BS IEC 62954:2019 pdf download – Nuclear power plants — Control rooms — Requirements for emergency response facilities
3 Terms and definitions For the purposes of this document, the following terms and definitions apply. ISO and IEC maintain terminological databases for use in standardization at the following addresses: • IEC Electropedia: available at http://www.electropedia.org/ • ISO Online browsing platform: available at http://www.iso.org/obp 3.1 Access Control Point ACP area (one or more) within the facility security boundary to control the entry and exit of off-site personnel, in particular emergency teams 3.2 assembly point location (one or more) where non-essential personnel at the facility are assembled, accounted for and sheltered or evacuated 3.3 emergency non-routine situation or event that necessitates prompt action, primarily to mitigate a hazard or adverse consequences for human life, health, property or the environment Note 1 to entry: This includes nuclear and radiological emergencies and conventional emergencies such as fires, release of hazardous chemicals, storms or earthquakes. Note 2 to entry: This includes situations for which prompt action is warranted to mitigate the effects of a perceived hazard. [SOURCE: IAEA GSR Part 7, 201 5] 3.4 emergency plan description of the objectives, policy and concept of operations for the response to an emergency and of the structure, authorities and responsibilities for a systematic, coordinated and effective response Note 1 to entry: The emergency plan serves as the basis for the development of other plans, procedures and checklists. [SOURCE: IAEA GSR Part 7, 201 5] 3.5 emergency response performance of actions to mitigate the consequences of an emergency for human life, health, property and the environment [SOURCE: IAEA GSR Part 7, 201 5]
3.7 Emergency Response Facility ERF facility or location needed for supporting an emergency response, for which specific functions are to be assigned at the preparedness stage, and which need to be usable under emergency conditions [SOURCE: IAEA GSR Part 7, 201 5] 3.8 function specific purpose or objective to be accomplished, that can be specified or described without reference to the physical means of achieving it 3.9 functional analysis examination of the functional goals of a system with respect to available manpower, technology, and other resources, to provide the basis for determining how the function may be assigned and executed [SOURCE: IEC 60964:201 8, 3.1 2] 3.1 0 functional goal performance objectives that shall be satisfied to achieve the corresponding function [SOURCE: IEC 60964: 201 8, 3.1 3] 3.1 1 Nuclear Power Plant site NPP site geographical area that contains the NPP, circumscribed by the security perimeter fence or other designated property marker [SOURCE: IAEA GSR Part 7, 201 5] 3.1 2 Operational Support Centre OSC area separate from the main control room where NPP operations support staff will assemble in an emergency situation to be assigned to various duties (e.g. environmental monitoring, health physics, damage control and fire fighting) 3.1 3 task analysis identification and description of an operator’s task, in terms of its components, to specify the detailed human activities involved, and their functional and temporal relationships Note 1 to entry: Frequently, task analysis in understood to also include the evaluation of the operator’s tasks. In the frame of IEC 60964, this evaluation is described in terms of verification and validation of function assignment and verification and validation of the integrated control room system (which also covers the operator tasks). [SOURCE: IEC 60964: 201 8, 3.31 ]
5 ERF basis for design 5.1 General An overarching principle of this document is that the emergency plan for the nuclear power plant site (assumed to comprise one or more reactor units and associated spent fuel storage facilities) imposes overall requirements for the ERF which are further detailed in this document. This includes criteria for the time of activation of the ERF and the responsibilities that are to be transferred from other NPP locations to the ERF. In some cases the specification and the design of the ERF and the ERF I&C systems will be done many years after the specification and design of the NPP to which the ERF relates. There will be technical interaction through interfaces between ERF individual systems and the NPP existing I&C systems, so that consistent provisions for the exchange of data and interoperability of the ERF with the NPP are established. The ERF buildings and equipment that are difficult to be replaced should be designed with the same life duration as the NPP to which they relate. This duration may include some of the decommissioning period if this is necessary for the plant safety.