Nuclear Regulatory Commission March 7, 2023 – Federal Register Recent Federal Regulation Documents

Applications for Amendments to Facility Operating Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Access to Sensitive Unclassified Non-Safeguards Information
Document Number: 2023-03293
Type: Notice
Date: 2023-03-07
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The U.S. Nuclear Regulatory Commission (NRC) received and is considering approval of four amendment requests. The amendment requests are for LaSalle County Station, Units 1 and 2; Prairie Island Nuclear Generating Plants, Unit Nos. 1 and 2; Callaway Plant, Unit No. 1; and Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2. For each amendment request, the NRC proposes to determine that it involves no significant hazards consideration (NSHC). Because each amendment request contains sensitive unclassified non-safeguards information (SUNSI), an order imposes procedures to obtain access to SUNSI for contention preparation by persons who file a hearing request or petition for leave to intervene.
Material Compatibility for Non-Light Water Reactors
Document Number: 2023-04577
Type: Notice
Date: 2023-03-07
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment on its draft Interim Staff Guidance (ISG) ``Material Compatibility for non-Light Water Reactors, DANU-ISG-2023-01.'' The purpose of this draft ISG is to assist the NRC staff in reviewing certain applications for construction and operation of non-light water reactor designs, including power and non-power reactors.
Consideration of Current Operating Issues and Licensing Actions in License Renewal
Document Number: 2023-04601
Type: Proposed Rule
Date: 2023-03-07
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The U.S. Nuclear Regulatory Commission (NRC) is seeking public comment on a draft regulatory issue summary (RIS) concerning how the NRC considers current operation of a facility in the NRC's license renewal review under NRC regulations. NRC regulations identify the technical information that must be submitted in a license renewal application (LRA) to enable the NRC staff to make a determination that the license may be renewed. In part, an applicant is required to demonstrate that the effects of aging on the functionality of structures and components subject to an aging management review will be adequately managed; the consideration of recent operating experience is an important aspect of that demonstration. In addition, as required by NRC regulations, license renewal applicants need to update their applications with new information related to any current licensing basis changes that could impact aging management of structures and components.
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