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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
- 05000336/LER-2001-004 +
- 05000272/LER-1990-012-01, :on 900409,reactor Trip on Steam Generator 12 lo-lo Level Occurred.Caused by Equipment Failure.Steam Generator 12 Governor Valve Linkage Repaired +
- ML19350D114 +
- L-03-077, April 2003 Monthly Operating Report for Beaver Valley, Units 1 and 2 +
- ML030800569 +
- ML20059C494 +
- ML021440160 +
- L-02-026, February 2002 Monthly Operating Report for Beaver Valley Units 1 & 2 +
- ML20086H808 +
- ML20079M941 +
- ML20100R429 +
- ML20100N128 +
- 05000311/LER-1982-128, Forwards LER 82-128/01T-0.Detailed Event Analysis Encl +
- ML20064H874 +
- ML20237A120 +
- ML20247E996 +
- ML20209J183 +
- 05000412/LER-1987-011, :on 870730,two Surveillance Procedures in Progress Requiring Channel IV Steam Pressure Bistables for Steam Generator 21C to Be in Tripped Condition.Caused by Personnel Error.Test Engineer Reassigned +
- 05000237/LER-1986-019-04, :on 860811,while Reactor Operating at 91%,main Turbine Tripped on +55 Inches Reactor Water Level Which Resulted in Full Reactor Scram.Caused by Failure of Feedwater Regulating Valve a to Close +
- 05000293/LER-1988-024-01, :on 881017,Group 1 Isolation Signal Due to High Water Level in Reactor Vessel Occurred.Caused by Disassociation of Pin from Feedback Cam Linkage of Valve Positioner for Valve.Linkage Secured +
- 05000265/LER-1987-009-10, :on 870801,reactor Scram Occurred from Turbine Generator Load Mismatch Due to Generator Trip as Result of Fault in Main Transformer.Cause Under Investigation.Main Transformer Replaced +
- 05000324/LER-1987-012-03, :on 871207,unplanned Div I Primary Containment Group 5 Isolation of RCIC Sys Occurred.Caused by Personnel Error.Jumper Reinstalled & RCIC Sys Returned to Standby Readiness +
- 05000382/LER-1985-022, :on 850524,automatic Actuation of Reactor Protective Sys Occurred.Caused by Lack of Pressure Equalization Across Main Valve Piston.Valves Stroked at Cold Conditions +
- 05000245/LER-1996-048, :on 960816,RPS Logic Testing Questions Identified During GL 96-01 Review.Subsequent Review Determined Surveillance Procedures Satisfactorily Meet All TS Requirements.No Corrective Action Needed +
- 05000412/LER-1992-006, :on 920501,bistables for Channel I Pressurizer Pressure Tripped,Resulting in Safety Injection Block Signal & ESF Actuation.Caused by Inadequate Work Request Review.Signal Reset +
- 05000325/LER-1995-015, :on 950713,automatic Reactor Shutdown Occurred Due to electro-hydraulic Control Pressure Regulator Malfunction.Replaced Four Electronic Circuit Boards Comprising a EHC Pressure Regulator +
- 05000324/LER-1991-010-02, :on 910806,RWCU Sys Automatically Isolated on High Differential Flow While Being Restored to Svc.Caused by Inadequate Procedures.Rwcu Reject to Main Condenser Isolation Valve Replaced +
- 05000346/LER-1993-007, :on 931020,after Preventive Maint,Determined Train of AFW & Motor Driven Feedwater Pump Incapable of Feeding SG 1 Should SG 2 Fail.Caused by Misunderstanding of AFW Sys.C/A:Review Chapter 15 of USAR +
- 05000311/LER-1981-065-03, /03L-0:on 810716,operator Noticed That Steam Generator 23 Feed Flow Channel 2 Had Failed Low & Was Declared Inoperable.Caused by Equipment Failure.Feed Flow Channel 2 Meter Was Replaced W/Spare +
- 05000311/LER-1981-065, Forwards LER 81-065/03L-0.Detailed Event Analysis Encl +
- 05000293/LER-1989-033, :on 891106,automatic Actuation of Group 1 Portion of Primary Containment Isolation Control Sys (PCIS) Occurred.Caused by High Reactor Vessel Water Level.Manual Valve Closed & PCIS Logic Circuitry Reset +
- 05000265/LER-1987-009-02, :on 870801,reactor Scram Occurred from Turbine Generator Load Mismatch Due to Generator Trip.Caused by Electrical Fault in Main Transformer C Phase Windings.Main Transformer Replaced W/Spare +
- 05000260/LER-1992-004-02, :on 920427,reactor Scrammed on Low Reactor Water Level.Caused by Failure of Feedwater Control Sys Resulting in Feedwater Pump run-back & Low Flow to Reactor Vessel.Maint Planning Guide Revised +
- 05000237/LER-1987-019, :on 860811,reactor Scram Occurred from Main Turbine Trip on High Water Level.Caused by Personnel Error. Event Will Be Reviewed W/All Operators & Action Item Record 12-87-10 Issued to BWR Engineering Dept +
- 05000454/LER-2015-003, Re One Train of Diesel Generator System Inoperable Longer than Allowed by Technical Specifications Due to Loss of Diesel Fuel Oil System Volume +
- 05000259/LER-2010-004, For Browns Ferry Nuclear Plant Unit 1, Residual Heat Removal Low Pressure, Injection System Pump Motor Failure +
- 05000259/LER-2010-003, Regarding Failure of a Low Pressure Coolant Injection Flow Control Valve +
- 05000280/LER-2003-006, Regarding Steam Generator AFW Isolation Unanalyzed Condition from Original Design +
- ML020850558 +
- ML031130136 +
- 05000482/LER-1996-004, :on 960323,violation of TS 3.5.4 Occurred. Caused by Personnel Error.Clearance Order 95-0510-EM Was Revised to Address Tagging Feeder Breakers de-energized for Four SI Pump Discharge Valves +
- 05000461/LER-1992-008-01, :on 920623,inattention to Detail Surveillance Resulted in Mispositioning Reactor Mode Switch & Actuation of Containment Isolation Valves & Reactor Protection Sys. Operator Counseled +
- 05000412/LER-1987-011-01, :on 870730,inadvertent Safety Injection Occurred Due to Low Steam Line Pressure.Caused by Personnel Error.Test Engineer Reassigned & Incident Will Be Reviewed at Safety Meetings +