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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
2024 ANS Annual Conference
June 9–12, 2024
Las Vegas, NV|The Mirage
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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NRC seeks comments on new fee schedule for FY 2024
The Nuclear Regulatory Commission is asking for feedback on proposed changes to the annual, licensing, inspection, and special projects fees for fiscal year 2024.
The proposed fee rule, published February 20 in the Federal Register, is based on the FY 2024 Congressional Budget Justification as a full-year appropriation, but it has not yet been enacted. The final rule will be based on the NRC’s actual appropriation, and the agency will update the final fee schedule as appropriate.
13th Nuclear Plant Instrumentation, Control & Human-Machine Interface Technologies (NPIC&HMIT 2023)
Thursday, July 20, 2023|8:00–9:30AM EDT|301B
Ted Quinn (Paragon Energy Solutions)
Ian Jung (NRC)
The nuclear industry is pursuing the development and licensing of a number of advanced reactor designs of various types and sizes. Instrumentation and control for these designs can play a key role in the operation and safety of the facilities. Multiple designers are in various pre- or post-application licensing review stages working with the United States Nuclear Regulatory Commission (NRC). The NRC has also been preparing for the review of the licensing applications. One major area is to enhance the NRC’s regulatory infrastructure that includes the development of the rules and regulatory guidance better suited for the designs. The application of the risk-informed and performance-based (RIPB) approach is one of the most significant areas for the review of the designs. Some of the key examples are the ongoing 10 CFR Part 53 rulemaking effort, the issuance of Regulatory Guide (RG) 1.233, which endorses NEI 18-04, and Trial RG 1.247, which endorses the ASME/ANS non-LWR probabilistic risk assessment (PRA) standard, and the NRC’s ongoing advanced reactor content of application project (ARCAP) along with the industry’s technology-inclusive content of application project (TICAP) in NEI 21-07. The enhanced regulatory infrastructure affects, and can provide opportunities for, the instrumentation and control (I&C) design and licensing. Specific to I&C, the NRC staff has also issued Design Review Guide (DRG) for I&C to be ready for the advanced reactors, and several designers are using this guidance. This panel will discuss the NRC and industry perspectives on the development and licensing of advanced reactor I&C. The emphasis is placed on the I&C-related regulatory infrastructure, the I&C approaches of some of the designers, the industry implementation of such regulatory infrastructure, including the RIPB approach in RG 1.233 and DRG for I&C, and the potential or unique challenges in the I&C licensing.
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