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| Start date | Site | Title | Description | |
|---|---|---|---|---|
| ML23317A199 | 24 November 2023 | Interim Letter on Level 3 Probabilistic Risk Assessment - Volumes 3 and 4, Pertaining to Reactor at-Power Events | ||
| ML22341A073 | 8 December 2022 | White Paper on - the Enduring Legacy of ACRS - Contributing to Safety-Licensing Review of Reactor Facilities | ||
| ML22159A285 | 8 June 2022 | Agenda - Level 3 PRA Project - Overview of Reactor, At-Power Results for Internal Events and Floods - Sc - June 22, 2022 | ||
| ML22046A226 | 25 February 2022 | Safety Evaluation for Holtec Licensing Topical Report HI-2200750, Revision 0, Holtec Spent Fuel Pool Heat Up Calculation Methodology | ||
| ML21327A072 | 13 December 2021 | Biennial Review and Evaluation of NRC Safety Research Program | ||
| ML21245A056 | 20 September 2021 | Agenda - Biennial Review of NRC Safety Research Program - Sc - September 20, 2021 | ||
| ML21197A027 | 23 July 2021 | Agenda - Safety Research Program - Sc - July 23, 2021 | ||
| ML21162A032 | 25 June 2021 | Agenda - Biennial Review of NRC Safety Research Program-Division of Systems Analysis - Sc - June 25, 2021 | ||
| ML18214A292 | 22 July 2018 | Acrs' Enduring Legacy Contributing to Reactor Safety - Proceedings of the 2018 26th International Conference on Nuclear Engineering | ||
| ML18214A397 | 22 July 2018 | Slides - Acrs' Enduring Legacy Contributing to Reactor Safety; 26th International Conference on Nuclear Engineering (Icone 26) | ||
| ML18107A797 | 16 April 2018 | Meeting of the Advisory Committee on Reactor Safeguards Regulatory Policies and Practices Subcommittee Meeting - October 18, 2017 | ||
| ML18057B139 | 26 February 2018 | Biennial Review and Evaluation of the NRC Safety Research Program | ||
| ML18022A068 | 23 January 2018 | Letter - ACRS Assessment of the Quality of Selected NRC Research Projects - Fy 2017 | ||
| ML18022A060 | 31 December 2017 | Report - ACRS Assessment of the Quality of Selected NRC Research Projects - Fy 2017 | ||
| ML17319A667 | 16 November 2017 | Sequoyah | State-of-the-Art Reactor Consequence Analysis (Soarca) Project: Sequoyah Integrated Deterministic and Uncertainty Analyses | |
| ML18004A157 | 18 October 2017 | Transcript of Advisory Committee on Reactor Safeguards Regulatory Policy and Practices Subcommittee Meeting - October 18, 2017 |