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List of results
- ML20267A090 + (Presentation to the National Academies of Science, Math, and Medicine Committee on the Overview of the NRCs Regulatory Programs on the Advanced Reactor Fuel Cycle)
- PMNS20240877, Presentation to the Pope County Quorum Court of the Nuclear Regulatory Commissions 2023 Annual Assessment of Safety Performance at Arkansas Nuclear One + (Presentation to the Pope County Quorum Court of the Nuclear Regulatory Commissions 2023 Annual Assessment of Safety Performance at Arkansas Nuclear One)
- PMNS20230582, Presentation to the St. Charles Parish Council of the Nuclear Regulatory Commissions 2022 Annual Assessment of Safety Performance at Waterford Unit 3 Steam Electric Station + (Presentation to the St. Charles Parish Council of the Nuclear Regulatory Commissions 2022 Annual Assessment of Safety Performance at Waterford Unit 3 Steam Electric Station)
- ML19340A391 + (Presentation, Approach for Responding to Draft Requests for Additional Information Related to NRC Review of Topical Report EPRI-AR-1(NP))
- ML061000273 + (Presentation, Braidwood Generating Station Groundwater Update)
- ML23067A315 + (Presentation, Case N-847-1, Excavate and Weld Repair, Technical Exchange with Electric Power Research Institute Welding and Repair Technology)
- ML061070598 + (Presentation, Groundwater Update Meeting)
- ML22014A019 + (Presentation, Materials for January 20, 2022, ACRS Subcommittee Meeting (Accident Analysis- T-H Subcommittee))
- ML23067A340 + (Presentation, N-853-1 Proposed Revision Technical Exchange with Electric Power Research Institute Welding and Repair Technology)
- ML19340A291 + (Presentation, TRISO Fuel Performance Topical Report)
- ML042610044 + (Presentation- NEI 99-01 Upgrade EALs)
- ML13155A447 + (Presentation-NRC/Research Use of Deterministic Tools for SFP Analysis in the Vogtle Units 1 & 2 Site)
- ML25220A273 + (Presentation: Centrifuge Storage Building - CASS Exemption Request Pre Application Meeting (August 14, 2025))
- ML18199A297 + (Presentation: Defining Unacceptable Radiological Consequences from a Security Perspective)
- ML19214A056 + (Presentation: Duke Energy Presubmittal Meeting - August 7, 2019)
- ML19233A046 + (Presentation: Harris/Nrc Pre-submittal Meeting: Risk-Informed Completion Times, August 22, 2019)
- ML090790850 + (Presentation: Introduction to Nuclear Graphite Workshop)
- ML18284A453 + (Presentation: Meeting Handout for Pre-Application Meeting for Certificate of Compliance No. 1014 for HI-STORM 100, Amendment No. 14)
- ML18029A821 + (Presentation: NRC 10 CFR 61 Update on Low-Level Waste Management)
- ML20339A385 + (Presentation: NRC Technical Assessment of Additive Manufacturing - Laser Powder Bed Fusion)
- ML20283A616 + (Presentation: NRCs Preparations for Advanced Reactor Licensing, ORNL Molten Salt Workshop, October 14-15, 2020)
- ML24338A167 + (Presentation: Overview of NRC Licensing for U.S. Navy)
- ML22130A523 + (Presentations - May 11, 2022 Advanced Reactor Stakeholder Meeting)
- ML24074A353 + (Presentations - RIC2024 - TH19 - Long-Term Operations: Meeting the Moment)
- ML17171A198 + (Presentations by Members of the Public - Indian Point Annual Assessment Meeting)
- ML23193B039 + (Presentations for 15th International Conference on Fracture)
- ML18012A096 + (Presentations for Industry NRC Nondestructive Examination Technical Information Exchange Public Meetings on January 16 - 18, 2018)
- ML20211L080 + (Presentations for July 30, 2020 Higher Burnup Workshop - NEI Presentation)
- ML20211L089 + (Presentations for July 30, 2020 Higher Burnup Workshop - Nuclear Energy Agency Presentation)
- ML20211L086 + (Presentations for July 30, 2020 Higher Burnup Workshop - NRC Quality Submittals)
- ML20211L077 + (Presentations for July 30, 2020 Higher Burnup Workshop - EPRI Presentation)
- ML20211L091 + (Presentations for July 30, 2020 Higher Burnup Workshop - Westinghouse Presentation)
- ML20211L082 + (Presentations for July 30, 2020 Higher Burnup Workshop - NRC Overview)
- ML22319A120 + (Presentations for Lessons Learned Public Meeting 11-15-2022)
- ML19291D231 + (Presentations for October 17, 2019 Regulatory Issues Task Force (RITF) Meeting (Part 2))
- ML19289D095 + (Presentations for October 17, 2019, Regulatory Issues Task Force (RITF) Public Meeting)
- ML22137A276 + (Presentations for the 8th NRC Workshop on Vendor Oversight - Thursday Session)
- ML22137A292 + (Presentations for the 8th NRC Workshop on Vendor Oversight - Thursday Session)
- ML22137A279 + (Presentations for the 8th NRC Workshop on Vendor Oversight - Thursday Session)
- ML22137A286 + (Presentations for the 8th NRC Workshop on Vendor Oversight - Thursday Session)
- ML22137A176 + (Presentations for the 8th NRC Workshop on Vendor Oversight - Wednesday Session)
- ML22137A144 + (Presentations for the 8th NRC Workshop on Vendor Oversight - Wednesday Session)
- ML22137A167 + (Presentations for the 8th NRC Workshop on Vendor Oversight - Wednesday Session)
- ML21230A354 + (Presentations for the Extremely Low Probability of Rupture (Xlpr) Probabilistic Fracture Mechanics Code User Experience Webinar, August 18, 2021)
- ML17296A216 + (Presentations on Reactor Decommissioning at Ma Ndcap at Plymouth Ma Public Meeting Oct 18, 2017)
- ML19095A728 + (Presenting Results of Outstanding Questions in IE Bulletins Nos. 75-04 and 75-04A)
- ML18347A545 + (Presenting Short-Term Measures Implemented to Minimize Potential Reactor Vessel Overpressurizations, as Responded in Letter of 10/7/1976)
- ML19095A284 + (Presenting, Unit 2 Steam Generator Surveillance Program Outage Schedule & Information of Program)
- ML16341B122 + (Presents ACRS Conclusion from 781102-04 Meeting That Dr Lucos Concerns Re Seismic Eval Bases for Subj Facils Were Considered in Findings & Recommendations in 780714 ACRS Rept)
- ML20138F090 + (Presents ACRS Position on Indian Point Special Proceeding. Schedule & Plan Development Recommended to Reduce Estimated Core Melt Frequency & Uncertainty.Detailed Containment Performance Evaluation for Particular Sites Suggested)
- ML20216J851 + (Presents Actions Staff Will Undertake to Develop Rulemaking for Transitioning to More risk-informed,performance-based Structure for Fire Protection Regulation at Nuclear Power Plants)