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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

• ML19008A348  + (TH37 Decommissioning RIC 2019 Speaker Invitation to Yamana, Japan Ndf)
• ML19084A209  + (TH37 RIC 2019 Speaker Presentations)
• ML19084A216  + (TH37 RIC2019 Slides for Gerard and Vladimir Ver 5 - with Speaker Notes)
• ML19009A284  + (TH37 Speaker Invitation Letter - RIC 2019 Bruno)
• ML19008A351  + (TH37 Speaker Invitation Letter RIC 2019 Yamana)
• ML18355A745  + (TH37 Speaker Invitation Letter RIC 2019 for Rimando)
• ML19084A160  + (TH37 Speaker Thank You Letter RIC 2019 Anton)
• ML19084A162  + (TH37 Speaker Thank You Letter RIC 2019 Bruno)
• ML19084A163  + (TH37 Speaker Thank You Letter RIC 2019 Rimando)
• ML19084A164  + (TH37 Speaker Thank You Letter RIC 2019 Yamana)
• ML18059A135  + (THC 2015- TN5392--THC 2015 May 27)
• ML23241A831  + (THC Correspondence with Caitlin Brashear as of 8_29)
• ML18026A603  + (THC-2011 TN5266 - THC 2011 March 31)
• ML18026A604  + (THC-2015-TN5263--Tennessee Historical Commission 04/07/2015 Letter to TVA Re Archaeological Assessment, Clinch River Small Modular Reactors)
• ML18026A605  + (THC-2016 - TN4950--THC 2016)
• ML20128M020  + (THERMAL-HYDRAULIC Analyses of Overcooling Sequences for the H.B. Robinson Unit 2 Pressurized Thermal Shock Study)
• ML20096D039  + (THERMAL-HYDRAULIC POST-TEST Analysis of OECD Loft LP-FP-2 Experiment)
• ML20101M284  + (THERMAL-HYDRAULIC Process Modeling in Risk Analysis: an Assessment of the Relevant Systems,Structures and Phenomena)
• ML20095H644  + (THERMAL-HYDRAULIC Processes During Reduced Inventory Operation with Loss of Residual Heat Removal)
• ML20148K637  + (THERMAL-HYDRAULIC Research Plan for Babcock and Wilcox Plants)
• ML20065L982  + (THERMAL-HYDRAULIC Test Facility Bundle 3 IN-CORE Instrumentation and Operating History)
• ML20209H688  + (THERMAL-HYDRAULIC and Characteristic Models for Packed Debris Beds)
• ML20039F037  + (THERMAL-SHOCK-RESISTANT Cermet Insulators)
• ML20032B158  + (THOR-1 (Pwr):Computer Code for Predicting Thermal Hydraulic Behavior of Nuclear Reactor Sys, Interim Rept)
• ML20092F186  + (THREE-DIMENSIONAL Calculations of Transient FLUID-THERMAL Mixing in the Downcomer of the Calvert CLIFFS-1 Plant Using SOLA-PTS)

• ML19343B376  + (THREE-DIMENSIONAL Fluid Finite Element)

• ML20039F043  + (THREE-DIMENSIONAL Thermodelastic Analysis of a Fort St. Vrain Core Support Block)
• ML20151R302  + (THREE-FREQUENCY EDDY-CURRENT Instrument)
• ML13254A315  + (TI-182 Phase 2 Final)
• ML13291A442  + (TI-182 Phase 2 RFI)
• ML13175A200  + (TI-182 Phase 2 RFI 2013-004)
• ML14022A041  + (TI-182 Phase 2 RFI Final)
• ML12138A024  + (TI-182 RFI - Caf)
• ML12244A329  + (TI-182 RFI - Lfl (2))
• ML12244A196  + (TI-182 RFI - Mfe)
• ML13365A171  + (TI-186 Public Inspection Report Rev 2)
• IR 05000445/2021012  + (TI-194 Report 05000445/2021012 and 05000446/2021012)
• IR 05000445/2022010  + (TI-194 Report 05000445/2022010 and 05000446/2022010)
• ML13212A229  + (TI-2515-182 - Phase 2 - Review of Implementation of the Industry Initiative to Control Degradation of Underground Piping and Tanks)
• ML13088A299  + (TI-2515-182 Phase II Request for Information)
• ML12145A772  + (TI177 Request for Information Njf)
• ML12096A439  + (TI182 Request for Information)
• ML100880536  + (TI2515/177 Request for Information)
• IR 05000346/2016403  + (TI2800/041, 10CFR37, Physical Protection of Cat. 1 and 2 Quantities of Radioactive Material at Facilities with a 10CFR37, Physical Protection Program IR 05000346/2016403 and Exercise of Enforcement Discretion)
• ML14058A022  + (TIA - Regarding the Licensing Basis for External Flooding (GDC-2) for the Oconee Nuclear Station Standby Shutdown Facility (Ssf))
• ML083660174  + (TIA - Task Interface Agreement - Evaluation at Pilgrim of Application of TS 4.0.3, 12/31/08)
• ML041590273  + (TIA 04-02 Request for Technical Assistance Re Degraded Voltage Protection at D. C. Cook)
• ML030170555  + (TIA 2003-001 - Request for Technical Assistance Re Application of ASME Code Section XI, IWB-2430 Requirements Associated with Scope of Volumetric Weld Expansion at the Prairie Island Nuclear Generating Plant)
• ONS-2015-065, TIA 2014-04, Request for Technical Assistance Regarding the Adequacy of the Station Design and Licensing Bases for the Degraded Voltage Relay  + (TIA 2014-04, Request for Technical Assistance Regarding the Adequacy of the Station Design and Licensing Bases for the Degraded Voltage Relay)
• ML15139A049  + (TIA 2014-05, Potential Unanalyzed Condition Associated with Emergency Power System)
• ML062280456  + (TIA Closure)