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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
- 05000315/LER-1982-041-03, /03L-0:on 820520,during Normal Startup,Feedwater Isolation Valve FMO-202 Failed While Being Utilized to Regulate Feedwater Flow.Caused by Heat Buildup Due to Frequent Cycling.Stem Nut & Motor Replaced +
- 05000259/LER-1982-041, Forwards LER 82-041/03L-0 +
- 05000373/LER-1982-041, Forwards LER 82-041/03L-0 +
- 05000331/LER-1982-041, Forwards LER 82-041/03L-0 +
- 05000311/LER-1982-041, Forwards LER 82-041/03L-0.Detailed Event Analysis Encl +
- 05000325/LER-1982-041, Forwards LER 82-041/01T-0 +
- 05000316/LER-1982-041, Forwards LER 82-041/03L-0 +
- 05000327/LER-1982-041, Forwards LER 82-041/03L-0 +
- 05000237/LER-1982-041, Forwards LER 82-041/03L-0 +
- 05000247/LER-1982-041, Forwards LER 82-041/03L-0 +
- 05000334/LER-1982-041, Forwards LER 82-041/03L-0 +
- 05000346/LER-1982-041, Forwards LER 82-041/03L-0 +
- 05000277/LER-1982-041, Forwards LER 82-041/01T-0.Detailed Event Analysis Submitted +
- 05000335/LER-1982-041, Forwards LER 82-041/03L-0 +
- 05000317/LER-1982-041, Forwards LER 82-041/03L-0 +
- 05000361/LER-1982-041, Forwards LER 82-041/03L-0.Detailed Event Analysis Submitted +
- 05000339/LER-1982-041, Forwards LER 82-041/03L-0 +
- 05000219/LER-1982-041, Forwards LER 82-041/01T-0.Detailed Event Analysis Encl +
- 05000395/LER-1982-041, Forwards LER 82-041/03L-0.Detailed Event Analysis Encl +
- 05000255/LER-1982-041, Forwards LER 82-041/03L-0 +
- 05000296/LER-1982-041, Forwards LER 82-041/03L-0 +
- 05000249/LER-1982-041, Forwards LER 82-041/03L-0 +
- 05000387/LER-1982-041, Forwards LER 82-041/03L-0 +
- 05000336/LER-1982-041, Forwards LER 82-041/03L-0 +
- 05000293/LER-1982-041, Forwards LER 82-041/03L-0 +
- 05000364/LER-1982-041, Forwards LER 82-041/03L-0 +
- 05000321/LER-1983-041, Forwards LER 83-041/03L-0 +
- 05000416/LER-1983-041, Forwards LER 83-041/03L-0 +
- 05000327/LER-1983-041, Forwards LER 83-041/03L-0 +
- 05000387/LER-1983-041, Forwards LER 83-041/03L-0 +
- 05000368/LER-1982-041, Forwards LER 82-041/03L-0 +
- 05000272/LER-1982-041, Forwards LER 82-041/03L-0.Detailed Event Analysis Encl +
- 05000366/LER-1978-041, Forwards LER 78-041/03L-0 +
- 05000336/LER-1996-041, Forwards LER 96-041-00,documenting Event at Plant on 961217.Commitments Made Re Event Listed +
- 05000352/LER-1989-041, :on 890613,four Channels of Primary Containment post-LOCA Radiation Monitor Instrumentation Inoperable. Caused by Procedural Deficiency.Temporary Procedure Change Implemented to Affected Surveillance Tests +
- 05000328/LER-1988-041, :on 881209,discovered That as-installed Instrument Cabinets Supplied by Bailey Meter Co Did Not Meet Seismic Qualification Requirements.Caused by Lack of Two Restraint Bars on Vendor Drawings +
- 05000456/LER-1987-041, :on 870808,licensed Control Room Operator Recognized That Surveillance for Tech Spec 4.2.1.1.b Not Performed When Unit at or Above 15 % Reactor Power.Caused by Programmatic Deficiency +
- 05000327/LER-1987-041, :on 870804,momentary Loss of RHR Flow Occurred When Valve 1-FCV-74-2 Inadvertently Closed,Isolating RHR Pump 1A-A Suction from RCS Loop 4 Hot Leg.Caused by Personnel Error.Student Assistant Counseled +
- 05000352/LER-1987-041, :on 870806,NSSS Isolations Occurred Due to Channel Reactor B Trip.Caused by Loose Power Supply Cable Connection to Radiation Monitor.Isolations Reset & Loose Connection Tightened +
- 05000423/LER-1987-041-01, :on 871116,discovered That 480 & 120 Volt Ac Circuit Breakers Not Tested in Accordance W/Tech Spec 4.8.4.1(a)(2).Caused by Failure to Perform Prelicensing Review +
- 05000312/LER-1987-041, :on 871026,design Review Revealed Potential for Class 2 Level Switches to Trip Nuclear Svc Cooling Water Pumps During Seismic Event.Cause Under Investigation.Trip Switch Will Be Removed from Circuitry +
- 05000245/LER-1987-041, :on 871016,discovered Design Change Implemented During Recent Refueling Outage,Requiring Tech Spec Change, Did Not Receive Prior NRC Approval.Nrc Notified & License Amend Request Submitted on 871020 +
- 05000341/LER-1987-041, :on 870329,accident Range Monitor Inoperable. Caused by Inadequate Sys Turn Over Following Preoperational Testing.Channel Parameters Will Be Verified Daily & Tech Spec Interpretation Issued +
- 05000482/LER-1987-041, :on 870927,reactor Trip Occurred from Approx 86% Power as Result of Power Range Flux High Negative Rate. Caused by Cognitive Personnel Error.Evaluation to Remove Switch Handles Will Be Conducted +
- 05000461/LER-1987-041, :on 870701,containment Penetrations Leak Tested W/Air Instead of Water Per Tech Spec 3.6.1.2(e).Caused by Util Personnel Error.Surveillance Procedure Changed Under Temporary Change Program +
- 05000424/LER-1987-041, :on 870623,reactor Trip Occurred Due to Automatic Trip of Main Turbine.Caused by Excessive Field Current Signal Due to Improperly Calibr Field Excitation Transducer.Transducer Recalibr +
- 05000424/LER-1988-041, :on 881213,containment Purge Supply Isolation Valve in Penetration 83 Not Fully Seated.Caused by Valve Not Fully Closing Even Though Limit Switch Indicated Valve Closed.Valve Manually Seated +
- 05000354/LER-1987-041, :on 870910,channel Functional Test Overdue on Primary Containment Instrument Gas Sys.Caused by Personnel Unfamiliar W/New Computerized Scheduling Sys.Training in Proper Use of New Scheduling Sys Enhanced +
- 05000327/LER-1986-041, :on 860914,power Inadvertently Removed from Logic Relay Panel for Shutdown Board 2B-B,starting Standby Diesel Generators.Caused by Procedural Inadequacy.Diesel Generators Shut Down +
- 05000413/LER-1986-041-01, :on 860801,surveillance Test Discovered Not Performed for Reactor Bldg Fire Detection Zones After Unit in Cold Shutdown for More than 24 H.Caused by Lack of Procedure Identifying Requirements +