January-February 2019 NPJ

18 NuclearPlantJournal.com Nuclear Plant Journal, January-February 2019 New Documents EPRI 1. Program on Technology Innovation: Early Integration of Safety Assessment into Advanced Reactor Design - Preliminary Body of Knowledge and Methodology . Product ID: 3002011801. Published September, 2018. Many advanced reactor concepts employ combinations of coolants, fuels, materials, and power conversion technologies that, if commercialized, could offer new options and substantial improvements in terms of safety, economics, performance, and long- term energy security. However, many technology developers—especially those new to nuclear—face substantial challenges in building a safety case in a balanced, incremental manner for technologies that have limited or no licensing and operational track records, incorporate novel design elements, and may include unique radiological and non- radiological source terms. Concurrently, most tools and methods available to evaluate the safety of nuclear technology slated for commercialization have been developed and applied in a back-fit fashion and are largely based on experience from light water reactor (LWR) technology development, licensing, and operations. Any embedded technology and regulatory mindset may limit flexible and efficient application to novel design concepts and new operational paradigms. Early integration of safety assessment into the design process via the application of fit-for-purpose tools and methods should support efficient design iteration and improvement as well as productive engagement with regulatory authorities. In addition, advanced nuclear technology development would benefit from a technology-neutral approach that utilizes hazards identification, risk characterization, and design integration techniques in a coordinated and efficient process—from conceptual design through start of operations. In light of challenges and concerns identified via engagement with advanced reactor developers and other stakeholders, EPRI seeks to define an approach and assemble best practices based on established process hazard analysis (PHA) methods to initiate and facilitate the design-to-license process. Established qualitative and semi-quantitative PHA methods offer a practical means to begin the development of the building blocks needed to support more quantitative design evaluations, including probabilistic risk assessment (PRA). The intent is to benefit from risk-based insights early in the design process and to incrementally develop and quantify the safety design basis as the reactor design matures. This report assembles best practices for and defines a structured incremental, iterative, and balanced approach to safety assessment of advanced reactor designs. The approach emphasizes the application of established, internationally recognized tools—including PHA and PRA methods—and complements ongoing efforts to integrate risk-informed, performance-based approaches into advanced reactor design and licensing. 2. BWRVIP-321: Boiling Water Reactor Vessel and Internals Project: Plan for Extension of the BWR Integrated Surveillance Program (ISP) Through the Second License Renewal (SLR) . Product ID: 3002013097. Published December, 2018. 10CFR50 Appendix H requires that reactor vessels that will exceed a neutron fluence of 1×10 17 n/cm 2 (E>1 MeV) by the end of license have a material surveillance program to monitor changes in the fracture toughness properties, which result from exposure to neutron irradiation and the thermal environment. Since 2002, the U.S. boiling water reactor (BWR) fleet has relied on an integrated surveillance program (ISP) to satisfy the requirements on 10CFR50 Appendix H. The U.S. Nuclear Regulatory Commission approved the program plan for the ISP: BWRVIP-86, Revision 1-A: BWR Vessel and Internals Project, Updated BWR Integrated Surveillance Program (ISP) Implementation Plan (1025144), designed to support the surveillance needs of the U.S. BWR fleet through 60 years of operation. Plants are currently evaluating the potential for a second license renewal (SLR), which would allow for operation to 80 years of plant life. This report provides a plan to extend the ISP for an SLR using a combination of existing data and the irradiation, reconstitution, and testing of previously tested surveillance specimens. 3. Nondestructive Evaluation Program: 2018 Product Catalog . Product ID: 3002014819. Published January, 2019. The EPRI Nondestructive Evaluation Program develops technologies and procedures to quickly, accurately, and cost-effectively inspect and characterize nuclear component condition and inform strategic decisions on whether and when to replace, repair, or continue operation. Research results also are used to inform regulatory actions related to pre-service and in-service inspections and to support the qualification of NDE workers and systems in the nuclear industry. This compilation is a complete listing of available EPRI NDE Program products. 4. Maintenance Rule Users Group ( MRUG) Update Newsletter, Winter 2019 . Product ID: 3002015068. Published January, 2019. The MRUG Update newsletter communicates issues and information important to Maintenance Rule coordinators and those involved in supporting Maintenance Rule programs. Articles are provided by MRUG members, industry experts, regulators, and EPRI personnel. The MRUG Update is published twice a year and is available to all EPRI-member utilities, not just MRUG members. It encourages communication among all Maintenance Rule personnel. The above EPRI documents may be ordered by contacting the Order and Conference Center at (800) 313-3774, Option 2, or email at orders@epri.com .