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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
- ML21110A049 + (NRC 898 Corrected Completeness Determination for EPRI Data Validation Topical Report)
- ML25078A432 + (NRC 898 Form)
- ML22021B652 + (NRC 898 Form GEH Proposed Revision 17 to NEDO-11209-A, Revision 16, GE Hitachi Nuclear Energy Quality Assurance Program Description (QAPD))
- ML23265A004 + (NRC 898 Revised Completeness Determination for NuScale Topical Report TR-124587, Extended Passive Cooling and Reactivity Control Methodology, Revision 0)
- ML23265A159 + (NRC 898 Revised Completeness Determination for NuScale Topical Report TR-0516-49416, Non-Loss-Of-Coolant Accident Analysis Methodology, Revision 4)
- ML25104A232 + (NRC 898 Topical Report Completeness Determination Form WCAP-16996-P/NP, Rev. 1, Suppl. 1, Rev. 0, Extension of Full Spectrum LOCA (Fsloca) Evaluation Methodology to Westinghouse Pressurized Water Reactors with Information.)
- ML25022A053 + (NRC 898 Transmittal - Additional Review for Rev. 3, BWRX-300 Steel-Composite Containment Vessel and Reactor Building Structural Design LTR)
- ML25101A199 + (NRC 898 and 897 Forms for WEC TR WCAP-16996-P/NP, Rev. 1, Suppl. 1, Rev. 0, Extension of Full Spectrum LOCA (Fsloca) Evaluation Methodology to 2-loop Westinghouse Pressurized Water Reactors...)
- ML21267A121 + (NRC 898, Completeness Determination, X Energy, LLC - Xe-100 Topical Report: TRISO-X Pebble Fuel Qualification Methodology)
- ML22101A279 + (NRC 898, Topical Report Completeness Determination - BWRVIP-321, Completeness and Proprietary Reviews for BWRVIP-321, BWR and Internals Project, Plan for Extension of the BWR ISP Through SLR)
- ML23179A266 + (NRC 898, Topical Report Completeness Determination, for EPRI Report 3002023774, EPRI MOV Performance Prediction Methodology (Ppm), Version 4.1)
- ML25142A233 + (NRC 898-Aalo-QAP-001, Quality Assurance Program for Aalo Atomics)
- IR 05000266/2013009 + (NRC 95001 Supplemental Inspection Report 05000266-13-009 and Assessment Follow-Up Letter)
- IR 05000461/2018041 + (NRC 95001 Supplemental Inspection Report 05000461/2018041 and Assessment Follow-Up Letter)
- IR 05000346/2018040 + (NRC 95001 Supplemental Inspection Report 05000346/2018040 and Assessment Follow-up Letter (DRS-A.Shaikh))
- IR 05000306/2016009 + (NRC 95001 Supplemental Inspection Report 05000306/2016009 and Assessment Follow Up Letter)
- ML22179A115 + (NRC ACMUI April 5, 2022 Meeting, Transcript Certification Memo)
- ML24326A234 + (NRC ACMUI April 8, 2024 Transcript Certification Memo)
- ML23012A006 + (NRC ACMUI December 5, 2022 Meeting, Transcript Certification Memo)
- ML22039A192 + (NRC ACMUI Meeting Transcript Certification)
- ML24317A132 + (NRC ACMUI November 4 2024 Meeting Transcript Certification Memo)
- ML24326A255 + (NRC ACMUI October 23 2023 Transcript Certification Memo)
- ML19009A287 + (NRC ADR Program Informational Manual)
- ML23122A138 + (NRC AMT 2023 - Collins)
- ML15014A084 + (NRC ANO Unit 1 Stator Drop SDP Evaluation)
- ML25262A113 + (NRC ASME Management Minutes August 2025)
- ML18152A781 + (NRC ATF PIRT Public Meeting Slides)
- ML18057A189 + (NRC ATF Public Meeting Project Plan Slides 02 27 18)
- ML18038A703 + (NRC ATL Public Meeting Feb 6 2018-final)
- ML120790567 + (NRC ATWS (4408 Mwt Cycle 19 Turbine Trip))
- ML120800155 + (NRC ATWS Mar 2012 4408 MSIV Closure)
- ML120800157 + (NRC ATWS March 2012 4408 Turbine Trip)
- ML16252A523 + (NRC Abq Meeting Np)
- ML19281C930 + (NRC Acceptance Criteria for Mark I Containment Long-Term Program)
- ML19210B994 + (NRC Acceptance Criteria for Mark I Containment Long-Term Program)
- ML19250C143 + (NRC Acceptance Criteria for Mark I Containment Long-Term Program)
- ML22083A214 + (NRC Acceptance Letter for WCS Request to Extend Possession Time of LANL Waste Until December 31, 2024)
- ML23023A047 + (NRC Acceptance Letter to FEMA Quad Cities ANS Evaluation Report)
- ML19288A029 + (NRC Acceptance Review - Northstar Request for Exemption from 10 CFR 20, App G, Section Iii.E (License DPR-28, Docket No. 50-271))
- ML14050A120 + (NRC Acceptance Review Meeting Slides on Sequoyah Nuclear Plant, Units 1 and 2, Improved Technical Specification Conversion)
- ML13290A375 + (NRC Acceptance Review Results for Hope Creek LAR)
- ML26043A011 + (NRC Acceptance Review Results for Limerick LAR for Drywell TS SR)
- ML13228A150 + (NRC Acceptance Review Results for Relief Request S2-I4R-131)
- ML13102A066 + (NRC Acceptance Review Results for Relief Request SCI4R-133)
- ML25350B053 + (NRC Acceptance Review Results for Salem LAR S22-06 (L-2025-LLA-0169))