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

• ML19322B870  + (Analysis & Resolution of Dye-Penetrant Indications in AISI-304 Alloy Cladding of RCS Elbows)
• ML19322B868  + (Analysis & Resolution of Dye-Penetrant Indications in Submerged Arc Weld Cladding of Reactor Coolant Sys Straight Piping)
• ML20079C402  + (Analysis & Safety Evaluation of Spent Fuel Shipping Cask Handling at Monticello Nuclear Generating Plant)
• ML18114A535  + (Analysis & Sys Mod for 480 Volt Emergency Power Sys)
• Regulatory Guide 5.24  + (Analysis & Use of Process Data for Protection of Special Nuclear Material. Label as Withdrawn 01/15/98)
• ML20056D311  + (Analysis Allowing Extended Operation W/One PPS Channel in Bypass for ANO Unit 2)
• ML19308C924  + (Analysis Branch Draft Input to SER Supporting Util Methods for Determining Mass & Energy Release to Containment Following Main Steam Line Break)
• ML19275H405  + (Analysis Branch Input to First Round Questions)
• 05000259/LER-1981-011-01, Analysis Indicated Potential Loss of Primary Containment If Purging Conducted During Hot Standby or Power Operations Concurrent W/Loca. Caused by Potential Failure of Dampers or Ductwork  + (Analysis Indicated Potential Loss of Primary Containment If Purging Conducted During Hot Standby or Power Operations Concurrent W/Loca. Caused by Potential Failure of Dampers or Ductwork)
• 05000259/LER-1980-011-01, Analysis Indicated Potential Loss of Primary Containment During Hot Standby. Caused by Not Considering Probability of LOCA in Initial Plant Design.Mods to Ductwork Completed  + (Analysis Indicated Potential Loss of Primary Containment During Hot Standby. Caused by Not Considering Probability of LOCA in Initial Plant Design.Mods to Ductwork Completed)
• ML052060263  + (Analysis Performed by EA Engineering, Science, and Technology of Mississippi River Flow Data)
• ML121010475  + (Analysis Report: Comparisons of Jet Calculations to Test Data)
• ML20211B090  + (Analysis Rept Structural Analyses of Main Steam Check & Isolation Valves for Prairie Island,Unit 1)
• ML19351C877  + (Analysis Rept for Semiscale Mod-3 Station Blackout Tests S-TR-1 & S-TR-2, Interim Rept)
• ML20106A126  + (Analysis Rept on Issues Re Pilgrim Evacuation Time Estimate,Pilgrim Nuclear Power Station)
• ML18243A542  + (Analysis Requests E-Mail Discussion with Region IV Public Affairs Officer)
• ML19254B002  + (Analysis Results of Environ Samples for TMI-2 for 790329-0401.Radiological Ref 173)
• ML19208D738  + (Analysis Summary in Support of Early Rc Pump Trip)
• ML19332B245  + (Analysis Summary in Support of Early Reactor Coolant Pump Trip. Related Correspondence)
• ML19209C615  + (Analysis Summary in Support of Early Reactor Coolant Pump Trip)
• ML19208A064  + (Analysis Summary in Support of Early Reactor Coolant Pump Trip)
• ML19256F653  + (Analysis Summary in Support of Inadequate Core Cooling Guidelines for Loss of RCS Inventory)
• ML19210E369  + (Analysis Summary in Support of Inadequate Core Cooling Guidelines for Loss of RCS Inventory)
• ML19322C318  + (Analysis Supporting Continued Operation of Davis-Besse 1 W/Dual Level Setpoint Control of Steam Generators)
• ML19256E966  + (Analysis Tool for Predicting Transient Hydrodynamics Resulting from Rapid Filling of Voided Piping Sys, Code Assessment & Applications Program Rept)

• ML20262G253  + (Analysis Zone Arrangement for Elkview Plant)

• ML20262G250  + (Analysis Zone for Coal Slurry Analyser System Westar MINING-ELKVIEW Plant.Sheet 1 of 1)
• ML21130A109  + (Analysis and Measurement Services (AMS) Request for Additional Information Response 2)
• ML24339B788  + (Analysis and Measurement Services Corp - Responses to NRCs Request for Acceptance Review for Supplemental Information)
• ML24339B790  + (Analysis and Measurement Services Corp. - Affidavit)
• ML24339B787  + (Analysis and Measurement Services Corporation - Supplemental Information Needed to Complete Acceptance Review of Technical Report Cable-TTR-RO, Condition Monitoring Methodology for Life Extension and Aging Management of Electrical Cables)
• ML24233A209  + (Analysis and Measurement Services Corporation - Affidavit)
• ML19347F936  + (Analysis and Modelling of Steam Explosion Experiments)
• ML20009A386  + (Analysis and Repair of WATER-CONTAMINATED Boron Nitride Insulation in BDHT-THTF Bundle 3 Fuel Rod Simulators)
• ML20138Q460  + (Analysis and Tests on SMALL-SCALE Shear Walls FY-82 Final Report)
• ML20046A329  + (Analysis for Bsep,Units 1 & 2 SWS for Analysis for TS 3.7.1.2 Proposed Change)
• ML20093J105  + (Analysis for Dissolved Hydrogen,Dissolved Oxygen,Boron, Chloride,Ph & Conductivity Under Normal & Post-Accident Conditions, Final Rept)
• ML19186A383  + (Analysis for the Maryland Department of Natural Resources Question of the Effect of Peach Bottom Station Uprate on Migratory Fishes. Prepared for Exelon Generation by Normandeau Associates, Inc. and Environmental Resource Management. July 2)
• ML20214M991  + (Analysis of 1957-58 Soviet Nuclear Accident)
• ML13310A230  + (Analysis of 2/3-g Housner Reanalysis Design Spectrum for San Onofre Nuclear Generating Station)
• ML18260A343  + (Analysis of 2017 Decommissioning Funding Status Report)
• ML20087L920  + (Analysis of 800129 Turbine Trip at Arkansas Nuclear One Unit 2)
• ML19321A056  + (Analysis of 800226 Pressurizer Transient Relief Valve Discharge)
• ML20087L911  + (Analysis of 800407 Loss of Offsite Power Transient at Arkansas Nuclear One Unit 1)
• ML20087L914  + (Analysis of 800624 Loss of Offsite Power Transient at Arkansas Nuclear One Unit 2)
• ML20126L296  + (Analysis of A&M 24-Inch Purge Valve)
• ML20027A761  + (Analysis of Abnormal Transient Operating Guidelines (Atog) as Applied to Apr 1981 Overfill Event at ANO Unit 1, Preliminary Rept)
• ML20058J792  + (Analysis of Accident & Transient Conditions in Design of NPP w/WWER-1000 Reactors)
• ML19247B184  + (Analysis of Accident Hazards of Storing Highly Radioactive Spent Fuel Rods in Spent Fuel Storage Pools at Nuclear Power Plants & at Other Offsite Storage Facilities)
• ML19273A979  + (Analysis of Addl Costs of Constructing Plant at Athens,Ny, Rather than at Proposed Cementon Site.Total Addl Const Costs Are $364 Million (32-month Delay Before Operation) & $591 Million (42-month Delay))
• ML20136C248  + (Analysis of Adsorbers & Adsorbents from TMI-2. Performed for Met Ed.Radiological Ref 136)