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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 three relief requests submitted on December 1, 2014, for Clinton Power Station, Unit 1, to support its transition to 1-year refueling cycles.
The purpose of this meeting is for NRC staff to solicit technical information from a panel of experts concerning degradation of concrete in spent nuclear fuel dry cask storage systems.
The purpose of this public meeting is for Energy Northwest, the licensee, to discuss the details of an upcoming relief request regarding the American Society of Mechanical Engineers Boiler and Pressure Vessel Code classification of the reactor water cleanup system at Columbia…
Discussion of Comments by AP1000 Utilities (APOG) on
Revision 0 of Generic Technical Specification Travelers (GTSTs)
Prepared by the Plant Systems Branch (SPSB) of the Office of New Reactors
To discuss resolution of issues to support the safety review of Tennessee Valley Authority's (TVA) Operating License Application related to Watts Bar Nuclear Plant Unit 2.
The purpose of the meeting is to discuss NRC staff actions to verify safe plant operation and to discuss licensee and vendor actions to ensure continued compliance with Title 10 of the Code of Federal Regulations 50.46 requirements.
The U.S. Nuclear Regulatory Commission (NRC) granted an inservice testing relief request on January 31, 2013 (ADAMS Accession No. ML13022A456), for the Core Spray System pumps. The relief request had 3 parts: (1) relief to continue running the quarterly test with dual pumps, (2…
The purpose of this public meeting is for STP Nuclear Operating Company (STPNOC) to discuss with U.S. Nuclear Regulatory Commission (NRC) staff modifications to "Supplement 1 to Revised STP Pilot Submittal and Requests for Exemptions and License Amendment for Risk-Informed…
The purpose of this meeting is for the Levy Nuclear Plant Units 1 and 2 applicant to present details of the methodology and proprietary calculations related to three AP1000 design matters addressed in RAI Letter Nos. 121 and 122: the estimated dose to main control room operators…
Discuss the technical basis for the Significance Determination Process (SDP) and to determine the appropriate process to model the safety significance of inspection findings that cause an initiating event occurrence.
The NRC Staff will provide an update to the staff’s proposed technical approach for the forthcoming security rulemaking to revise 10 CFR Parts 72, “Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High Level Waste and Reactor Related Class C Waste,” and…
