Nuclear Regulatory Commission 2020 – Federal Register Recent Federal Regulation Documents

Results 501 - 515 of 515
Sunshine Act Meetings
Document Number: 2020-00342
Type: Notice
Date: 2020-01-10
Agency: Nuclear Regulatory Commission, Agencies and Commissions
SHINE Medical Technologies, LLC
Document Number: 2020-00208
Type: Notice
Date: 2020-01-10
Agency: Nuclear Regulatory Commission, Agencies and Commissions
On October 8, 2019, the U.S. Nuclear Regulatory Commission (NRC) staff accepted and docketed an application submitted by SHINE Medical Technologies, LLC (SHINE), dated July 17, 2019, filed pursuant to the Atomic Energy Act of 1954, as amended, and the NRC's regulations, for an operating license for the SHINE Medical Isotope Production Facility. In accordance with the NRC's regulations, any persons whose interest may be affected by the issuance of an operating license to SHINE may file a request for a hearing and petition for leave to intervene with respect to the action. Because the license application contains Sensitive Unclassified Non-Safeguards Information (SUNSI) and Safeguards Information (SGI), an included Order imposes procedures to obtain access to SUNSI and SGI for contention preparation.
Supplemental Guidance Regarding the Chromium-Coated Zirconium Alloy Fuel Cladding Accident Tolerant Fuel Concept
Document Number: 2020-00124
Type: Notice
Date: 2020-01-09
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The U.S. Nuclear Regulatory Commission (NRC) is issuing Interim Staff Guidance (ISG) ATF-ISG-2020-01, ``Supplemental Guidance Regarding the Chromium-Coated Zirconium Alloy Fuel Cladding Accident Tolerant Fuel Concept.'' This ISG is intended to facilitate the NRC staff's understanding of the in-reactor phenomena important to safety for the chromium-coated zirconium alloy fuel cladding concepts, as well as to provide guidance for NRC staff reviewing vendor applications. Chromium-coated zirconium alloy fuel cladding concepts are being pursued by several U.S. fuel vendors as part of the U.S. Department of Energy's accident tolerant fuel program.
List of Approved Spent Fuel Storage Casks: NAC International MAGNASTOR® System, Certificate of Compliance No. 1031, Amendment No. 8
Document Number: 2019-28375
Type: Rule
Date: 2020-01-09
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by revising the NAC International, Inc. (NAC) MAGNASTOR[supreg] System listing within the ``List of approved spent fuel storage casks'' to include Amendment No. 8 to Certificate of Compliance No. 1031. Amendment No. 8 revises the technical specifications to delete Technical Specification A5.6 and revise the maximum pellet diameter in the technical specifications, Appendix B, Table B2-3, from 0.325 inches to 0.3255 inches for the CE16H1 hybrid fuel assembly, which includes Combustion Engineering 16 x 16 fuel assemblies. These revisions are discussed in more detail in the ``Discussion of Changes'' section of this document.
List of Approved Spent Fuel Storage Casks: NAC International MAGNASTOR® System, Certificate of Compliance No. 1031, Amendment No. 8
Document Number: 2019-28374
Type: Proposed Rule
Date: 2020-01-09
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its spent fuel storage regulations by revising the NAC International, Inc. (NAC) MAGNASTOR[supreg] System listing within the ``List of approved spent fuel storage casks'' to include Amendment No. 8 to Certificate of Compliance No. 1031. Amendment No. 8 revises the technical specifications to delete Technical Specification A5.6 and revise the maximum pellet diameter in the technical specifications, Appendix B, Table B2-3, from 0.325 inches to 0.3255 inches for the CE16H1 hybrid fuel assembly, which includes Combustion Engineering 16x16 fuel assemblies.
Arizona Public Service Company; Palo Verde Nuclear Generating Station, Units 1, 2, and 3; Extend Implementation Times
Document Number: 2020-00054
Type: Notice
Date: 2020-01-08
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of amendments to Renewed Facility Operating License Nos. NPF- 41, NPF-51, and NPF-74, issued to Arizona Public Service Company (the licensee), for operation of the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Palo Verde). The proposed amendments would extend the implementation time from February 23, 2020, to August 31, 2020, for the NRC-approved license amendments issued May 29, 2019, associated with risk-informed completion times in accordance with Nuclear Energy Institute (NEI) Topical Report NEI 06-09, Revision 0-A, ``Risk-Informed Technical Specification Initiative 4b, Risk-Managed Technical Specifications (RMTS) Guidelines.'' The licensee is requesting this extension due to unforeseen circumstances.
Modifications to Pressure-Temperature Limits
Document Number: 2019-28061
Type: Proposed Rule
Date: 2020-01-08
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The U.S. Nuclear Regulatory Commission (NRC) is discontinuing the rulemaking activity, ``Modifications to Pressure-Temperature Limits,'' and denying the associated petition for rulemaking, (PRM)-50- 69. The NRC determined that its relevant past decisions and current policies are sufficient to protect the public health and safety in this area and that the potential benefits of proceeding with a rulemaking do not outweigh the associated costs. The rulemaking activity will no longer be reported in the NRC's portion of the Unified Agenda of Regulatory and Deregulatory Actions (the Unified Agenda).
Sunshine Act Meetings
Document Number: 2020-00090
Type: Notice
Date: 2020-01-07
Agency: Nuclear Regulatory Commission, Agencies and Commissions
Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Safeguards Information and Order Imposing Procedures for Access to Sensitive Unclassified Non-Safeguards Information and Safeguards Information
Document Number: 2019-26931
Type: Notice
Date: 2020-01-07
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The U.S. Nuclear Regulatory Commission (NRC) received and is considering approval of five amendment requests. The amendment requests are for Fermi 2; Oconee Nuclear Station, Units 1, 2, and 3; Center for Neutron Research Test Reactors; Joseph M. Farley Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 2. For each amendment request, the NRC proposes to determine that it involves no significant hazards consideration. Because the amendment request contains sensitive unclassified non-safeguards information (SUNSI) and safeguards information (SGI) an order imposes procedures to obtain access to SUNSI and SGI for contention preparation.
Tennessee Valley Authority; Clinch River Nuclear Site
Document Number: 2019-28520
Type: Notice
Date: 2020-01-06
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The U.S. Nuclear Regulatory Commission (NRC) has issued early site permit (ESP) number ESP-006 to Tennessee Valley Authority (TVA). In addition, the NRC has prepared a Summary Record of Decision (ROD) that supports the NRC's decision to issue ESP number ESP-006.
Information Collection: NRC Form 314, Certificate of Disposition of Materials
Document Number: 2019-28438
Type: Notice
Date: 2020-01-06
Agency: Nuclear Regulatory Commission, Agencies and Commissions
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 314 Certificate of Disposition of Materials.''
Methodology for Modeling Transient Fires in Nuclear Power Plant Fire Probabilistic Risk Assessments
Document Number: 2019-28323
Type: Notice
Date: 2020-01-02
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft NUREG entitled, ``Methodology for Modeling Transient Fires in Nuclear Power Plant Fire Probabilistic Risk Assessments'' (NUREG-2233/EPRI 3002016054). This report is a joint product of the NRC and the Electric Power Research Institute (EPRI) collaborating under a memorandum of understanding for fire research. This report contains a methodology to increase the realism in the modeling of transient ignition sources in fire probabilistic risk assessment (FPRA). Additionally, the report develops a method for the detailed modeling of transient fires that includes fire growth and decay parameters, yields of minor products of combustion, heat of combustion, and the physical size and effective elevation of the fire.
Southern Nuclear Operating Company, Inc.; Vogtle Electric Generating Plant, Units 3 and 4
Document Number: 2019-28311
Type: Notice
Date: 2020-01-02
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Facility Operating License Nos. NPF-91 and NPF-92, issued to Southern Nuclear Operating Company, for the Vogtle Electric Generating Plant (VEGP), Units 3 and 4. The proposed amendment requests changes to the VEGP Units 3 and 4 Cyber Security Plan (CSP) to identify the VEGP Units 1 and 2 CSP for cyber security protection of digital assets in common systems, to align language in the VEGP Units 3 and 4 CSP with the corresponding elements of the NRC-endorsed CSP template contained in Nuclear Energy Institute (NEI) 08-09, Revision 6, including Addendum 1, and to enhance certain controls for the VEGP Units 3 and 4 protection and safety monitoring system. For this amendment request, the NRC proposes to determine that it involves no significant hazards consideration. Because this amendment request contains sensitive unclassified non-safeguards information (SUNSI), an order imposes procedures to obtain access to SUNSI for contention preparation.
Advanced Power Reactor 1400 (APR1400) Design Certification
Document Number: 2019-28287
Type: Notice
Date: 2020-01-02
Agency: Nuclear Regulatory Commission, Agencies and Commissions
On May 22, 2019, the U.S. Nuclear Regulatory Commission (NRC) published a direct final rule to certify the Advanced Power Reactor 1400 (APR1400) standard design. The direct final rule contained changes to the information collections in NRC's regulation that needed approval from the Office of Management and Budget (OMB). This document provides notice that OMB has approved the information collection changes associated with the APR1400 direct final rule. The OMB Control Number is 3150-0236.
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