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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

• ML19240B371  + (To DG-1286 for Proposed Rev 1 of Regulatory Guide (RG) 1.175, an Approach for Plant-Specific, Risk Informed Decisionmaking: Inservice Testing)
• ML20141B515  + (To DOE/AL/62350-207, Long-Term Surveillance Plan for Mexican Hat Disposal Site Mexican Hat,Ut)
• ML050970098  + (To David Lochbaum Re Davis-Besse Mid-Cycle Outage Scope)
• CY-04-156, To Defueled Physical Security Plan  + (To Defueled Physical Security Plan)
• ML19011A202  + (To Defueled Safety Analysis Report, Appendices 2.3A Through 2.5B)
• ML19011A203  + (To Defueled Safety Analysis Report, Appendices 2.5C Through 2.5K)
• ML19011A205  + (To Defueled Safety Analysis Report, Appendices 2.5L Through 2.5T)
• ML19011A208  + (To Defueled Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems)
• ML19011A215  + (To Defueled Safety Analysis Report, Chapter 10, Steam and Power Conversion System)
• ML19011A201  + (To Defueled Safety Analysis Report, Chapter 1, Introduction and General Description of Plant)
• ML19011A212  + (To Defueled Safety Analysis Report, Chapter 7, Instrumentation and Controls)
• ML19011A211  + (To Defueled Safety Analysis Report, Chapter 6, Engineered Safety Features)
• ML19011A220  + (To Defueled Safety Analysis Report, Chapter 15, Appendix 15G, Dose Models Used to Evaluate the Consequences of Accidents Analyzed with the Alternative Source Term Methodology)
• ML19011A210  + (To Defueled Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems)
• ML19011A216  + (To Defueled Safety Analysis Report, Chapter 11, Radioactive Waste Management)
• ML19011A217  + (To Defueled Safety Analysis Report, Chapter 12, Radiation Protection)
• ML19011A218  + (To Defueled Safety Analysis Report, Chapter 13, Conduct of Operations)
• ML19011A219  + (To Defueled Safety Analysis Report, Chapter 14, Initial Test Program)
• ML19011A221  + (To Defueled Safety Analysis Report, Chapter 15, Accident Analyses)
• ML19011A223  + (To Defueled Safety Analysis Report, Chapter 16, Technical Specifications)
• ML19011A224  + (To Defueled Safety Analysis Report, Chapter 17, Quality Assurance)
• ML19011A206  + (To Defueled Safety Analysis Report, Chapter 2, Site Characteristics)
• ML19011A209  + (To Defueled Safety Analysis Report, Chapter 4, Reactor)
• ML19011A213  + (To Defueled Safety Analysis Report, Chapter 8, Electric Power)
• ML19011A214  + (To Defueled Safety Analysis Report, Chapter 9, Auxiliary Systems)

• ML19011A225  + (To Defueled Safety Analysis Report, Chapter 9A Redacted)

• ML19011A226  + (To Defueled Safety Analysis Report, Master Contents)
• ML18046B414  + (To Design Assessment Rept)
• ML17138B440  + (To Design Assessment Rept,Including Updated Pages,Figures & Tables to Vol 1,nonproprietary Version)
• ML18046B281  + (To Design Codes,Design Criteria & Loading Combinations, Draft Technical Evaluation Rept)
• ML20010E527  + (To Design Criteria for Pipe Stress)
• ML20066K066  + (To Design Rept for Recirculation Line End Cap Repair,Monticello Nuclear Generating Plant)
• ML20066K002  + (To Design Rept for Recirculation Line Safe-End & Elbow Repairs,Monticello Nuclear Generating Plant)
• ML20062J344  + (To Design Spec for Component Supports for Nuclear Svc Piping for Midland 1 & 2, Sheet I,App C. Revision Date Illegible.Incomplete B&W Spec 18-1391000012-01 Encl)
• ML20062J506  + (To Disc Impact Velocity for Containment Ventilation Sys Check Valve Closure)
• PMNS20180381, To Discuss with Exelon Generation Company, LLC, the U.S. Nuclear Regulatory Commission Staffs Second Round Request for Additional Information for Limerick Generating Station, Units 1 and 2, Adopt 10 CFR 50.69, Risk Categorization  + (To Discuss with Exelon Generation Company, LLC, the U.S. Nuclear Regulatory Commission Staffs Second Round Request for Additional Information for Limerick Generating Station, Units 1 and 2, Adopt 10 CFR 50.69, Risk Categorization)
• ML14161A036  + (To Doc. No. SA-1330117 B50E, Introduction and Overview for the Set of Qualification Documents Concerning the Digital Wide Range Channel Dwk 250 Intended to Be Installed at the Massachusetts Institute of Technology Mit)
• ML19326C237  + (To Draft Ets,App B to Facility OL)
• ML083430064  + (To Draft Safety Evaluation for Nuclear Energy Institute Addenda 3,4,5,6 & 7 to Electric Power Research Institute Topical Report 103237, EPRI Mov (Motor-Operated Valve) Performance Prediction Program, Rev. 2)
• ML20040A593  + (To Draft Technical Evaluation Rept for Containment Purging & Venting During Normal Operation of Lcbwr,Unit 1)
• ML17292A810  + (To Draft, Sys Analyses for Simplification of Selected Response Time Testing Requirements)
• ML20071Q036  + (To Dresden Unit 2 LOCA Analysis Using Exem/Bwr Evaluation Model MAPLHGR Results)
• E900-01-030, To E900-01-030, SNEC Radionuclide List  + (To E900-01-030, SNEC Radionuclide List)
• ML022520011  + (To E900-01-030, SNEC Radionuclide List, Appendix 1 - 6)
• ML033650371  + (To EA-254, Emergency Service Water System Pump Shaft Coupling Failure Analysis)
• ML19332B238  + (To ECCS Analysis of B&W 177-Fuel Assembly-Loop Nss. Related Correspondence)
• ML050960083  + (To EI-7.10, Post Accident Sampling, Radioactive Gaseous Effluent Monitoring)
• ML033110045  + (To EM-210A, Duties of the Radiation Monitoring Team: CR-3 and Generating Complex Personnel and Area Monitoring)
• ML020440673  + (To EM-225A, Post Accident RB Hydrogen Control, and Revision 9 to EM-225B, Post-Accident Boron Concentration Management)
• ML041050152  + (To EMG-3200.12, Radioactivity Release Control)
• ML20217F890  + (To EMIP-102, Emergency Field Response)