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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
- 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)
- ML20125D457 + (Reactor Sys Branch Technical Position,Overpressurization Protection of PWRs While Shutdown & Cooled Down)
- ML19352A279 + (Reactor Sys Transient Analyses Using Retran Computer Code)
- ML15259A508 + (Reactor Systems Branch Safety Evaluation Input: Palo Verde Unit 2 Exigent License Amendment Request to Amend Technical Specification Surveillance Requirement 3.1.5.3 for Control Element Assembly 88 for the Remainder of Unit 2, Cycle 19)
- ML13267A080 + (Reactor Systems Branch Safety Evaluation Input to Byron Station Units 1 and 2 and Braidwood Station Units 1 and 2 Measurement Uncertainty Recapture Power Update)
- ML20148A771 + (Reactor Technology Memo RTM-4, ECCS Evaluation Guidelines)
- ML111820337 + (Reactor Test Program)
- ML20265A966 + (Reactor Themalcycles Reactors)
- ML20105B910 + (Reactor Theory & Nuclear Physics)
- ML20259D344 + (Reactor Thermal Cycles Reactor Vessel. Sheet 1.Rev Date Illegible)
- ENS 42996 + (Reactor Trip)
- ENS 42947 + (Reactor Trip)
- ENS 56544 + (Reactor Trip)
- ML19323F655 + (Reactor Trip)
- ML18087A728 + (Reactor Trip & Bypass Acb Semiannual Insp & Testing)
- ML20262J254 + (Reactor Trip (Zero Power Mode & Low SG Pressure) Bypass Schematic)
- ENS 51467 + (Reactor Trip After a Turbine Trip)
- ML20259A822 + (Reactor Trip Assemblies Detailed Schematic Diagrams)
- 05000338/LER-1981-063-03, Reactor Trip Breaker B Failed to Open When High Pressurizer Pressure Signal Simulated.Caused by Failure of Metal Latch in Undervoltage Trip Attachment.Attachment Replaced + (Reactor Trip Breaker B Failed to Open When High Pressurizer Pressure Signal Simulated.Caused by Failure of Metal Latch in Undervoltage Trip Attachment.Attachment Replaced)
- ML17251A680 + (Reactor Trip Breaker Control Schematic, as-built.Sheet 1 of 3)
- ML17251A675 + (Reactor Trip Breaker Control Schematic, as-built.Sheet 2 of 3)
- ML17254A290 + (Reactor Trip Breaker Control Schematic. Sheet 1 of 3)
- ML20265A865 + (Reactor Trip Breaker Control Schematic. Sheet 1 of 3)