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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 43773 + (Reactor Scram as a Result of Loss of Normal Power 13.8 Kv Bus)
- 05000220/FIN-2010002-03 + (Reactor Scram due to Inadequate Procedure for RHR Detector Restoration)
- 05000388/FIN-2013011-01 + (Reactor Scram due to Loss of Integrated Control System)
- 05000388/FIN-2014002-02 + (Reactor Scram due to Loss of Reactor Feed Pumps)
- 05000341/FIN-2011002-03 + (Reactor Scram due to Loss of Vacuum)
- ENS 42505 + (Reactor Scram from 100% Power)
- ENS 40604 + (Reactor Scram from 93% Power Due to Generator Trip)
- ENS 48598 + (Reactor Scram from 98% Power During Turbine Control Valve Testing)
- ENS 43011 + (Reactor Scram from Full Power Due to Generator Load Reject)
- 05000296/LER-2004-002 + (Reactor Scram from Main Turbine Trip from Loss of All Speed Feedback)
- 05000296/LER-2005-002, Reactor Scram from Main Turbine Trip on Low Condenser Vacuum + (Reactor Scram from Main Turbine Trip on Low Condenser Vacuum)
- ENS 42685 + (Reactor Scram on Group 1 Isolation)
- 05000341/LER-2022-001, Reactor Scram on Low Reactor Pressure Vessel Level + (Reactor Scram on Low Reactor Pressure Vessel Level)
- ENS 45866 + (Reactor Scram on Low Reactor Vessel Water Level During Feedwater Integrated Control System Testing)
- ENS 43552 + (Reactor Scram on Low Reactor Water Level Following Partial Loss of Condensate Feedwater Flow)
- ENS 43088 + (Reactor Scram with Stuck Open Main Turbine Control Valves)
- 05000263/LER-2024-001, Reactor Scram, Containment Isolation, and Cooldown Rate Outside of Limits Following Technician Adjustment of Wrong Component + (Reactor Scram, Containment Isolation, and Cooldown Rate Outside of Limits Following Technician Adjustment of Wrong Component)
- ENS 41582 + (Reactor Scrammed from 61% Power Due to Low Reactor Water Level)
- ML24101A200 + (Reactor Seismic Isolation System Qualification Topical Report - NRC 898)
- ML14091A724 + (Reactor Shield Plug)
- ML20262E669 + (Reactor Shroud Section & Details.Sheet 1)
- ML20262E672 + (Reactor Shroud Section & Details.Sheet 2)
- ML20266A336 + (Reactor Shut Down Cooling Sys 38 Piping Isometric. Sheet 1)
- ENS 52054 + (Reactor Shutdown After Technical Specification Violation)
- 05000416/LER-2017-003-02, Reactor Shutdown Because of Condensate System Inventory Depletion and a Manual Reactor Core Isolation Cooling (RCIC) Initiation Because of a Feedwater System Shutdown + (Reactor Shutdown Because of Condensate System Inventory Depletion and a Manual Reactor Core Isolation Cooling (RCIC) Initiation Because of a Feedwater System Shutdown)
- ML20266G988 + (Reactor Shutdown Cooling P&I Diagram)
- ML17055E057 + (Reactor Shutdown Cooling P&I Diagram, as-built.Sheet 1 of 2)
- ML20266A340 + (Reactor Shutdown Cooling System 38 Piping Isometric. Sheet 2)
- ENS 55380 + (Reactor Shutdown Due to Control Rod Drive Failure)
- 05000254/LER-2003-001, Reactor Shutdown Due to Reactor Head Vent Steam Leak Consulting Pressure Boundary Leakage + (Reactor Shutdown Due to Reactor Head Vent Steam Leak Consulting Pressure Boundary Leakage)
- ENS 44400 + (Reactor Shutdown Due to Small Steam Leak)
- ENS 45333 + (Reactor Shutdown Required by Technical Specifications Due to an Unisolable Leak in a Core Spray Minimum Flow Line)
- 05000389/LER-2022-001, Reactor Shutdown Required by Technical Specifications Due to a Misaligned Control Element Assembly + (Reactor Shutdown Required by Technical Specifications Due to a Misaligned Control Element Assembly)
- ENS 44994 + (Reactor Shutdown Required by Technical Specifications)
- ML13322A892 + (Reactor Shutdown from Hot Standby to Hot Shutdown, Revision 5)
- ML20053D509 + (Reactor Site Criteria:Rept to Director of Regulation by Director,Licensing & Regulation)
- ML20053D547 + (Reactor Site Criteria:Rept to General Manager by Director, Div of Licensing & Regulations)
- ML20053D519 + (Reactor Site Criteria:Rept to General Manager by Director, Div of Licensing & Regulation)
- ML20053D555 + (Reactor Site Criteria:Rept to General Manager by Director, Div of Licensing & Regulation)
- ML19345F113 + (Reactor Siting Risk Comparisons Re Recommendations of NUREG-0625, Prepared for San Francisco Operations Ofc,Doe)
- ML19261B492 + (Reactor Standby Condition for Nasa Plum Brook Mockup Reactor,Annual Rept for 1978. 4)
- ML101740432 + (Reactor Start-Up Report Following Order to Convert from High to Low Enriched Uranium Fuel at the University of Wisconsin Nuclear Reactor TAC No. MD9592 (EA-09-141))
- ENS 40735 + (Reactor Startup Cancelled Due to Erratic Source Range Monitor)
- ML19322C696 + (Reactor Startup Certification Program)
- ML031830958 + (Reactor Steam Dryer Degradation Issue)
- ML13333A776 + (Reactor Structustructural Framing Plan Elev 14 Ft)
- ML13333A777 + (Reactor Structustructural Framing Plan Elev 31 Ft)
- ML18295A195 + (Reactor Supervisor Update)
- ML20262J750 + (Reactor Support,Plan,Sections & Details)
- ML19275H317 + (Reactor Sys Branch Input to First Round Questions)
- ML19329C634 + (Reactor Sys Branch Input to Second Round Questions)