Every nuclear power plant in the U.S. and around the world is obligated to maintain high levels of safety with measures that ensure plant reliability and integrity. These programs have become increasingly risk-informed in recent years. New reactor designs are very focused on risk-informed approaches to support all stages of development—from initial design and licensing to plant operation and retirement. The License Modernization Project (LMP) initiative by the U.S. Nuclear Regulatory Commission (NRC) is just one example of a risk-informed approach being encouraged for implementation.
The LMP initiative resulted in issuance of Regulatory Guide (RG) 1.233, "Guidance for a Technology-Inclusive, Risk-Informed, and Performance-Based Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light Water Reactors." RG 1.233 endorses Nuclear Energy Institute (NEI) 18-04, Revision 1, “Risk-Informed Performance-Based Guidance for Non-Light Water Reactor Licensing Basis Development,” as one acceptable method for non-LWR designers to use for selection of licensing-basis events (LBEs); classification and special treatments of structures, systems, and components (SSCs); and assessment of defense in depth (DID), activities that are fundamental to the safe design of non-LWRs.
In August 2020, the NRC communicated to the American Society of Mechanical Engineers (ASME) that it has initiated efforts to review and endorse the 2019 Edition of ASME Boiler & Pressure Vessel Code (BPVC) Section XI, Division 2 (hereafter referred to as Division 2) for application to non-light-water reactors (LWRs).
Draft Regulatory Guide DG-1383 was issued for public comments in September 2021 with full issuance expected in 2022. This endorsement adds urgency for developers of new reactor designs to understand how Division 2 is to be implemented.
Regulatory Guide DG-1383 “describes an approach that is acceptable to the staff of the NRC for the development and implementation of a preservice (PSI) and inservice (ISI) program for non-light water reactors.” Division 2 also provides the requirements for the creation of the Reliability and Integrity Management (RIM) program for any type of non-LWR nuclear power plant. The RIM program can be beneficial to the industry by reducing implementation costs and providing consistency in implementation for users. However, because Division 2 complies with ISI requirements through application of processes that are common to current LWR designs, there is limited experience to draw from and limited guidance on meeting the requirements for the development of the risk-informed RIM program.
Therefore, Idaho National Laboratory’s (INL) Regulatory Development R&D area supporting the Department of Energy’s (DOE) Advanced Reactor Demonstration Program initiated a project to develop guidance based on the pending Division 2 requirements for non-LWR developers through the establishment of the risk-informed RIM program. INL’s project covers a limited scope focused on a few key steps:
- Plant, safety systems, and SSC reliability allocations
- Identification and evaluation of RIM strategies
- Evaluation of uncertainties.
The scope was selected based on industry feedback about the development of the RIM program. INL’s project demonstrates the RIM development process using a case study that presents various possibilities and options for meeting RIM program requirements, including considerations of a tradeoff between reliability and economics, and optimization of design options.
This paper presents activities, findings, and available outcomes of this project as well as identifies needs for additional research.
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