Search by property

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

• HNP-12-082, Request for Enforcement Discretion, Technical Specification (TS) 3.8.1 A.C. Sources - Operating  +
• ML18219E086  +
• NL-04-004, December 2003 Monthly Operating Report for Indian Point, Units 2 and 3  +
• ML20070F946  +
• 05000414/LER-1988-004-04, :on 880103,initial Evaluation of Eddy Current Testing Revealed Defective Tube in Steam Generator 2B.Caused by Mfg Deficiency.Foreign Objects Responsible for Tube Damage Removed & Tubes Plugged  +
• 05000414/LER-1986-005-03, :on 860417,discovered Leak Rate Retest Not Performed on Containment Isolation Valve Following Maint. Caused by Personnel Error.Personnel Counseled  +
• 05000414/LER-1988-021, :on 880603,manual Reactor Trip Initated Due to Imminent lo-lo Steam Generator Level.Caused by Closed Auxiliary Steam Header Supply Isolation Valve IAS59. Extensive Investigation of IAS59 Performed  +
• 05000413/LER-1988-009, :on 880206,Limitorque Valve Actuator T-drains Found Painted Over or Missing on 27 Valves.Caused by Lack of Communication & Mgt Deficiency.Painters Will Receive Periodic Retraining.Drains Repaired  +
• 05000254/LER-1997-005-03, :on 970319,HPCI Subsystem Was Made Inoperable to Protect Equipment Due to Uncertainties Re Abandoned Power Feed Cable,Which Had Been Inappropriately Abandoned. Plant Design Documents Have Been Updated  +
• ML20035E799  +
• ML20027A157  +
• ML20036B253  +
• ML20042E319  +
• 05000346/LER-1978-029-01, /01T-1:on 780405,util Was Notified of Possible Design Deficiency of Burnable Poison Rod Assembly Locking Mechanism.B&W Recommended Reduced Reactor Coolant Flow. Reactor Coolant Pump 1-1 Shut Down to Decrease Flow Uplift  +
• 05000338/LER-2016-003, Regarding Engineered Safety Feature Actuation Due to Loss of Power to a Reserve Station Service Transformer  +
• 05000388/LER-2015-003, Regarding Automatic Reactor Scram Caused by Main Turbine Trip Due to Loss of Main Condenser Vacuum  +
• 05000440/LER-2005-001, And LER 05-001-00 Perry Nuclear Power Plant Regarding Unplanned Automatic Oscillation Power Range Monitor Scram and Manual Reactor Scram Following Unexpected Reactor Recirculation Pump Trip  +
• ML040200250  +
• IR 05000254/1977014  +
• 05000499/LER-1995-005-01, :on 950412,experienced Inadvertent ESF Actuation of CCW Pump Due to Essential Cooling Water Sys Pressure Switch Being Isolated & Depressurized.Verified Position of Essential CW Isolation Valves  +