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- ML20211D111 + (Appended History of Issues Determined to Have Validity by by Comanche Peak Response Team in Results Repts I.a.5 & I.b.3,submitted in Response to ASLB 860808 & 0902 Requests. Certificate of Svc Encl)
- ML042110289 + (Appendices)
- ML22095A133 + (Appendices)
- ML23062A241 + (Appendices)
- ML21056A531 + (Appendices - No Fear Act Report Fy 2020)
- ML030090226 + (Appendices - Safety Evaluation Report Related to the License Renewal of McGuire Nuclear Station, Units 1 and 2, Catawba Nuclear Station, Units 1 and 2)
- ML25084A246 + (Appendices 1 & 2 - No Fear Act Annual Notification of Employee Rights, and Annual Federal Equal Employment Opportunity Statistical Report of Discrimination Complaints Respectively)
- ML041100023 + (Appendices 2A, 4A, 5A, and 9A to Technical Report TR-HBIP-2002-01, Seismic Hazard Assessment for the Humboldt Bay ISFSI Project)
- ML11175A207 + (Appendices a, B and C)
- ML022270707 + (Appendices a, B and C, Draft SER with Open Items)
- ML11098A001 + (Appendices a, B, C, and D - Palo Verde Nuclear Generating Station, Unit 3)
- ML11098A000 + (Appendices a, B, C, and D - Palo Verde Nuclear Generating Station, Unit 2)
- ML24121A273 + (Appendices for Response to Request for Additional Information 2)
- ML20198R278 + (Appendices to Characterization Rept for Iowa State Univ UTR-10 Reactor)
- ML21008A574 + (Appendices to Marssim Revision 2 Draft for Public Comment)
- ML19308C211 + (Appendices,Nrc Incident Response)
- ML24057A415 + (Appendices: No Fear Act - Notification of Employee Rights)
- ENS 42337 + (Appendix "R" Related Unanalyzed Condition)
- ML23356A050 + (Appendix - 2023-12-22T084414.590)
- ML20119A482 + (Appendix 1 - Radiological Environmental Monitoring Program)
- ML13030A498 + (Appendix 1 to NRC Staff Answering Brief - Documents That Provide Material Support for Staffs Arguments)
- ML23331A675 + (Appendix 1, Cover Page, Document No. Ae 11543/Dok, Rev. 2, Radiation Protection (Shielding Calculation), Safety Documentation of the Cask SKODA Vpvr/M)
- ML22019A119 + (Appendix 1-A - Oconee Nuclear Station 122.21(r)(2)-(13) Submittal Requirement Checklist)
- RA-22-0002, Appendix 10-B - Pump and Pipe Selection Calculations for a Hypothetical Cooling Tower Retrofit at Oconee Nuclear Station + (Appendix 10-B - Pump and Pipe Selection Calculations for a Hypothetical Cooling Tower Retrofit at Oconee Nuclear Station)
- ML22019A121 + (Appendix 13-B Peer Reviewer Communication Log)
- NRC 2020-0009, Appendix 2 - Offsite Dose Calculation Manual, Revision 21 + (Appendix 2 - Offsite Dose Calculation Manual, Revision 21)
- ML22063B111 + (Appendix 2 Quality Management System)
- ML23331A679 + (Appendix 2, Ae 11543/Dok, Rev. 2, Cover Page Only, SKODA Vpvr/M Safety Analysis Report, Cask Dynamic Behaviour SKODA Vpvr/M)
- ML23331A681 + (Appendix 2, Vz 04/01, Revision 3, Strength Analysis of SKODA Vpvr/M Cask for Spent Fuel Assemblies from Research Reactors Drop from the Height of 9 Meters)
- ML19018A090 + (Appendix 2.10.1 Center of Gravity Report - Redacted)
- ML19015A370 + (Appendix 2.10.5 - Finite Element Analysis for Drop Test Position)
- ML19015A377 + (Appendix 2.10.9 - Alternative Secondary Lid Leak Test Port Performance Through Chapter 8)
- ML20148K429 + (Appendix 2B Groundwater Hydrology McGuire Nuclear Station FSAR for Dpc. W/One Oversize Drawing)
- ML062830422 + (Appendix 3 to Report: 316(a) Demonstration in Support of a Request for Increased Discharge Temperature Limits at Vermont Yankee Nuclear Power Station During May Through October Report 30)
- ML23331A684 + (Appendix 3, Cover Page Only, Ae 11543/Dok, Rev. 2, Safety Analysis Report of SKODA Vpvr/M Cask, Decontamination Effect on Structural Materials)
- ML23331A683 + (Appendix 3, Ujv Report: Z-1336, Revision 2, Decontamination Effect on Structural Materials of the SKODA Vpvr/M Cask)
- ML23331A686 + (Appendix 3, Újv Report: Z-1336, Revision 2, Decontamination Effect on Structural Materials of SKODA Vpvr/M Cask, July 2005)
- ML23331A690 + (Appendix 4, Cover Page Only, Ae 11543/Dok, Revision 2, Nuclear Safety Subcriticality Evaluation)
- ML23331A692 + (Appendix 4, Ujv Report Z-1172, MCP Calculation of Cask Criticality for Atabor Internals of Thickness 4 Mm, March 2004)
- ML23331A688 + (Appendix 4, Ujv Report Z-1296, SKODA MCP Calculation of Cask Criticality for Atabor Internals of Thickness 4 Mm, Nuclear Research Institute, Division of Reactor Services, August 2005)
- ML23331A695 + (Appendix 4, Ujv Report: Z-1172- Amendment 2, SKODA MCNP Calculation of Cask Criticality for Atabor Internals of Thickness 4 Mm, Amendment 2)
- ML23331A693 + (Appendix 4, Ujv Report: Z-1172-Amendment 1, a SKODA MCNP Calculation of Cask Criticality for Atabor Internals of Thickness 4 Mm, Amendment 1, May 2004)
- ML24047A221 + (Appendix 4.2-1a Regulations 02-08-2024 (CR))
- ML24047A218 + (Appendix 4.2-1b Regulations 02-02-2024 (CR))
- ML24047A219 + (Appendix 4.2-1c Regulations 02/02/2024(CR))
- ML24047A220 + (Appendix 4.2-2 NRC Comment and State Response Letters 02/01/2024)
- ML24047A153 + (Appendix 4.4-1, CT Deep Radiation Division Instrumentation, 02/01/2024)
- ML24047A263 + (Appendix 4.6.3-1 Letter of Current Staff Qualification)
- ML24047A260 + (Appendix 4.6.3-2 Current Staff Qualifications 02/02/2024)
- ML24047A261 + (Appendix 4.6.3-3 Resumes 01-31-2024 - Redacted)
- ML24047A296 + (Appendix 4.7-1 RCP-904.1 Management of Allegations (CR) 11/09/2023)