Search by property

Jump to navigation Jump to search

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.

Search by property

A list of all pages that have property "Title" with value "NRC ACMUI Meeting Transcript Certification". Since there have been only a few results, also nearby values are displayed.

â§Ľshowingresultsâ§˝

View (previous 50 | next 50) (20 | 50 | 100 | 250 | 500)


    

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))