首页> 外文会议>International topical meeting on probabilistic safety assessment and analysis >EXPERIENCE WITH IMPLEMENTING PART 7 OF THE ASME PRA STANDARD (HIGH WIND): CANADIAN PERSPECTIVE
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EXPERIENCE WITH IMPLEMENTING PART 7 OF THE ASME PRA STANDARD (HIGH WIND): CANADIAN PERSPECTIVE

机译:实施ASME PRA标准(大风)第7部分的经验:加拿大的观点

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Canadian Regulatory Standard S-294 "Probabilistic Safety Assessments (PSA) for Nuclear Power Plants" has forced the Canadian nuclear utilities to rigorously assess external hazards using probabilistic approaches. In support of this standard, AMEC NSS and ARA have worked together over the past three years to complete High Wind Probabilistic Risk Assessments (PRAs) for all five of Ontario's multi-unit CANDU nuclear generating stations (Pickering A, Pickering B, Bruce A, Bruce B and Darlington). This work followed the guidance provided in Part 7 of ASME/ANS RA-S-2009 "Standard for Level I/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications ". To execute these projects within reasonable timelines, a phased approach was applied. Phase 1 utilized simplified approaches and techniques to assess and identify the most important aspects of high wind risk for a particular plant, and Phase 2 utilized enhanced techniques to evaluate these important aspects in greater detail. The enhancements can generally be categorized as follows: First, civil/structural modelling issues; And second, PRA modelling issues. The civil/structural enhancements include items such as detailed fragility analysis of the buildings housing credited equipment, and consideration of the physical layout of equipment within the buildings. PRA modelling issues include items such as the number of wind speed intervals, wind duration and the impact on operator action credits, modelling of the correlation of wind and rain, credit for FLEX/EME and the number of high wind targets. This paper looks at the assumptions and methods followed in the Phase 1 "Simple Approach " as applicable to the PRA items identified above and compares them with the Phase 2 "Enhanced Approaches" along with insights with regard to the impact the enhanced approaches may have on high wind risk based on experience with the Canadian nuclear power plants assessed to date. Topics include the following: 1. Increased Number of Wind Speed Intervals 2. Duration of Storm and Human Actions 3. Credit for Flex/EME 4. Number of High Wind Targets 5. Missile Hit vs. Damage Probabilities for Cable Bridges 6. Importance of Loss of Off-Site Power.
机译:加拿大监管标准S-294“核电厂的概率安全评估(PSA)”已迫使加拿大核电公司使用概率方法严格评估外部危害。为了支持该标准,AMEC NSS和ARA在过去三年中共​​同完成了安大略省所有五个多机组CANDU核电站(Pickering A,Pickering B,Bruce A,布鲁斯·B和达林顿)。这项工作遵循了ASME / ANS RA-S-2009第7部分“核电厂应用中I级/大型早期发布频率概率风险评估的标准”中提供的指导。为了在合理的时间表内执行这些项目,采用了分阶段的方法。第1阶段使用简化的方法和技术来评估和识别特定工厂的高风风险的最重要方面,而第2阶段则使用增强的技术来更详细地评估这些重要方面。增强通常可以归纳如下:首先,土木/结构模型问题;其次,PRA建模问题。土建/结构改进包括诸如对装有信贷设备的建筑物进行详细的脆弱性分析,以及考虑建筑物内设备的物理布局之类的项目。 PRA建模问题包括诸如风速间隔数,风力持续时间及其对操作员信用的影响,风雨相关性的建模,FLEX / EME信用和高风目标的数量等项目。本文研究了适用于上述PRA项目的第1阶段“简单方法”中遵循的假设和方法,并将它们与第2阶段“增强方法”进行了比较,并就增强方法可能产生的影响进行了深入分析。根据迄今为止评估的加拿大核电厂的经验,存在较高的风能风险。主题包括以下内容:1.增加风速间隔2.风暴和人为行动的持续时间3. Flex / EME的功劳4.高风目标的数量5.导弹打击与电缆桥架的损坏概率6.重要性场外功率损失。

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