首页> 外文会议>American Nuclear Society;Conference on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies >MODERNIZING APPROCHES TO ADDRESS COMMON CAUSE FAILURE IN DIGITAL INSTRUMENTATION AND CONTROL SYSTEMS
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MODERNIZING APPROCHES TO ADDRESS COMMON CAUSE FAILURE IN DIGITAL INSTRUMENTATION AND CONTROL SYSTEMS

机译:解决数字仪器和控制系统中常见原因失败的现代化方法

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As microprocessor-based safety systems were first introduced in nuclear power plants in theUS in the 1980s, the U.S. Nuclear Regulatory Commission (NRC) recognized that digitalinstrumentation and control (DI&C) can provide advantages in reliability and functionality, but thatit also creates the potential for a new vulnerability to a common cause failures (CCFs) amongsystems in which functions are performed by identical software executed in identical hardware.Specifically, the staff recognized that a latent, systemic fault in design or implementation of softwarecould result in the concurrent failure of essential safety or compensating systems. The potential forpervasive and latent systemic faults resulting in a CCF could be more significant for DI&C systemsbecause of increased resource sharing and the potential for unspecified interactions or unanalyzedconditions. In SECY-93-087, “Policy, Technical, and Licensing Issues Pertaining to Evolutionaryand Advanced Light-Water Reactor (ALWR) Designs,” dated April 2, 1993 [1], the NRC staffidentified policy, technical, and licensing issues pertaining to evolutionary and advanced light waterreactor designs, one of which was defense against CCF in DI&C systems. The staff presentedposition recommendations for addressing the potential for CCFs in DI&C safety systems. In theStaff Requirements Memorandum (SRM) to SECY SECY-93-087 [2], the Commission approved,in part, and disapproved, in part, the staff’s recommendation. The NRC staff implemented theCommission direction into staff guidance for the review of digital I&C systems in a BranchTechnical Position (BTP) 7-19, “Guidance for Evaluation of Defense-in-Depth and Diversity inDigital Computer-Based Instrumentation and Control Systems,” [3] in the Standard Review Planused for new digital systems for new reactors and operating reactors. In the SRM to SECY 16-0070[4], “Integrated Strategy to Modernize the Nuclear Regulatory Commission’s DigitalInstrumentation and Control Regulatory Infrastructure”, dated October 25, 2016, the Commissionapproved implementation of the staff’s integrated action plan (IAP) to modernize the NRC’s digitalinstrumentation and control regulatory infrastructure. As part the work outlined in the IAP NRCstaff has reviewed the current NRC position on defense against CCF in digital I&C systems. Thispaper outlines the high level principles the staff will be using to update the CCF guidance based oncurrent Commission direction.
机译:随着基于微处理器的安全系统首次被引入到美国的核电站中。 在1980年代的美国,美国核监管委员会(NRC)承认数字 仪表和控制(DI&C)可以提供可靠性和功能性方面的优势,但是 它还为潜在的常见原因故障(CCF)创造了新漏洞的可能性。 系统是由在相同硬件中执行的相同软件执行功能的系统。 特别是,员工认识到软件设计或实施中潜在的系统性错误。 可能会导致基本安全或补偿系统并发故障。潜在的 导致CCF的普遍性和潜在性系统性故障对于DI&C系统可能更为重要 由于资源共享的增加以及未指定的交互或未分析的潜力 情况。在SECY-93-087中,“与演进有关的政策,技术和许可问题 和先进的轻水反应堆(ALWR)设计”,1993年4月2日[1],NRC的工作人员 确定与进化和先进轻水有关的政策,技术和许可问题 反应堆设计,其中之一是防御DI&C系统中的CCF。工作人员介绍 定位建议,以解决DI&C安全系统中CCF的潜力。在里面 委员会批准了SECY SECY-93-087 [2]的员工要求备忘录(SRM), 部分被员工的建议所拒绝。 NRC员工实施了 委托指导人员指导分支机构数字I&C系统的审查 技术职位(BTP)7-19,“评估防御深度和多样性的指南 基于数字计算机的仪表和控制系统,” [3]在标准审查计划中 用于新反应堆和运行反应堆的新数字系统。在SRM中对SECY 16-0070 [4],“使核监管委员会数字化现代化的综合策略 仪表和控制监管基础设施”,委员会,2016年10月25日 已批准实施员工的综合行动计划(IAP),以实现NRC数字化的现代化 仪表和控制法规基础架构。作为IAP NRC中概述的工作的一部分 工作人员已审查了NRC当前在数字I&C系统中防御CCF的立场。这 论文概述了员工将根据以下原则更新CCF指南的高级原则 当前的委员会方向。

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