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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

• 05000261/LER-2002-001, From H.B. Robinson, Unit 2 Regarding Four Main Steam Safety Valves Failure to Meet Acceptance Criteria During Lift Pressure Testing  +
• ML14188B474  +
• ML17262A418  +
• ML092260131  +
• ML092240077  +
• ML19056A409  +
• ENS 44153  +
• ENS 46199  +
• ML20054G215  +
• ML20086F644  +
• ML20084E231  +
• ML20102B143  +
• ML20092L917  +
• ML20112E086  +
• ML20148J589  +
• ML20138Q549  +
• ML20198J535  +
• ML20212G726  +
• ML20217P355  +
• 1CAN038605, Monthly Operating Rept for Feb 1986  +
• 2CAN129202, Monthly Operating Rept for Nov 1992 for Arkansas Nuclear One Unit 2  +
• NG-75-1089, Revised AO 50-261/75-8:on 750429,RHR Suction Valve RHR-862A Failed.Caused by Torque Switch on Motor Operator Being Out of Adjustment,Causing Valve to Be Wedged Onto Seat & Preventing Motor from Opening Valve  +
• ML20058K863  +
• ML22014A020  +
• 05000414/LER-1988-032, :on 881124,automatic Start of Auxiliary Feedwater Pump 2A Occurred.Caused by Equipment Malfunction. Work Request 41991 initiated,2CF6 Repaired,Pump 2A Secured & Blowdown Isolation Realigned  +
• 05000029/LER-1989-005, :on 890406,reactor Was Manually Tripped When Main Steam Line 1 Isolation Valve Inadvertently Closed. Caused by Technician Performing Routine Surveillance Test Missing One Step.Technicians Counseled  +
• 05000461/LER-1989-022, :on 890526,insertion of Manual Scram Signal Caused Reactor Water Level to Drop.On 890601,valve 1FW004 Failed to Shut in Response to Control Signal.First Event Caused by Faulty servo-amplifier Board  +
• 05000219/LER-1989-015, :on 890518,reactor Automatically Shut Down Due to Trip of Main Turbine Generator.Caused by Personnel Error. Administrative Controls Implemented & Operators Briefed on Need to Use All Available Indications  +
• 05000265/LER-1988-022-05, :on 880531 & 0601,loss of Chimney Monitors Occurred When Power Supply Deenergized for Maint.Caused by Procedure Inadequacies Since Ref Documents Did Not Clearly Identified Affected Equipment  +
• 05000293/LER-1987-009, :on 871023,Failure & Malfunction Rept 87-600 Written to Document Original Design/Const Deficiency Identified During Review of Conduit Layout Drawing E-343. Caused by Deficiency in Original Plant Design  +
• 05000498/LER-1989-005, :on 890120,alarms for Turbine Generator High Vibration & Bearing 8 & 9 High Temp Received W/Fire Subsequently Reported at Bearing 9.Caused by Loss of Cooling Hydrogen Due to Loose Temp Sensor Connection  +
• 05000410/LER-1986-010, :on 861123,25% of Control Rods Received Full Scram Signal When Group 2 Control Rod Scram Solenoid Valves Deenergized.Cause Not Positively Determined.Training Mod Request Will Be Issued.Procedures Revised  +
• 05000311/LER-1984-006-01, :on 840318,loss of 2B 4 Kv Vital Bus Occurred While Paralleling Emergency Diesel Generator 2B W/Grid. Caused by Phase Mismatch.All 4 Kv Breakers Racked Out & Inspected  +
• 05000311/LER-1981-094-01, /01T-0:on 810918,during Routine Containment Insp, Operator Found Svc Water Leaking from Primary Coil on Containment Fan Coil 23 at Approx 0.5 Gpm.Caused by Primary Coil Failure.Cooling Coil Blank Flanged Off  +
• 05000311/LER-1981-094, Forwards LER 81-094/01T-0.Detailed Event Analysis Encl  +
• ML20003F761  +
• 05000334/LER-1980-111-03, /03L-0:on 801211,steam Generator Feed Pump Suction Pressure Low Alarm Was Received.Caused by Control Rod Insertion.Rods Partially Borated Back Out of Core,Restoring Delta Flux to within Target Band  +
• NUREG-0227, Partial Draft of Nuclear Power Plant Operating Experience - 1978, Section 3.0, Plant Outages. Portions of NUREG-0483, NUREG-0366 & NUREG-0227 (Plant Operating Experience for 1977,1976 & 1974-75,respectively) Encl  +
• 05000311/LER-1989-001, :on 890103,2C Sec Declared Inoperable Due to Auto Test Fault.Caused by Equipment problems.2C Chassis Replaced & Tested Successfully  +
• IR 05000275/1987013  +
• 05000440/LER-2016-001, Regarding Drywell Leakage, Level 8 Automatic Scram and APRM Loss of Safety Function  +
• ML17059B820  +
• 05000446/LER-2008-001, Re Reactor Trip Due to a Sheared Condenser Vacuum Instrument Sensing Line  +
• ML16341E256  +
• ML16341E255  +
• 05000368/LER-1986-006, :on 860421,inadvertent Actuation of Reactor Protective Sys Occurred.Caused by Channel a Sys Departure from Nucleate Boiling Ratio & High Local Power Density Trip Functions Bypassed During Shutdown Operations  +