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

• IR 05000443/2006016  +
• ML18045A052  +
• ML101260445  +
• ML19112A078  +
• ML19029B020  +
• ML18045A216  +
• ML19310A362  +
• NL-02-008, December 2001 Monthly Operating Report for Indian Point, Unit 2  +
• ML20093H193  +
• ML20244E000  +
• ML20210B049  +
• ST-HL-AE-4258, Special Rept:On 921007,SDG Tripped on Turbocharger Thrust Bearing Failure.Caused by Improper Installation of New Eutectic or Degradation of Turbocharger.Turbocharger Replaced.Vendor Manual,Drawings & Procedures Revised  +
• ML24172A022  +
• L-2024-061, NextEra Energy Seabrook, LLC, License Amendment Request - One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite Transmission Network and the Onsite Class 1E Distribut  +
• ML24239A538  +
• L-2024-137, Second Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent .  +
• L-2024-127, Supplement to Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent  +
• L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite.  +
• 05000324/LER-1989-004, :on 890225,steam Leak Occurred on RCIC Outboard Steam Supply Isolation Valve in Vicinity of Steam Leak Detection Temp Switch.Caused by Actuation of Steam Supply Isolation Valve.Weld Seal Completed  +
• 05000324/LER-1989-004-02, :on 890225,channel a of RCIC Sys Steam Leak Detection Instrumentation Received Isolation Signal & Inboard Isolation Valve Isolated.Caused by Steam Leak.Valve Body to Bonnet Joint Wrapped W/Blankets  +
• 05000333/LER-1997-005, :on 970525,manual Reactor Scram Occurred Due to Failure of Number 3 Main Tcv.Caused by Damaged Valve Spring Can Coupling.Replaced Valve Spring Can Coupling Bolt of Four TCVs & Four CIVs & Completed Review  +
• 05000267/LER-1988-014, :on 881008,plant Protective Sys Loop Shutdown Function for Loop II Unexpectedly Actuated.Specific Cause Unidentified.Station Svc Requests to Blowdown All Circulator Water Flow Performed  +
• 05000414/LER-1997-004-03, :on 970424,inadequate Test of Containment Isolation Valve Identified.Caused by Inadequate Work Practices.Personnel Involved Counseled Re Improved Performance  +
• 05000254/LER-1986-032, :on 861108,1/2 DG Feed Breaker to Bus 13-1 Tripped,Causing Loss of Power to Bus 13-1 & RPS Bus A.Caused by Trip of Underexcitation Relay.Work Request Q50657 Written to Calibrate Underexcitation Relay  +
• 05000374/LER-1995-008-02, :on 950415,reactor Scrammed from High Scram Discharge Vol Water Due to Mgt Deficiency.Operating Personnel Responded to Alarm/Annunciator Conditions & Performed Required Immediate Action  +
• ML20050A820  +
• ML20058P269  +
• 05000280/LER-1999-004-01, :on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms  +
• 05000272/LER-1980-024-03, /03L-0:on 800425,during Normal Operation,Svc Water Flow to Number 12 Containment Fan Coil Unit Decreased to Zero.Caused by Failure of Solenoid Valve SV-624.Action Statement 3.6.2.3. Entered & Valve Replaced  +
• 05000260/LER-1991-018-01, :on 911018,reactor Manually Scrammed from Approx 8% Thermal Power Due to Expected Equipment Response. Caused by Inappropriate Personnel Action.Reverse Power Relay Tested & Plant Design Will Be Changed  +
• 05000354/LER-2005-003, Regarding Reactor Coolant System Leak from Check Valve Position Indicator  +
• IR 05000352/1987025  +
• RS-90-203, Circulating Water Sys Availability Analysis River Bend Nuclear Station  +