Search by property

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

• ML20196A246  + (Evaluation of Loss of Offsite Power Events at Nuclear Power Plants: 1980 - 1996)
• ML20137N655  + (Evaluation of Low Carbon Type 316 Stainless Steel Recirculation Outlet Safe Ends at Peach Bottom Unit 3)
• ML20137S218  + (Evaluation of Low-Velocity Impact Tests of Solid Steel Billet Onto Concrete Pads & Application to Generic ISFSI Storage Cask for Tipover & Side Drop)
• 05000348/FIN-2011010-09  + (Evaluation of MDAFW Pump Suction Check Valves)
• ML25017A059  + (Evaluation of Maccs Ki Modeling Capability)
• ML18102B465  + (Evaluation of Macrohabitat Utilization by Loggerhead Sea Turtles in Delaware Estuary Using Sonic & Satellite Tracking Techniques)
• ML20067E400  + (Evaluation of Main Feedwater Piping Misalignment & Steam Generator Nozzle Cracking Final Rept)
• ML20127L719  + (Evaluation of Main Steam Line Break in Doghouse)
• NL-06-0422, Evaluation of Main Steam Nozzle Indications  + (Evaluation of Main Steam Nozzle Indications)
• ML20237J415  + (Evaluation of Main Steam Sys)
• ML20024C147  + (Evaluation of Maine Yankee Atomic Power Plant for 1983)
• ML20154P808  + (Evaluation of Materials of Construction for the Reinforced Concrete Reactor Containment Model)
• ML19347C238  + (Evaluation of Mathematical Models for Characterizing Plume Behavior from Cooling Towers.Salt Drift Deposition from Natural Drift Cooling Towers)
• ML19347C190  + (Evaluation of Mathematical Models for Characterizing Plume Behavior from Cooling Towers)
• ML20205Q542  + (Evaluation of Matl Performance Suitability of New Vermont Yankee Spent Fuel Storage Rack Design)
• ML19225A475  + (Evaluation of Matl for Retention of Sodium & Core Debris in Reactor Sys, Annual Progress Rept for Sept 1977-Dec 1978)
• ML19320C718  + (Evaluation of Matls Interactions for Advanced Reactor Sys, Annual Progress Rept)
• ML19211A174  + (Evaluation of Matls Used in Fire Resistant Phenolic Foam)
• ML19351A246  + (Evaluation of Max Density Spent Fuel Rack Structural Analysis for Indian Point Station Unit 3, Technical Evaluation Rept)
• ML20126D536  + (Evaluation of Max Earthquake & Site Ground Motion Parameters Associated W/Offshore Zone of Deformation,San Onofre Nuclear Generating Station)
• ML20087Q085  + (Evaluation of McGuire Units 1 & 2 Undervoltage Trip Attachment Failures, Technical Evaluation Rept)
• ML20085F252  + (Evaluation of McGuire Units 1 & 2 Undervoltage Trip Attachment Failures, Interim Technical Evaluation Rept)
• ML19211A048  + (Evaluation of Method for Predicting Residual Stresses in Girth-Butt Welds)
• ML18086B013  + (Evaluation of Methods for Analysis of Sr-89 & Sr-90 in Environ Samples)
• ML19225A049  + (Evaluation of Methods for Determination of X-Ray & Gamma-Ray Exposure Attributable to Nuclear Facility Using Environmental TLD Measurements)

• ML20114B025  + (Evaluation of Mhtgr Fuel Reliability)

• ML20040C573  + (Evaluation of Midland Nuclear Power Plant Borated Water Storage Tanks for Nonuniform Support Loading Resulting from Ring Wall Settlement)
• ML20040F458  + (Evaluation of Midland Nuclear Power Plants Borated Water Storage Tanks for Non-Uniform Support Loading Resulting from Ring Wall Settlement)
• ML20052G638  + (Evaluation of Midland Nuclear Power Plant Borated Water Storage Tank for Nonuniform Support Loading Resulting from Ring Wall Settlement)
• ML20040D872  + (Evaluation of Millstone Nuclear Power Station)
• ML20044G568  + (Evaluation of Millstone Unit 1 Containment Isolation Failure)
• ML17207A485  + (Evaluation of Min Fire Brigade Shift Size W/Nrc Position Re Min Fire Brigade Training)
• ML19208D744  + (Evaluation of Min Fire Brigade Shift Size)
• ML19208D065  + (Evaluation of Min Fire Brigade Shift Size)
• ML20155A688  + (Evaluation of Min Post-LOCA Heat Removal Requirements to Assure Adequate NPSH for Core Spray & Lpci/Containment Cooling Pumps)
• ML062280075  + (Evaluation of Minimum Fire Brigade Shift Size, June 8, 1979)
• ML19352B263  + (Evaluation of Multiparameter Eddy Current Technology for Inspection of Steam Generator Tubing)
• ML19255B838  + (Evaluation of NDE Responses from Ciscc Flaws)
• ML20244A731  + (Evaluation of NON-RADIOLOGICAL Water Chemistry at Power Reactors)
• ML20238E400  + (Evaluation of NPRDS Component Boundary Document. Supporting Documentation Encl)
• ML24275A001  + (Evaluation of NRC Knowledge Management Program)
• ML20215A173  + (Evaluation of NRC Operational Data Requirements)
• ML20059B790  + (Evaluation of NRC Proposed Maint Effectiveness Indicator)
• ML22125A247  + (Evaluation of NRC Recognized Specialty Boards)
• ML072000113  + (Evaluation of NRC SER Restriction for Realistic Large Break Loss of Coolant Accident (Rlbloca) Analyses)
• ML24275A004  + (Evaluation of NRC Strategic Workforce Planning Program)
• ML20003G709  + (Evaluation of NRCs Revised Inspection Program:Phase I. FY1979)
• ML19282C810  + (Evaluation of NU-QA-1 Revision 3A, Northeast Utils QA Program Topical Rept. Rept Is Acceptable)
• ML20077G264  + (Evaluation of NUREG-0808 Load Definition)
• ML20076K920  + (Evaluation of NUREG-0808 Load Definition)
• ML20198S350  + (Evaluation of National Seismograph Network Detection Capabilities.Final Report)