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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
- ML18323A200 + (To Cimarron Facility Decommissioning Plan, Figures - Sections 8-10)
- ML18323A202 + (To Cimarron Facility Decommissioning Plan, Plan Appendices a)
- ML18323A196 + (To Cimarron Facility Decommissioning Plan, Text and Tables)
- ML20010A515 + (To Class IE Qualification - Qualification of Class IE Electrical Equipment)
- ML20040E789 + (To Class IE Qualification - Qualification of Class IE Electrical Equipment)
- ML20033A638 + (To Clinch River Breeder Reactor Plant Requirements for Environ Qualification of Class IE Equipment)
- ML19225A450 + (To Comm Ed QA Program Topical Rept CE-1-A)
- ML20010A293 + (To Comprehensive Vibration Assessment Program Final Rept)
- ML20065N539 + (To Control Room Design Review Program Plan)
- ML092790469 + (To Core Operating Limits Report Reload 17, Cycle 18, Enclosure 2)
- ML102790129 + (To Core Operating Limits Report Reload 18, Cycle 19, Attachment 2, Non-Proprietary Version)
- ML092790471 + (To Core Operating Limits Report for Reload 16, Cycle 17, Non-Proprietary Version, Enclosure 7)
- ML092790472 + (To Core Operating Limits Report for Reload 16, Cycle 17, Non-Proprietary Version, Enclosure 8)
- ML092790470 + (To Core Operating Limits Report for Reload 15, Cycle 16, Non-Proprietary Version, Enclosure 6)
- 05000255/LER-1977-038, To Correct as Prompt Report, Not 30-Day Report, LER-77-038-00 Re Change to Reflect Violation of Technical Specifications as a Result of IE Inspection Report 77-11 + (To Correct as Prompt Report, Not 30-Day Report, LER-77-038-00 Re Change to Reflect Violation of Technical Specifications as a Result of IE Inspection Report 77-11)
- ML20058H220 + (To Cranes & Hoist Program)
- ML20058H080 + (To Cranes & Hoists - Safety Insp)
- ML20050J052 + (To Crbr Requirements for Environ Qualification of Class IE Equipment)
- ML20149J721 + (To Critical Design Characteristics Overcooling Events)
- ML20207G860 + (To Criticality Safety Analyses for Vogtle Electric Generating Plant Spent Fuel Storage Racks)
- ML031630873 + (To Cycle 10 Startup Testing Summary Report)
- BYRON 2002-0023, To Cycle 11A Core Operating Limits Report + (To Cycle 11A Core Operating Limits Report)
- 1CAN110202, To Cycle 18 Core Operating Limits Report Per Technical Specification 5.6.5.d + (To Cycle 18 Core Operating Limits Report Per Technical Specification 5.6.5.d)
- 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)