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Full Description

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 60709
IEC 60964:2009
IEC 61226
IEC 61513
IEC 61771
IEC 62646
ISO 11064
ISO 11064-1
ISO 11064-3
ISO 11064-6
IAEA SSR-2/1:2012
IAEA NS-G-1.3:2002
EN 60709
EN 60964:2010
EN 61226
EN 61513
EN ISO 11064
EN ISO 11064-1
EN ISO 11064-3
EN ISO 11064-6
IEC 60780
IEC 60880
IEC 60980
IEC 61227
IEC 61508-1
IEC 61508-2
IEC 61508-3
IEC 61508-4
IEC 61772
IEC 61839
IEC 62138
IEC 62241
IEC 62645
ISO 9241
IAEA GS-R-3:2006
GS-G-3.1:2006
GS-G-3.5:2009
IAEA SSR-2/2
NS-G-1.3:2002


All current amendments available at time of purchase are included with the purchase of this document.
 

Document History

  1. BS EN 60965:2016

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

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  2. BS EN 60965:2011


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