Nuclear Regulatory Commission January 2, 2020 – Federal Register Recent Federal Regulation Documents
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Methodology for Modeling Transient Fires in Nuclear Power Plant Fire Probabilistic Risk Assessments
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
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
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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