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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.
The U.S. Nuclear Regulatory Commission (NRC) will hold a hybrid meeting (in-person with webinar option) to discuss the NRC’s assessment of safety performance at the Virgil C. Summer Nuclear Station for the 2022 assessment period.
The NRC staff will host a hybrid meeting to present the NRC’s assessment of safety performance at Monticello Nuclear Generating Plant for 2022, as described in the 2022 annual assessment letter. Following the presentation, the NRC will respond to questions specific to the safety…
The purpose of this pre-decisional enforcement conference is to discuss the circumstances of a supervisor employed by Day and Zimmerman (D&Z), a contractor of SNC at Vogtle Electric Generating Plant Unit 1 and 2 involving apparent willful violations. This conference is closed…
The purpose of this meeting is for the staff to provide preliminary feedback to Oklo on its proposed approach to seismic design categorization and site characterization for its reactors.
The purpose of this meeting is to begin an ongoing discussion of the proposed guidance document developed by members of TRTR on compliance with the regulations in Title 10 Code of Federal Regulations, Section 50.59 “Changes, tests and experiments,” emphasizing aspects of digital…
To Discuss Staff's Remaining Questions and Proposed Limitations and Conditions on MRP-227, Revision 2, Pressurized Water Reactor Internals Inspection and Evaluations Guideline
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 between Nebraska Public Power District (NPPD, the licensee) and the U.S. Nuclear Regulatory Commission (NRC) staff is to discuss the licensee's planned license amendment request (LAR) concerning the proposed addition of a temporary note to…
The purpose of this preapplication meeting is to discuss technical and regulatory issues related to the expected Carbon Free Power Project (CFPP) combined license application
The purpose of this teleconference meeting between Nebraska Public Power District (NPPD, the licensee) and the U.S. Nuclear Regulatory Commission (NRC) staff is to discuss the licensee's plans related to the future submittal of a relief request concerning drywell head…
Preapplication Meeting to discuss details of the licensee's approach to pursuing a POL in preparation for a planned license transfer and commencement of decommissioning.
The purpose of the meeting is to discuss items of mutual interest concerning INPO’s training program accreditation process. Topics will include regulatory issues, small modular accreditation, and advanced reactor accreditation and other initiatives. Such meetings are conducted in…
The NRC staff will host a webinar to present the NRC’s
assessment of safety performance at Braidwood Station and Byron Station for 2022, as described in the 2022 annual assessment letters. Following the presentation, the NRC will respond to questions specific to the safety…
The purpose of this meeting is to discuss Holtec’s proposed responses to the structural and criticality request for additional information for UMAX Amendment No. 3, issued on March 31, 2023 (ML22258A260).
The NRC will be available to discuss its assessment of safety performance at Comanche Peak Nuclear Power Plant during calendar year 2022, as described in the attached 2022 annual assessment letter. NRC resident inspectors will be available to answer questions about the safety…
On June 2, 2023 the NRC staff will hold a closed observation meeting with the Institute of Nuclear Power Operations (INPO). Such meetings are conducted in accordance with the NRC/INPO Memorandum of Agreement dated December 1, 2022 (ML23026A093).
The purpose of this meeting is to discuss the change in the neutron fluence values for the W2 reactor pressure vessel welds at Prairie Island, Units 1 and 2.
The purpose of this meeting is to discuss the development of updates to NRC Inspection Manual Chapter 0612 Appendix E, section on cybersecurity examples of minor issues.
