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.
List of results
- ML13354B947 + (MIP-Dresden Nuclear Power Station 2014 Master Inspection Plan)
- ML12356A438 + (MIP-Zion Nuclear Power Station Master Inspection Plan (Mip) for CY2013)
- ML14197A287 + (MISI-1462.10-0040, Revision 0, Fourth Inspection Interval Inservice Inspection Plan, Enclosure 1)
- MNS-14-053, MISI-1462.20-0040, Revision 0, Fourth Inspection Interval Inservice Inspection Pressure Test Plan + (MISI-1462.20-0040, Revision 0, Fourth Inspection Interval Inservice Inspection Pressure Test Plan)
- ML20266F332 + (MIXED-WASTE Facility Layout with Locations of Mixed Waste Expansion Monitoring Wells)
- ML20198C073 + (MKF-UMTRA-3,Copy 53, Quality Assurance Program Plan)
- ML20151T952 + (ML 5.0 Earthquake,860131,Strong-Motion Data from Perry Nuclear Power Plant Seismic Instrumentation)
- ML010890299 + (ML010890299 United States Enrichment Corporation Responses to NRC Letter of November 17, 2000, Exercise of Enforcement Discretion (EA-99-333) and Notice of Violation (EA 99-334), Resulting from the NRC Review of 1999 Update to Certification)
- ML090260556 + (ML090260556 Checked Into ML090260403 Jan 26 09. Corrected NRC Staff Answer to the State of Nevadas Motion to Amend Petition to Intervene as a Full Party)
- ML14251A264 + (ML140908 - Closed Commission Meeting Certification)
- ML20049A040 + (ML20017A278; Audit Report December 11, 2019 Regarding the License Amendment for a Possession-Only Facility License)
- ML20035D427 + (ML20035D427-Plant Hatch RP Baseline Inspection Document Request 2020001)
- ML21208A424 + (ML20308A515_003 SPS UFSAR Chapter 3 - Redacted)
- ML21322A234 + (ML21322A234 - Trtr 2021 Annual Conference Presentation by Duane Hardesty on Endorsing NEI 21-06)
- ML24319A203 + (ML22251A242 SA-300 August 23 2024)
- ML24353A302 + (ML24263A235 Limerick Generating Station, Units 1 and 2 - Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 22 and UFSAR Reference Drawings - Redacted)
- ML24332A015 + (ML24332A015 - Withholding Determination Oklo Safety Analysis White Paper)
- ML25266A131 + (ML25266A131-Summary of the August 12, 2025, Public Meeting with SMR, LLC (a Holtec International Company) to Discuss the SMR-300 Structural Modularity)
- ML25325A037 + (ML25325A037 - Summary of the August 27, 2025, Public Meeting with SMR (Holtec) to Discuss an Update for Planned LWA Application for SMR-300)
- ML25345A481 + (ML25345A481-SMR (Holtec) Draft Safety Evaluation of Licensing Topical Report HI-2241098, SMR Design Basis Radiological Consequences Analysis Methodology, Revision 1)
- ML20058J826 + (MMKT-2 Software Complex for Calculating Criticality in Analyses of Nuclear Safety)
- ML021290659 + (MN-DRS, Notice of Licensee Meeting with Columbia Generating Station to Discuss Plant Fuel Corrosion Issues and Engineering Initiatives)
- L-MT-12-059, MNGP 90-Dav Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident + (MNGP 90-Dav Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident)
- L-MT-12-058, MNGP 90-Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendations 2.1 and 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident + (MNGP 90-Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendations 2.1 and 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident)
- ML081010194 + (MNGP Extended Power Uprate Environmental Assessment)
- ML13233A096 + (MNGP ISFSI Amendment 10 to Technical Specifications)
- ML20125A625 + (MNGP Loss-of Coolant Accident Analyses Conformance W/ 10CFR50 App K)
- ML17250A870 + (MNGP TSTF-542 Draft Variations)
- ML17250A871 + (MNGP TSTF-542 TS Draft Markups)
- ML13261A146 + (MNGP Technical Specification Bases Updating Instructions)
- L-MT-13-051, MNGP Updated Final Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident + (MNGP Updated Final Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident)
- L-MT-14-052, MNGPs Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109) + (MNGPs Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109))
- L-MT-13-038, MNGPs Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident + (MNGPs Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident)
- ML21265A549 + (MNRC Soil Permeability Information)
- ML12066A022 + (MNS Annual Assessment Letter)
- ML17235A612 + (MNS EPIP Manual)
- ML15230A594 + (MNS Ice Condenser Door LAR Presentation - 08/12/15)
- ML18264A022 + (MNS RFI Email 2018004)
- ML15219A566 + (MNS-TS-5,6 - Distribution to Manual Holders - Amendment 278/258)
- ML20214Q890 + (MO-7068 Thermal Degradation Equivalency Evaluation)
- ML14302A579 + (MOD 50.59 Request for Information)
- ML14196A515 + (MOD 50.59 Request for Information)
- ML13018A316 + (MOD 50.59 Request for Information)
- ML12257A148 + (MOD 50.59 Request for Information)
- ML12003A291 + (MOD 50.59 Request for Information)
- ML11321A219 + (MOD 50.59 Request for Information)
- ML091400754 + (MOD 50.59 Request for Information)
- 05000254/FIN-2010003-04 + (MODE Change without Required RPS Instrument)
- ML20128H016 + (MONSTER:Multi-Compartment Containment Sys Analysis Program)
- ML20126J478 + (MORECA-2: Interactive Simulator for Modular HIGH-TEMPERATURE GAS-COOLED Reactor Core Transients and Heatup Accidents with ATWS Options)
- ML19308B832 + (MORT Users Manual,For Use W/Mgt Oversight & Risk Tree Analytical Locic Diagram, Prepared for Erda)