January-February 2019 NPJ

Nuclear Plant Journal, January-February 2019 NuclearPlantJournal.com 37 explore potential alternative standards for NRC endorsement, such as international nuclear standards like the International Electrotechnical Commission (IEC) 61513, “Nuclear Power Plants- Instrumentation and Control Important to Safety - General Requirements for Systems.” Given the more graded approach IEC nuclear standards have taken for classification of I&C equipment with an appropriate set of design and development criteria, adopting these standards could potentially enhance incorporation of these elements from the FAA’s and FDA’s permitting approach. As part of this digital I&C regulatory framework strategic improvement project, the NRC is evaluating approaches for improved licensing methods, including those used within non-nuclear safety- critical industries and the military, to develop a performance-based and risk- informed regulatory infrastructure that will anticipate the evolution and future development of digital I&C technology as it is applied to nuclear safety applications. Summary The NRC recognizes the advantages, including the safety benefits, of using digital technology in nuclear safety applications and continues to adapt the regulatory framework for licensing the use of digital technology in the nuclear industry. As part of the broader initiative on the digital I&C regulatory framework, the NRC continues to evaluate other ways in which processes to permit the use of digital I&C in safety applications outside of the nuclear industry may be incorporated into the NRC’s regulatory framework. The NRC has made changes to several aspects of the digital I&C permitting approach. The NRC will continue to develop risk-informed, safety-focused approaches for permitting digital I&C for nuclear power plant safety applications in a manner that provides adequate protection of the public health and safety and the common defense and security. References 1 The Joint Explanatory Statement and this report use the terms “approaches to permitting digital I&C.” It should be noted that the regulatory authorities discussed in this report may use other terms such as “regulatory approval” or “certification.” 2 IEEE Std. 603-1991 is an industry consensus standard that is incorporated by reference in 10 CFR 50.55a(h) as part of the requirements for I&C and electrical systems in nuclear power plants. The design criteria within this standard are not specific to the technology employed (e.g. analog vs. digital). 3 RIS 2002-22, Supplement 1, “Clarification on Endorsement of Nuclear Energy Institute Guidance in Designing Digital Upgrades in Instrumentation and Control Systems.” A RIS is used to (1) communicate and clarify NRC technical or policy positions on regulatory matters that have not been communicated to or are not broadly understood by the nuclear industry, (2) inform the nuclear industry of opportunities for regulatory relief, (3) communicate previous NRC endorsement of industry guidance on technical or regulatory matters, (4) provide guidance to applicants and licensees on the scope and detail of information that should be provided in licensing applications to facilitate NRC review, and (5) request the voluntary participation of the nuclear industry in NRC-sponsored pilot programs or the voluntary submittal of information which will assist the NRC in the performance of its functions. 4 NUREG/CR-7007, “Diversity Strategies for Nuclear Power Plant Instrumentation and Control Systems,” February 2009. 5 The Working Group on Digital I&C was formerly known as the Multinational Design Evaluation Program, Digital Instrumentation and Controls Working Group. 6 The FAA and Industry Guide to Product Certification, Third Edition, 2017. 7 A designated engineering representative is an individual, appointed in accordance with 14 CFR 183.29, who holds an engineering degree or equivalent, possesses technical knowledge and experience, and meets the qualification requirements of Order 8100.8. 8 14 CFR § 25.1309, “Equipment, systems, and installations” is an example of an airworthiness regulation. 9 14 CFR Part 21, “Certification Procedures for Products and Articles.” 10 TheFAA’sAdvisoryCircularAC20- 115D, “Airborne Software Development Assurance Using EUROCAE ED-12() and RTCA DO-178(),” recognizes DO- 178C as an acceptable means, but not the only means, for showing compliance with the applicable airworthiness regulations. 11 The National Traffic and Motor Vehicle Safety Act has been codified under Title 49 United States Code (USC) Chapter 301: Motor Vehicle Safety. 12 Federal Motor Vehicle Safety Standards are codified in 49 CFR Part 571. 13 Automated Driving Systems 2.0: A Vision for Safety. 01/16/2019 G.D. 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