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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
- ML20076G233 + (Structural Analysis of GE Spent Fuel Racks for Zimmer Nuclear Power Station)
- ML20027D036 + (Structural Analysis of Peach Bottom Units 2 & 3 Reactor Pressure Vessel Head Drop,Shroud Head Assembly Drop & Steam Dryer Assembly Drop Conditions)
- ML20079P200 + (Structural Analysis of Pilgrim Vessel Head Drop,Shroud Head Assembly Drop & Steam Dryer Assembly Drop Conditions)
- ML20133D254 + (Structural Analysis of Pressurizer Safety & Relief Line for Alvin W Vogtle Nuclear Plant,Unit 1)
- ML20052B411 + (Structural Analysis of Spent Fuel Pool Liner & Concrete Due to Coolant Sys Failure for Big Rock Point Nuclear Power Plant, Revision 1)
- ML18059A480 + (Structural Analysis of Temperature Nozzle Weld Mods for Consumers Power Palisades Pressurizer)
- ML20211G374 + (Structural Assessment of Candidate Fuel Basket Designs for Storage & Transport of Spent Nuclear Fuel, Presented at 980114-16 Inmm Meeting in Washington,Dc)
- ML121160414 + (Structural Assessment of Seabrook Station - Role of Concrete Material Testing)
- ML121160349 + (Structural Assessment of Seabrook Station - Role of Concrete Material Testing)
- ML19323E722 + (Structural Bldg Response Review)
- ML19323E929 + (Structural Bldg Response Review,Seismic Safety Margins Research Program)
- ML20236N936 + (Structural Calculation Rept for Rpv,Sg & Pzr Shipping Skids & Tiedowns)
- ML17037A662 + (Structural Comparison of Fault Zone in Boring Series T-3, Plate 5-11)
- ML17037A663 + (Structural Comparison of Fault Zone in Boring Series T-4, Plate 6-12)
- ML19210D161 + (Structural Condition Documentation & Structural Capacity Evaluation of Battelle Memorial Inst Columbus Labs,West Jefferson Site for Earthquake & Flood, Prepared for Lll)
- ML19242C807 + (Structural Condition Documentation & Structural Capacity Evaluation for Earthquakes & Flood, Task Ii,Structural Capacity Evaluation,Vol I,Seismic Evaluation,Prepared for Lll)
- ML19210C919 + (Structural Condition Documentation & Structural Capacity Evaluation of Atomics Intl Nuclear Matls Development Facility at Santa Susana,Ca,For Earthquake & Flood, Prepared for Lll)
- ML19250C221 + (Structural Condition Documentation & Structural Capacity Evaluation of Atomics Intl Nuclear Matls Development Facility at Santa Susana,Ca for Earthquake & Flood, Task II Structural Capacity Evaluation)
- ML20058J639 + (Structural Consequences of In-Place Thermal Annealing of Nuclear Reactor Pressure Vessels)
- ML17279A818 + (Structural Containment Vessel. Sheet 6)
- ML20210J412 + (Structural Controls on Groundwater Flow in Yucca Mountain Region)
- ML19309F828 + (Structural Design Assessment for Safe-End Break)
- ML20024D971 + (Structural Design Audit Guidelines)
- ML20234E082 + (Structural Design Considerations & Safety Against Earthquakes,Bodega Bay Atomic Park,Unit 1)
- ML19308E098 + (Structural Design Criteria for Evaluating Effects of High Energy Pipe Breaks on Category I Structures Outside Containment)
- ML19319D545 + (Structural Design Criteria for Evaluating Effects of High- Energy Pipe Breaks on Category 1 Structures Outside Containment)
- ML20265B396 + (Structural Details)
- ML20265B407 + (Structural Details)
- PMNS20240050, Structural Discussion Align on NRC Supplement for the TRISO-X Responses to the Building Risk Category Programmatic RAI + (Structural Discussion Align on NRC Supplement for the TRISO-X Responses to the Building Risk Category Programmatic RAI)
- ML20126B159 + (Structural Effects of ATWS Overpressure Transients in Byron Jackson Primary Pumps, Addendum to Baw 1610, Analysis of B&W NSS Response to ATWS Events,Jan 1980)
- ML19296D385 + (Structural Effects of ATWS Overpressure Transients in Byron Jackson Primary Pumps)
- ML20028B784 + (Structural Engineering Branch Criteria for Safety-Related Masonry Wall Evaluation)
- ML20212L162 + (Structural Engineering Branch Position Re Plant Seismic Design)
- ML19329C616 + (Structural Engineering Branch SER Input Per Amends 1-28 to OL Application)
- ML17059A522 + (Structural Evaluation & Justification of Nine Mile Point 1 Core Shroud for Continued Operation)
- ML13333B126 + (Structural Evaluation & Repair of San Onofre Nuclear Generating Station Unit 1 Intake Structure)
- ML19319B261 + (Structural Evaluation Rept)
- ML18059A483 + (Structural Evaluation for Machined Thermawell for TE-0101)
- L-01-014, Structural Evaluation of AR Nuclear One-Unit 1 Spent Fuel Storage Facility for Consolidated Fuel Storage + (Structural Evaluation of AR Nuclear One-Unit 1 Spent Fuel Storage Facility for Consolidated Fuel Storage)
- L-02-013, Structural Evaluation of Arkansas Nuclear One-Unit 2 Spent Fuel Storage Facility for Consolidated Fuel Storage + (Structural Evaluation of Arkansas Nuclear One-Unit 2 Spent Fuel Storage Facility for Consolidated Fuel Storage)
- ML19310D147 + (Structural Evaluation of Byron & Braidwood Units 1 & 2 Pressurizer Surge Lines,Considering Effects of Thermal Stratification)
- ML20082A693 + (Structural Evaluation of Com Ed BWR Reactor Pressure Vessel Head Stud Cracking)
- ML20094M873 + (Structural Evaluation of Diesel Generator Bldg Assessment of Structural Performance Capability & Serviceability as Potentially Affected by Settlement Induced Cracking. Handwritten Notes Encl)
- ML20079F918 + (Structural Evaluation of Indian Point,Units 2 & 3 Pressurizer Surge Lines,Considering Effects of Thermal Stratification)
- ML20043C745 + (Structural Evaluation of Indications in Reactor Top Head at Ja Fitzpatrick Power Station)
- ML20083G874 + (Structural Evaluation of Midland Diesel Generator Bldg: Assessment of Structural Performance Capability & Serviceability as Potentially Affected by Settlement Induced Cracking)
- ML20073P546 + (Structural Evaluation of Salem Nuclear Plant Units 1 & 2 Pressurizer Surge Lines,Considering Effects of Thermal Stratification)
- ML20128B759 + (Structural Evaluation of Spent Fuel Pool)
- ML20214H129 + (Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Nine Mile Point Unit 1 Nuclear Generating Station, Supplementary Technical Evaluation Rept)
- ML20204G392 + (Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Edwin I Hatch Nuclear Plant Units 1 & 2, Supplementary Technical Evaluation Rept)
- ML20211P078 + (Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Brunswick Steam Electric Plant Units 1 & 2, Supplementary Technical Evaluation Rept)
- ML20214R612 + (Structural Evaluation of Vacuum Breakers (Mark I Containment Program),Ja Fitzpatrick Nuclear Power Plant, Technical Evaluation Rept)