NEN-EN-IEC 60965:2011 en

Nuclear power plants - Control rooms - Supplementary control points for reactor shutdown without access to the main control room

  • Deze norm is ingetrokken sinds 23-09-2016

90,57 109,59 Incl BTW

Over deze norm

Status Ingetrokken
Aantal pagina's 20
Commissie Kerntechnische instrumentatie
Gepubliceerd op 01-08-2011
Taal Engels
This International Standard establishes requirements for the supplementary control points provided to enable the operating staff of nuclear power plants to shut down the reactor 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 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 points. It is assumed that supplementary control points 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 Requirements NS-R-1 “Safety of Nuclear Power Plants: Design” and IAEA Safety Guide NS-G-1.3 “Instrumentation and Control Systems Important to Safety in Nuclear Power Plants”. The purpose of this standard is to provide functional design requirements to be used in the design of the supplementary control points of a nuclear power plant to meet safety requirements. This standard is intended for application to supplementary control points 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 points and the main control room, the ergonomic approach, the automation level and the information technology.


ICS-code 27.120.20
Engelse titel Nuclear power plants - Control rooms - Supplementary control points for reactor shutdown without access to the main control room
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