Search by property
Jump to navigation
Jump to search
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
- RS-14-096, Braidwood & Byron, Units 1 and 2 - License Amendment Request to Administratively Clarify Technical Specifications (TS) 3.3.1, Reactor Trip System (RTS) Instrumentation, and TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instr + (ML14111A257)
- RS-14-096, Units 1 and 2 - License Amendment Request to Administratively Clarify Technical Specifications (TS) 3.3.1, Reactor Trip System (RTS) Instrumentation, and TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation + (ML14111A257)
- ML14111A274 + (ML14111A274)
- ML14111A276 + (ML14111A276)
- L-14-121, License Amendment Request to Extend Containment Leakage Test Frequency + (ML14111A291)
- ML14111A292 + (ML14111A292)
- ML14111A293 + (ML14111A293)
- TMI-14-002, Draft - Outlines (Folder 2) + (ML14111A294)
- ML14111A295 + (ML14111A295)
- ML14111A296 + (ML14111A296)
- ML14111A300 + (ML14111A300)
- ML14111A316 + (ML14111A316)
- ML14111A319 + (ML14111A319)
- Press Release-II-14-022, NRC Schedules May 1 Meeting in Metropolis to Discuss Honeywell Uranium Facility + (ML14111A322)
- ML14111A333 + (ML14111A333)
- ML14111A341 + (ML14111A341)
- RA-14-035, Submittal of Changes to Technical Specifications Bases + (ML14111A343)
- ML14111A344 + (ML14111A344)
- ML14111A349 + (ML14111A349)
- ML14111A351 + (ML14111A351)
- ML14111A352 + (ML14111A352)
- ML14111A355 + (ML14111A355)
- ML14111A356 + (ML14111A356)
- ML14111A367 + (ML14111A367)
- ML14111A368 + (ML14111A368)
- ML14111A370 + (ML14111A370)
- ML14111A374 + (ML14111A374)
- ML14111A375 + (ML14111A375)
- ML14111A376 + (ML14111A376)
- BVY 14-027, Request for Exemption from 10 CFR 140.11(a)(4), Vermont Yankee Nuclear Power Station + (ML14111A400)
- BVY 14-023, Request for Exemption from 10 CFR 50.54(w)(1), Vermont Yankee Nuclear Power Station + (ML14111A401)
- SBK-L-14073, Best Estimate Large Break Loss of Coolant Accident 10 CFR 50.46 30-Day Report + (ML14111A402)
- ML14111A404 + (ML14111A404)
- ML14111A407 + (ML14111A407)
- ML14111A457 + (ML14111A457)
- ML14111A458 + (ML14111A458)
- ML14111A459 + (ML14111A459)
- ML14111A463 + (ML14111A463)
- ML14111A464 + (ML14111A464)
- ML14111A465 + (ML14111A465)
- ML14111A466 + (ML14111A466)
- ML14112A003 + (ML14112A003)
- ML14112A004 + (ML14112A004)
- ML14112A005 + (ML14112A005)
- ML14112A006 + (ML14112A006)
- ML14112A007 + (ML14112A007)
- ML14112A008 + (ML14112A008)
- ML14112A009 + (ML14112A009)
- ML14112A071 + (ML14112A071)
- ML14112A072 + (ML14112A072)
- ML14112A073 + (ML14112A073)