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By default, this page lists all upcoming meetings (From date = today). You can search via keywords as well as date ranges for past or upcoming meetings. Click Reset to return the list to all upcoming meetings.
To discuss the application that would modify the licensing basis by revising the License Condition in Appendix C for each unit to implement an alternate defense-in-depth categorization process, an alternate pressure boundary categorization process, and an alternate seismic tier 1…
Discuss the NRC Staff Draft White Paper: Demonstrating the Acceptability of Probabilistic Risk Assessment Results Used to Support Advanced Non-Light Water Reactor Plant Licensing (ADAMS accession no. ML21015A434) and staff observations of NEI 20-09, “Performance of PRA Peer…
The purpose of this teleconference is to discuss SCE’s proposed exemption request to decrease minimum boundary of the San Onofre Nuclear Generating Station (SONGS) Independent Spent Fuel Storage Installation (ISFSI) controlled area.
The purpose of this meeting is to discuss with the National Organization of Test, Research and Training Reactors (TRTR) Executive Committee members, current issues related to operations at research and test reactors.
Public teleconference meeting to discuss the pre-application matters related to construction permitting of the GEH BWRX-300 power reactor design. A portion of the meeting may be closed to the public for discussion of proprietary information.
Staff and contractors from the NRC, as well as participants from federal agencies, industry, and other domestic and international organizations involved in flood hazard assessment, flood risk assessment, and flood protection/mitigation research will provide information on recent…
To discuss Framatome’s plan to assess fuel particle transport and settling in the Fuel Fragmentation, Relocation and Dispersal (FFRD) evaluation for higher burnup fuels.
To discuss issues associated with the safety review of licensing actions and/or Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) closures for SNC's Vogtle Electric Generating Plant, Units 3 and 4
The purpose of this meeting is to discuss with the nuclear industry and other stakeholders the initiatives within the industry and NRC related to construction permit guidance for light water and non-light water reactors and other issues associated with the development and…
The purpose of this meeting between Nuclear Energy Institute (NEI) and the U.S. Nuclear Regulatory Commission (NRC) staff, is to further discuss the inclusion of Technical Specifications Task Force (TSTF) Improved Standard Technical Specifications Change Traveler TSTF 425,…
Staff will present updates to the Public Radiation Safety SDP. These updates include revisions to the process used to disposition transportation-related findings, the addition of a process to disposition findings involving violations of 10 CFR Part 37 requirements and updates to…
The purpose of this meeting is for the NRC to provide licensees with a demonstration on how to use and electronically submit Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(1) and (z)(2) alternative requests.
To discuss future submittal of Westinghouse WCAP-18546-P, "Westinghouse AXIOM® Cladding for Use in Pressurized Water Reactor Fuel" topical report. Information that will be discussed was determined to be proprietary by the NRC staff.
The purpose of this meeting, between Duke Energy Progress, LLC (Duke Energy) and the U.S. Nuclear Regulatory Commission (NRC) staff, is to discuss the outline and technical details for a future relief request concerning the H. B. Robinson Steam Electric Plant, Unit No. 2
The purpose of the meeting is for the NRC staff to discuss its approach to developing alternative criteria for postulating pipe break locations in high-energy piping systems and the corresponding technical basis.
The purpose of this meeting is for the U.S. Nuclear Regulatory Commission (NRC) staff and Tennessee Valley Authority (TVA) to discuss a planned request to use the alternative repair criteria of American Society of Mechanical Engineers Code Case N-504-4 at Sequoyah Nuclear Plant,…
