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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

• ENS 48651  +
• 05000416/LER-2003-003, Re Containment Airlock Seal Air Leakage in Excess of Technical Specification Allowable Rate  +
• ML100550484  +
• ML092260131  +
• ML092240077  +
• ML18096A230  +
• PLA-7699, Annual Radiological Environmental Operating Report for 2017  +
• ML20079E727  +
• ML20104B169  +
• ML20078H441  +
• IR 05000312/1985036  +
• IR 05000255/1985027  +
• ML20151U171  +
• ML20150A629  +
• IR 05000395/1999002  +
• ML20206N226  +
• ML20065F842  +
• ML20214V282  +
• 2CAN058904, Monthly Operating Rept for Apr 1989 for Arkansas Nuclear One Unit 2  +
• RBG-22911, Summary Rept of Notification of Unusual Event:On 860101,trip of Preferred Station Transformers 1RTX-XSR1A & 1RTX-XSR1C Occurred.Caused by Fancy Point Breakers Receiving Spurious Trip Signal from Fiber Optic Cable Sys.Sys Isolated  +
• 05000301/LER-1987-005, :on 871120,control Rod C7 Discovered to Be Out of Alignment.Caused by Blown Fuse.Quadrant Flux Tilt Verified & Found Acceptable.Fuse Replaced  +
• 05000412/LER-1987-004, :on 870626,reactor Trip Breakers Reclosed & Control Rod Test Commenced Following Suspension of Test Due to Potential Tech Spec Violation.On 870627,breakers Reopened When Tech Spec 3.0.3 Violation Confirmed  +
• 05000412/LER-1987-004-01, :on 870626,intermediate Range Neutron Flux Instruments Not Verified Operable in Accordance W/Tech Spec. Caused by Failure to Identify Implications of Closing Reactor Trip Breakers.Test Completed  +
• 05000334/LER-1999-012, :on 990915,inoperability of Loop 1 Over Temperature Delta Temperature Function,Was Discovered.Caused by Personnel Error.Discussed with I&C Technicians.With  +
• 05000373/LER-1999-003-04, :on 990902,reactor Scram on Low Reactor Water Level,Was Received.Caused by Personnel Error.Appropriate Disciplinary Action Taken with non-licensed Operator  +
• 05000414/LER-1986-033-01, :on 860711,Phase a Containment Isolation Occurred,Closing Nonessential Containment Penetration Isolation Valves.Cause Not Determined.Valves Will Be Tested to Verify Proper Operation.Tech Specs Will Be Revised  +
• 05000219/LER-1988-008, :on 880414,reactor Bldg Isolation & Standby Gas Treatment Sys Automatic Initiation Occurred.Caused by Personnel Error.Emergency Operating Procedures Entered for Secondary Containment Control  +
• 05000277/LER-1992-005, :on 920326,2B Reactor Water Level Reference Leg Condensing Chamber Was Declared Inoperable.Caused by Loss of Inventory in 2B Condensing Chamber.Leaks Were Repaired & Instrument Lines Were Backfilled  +
• 05000260/LER-1983-026-03, /03L-0:on 830521,during Rod Sequence Exchange, Calculated R Factor Less than R Setpoint.Caused by R Factor Calculated Out During Power Shaping Rod Moves.Rod Pattern Adjusted & Verified  +
• 05000353/LER-1990-015-02, :on 900910,reactor Scram Occurred Due to Spurious Trip Signal from Steam Leak Detection Sys Temp Switch.Caused by Equipment Failure.Temp Switch TTS-25-216D Was Replaced  +
• 05000353/LER-1990-012-02, :on 900715,reactor Scram Occurred Due to Main Turbine Trip on Low Main Condenser Vacuum Due to Failed Pipe.Caused by Insufficient Pipe Support Resulting in Vibration Induced Metal Fatigue.Pipe Replaced  +
• 05000346/LER-1980-044-03, /03L-0:on 800531,decay Heat Flow Indication FI-DH2B Dropped Low Off Scale.Caused by Technician Performing Surveillance Test on Inservice Flow Transmitter String W/O Shift Supervisor Knowledge  +
• ML19320B484  +
• 05000397/LER-1989-016, :on 890514,reactor Operator Inadvertently Tripped Div 1 & 2 Offsite Power Supply Feeders Resulting in Loss of Power to Buses SM-7 & SM-4.Caused by Inadvertent Removal of Transformer Fuses.Fuses Reinserted  +
• 05000316/LER-2006-001, Re Failure to Comply with Technical Specification 3.6.2, Containment Air Locks  +
• 05000254/LER-2000-010-01, Re Automatic Reactor Scram from Low Reactor Vessel Level  +
• ML20216D333  +
• TXX-9335, Forwards Omega Point Lab Test Repts for Most Recent Util Fire Endurance Tests.Engineering Rept ER-EE-006,Rev 0, Evaluation of Fire Endurance Test Results Related to Cable Functionality in 1-1/2 & 2 Inch Conduits Also Encl  +