Advanced reactors comprise one of four sub-arenas that the staff of the U.S. Nuclear Regulatory Commission (NRC) identified in considering which areas of the reactor safety arena to target for greater use of risk information. This page summarizes the following aspects of this sub-arena with expanding menus:
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List of Risk-Informed and Performance-Based Activities
This list shows the ongoing licensing initiatives, projects, and activities that the staff of the U.S. Nuclear Regulatory Commission (NRC) has targeted for greater use of risk information in the Advanced Reactors Sub-Arena within the Reactor Safety Arena:
Technical Assistance for Research on Innovative Methods and Technologies to Enhance Seismic Safety for Design and Construction of Commercial Reactors
Two new regulatory guides (RGs) are currently under development as part of this research. The first one RG for RIPB Seismic Safety, provides an alternative seismic safety approach that incorporates RIPB principles in graded seismic design using a combination of seismic design category (SDC) and design limit state (LS). The document will provide regulatory positions and process for how to determine alternate SDCs and LSs for SSCs considering LMP or other framework in combination the performance standards such as ASCE 1,4, and 43. This RG will provide considerations for applications referencing the RIPB approach under several regularity environments (e.g., Part 50/52 or Part 53). The preliminary draft guide will be completed by February 2022 and the final draft by June 2022.
The other RG under development provides guidance for incorporating seismic isolation technologies in future reactor applications. This guideline will provide criteria and implementation process that leverage ASCE 4 and 43 relevant provisions to extent practicable and the safety aspects with RIPB and LMP under several regularity environments (e.g., Part 50/52 or Part 53). The preliminary draft guide will be completed by February 2022 and the final draft by June 2022.
Risk-Informed Review of Small Modular Reactor (SMR) Designs
Non-Light Water Reactor Licensing Modernization
Risk-informed Emergency Planning Zone Size Evaluation
Advanced Reactor Regulatory Framework
Physical Security for Advanced Reactors
Regulatory Guidance on Advanced Non-LWR PRA Acceptability
The staff reviewed the published ASME/ANS NLWR PRA consensus standard, ASME/ANS RA-S-1.4-2021, “Probabilistic Risk Assessment Standard for Advanced Non- Light Water Reactor Nuclear Power Plants.” The staff made publicly available a pre-decisional draft version of the trial use RG 1.247 to facilitate discussions of stakeholder views and perspectives. Publication of RG 1.247 for trial use is anticipated by mid-FY2022.
Page Last Reviewed/Updated Tuesday, April 12, 2022