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SNAPSHOT REVIEW OF THE REGULATION OF GAS VOIDS IN NUCLEAR STEAM SUPPLY SYSTEMS IN THE UNITED STATES

机译:SNAPSHOT审查美国核蒸汽供应系统中的气体调节

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The recent NRC Generic Letter (GL) 2008-01 titled "Managing Gas Intrusion in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems" to nuclear power plant licensees in the United States requires demonstration of suitable design, operational testing and control measures in order to maintain licensing commitments [1]. The generic letter outlines a number of actions that are detailed in nature; such as establishing pump void tolerance limits, limits on pump suction void fractions, etc. Each addressee was requested to evaluate their Emergency Core Cooling System (ECCS), Decay Heat Removal (DHR) system, and Containment Spray (CS) system. For each of these systems, design, operation, and test procedures were evaluated to assure that gas intrusion is minimized and monitored in order to maintain system operability and compliance with the requirements of 10 Code of Federal Regulation (CFR) 50 Appendix B [2]. In the GL 2008-01, licensees were requested to evaluate the ECCS, DHR and CS systems along four principal areas to ensure that gas accumulation is maintained less than the amount that challenges the operability of the systems, and that licensees shall take appropriate actions when the conditions are identified. The four principal areas are licensing basis, design, testing, and corrective actions. Each addressee was requested to provide a summary description of how the "REQUESTED ACTIONS" in the generic letter were addressed within nine months of the generic letter issue date. If an addressee determined that system or procedure modifications were necessary based on the review of the requested actions but cannot be accomplished within nine months of the date of the generic letter, then theaddressee should provide a plan and schedule for completion of the actions. Many plants used their corrective action programs to accomplish this task. In its response, the licensee addressed any alternative course of action that it proposed to take, including the basis for the acceptability of the proposed alternative course of action. The nuclear industry, under the auspices of the Nuclear Energy Institute, has worked collaboratively with the industry to develop solutions and responses to the nine month NRC request, and these responses were submitted in October of 2008. Since that time, the NRC has been reviewing the plant submittals and issuing requests for additional information (RAIs) to the plants for clarification of their respective programs. This paper provides a snapshot review of the regulation of gas voids in the United States by focusing not only on industry actions to address the generic letter but also on the nature of the NRC requests to the nuclear plants for clarification of plant gas mitigation programs. The goal of the paper is to explore if the RAIs will provide some insights on NRC expectations of the industry as plants address gas intrusion in safety related Nuclear Steam Supply Systems (NSSS).
机译:最近发布给美国核电厂被许可人的NRC通用信函(GL)2008-01,标题为“管理应急堆芯冷却,腐烂除热和安全壳喷雾系统中的气体入侵”,要求证明适当的设计,运行测试和控制措施为了维持许可承诺[1]。通用字母概述了许多详细的动作;例如,建立泵空隙公差极限,对泵吸入空隙分数的限制等。要求每个收件人评估其紧急堆芯冷却系统(ECCS),衰减散热(DHR)系统和安全壳喷雾(CS)系统。对于这些系统中的每一个,都对设计,操作和测试程序进行了评估,以确保最小化和监控瓦斯入侵,以保持系统的可操作性并符合10联邦法规(CFR)50附录B [2]的要求。 。在GL 2008-01中,要求被许可方评估四个主要领域的ECCS,DHR和CS系统,以确保气体累积量保持在小于挑战系统可操作性的水平,并且被许可方应在采取措施时采取适当的措施。确定条件。四个主要领域是许可基础,设计,测试和纠正措施。请每个收件人提供一份概述,说明在普通信件发出之日起九个月内如何处理普通信件中的“要求的措施”。如果收件人根据对请求采取的措施的审查确定有必要对系统或程序进行修改,但是在发出通用信函之日起九个月内无法完成修改,则该收件人应提供完成该措施的计划和时间表。许多工厂使用其纠正措施程序来完成此任务。被许可人在答复中谈到了其提议采取的任何替代措施,包括所提议替代方案的可接受性的基础。在核能研究所的主持下,核工业已与核工业合作开发针对九个月NRC要求的解决方案和响应,这些响应已于2008年10月提交。自那时以来,NRC一直在审查工厂提交并向工厂发出要求提供更多信息(RAI)的请求,以澄清其各自的计划。本文不仅着眼于解决通用信函的行业行动,而且着眼于NRC向核电厂提出的澄清植物气体缓解计划的要求的性质,从而简要回顾了美国对气体空隙的监管。本文的目的是探索当工厂解决安全相关的核蒸汽供应系统(NSSS)中的气体入侵问题时,RAI是否将对NRC对行业的期望提供一些见解。

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