Nuclear Regulatory Commission April 3, 2024 – Federal Register Recent Federal Regulation Documents
Results 1 - 14 of 14
Information Collection: NRC Form 149, OCFO Invitational Traveler Request Form
The U.S. Nuclear Regulatory Commission (NRC) has recently submitted a request for renewal of an existing collection of information to the Office of Management and Budget (OMB) for review. The information collection is entitled, NRC Form 149, "OCFO Invitational Traveler Request Form."
United States Maritime Administration; Nuclear Ship Savannah; License Termination Plan
On October 23, 2023, the U.S. Nuclear Regulatory Commission (NRC) received from the United States Maritime Administration (MARAD, the licensee) a license amendment request to include a License Termination Plan (LTP) for the Nuclear Ship Savannah (NS Savannah). The LTP provides details about the known radiological information for the ship, the planned demolition and decommissioning tasks to be completed, and the final radiological surveys and data that must be obtained for termination of the NRC's license for NS Savannah. The NRC is requesting public comments on NS Savannah's LTP and will hold a public meeting to discuss the LTP.
Interim Staff Guidance: Advanced Reactor Content of Application Project, “Risk-Informed, Performance-Based Fire Protection Program (for Operations)”
The U.S. Nuclear Regulatory Commission (NRC) is issuing Interim Staff Guidance (ISG) DANU-ISG-2022-09, "Risk-Informed, Performance-Based Fire Protection Program (for Operations)." The purpose of this ISG is to provide guidance for prospective applicants in preparing applications for non-light water reactor (non-LWR) designs that use the Licensing Modernization Project (LMP) process and to assist the NRC staff in determining whether such applications meet the minimum requirements for operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
Interim Staff Guidance: Advanced Reactor Content of Application Project, “Risk-Informed Technical Specifications”
The U.S. Nuclear Regulatory Commission (NRC) is issuing Interim Staff Guidance (ISG) DANU-ISG-2022-08, "Risk-Informed Technical Specifications." The purpose of this ISG is to provide guidance for prospective applicants in preparing applications for non- light water reactor (non-LWR) designs that use the Licensing Modernization Project (LMP) process and to assist the NRC staff in determining whether such applications meet the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
Interim Staff Guidance: Advanced Reactor Content of Application Project Chapter 12, Post-Manufacturing and Construction Inspection, Testing, and Analysis Program
The U.S. Nuclear Regulatory Commission (NRC) is issuing Interim Staff Guidance (ISG) DANU-ISG-2022-06, Chapter 12, "Post- manufacturing and construction Inspection, Testing, and Analysis Program." The purpose of this ISG is to provide guidance for prospective applicants in preparing applications for non-light water reactor (non-LWR) designs that use the Licensing Modernization Project (LMP) process and to assist the NRC staff in determining whether such applications meet the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
Interim Staff Guidance: Advanced Reactor Content of Application Project Chapter 11, Organization and Human-System Considerations
The U.S. Nuclear Regulatory Commission (NRC) is issuing Interim Staff Guidance (ISG) DANU-ISG-2022-05, Chapter 11, "Organization and Human-System Considerations." The purpose of this ISG is to provide guidance for prospective applicants in preparing applications for non-light water reactor (non-LWR) designs that use the Licensing Modernization Project (LMP) process and to assist the NRC staff in determining whether such applications meet the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
Interim Staff Guidance: Advanced Reactor Content of Application Project Chapter 10, Control of Occupational Dose
The U.S. Nuclear Regulatory Commission (NRC) issuing Interim Staff Guidance (ISG) DANU-ISG-2022-04, Chapter 10, "Control of Occupational Dose." The purpose of this ISG is to provide guidance for prospective applicants in preparing applications for non-light water reactor (non-LWR) designs that use the Licensing Modernization Project (LMP) process and to assist the NRC staff in determining whether such applications meet the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
Interim Staff Guidance: Advanced Reactor Content of Application Project Chapter 9, Control of Routine Plant Radioactive Effluents, Plant Contamination and Solid Waste
The U.S. Nuclear Regulatory Commission (NRC) is issuing Interim Staff Guidance (ISG) DANU-ISG-2022-03, Chapter 9, "Control of Routine Plant Radioactive Effluents, Plant Contamination and Solid Waste." The purpose of this ISG is to provide guidance for prospective applicants in preparing applications for non-light water reactor (non-LWR) designs that use the Licensing Modernization Project (LMP) process and to assist the NRC staff in determining whether such applications meet the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
Notice of Intent To Conduct Scoping Process and Prepare Environmental Impact Statement; Tennessee Valley Authority; Browns Ferry Nuclear Plant, Units 1, 2, and 3
The U.S. Nuclear Regulatory Commission (NRC) will conduct a scoping process to gather information necessary to prepare an environmental impact statement (EIS) to evaluate the environmental impacts for an application for the subsequent license renewal (SLR) of the Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 for Browns Ferry Nuclear Plant, Units 1, 2, and 3 (Browns Ferry). The NRC is seeking public comment on this action and has scheduled two virtual public scoping meetings.
Interim Staff Guidance: Advanced Reactor Content of Application Project Chapter 2, Site Information
The U.S. Nuclear Regulatory Commission (NRC) is issuing Interim Staff Guidance (ISG) DANU-ISG-2022-02, Chapter 2, "Site Information." The purpose of this ISG is to provide guidance for prospective applicants in preparing applications for non-light water reactor (non-LWR) designs that use the Licensing Modernization Project (LMP) process and to assist the NRC staff in determining whether such applications meet the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
Interim Staff Guidance: Review of Risk-Informed, Technology-Inclusive Advanced Reactor Applications-Roadmap
The U.S. Nuclear Regulatory Commission (NRC) is issuing Interim Staff Guidance (ISG) DANU-ISG-2022-01, "Review of Risk- Informed, Technology-Inclusive Advanced Reactor Applications Roadmap." The purpose of this ISG is to provide guidance for prospective applicants in preparing applications for non-light water reactor (non-LWR) designs that use the Licensing Modernization Project (LMP) process and to assist the NRC staff in determining whether such applications meet the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
Regulatory Guide: Guidance for a Technology-Inclusive Content of Application Methodology To Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors
The U.S. Nuclear Regulatory Commission (NRC) is issuing a new Regulatory Guide (RG) 1.253, Revision 0, "Guidance for a Technology- Inclusive Content of Application Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors." This new RG provides guidance to assist interested parties and prospective applicants in the development of content for major portions of their safety analysis reports required in applications for permits, licenses, certifications, and approvals by the NRC to ensure that applications for non-light water reactor (non-LWR) facility designs using the Licensing Modernization Project (LMP) process meet the minimum requirements for construction permit, operating license, combined license, or design certification applications.
Interim Staff Guidance: Advanced Reactor Content of Application Project, Risk-Informed Inservice Inspection/Inservice Testing Programs for Non-LWRs
The U.S. Nuclear Regulatory Commission (NRC) is issuing Interim Staff Guidance (ISG) DANU-ISG-2022-07, "Risk-Informed Inservice Inspection/Inservice Testing Programs for Non-LWRs." The purpose of this ISG is to provide guidance to prospective applicants in preparing applications for non-light water reactor (non-LWR) designs that use the Licensing Modernization Project (LMP) process and to assist the NRC staff in determining whether such applications meet the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
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