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List of results

• 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)
• ML24047A297  + (Appendix 4.7-2 RCP-904.2 Incident Response (CR) 11.09.23)
• ML24047A298  + (Appendix 4.7-3 RCP-904.3 Nuclear Material Events Database (NMED) Input (CR) 11.09.23)
• ML24047A299  + (Appendix 4.7-4 RCP-403 Rev 03 (CR))
• ML20321A089  + (Appendix 4A - Computational Modeling Software Technical Review Guidance)
• ML23331A697  + (Appendix 4A, Cover Page, Ae 11543/Dok, Revision 2, Safety Documentation of the Cask SKODA Vpvr/M, Nuclear Safety (Subcriticality Calculation), Supplements 1 and 2))
• ML20321A090  + (Appendix 4B - Pool and Pool Confinement Facilities)
• ML23331A698  + (Appendix 5, Ae 11543/Dok, Rev. 2, Cover Page Only, Safety Documentation of the Cask SKODA Vpvr/M, Q.A. - 1)
• ML23331A700  + (Appendix 5, Cover Page Only, PZJ-02-04, Vision 2, Quality Plan, Vpvr Cask / SKODA Vpvr/M Cask)
• ML23331A702  + (Appendix 5, Pzj 02-04, Revision 2, Vpvr Cask, SKODA Vpvr/M Cask)
• ML20321A091  + (Appendix 7A - Technical Recommendations for the Criticality Safety Review of PWR Transportation Packages and Storage Casks)
• ML20321A092  + (Appendix 8A - Clarifications, Guidance, and Expectations to ASTM Standard Practice C1671-15)
• ML20321A093  + (Appendix 8B - Fuel Cladding Creep)
• ML20321A094  + (Appendix 8C - Fuel Oxidation and Cladding Splitting)
• ML18355A374  + (Appendix A-100U to Certificate of Compliance No. 1014 Amendment No. 11)
• ML18355A381  + (Appendix A-100U to Certificate of Compliance No. 1014 Amendment No. 12)
• ML13284A111  + (Appendix AD - Area Walk-by Checklists (Awcs))
• A33009, Appendix B (TS 4 Figures Rev. 6) - Amendment Number 16 to CoC 1004  + (Appendix B (TS 4 Figures Rev. 6) - Amendment Number 16 to CoC 1004)
• ML19095A030  + (Appendix B - 20160323_UNCNH_SupSurveyPlan_Rev0)
• ML060320160  + (Appendix B - Additional Conditions Operating License No. DPR-49)
• ML032820149  + (Appendix B - Chronology (1).wpd - Safety Evaluation Report with Open Items Related to the License Renewal of the R.E. Ginna Nuclear Power Plant)
• ML22271A896  + (Appendix B - Definitions)
• ML18162A073  + (Appendix B - Enhanced Strategic Workforce Planning Process)

• ML23067A149  + (Appendix B - Environmental Protection Plan (Non-Radiological))

• ML17165A311  + (Appendix B - Field Parameter Sampling Forms)
• ML18137A215  + (Appendix B - R.E. Ginna Nuclear Power Plant - Offsite Dose Calculation Manual Revision 33)
• ML19212A752  + (Appendix B - Response to Comments on Draft Interim Staff Guidance NMSS-ISG-02, Guidance for Conducting the Section 106 Process of the National Historic Preservation Act for Uranium Recovery Licensing Actions)
• ML19352D306  + (Appendix B - Start Site Logbooks)
• ML19308B570  + (Appendix B - Subsequent Renewed Facility Operating Licenses Nos. DPR-31 and DPR-41 Turkey Point Nuclear Generating Units Nos. 3 and 4 Environmental Protection Plan (EPP) Non-Radiological)
• ML21113A082  + (Appendix B - Workshop Slides)
• ML063480410  + (Appendix B - YA-REPT-00-015-04, Rev 0 Instrument Efficiency Determination for Use in Minimum Detectable Concentration Calculations in Support of the Final Status Survey at Yankee Rowe)
• ML20343A206  + (Appendix B Differences Between Thermal and Radiation Properties of Mixed Oxide and Low-Enriched Uranium Radioactive Materials)
• ML21259A156  + (Appendix B Postclosure Safety Review for a Potential Repository at Yucca Mountain)
• ML052090304  + (Appendix B SNEC Calculation Dose Assessment of Results)
• ML25218A079  + (Appendix B Sdi Driving Regulatory Decisions Through More Effective Communications)
• ML18355A373  + (Appendix B to Certificate of Compliance No. 1014 Amendment No. 11)
• ML18355A380  + (Appendix B to Certificate of Compliance No. 1014 Amendment No. 12)
• ML051430137  + (Appendix B to Facility License No. NPF-2, Joseph M. Farley Nuclear Plant, Unit 1)
• ML19031A149  + (Appendix B to Operating License DPR - Environmental Technical Specifications for Salem Nuclear Generating Station Units 1 and 2)
• ML19031A152  + (Appendix B to Operating License DPR, Environmental Technical Specifications for Salem Nuclear Generating Station Units 1 and 2)
• ML18018B059  + (Appendix B to Provisional Operating License No. DPR-17 Draft of Proposed Environmental Technical Specifications)
• ML021560339  + (Appendix B to Renewed Facility Operating Licenses Nos. DPR-31 & DPR-41 Turkey Point Nuclear Generating Units Nos. 3 & 4 Environmental Protection Plan (EPP) (Non-Radiological))
• ML22340A008  + (Appendix B, Activation Study of Components of the Aerotest Radiography and Research Reactor in Support of Its Characterization - Redacted)
• ML25003A197  + (Appendix B, Conditions for Cask Use and Technical Specifications, Renewed Certificate of Compliance No. 1015, Amendment 10, NAC-UMS Storage System)
• ML25003A182  + (Appendix B, Conditions for Cask Use and Technical Specifications, Renewed Certificate of Compliance No. 1015, Amendment 5, Revision 1, NAC-UMS Storage System)
• ML25003A188  + (Appendix B, Conditions for Cask Use and Technical Specifications, Renewed Certificate of Compliance No. 1015, Amendment 7, Revision 1, NAC-UMS Storage System)
• ML25003A194  + (Appendix B, Conditions for Cask Use and Technical Specifications, Renewed Certificate of Compliance No. 1015, Amendment 9, Revision 1, NAC-UMS Storage System)
• ML25003A185  + (Appendix B, Conditions for Cask Use and Technical Specifications, Renewed Certificate of Compliance No. 1015, Amendment 6, Revision 1, NAC-UMS Storage System)
• ML25003A191  + (Appendix B, Conditions for Cask Use and Technical Specifications, Renewed Certificate of Compliance No. 1015, Amendment 8, Revision 1, NAC-UMS Storage System)