BS IEC 62954-2019 pdf free download – Nuclear power plants — Control rooms — Requirements for emergency response facilities.
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.
5.2 Role and main features
5.2.1 General The role of the ERF is to provide adequate means, including organization and human expertise, when a plant has experienced a reactor incident, accident or other emergency situation, including a severe reactor accident or severe external hazard, in order:
• to manage the situation and mitigate its consequences;
• to bring relief and assistance to the operating staff on duty;
• to inform official authorities.
The ERF shall be able to cope simultaneously with all units of the NPP in which it is implemented.
As it is impossible to specify all scenarios for which ERF operation may be required, it is necessary to incorporate flexibility and intelligence into the design and operational arrangements in order to maximise the potential for adapting to the actual situation.
Each facility listed below (i.e. ERC, TSC and OSC) may be a building, part of a building or a room.
The organizational relationship between the parts of ERF shall be defined early in the design.
This definition shall comprise clarification of:
• leadership and hierarchy between the parts;
• scope and role of internal and external communication;
• principles for sharing of responsibilities between the three parts and the MCR / SCR.
5.2.2Emergency Response Centre (ERC)
The ERC is a facility,separate from the MCR,which leads and manages the overallemergency response. This includes coordination with the osC for the field operations(see 5.2.4) and with the TSC for the technical advice to the operators (see 5.2.3). lt alsoincludes managing the flow of information to and from external bodies,including requests forexternal assistance and any necessary briefings to relevant off-site organizations.
The ERC should have the following operational features:
.a layout that promotes a “command and control”organisational structure,with facilities for
regular briefing sessions,etc., and separate areas for teams performing independenttasks;
secure and reliable communications with other parts of the ERF, with the MCR (or SCR,as applicable), with off-site authorities and with other parts of the off-site emergencyresponse organisation;
a monitoring capability similar to that available in the MCR,including monitoring ofradiation levels throughout the NPP and in the immediate locality of the site,and includingparameters assigned to severe accidents; the monitored elements should be definedbased on a task analysis;
access to the emergency plans,NPP design information,operating procedures,etc.;suitable space / working surfaces for reading documents, writing,etc.BS IEC 62954 pdf download
BS IEC 62954-2019 pdf free download – Nuclear power plants — Control rooms — Requirements for emergency response facilities
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