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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
- 05000325/LER-1982-048, Forwards LER 82-048/03L-0 +
- 05000311/LER-1982-048, Forwards LER 82-048/03L-0.Detailed Event Analysis Encl +
- 05000316/LER-1982-048, Forwards LER 82-048/03L-0 +
- 05000321/LER-1982-048, Forwards LER 82-048/03L-0 +
- 05000366/LER-1982-048, Forwards LER 82-048/03L-0 +
- 05000219/LER-1982-048, Forwards LER 82-048/03L-0.Detailed Event Analysis Encl +
- 05000317/LER-1982-048, Forwards LER 82-048/03L-0 +
- 05000338/LER-1982-048, Forwards LER 82-048/03L-0 +
- 05000272/LER-1982-048, Forwards LER 82-048/03L-0.Detailed Event Analysis Encl +
- 05000259/LER-1982-048, Forwards LER 82-048/03L-0 +
- 05000339/LER-1982-048, Forwards LER 82-048/03L-0 +
- 05000331/LER-1982-048, Forwards LER 82-048/03L-0 +
- 05000302/LER-1982-048, Forwards LER 82-048/03L-0.Detailed Event Analysis Encl +
- 05000361/LER-1982-048, Forwards LER 82-048/03L-0.Detailed Event Analysis Submitted +
- 05000317/LER-1978-048, Forwards LER 78-048/03L-0 +
- 05000302/LER-1978-048, Forwards LER 78-048/03L-0 +
- 05000368/LER-1982-048, Forwards LER 82-048/03L-0 +
- 05000395/LER-1982-048, Forwards LER 82-048/03L-0.Detailed Event Analysis Encl +
- 05000387/LER-1982-048, Forwards LER 82-048/03L-0 +
- 05000293/LER-1982-048, Forwards LER 82-048/03L-0 +
- 05000346/LER-1982-048, Forwards LER 82-048/03L-0 +
- 05000335/LER-1982-048, Forwards LER 82-048/03L-0 +
- 05000333/LER-1982-048, Forwards LER 82-048/03L-0 +
- 05000327/LER-1983-048, Forwards LER 83-048/03L-0 +
- 05000387/LER-1983-048, Forwards LER 83-048/03L-0 +
- 05000249/LER-1982-048, Forwards LER 82-048/03L-0 +
- 05000369/LER-1982-048, Forwards LER 82-048/03L-0 +
- 05000528/LER-1985-048, Corrected LER 85-048-00:on 850819,ECCS Subsystem RQ & Bp Declared Inoperable Due to Noncompliance W/Surveillance Requirement 4.5.2.g.1.Temporary Change Initiated to Permit Testing of ECCS Throttle Valves +
- 05000315/LER-1982-048, Forwards LER 82-048/03L-0 & LER 82-049/03L-0 +
- 05000369/LER-1988-048, :on 880822,noted That Shrinkage of Boraflex Neutron Absorbing Matl Could Cause Increase in Reactivity, Per NRC Info Notice 87-043.Caused by Design Deficiency.Util & Westinghouse Performed Analyses +
- 05000352/LER-1989-048, :on 890801,various Primary & Secondary Containment Isolation Valves Received Isolation Signals. Caused by Instrumentation & Control Technician Error.Trip Signal & Associated Isolations Reset +
- 05000461/LER-1987-048, :on 870817,limiting Condition for Operation Entered When Main Condenser Offgas Treatment Sys Hydrogen Monitors Declared Inoperable.Caused by Personnel Error. Revised Scheduling Directive Issued +
- 05000354/LER-1987-048, :on 871125,trip of Safety Auxiliary Cooling Sys (Sacs) Pumps B & D & Automatic Start of Pump a Occurred. Caused by Lack of Precautions in Sacs Venting Procedure. Procedure for Venting Room Coolers Revised +
- 05000424/LER-1987-048, :on 870618,required Tech Spec Leakage Test Not Performed.Caused by Personnel Error.Work Control Process Evaluated to Ensure That Work Orders Which Effect Tech Spec Surveillance Requirements Adequately Reviewed +
- 05000440/LER-1987-048, :on 870703,containment Fire Hose Reel Inboard/ Outboard Supply Isolation Valves Discovered in Open Position Since 870622.Caused by Procedural Deficiency.Integrated Operating Instructions Will Be Reviewed & Revised +
- 05000327/LER-1987-048, :on 870422,3 of 16 Conductors Considered worst- Case Vertical Drop Cables Failed high-potential Test.Lab Testing Found Silicone Rubber Cables More Susceptable to Impact Damage.Root Cause Unknown +
- 05000352/LER-1987-048, :on 870919,reactor Scrammed Following Main Turbine Trip on electro-hydraulic Control Low Oil Pressure. Caused by Failure of Tubing Socket Weld in Fluid Actuating Supply Line.Failed Weld Replaced W/New Section +
- 05000423/LER-1987-048, :on 871203 & 05,drain Hoses Discovered Strung Through Train B Recirculation Spray Sys Cubicle & Control Bldg Equipment Room Door,Respectively.Caused by Human Error. Memo to Reinforce Correct Methods Issued +
- 05000423/LER-1997-048, :on 970806,oversized Primary Grade Water Sys Pump Impeller Could Result in Boron Dilution Event Was Determined.Caused by Insufficient Configuration Control in Design Program.Valves Administratively Locked Closed +
- 05000352/LER-1986-048, :on 861003,nuclear Steam Supply Shutoff Sys Isolation Occurred.Caused by Improper Valve Sequencing by Personnel.Isolation Reset & Personnel Counseled +
- 05000414/LER-1986-048-01, :on 861107,during Performance of Manual Reactor Trip Functional Test Procedure,Main Feedwater Sys Isolation Occurred.Cause Undetermined.Isolation Reset & Affected Valves Returned to Previous Alignment +
- 05000327/LER-1986-048, :on 860820,during Review of Plant Surveillance Instructions,Adequacy of SI-260.2, Bit Cold Leg... Questioned.On 861016,CCP 2A-A Failed to Meet Acceptance Criteria.Caused by Inadequate Procedure +
- 05000354/LER-1986-048, :on 860730,reactor Scrammed on Reactor Vessel Low Water Level 3 Signal.Caused by Electrohydraulic Control Sys (EHC) Power Failure.Ehc Power Supply Trip Points Calibr & Event Reviewed W/Operators +
- 05000528/LER-1986-048-01, :on 860902,Limiting Condition for Operation 3.0.3 Entered Due to Inoperable MSIV Accumulators a & B. Caused by Oil Returning to Reservoir.Tech Spec Change Pursued +
- 05000440/LER-1986-048, :on 860819 & 20,unexpected RHR Sys Isolations Occurred During Performance of Maint Retest.Caused by Inadequate Surveillance Test Instruction (Svi) & Poor Jumper Connection,Respectively.Svi Revised +
- 05000321/LER-1985-048, LERs 85-048,85-049 & 85-051 Have Been Canceled +
- 05000458/LER-1986-048, :on 860804,discovered That Daily Surveillance Test STP-500-4550 Re Control Sys High & Low Power Setpoint, Not Performed Since 860802.Control Rods Also Pulled.Caused by Poor Scheduling.Schedule to Be Distributed +
- 05000213/LER-1986-048, :on 861212,discovered That Adequate Core Cooling Could Not Be Insured for Intermediate Break LOCA Postulated in Core Deluge Sys.Caused by Inaccurate Tech Specs.Sys Mods Initiated +
- 05000423/LER-1986-048, :on 860817,while in Mode 1 at 1190 Power, Reactor Trip Occurred When Steam Generator 3 Level Reached lo-lo Level Trip Setpoint.Caused by Operator Error.Steam Generator 3 Level Controller Regroomed +
- 05000341/LER-1986-048, :on 861226,during Calibr of Instrument Channel, Two Occurrences of RCIC & HPCI Being Inoperable Resulted. Caused by Personnel Error & Inadequate Communication. Personnel Involved in Incident Counseled +