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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

• ML21323A076  + (NRC Ciso Advisory ICS-21-322-01)
• ML25042A031  + (NRC Clarification Questions Regarding Tn Draft RAI Response)
• ML26021A080  + (NRC Clarification Questions for December 18 2025 Public Meeting with Kairos Power Regarding Hermes External Event Design Criteria)
• ML21242A036  + (NRC Clarification Questions on MPPB Modeling Information)
• ML24362A077  + (NRC Clarification Questions on the Response to the RAIs for the Phase 1 Fssrs Fort Calhoun Station, Unit 1,- License No. DPR-40, Docket No. 50-285)
• ML20091P014  + (NRC Classification Guide for National Security Information Concerning Nuclear Materials and Facilities (CG-NMF-2))
• ML20079S020  + (NRC Classification Guide for Safeguards Information)
• PMNS20260158, NRC Closed Hybrid Preapplication Meeting with Alva Inc. on a Conceptual Topical Report Regarding Balance of Plant Solutions for Extended Power Uprates  + (NRC Closed Hybrid Preapplication Meeting with Alva Inc. on a Conceptual Topical Report Regarding Balance of Plant Solutions for Extended Power Uprates)
• ML20015A419  + (NRC Closed Meeting with Westinghouse Electric Company CRDM Thermal Sleeve Repair - Attendance Sheet)
• PMNS20211267, NRC Closed Meeting with the Pressurized Water Reactor Owners Group (PWROG) on the Review of Topical Report WCAP-17096 Revision 3, Reactor Internals Acceptance Criteria Methodology and Data Requirements  + (NRC Closed Meeting with the Pressurized Water Reactor Owners Group (PWROG) on the Review of Topical Report WCAP-17096 Revision 3, Reactor Internals Acceptance Criteria Methodology and Data Requirements)
• PMNS20220250, NRC Closed Meeting with the Pressurized Water Reactor Owners Group (PWROG) on Conceptual Generic Topics Associated with Risk-Informed Process for Exemptions (RIPE-G)  + (NRC Closed Meeting with the Pressurized Water Reactor Owners Group (PWROG) on Conceptual Generic Topics Associated with Risk-Informed Process for Exemptions (RIPE-G))
• PMNS20220251, NRC Closed Meeting with the Pressurized Water Reactor Owners Group (PWROG) on the Review of Topical Report PWROG-18068-NP, Revision 1, Use of Direct Fracture Toughness for Evaluation of RPV Integrity  + (NRC Closed Meeting with the Pressurized Water Reactor Owners Group (PWROG) on the Review of Topical Report PWROG-18068-NP, Revision 1, Use of Direct Fracture Toughness for Evaluation of RPV Integrity)
• PMNS20240457, NRC Closed Pre-Application Meeting with the Pressurized Water Reactor Owners Group on Key Considerations Regarding an On-Line Monitoring Program for Technical Specification Instrumentation,  + (NRC Closed Pre-Application Meeting with the Pressurized Water Reactor Owners Group on Key Considerations Regarding an On-Line Monitoring Program for Technical Specification Instrumentation,)
• PMNS20241456, NRC Closed Pre-Application Meeting with the Pressurized Water Reactor Owners Group Regarding the On-Line Monitoring Program for Technical Specification Instrumentation,  + (NRC Closed Pre-Application Meeting with the Pressurized Water Reactor Owners Group Regarding the On-Line Monitoring Program for Technical Specification Instrumentation,)
• PMNS20251119, NRC Closed Pre-Application Meeting with the Pressurized Water Reactor Owners Group on a Proprietary Topical Report, Hydrogen-Based Transient Cladding Strain Limit to Axiom Cladding  + (NRC Closed Pre-Application Meeting with the Pressurized Water Reactor Owners Group on a Proprietary Topical Report, Hydrogen-Based Transient Cladding Strain Limit to Axiom Cladding)
• PMNS20251188, NRC Closed Pre-Application Meeting with the Pressurized Water Reactor Owners Group on a Conceptual On-Line Monitoring Program for Technical Specification Instrumentation  + (NRC Closed Pre-Application Meeting with the Pressurized Water Reactor Owners Group on a Conceptual On-Line Monitoring Program for Technical Specification Instrumentation)
• ML20137Q928  + (NRC Closed Predecisional Enforcement Conference W/St Lucie Np, on 960816 in Atlanta Ga)
• ML20137P391  + (NRC Closed Predecisional Enforcement Conference,St Lucie Nuclear Plant)
• PMNS20260143, NRC Closed Virtual Preapplication Meeting with the Pressurized Water Reactor Owners Group-Framatome Inc. on Topical Report ANP-10337-P Revision 0 Supplement 2, Evaluation of the Effect of Grid Crush on LOCA  + (NRC Closed Virtual Preapplication Meeting with the Pressurized Water Reactor Owners Group-Framatome Inc. on Topical Report ANP-10337-P Revision 0 Supplement 2, Evaluation of the Effect of Grid Crush on LOCA)
• ML17354A636  + (NRC Cloud Computing Strategy, Version 1.3)
• ML20236Y389  + (NRC Collection of Abbreviations)
• ML20101A219  + (NRC Collection of Abbreviations)
• ML22039A274  + (NRC Comment on DOE Draft Investigation of Mill and Non-Mill Related Groundwater in the Floodplain at the Shiprock, New Mexico, Disposal Site)
• ML091730031  + (NRC Comment on Draft Licensee-Developed (Vermont Yankee) Exam (Written Tests))
• ML18330A126  + (NRC Comment on NEI 96-07, Appendix D Revision 0g Rev 2)

• ML021610211  + (NRC Comments)

• ML20197E721  + (NRC Comments & DOE Responses on Draft Remedial Action Plan for Inactive U Mill Tailings at Tuba City,Az)
• ML19206A098  + (NRC Comments (7-24-19) on NEI 17-07 R1 Dec 2018)
• ML042190023  + (NRC Comments (Written))
• ML041620421  + (NRC Comments (Written))
• ML040960287  + (NRC Comments (Written))
• ML040150446  + (NRC Comments (Written))
• ML033100022  + (NRC Comments (Written))
• ML032880197  + (NRC Comments (Written))
• ML042730226  + (NRC Comments (Written) (Es 401-9) (Folder 2))
• ML23355A268  + (NRC Comments - Comanche Peak LRA Supplement 3 (1))
• ML24274A158  + (NRC Comments Draft TSTF-604, Revise Ventilation System Actions)
• ML19045A453  + (NRC Comments February 2019)
• ML030780128  + (NRC Comments No the Operating Test and the Written Examination - ES-401-9 for the Perry Examination - Jan/Feb 2003)
• ML18187A190  + (NRC Comments Regarding Re-Calculation of the Maximum Potential Enrichment at the Cimarron Site)
• ML21181A280  + (NRC Comments and Questions for NEI 20-07 Regarding New Approach)
• ML20245E570  + (NRC Comments and Resolution on Licensee Outlines)
• ML22243A221  + (NRC Comments and Resolution on PINGP Outline - Final)
• ML23079A237  + (NRC Comments and Resolutions on Licensee Outlines (Quad Cities, 2023))
• ML24038A349  + (NRC Comments for Pre-submittal Meeting TSTF-600, Revise the Reactor Coolant System (RCS) Pressure Isolation Valve (PIV) Leakage Testing Frequency)
• ML15335A327  + (NRC Comments of Draft Licensee-Developed Exam (Operating) (Folder 2))
• ML17261B169  + (NRC Comments of Draft Licensee-Developed Exam (Operating) (Folder 2))
• ML19039A362  + (NRC Comments of Vermont Revised Agreement Application Sections 4.5 - 4.7)
• ML18017A966  + (NRC Comments on American Society of Mechanical Engineers (Asme)/American Nuclear Seismic Probabilistic Risk Assessment (PRA) Code Case)
• ML19308C223  + (NRC Comments on Analysis of Legal Authority Currently Available to Support Federal Responses in Emergencies Contemplated by Federal Response Plan for Peacetime Nuclear Emergencies)
• ML003734245  + (NRC Comments on Appendix B to NEI 97-04, Design Bases Program Guidelines)