BS EN 60965:2016规定了辅助控制室的要求 提供给核电站的运行人员，使其能够关闭反应堆 之前的操作，并在发生以下情况时将电厂保持在安全关闭状态: 由于 主控室或其设施不可用。设计必须确保 辅助控制室受到保护，免受危害，包括任何局部 极端危险，导致主控制室不可用。本标准还规定了功能选择、设计和安装的要求 人权组织- 机器接口，以及应使用的程序 系统地验证和验证辅助控制室的功能设计。假设辅助控制室用于从外部进行停堆操作 在正常电厂条件下，主控制室将无人值守，而非 定期检测。这些要求反映了人体工程学原理的应用 它们适用于此类定期测试和异常情况下的人机界面 工厂条件。本标准不包括特殊应急响应设施（例如技术支持 或为放射性废物处理提供的设施。详细的设备设计也在讨论中 超出标准范围。本标准遵循IAEA特定安全要求SSR-2/1和IAEA的原则 安全指南NS-G-1.3。本标准的目的是提供本标准中使用的功能设计要求 满足安全要求的核电站辅助控制室设计 要求。本标准适用于辅助控制室，其概念 本标准发布后开始设计。如果希望将其应用于现有 在工厂或设计中，必须特别注意确保一致的设计基础。这 例如，与补充控制之间的一致性等因素有关 控制室和主控室，人机工程学方法，自动化水平和 信息技术，以及仪控系统改造的程度。交叉引用:IEC 60709IEC 60964:2009IEC 61226IEC 61513IEC 61771IEC 62646ISO 11064ISO 11064-1ISO 11064-3ISO 11064-6IAEA SSR-2/1:2012AEA NS-G-1.3:2002EN 60709EN 60964:2010EN 61226EN 61513EN ISO 11064-1EN ISO 11064-3EN ISO 11064-6IEC 60780IEC 6080IEC 60227IEC 61508-1IEC 61508-2IEC 61508-4IEC 61778IEC 616262419IEC 616162624IECGS-R-3:2006GS-G-3.1:2006GS-G-3.5:2009IAEA SSR-2/2NS-G-1.3:2002购买本文件时可用的所有现行修订版均包含在购买本文件中。

BS EN 60965:2016 establishes requirements for the Supplementary Control Room provided to enable the operating staff of nuclear power plants to shut down the reactor, where previously operating, and maintain the plant in a safe shut-down state in the event that control of the safety functions can no longer be exercised from the Main Control Room, due to unavailability of the Main Control Room or its facilities. The design has to ensure that the Supplementary Control Room is protected against the hazards, including any localised extreme hazards, leading to the unavailability of the Main Control Room.The standard also establishes requirements for the selection of functions, the design and organisation of the human-machine interface, and the procedures which shall be used systematically to verify and validate the functional design of the supplementary control room.It is assumed that supplementary control room provided for shutdown operations from outside the main control room would be unattended during normal plant conditions other than for periodic testing. The requirements reflect the application of human engineering principles as they apply to the human-machine interface during such periodic testing and during abnormal plant conditions.This standard does not cover special emergency response facilities (e.g. a technical support centre) or facilities provided for radioactive waste handling. Detailed equipment design is also outside the scope of the standard.This standard follows the principles of IAEA Specific Safety Requirements SSR-2/1 and IAEA Safety Guide NS-G-1.3.The purpose of this standard is to provide functional design requirements to be used in the design of the supplementary control room of a nuclear power plant to meet safety requirements.This standard is intended for application to a supplementary control room whose conceptual design is initiated after the publication of this standard. If it is desired to apply it to existing plants or designs, special care must be taken to ensure a consistent design basis. This relates, for example, to factors such as the consistency between the supplementary control room and the main control room, the ergonomic approach, the automation level and the information technology, and the extent of modifications to be implemented in I&C systems.Cross References:IEC 60709IEC 60964:2009IEC 61226IEC 61513IEC 61771IEC 62646ISO 11064ISO 11064-1ISO 11064-3ISO 11064-6IAEA SSR-2/1:2012IAEA NS-G-1.3:2002EN 60709EN 60964:2010EN 61226EN 61513EN ISO 11064EN ISO 11064-1EN ISO 11064-3EN ISO 11064-6IEC 60780IEC 60880IEC 60980IEC 61227IEC 61508-1IEC 61508-2IEC 61508-3IEC 61508-4IEC 61772IEC 61839IEC 62138IEC 62241IEC 62645ISO 9241IAEA GS-R-3:2006GS-G-3.1:2006GS-G-3.5:2009IAEA SSR-2/2NS-G-1.3:2002All current amendments available at time of purchase are included with the purchase of this document.