W/Excessive Force.Seal Replaced & Personnel Trained in Proper Door Closing +
- 05000373/LER-1994-001-02, :on 940117,half Scram & Several Isolations & Half Isolations Occurred Due to Failure of Underfrequency Relay Located Inside MG Set.Rps Bus 1B Energized from Alternate Supply +
- 05000382/LER-1990-011, :on 900721,ESF Control Room Ventilation Actuations Occurred Due to Equipment Malfunction.Cause Under Investigation.Insp of Radiation Monitor Performed +
- 05000313/LER-1990-006, :on 900720,discovered motor-operated Valves & Actuators Located Below Current Accident Flood Elevation W/O Being Qualified for Submergence.Caused by Personnel Error. Change Initiated to Replace Components +
- 05000499/LER-1990-010-01, :on 900515,unplanned Actuation of ESF Train C Standby Diesel Generator Occurred.Caused by Personnel Error. Training Bulletin Will Be Issued to Maint Personnel Re Event +
- ML20096E075 +
- PLA-8095, 2023 Annual Radiological Environmental Operating Report (PLA-8095) +
- PLA-8122, Annual Radiological Environmental Operating Report (PLA-8122) +
- 05000311/LER-1988-007-02, :on 880422,reactor Trip Occurred Due to Turbine Trip as Result of Steam Generator hi-hi Level.Caused by electro-hydraulic Control (EHC) Equipment Problems.Ehc Rate Amplifier Card Replaced & Successfully Tested +
- 05000272/LER-1979-018, Forwards LER 79-018/03L-0 +
- 05000250/LER-1992-002-02, :on 920319,steam/feedwater Flow Mismatch Bistables Not Tripped within 1 H Action Statement When Steam Flow Testing in Progress.Caused by Personnel Error.Procedure Revised to Add Bistables +
- 05000315/LER-1998-023, :on 980416,potential Failure Due to Cross Train Routing of non-safety Related Cables Was Noted.Ler 98-023-00 & 98-023-01,retracted +
- 05000316/LER-1994-001-01, :on 940221,reactor Tripped on low-low Level in Steam Generator 4 as Result of Inadequate Valve Actuator/ Stroke Adjustment Procedure.Procedures Revised +
- 05000397/LER-1993-013, :on 930318 & 0412,design Errors Noted in Component Safety Classification & Design Requirements Document Programs for RCIC Primary Containment Release path.RCIC-V-31 Closed & motor-operator Deenergized +
- 05000271/LER-1991-014, Hearing - Entergy Exhibit 19, LER 1991-014-00, Vermont Yankee, Reactor Scram Due to Loss of 345KV Switchyard Caused by Defective Off-Site Carrier Equipment +
- 05000251/LER-2005-006, Regarding Manual Reactor Trip Due to Rod Control Urgent Failure Alarm +
- 05000354/LER-2005-003, Regarding Reactor Coolant System Leak from Check Valve Position Indicator +
- 05000247/LER-2002-003, Loss of 138 Kv Offsite Power Source Due to Ground Protection Trip Results in Auto Start of Emergency Diesel Generators +
- BW020004, Supplemental Startup Report for Braidwood Station, Unit 1 - Full Power Uprate Power Ascension +