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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

• ML20041F387  +
• GNRO-2003/00009, Annual Operating Report  +
• L-03-043, February 2003 Monthly Operating Report for Beaver Valley Power Station, Units 1 & 2  +
• ML021130711  +
• ML20082H545  +
• ML20072T668  +
• ML20136G796  +
• ML20136G779  +
• ML20136C184  +
• ML20244E000  +
• ML20249A533  +
• LIC-97-0137, Monthly Operating Rept for Jul 1997 for Fort Calhoun Station  +
• 2CAN109015, Monthly Operating Rept for Sept 1990 for Arkansas Nuclear One - Unit 2  +
• ML24299A217  +
• 05000414/LER-1987-023, :on 870807,unit Shutdown Commenced Per Tech Specs When One Steam Generator Main Feedwater Bypass to Auxiliary Feedwater Nozzle Valves Discovered Partially Open. Caused by Mgt Deficiency.Evaluation Initiated  +
• 05000499/LER-1992-006, :on 920522,component Cooling Water Outlet Valve from RHR HX 2C Opened & Header Pressure Decreased & Pump 2A Automatically Started.Possibly Caused by Loss of Power to Solenoid Valve.Visual Insp of Valve Performed  +
• 05000414/LER-1991-012-02, :on 911017,unexpected ESF Actuation Occurred, Resulting in Partial Actuation of ATWS Mitigation Sys & Actuation Circuit.Caused by Functional Design Deficiency in Circuit.Pump 2B Secured & Sys Realigned  +
• 05000368/LER-1990-020, :on 900928,motor-operated Valved Failed to Close on Main Condenser Circulating Water Pump Resulting in Loss of Vacuum & Subsequent Manual Reactor Trip  +
• 05000293/LER-1993-015, :on 930630,HPCI Sys Declared Inoperable Due to Indicated Flow During Surveillance.Caused by Foreign Matl That Plugged Portion of Restricting Orifice.Restricting Orifice Removed,Cleaned & Reinstalled  +
• 05000278/LER-1993-002-03, :on 930307,automatic Scram on Reactor Water Level When Reactor Feed Pump Feed Tripped on High Vibrations.Evaluation Will Be Performed on Defective Controller to Identify C/As Necessary  +
• 05000280/LER-1987-034, :on 871126,specific Activity Sample of Reactor Coolant Showed Dose Equivalent I-131 of 1.19 Uci/Cc.Caused by Fuel Element Defect in Reactor Core.Required Tech Spec 4.1.2B Implemented  +
• GO2-96-247, Requests Enforcement Discretion from DG Testing Per TS 3.8.1.1.A.Request Specifically Asks That SR 4.8.1.1.2.a.4 Not Be Repeated for Duration of Current Entry to TS Action 3.8.1.1.a  +
• ML17317B508  +
• 05000259/LER-2009-006-01, 1 for Brown Ferry, Unit 1 Regarding Inoperable High Pressure Coolant Injection Pump Due to Emergency Core Cooling System Inverter Failure  +
• 05000263/LER-2011-003, Regarding Secondary Containment Damper Icing  +
• ML061360319  +
• ML25077A178  +