Exigences pour le suivi et l'affichage des fonctions de sécurité de la centrale nucléaire en cas d'accident

1.1
This Standard provides requirements for the design, testing, installation, and qualification of equipment for the display of nuclear power plant safety functions in the event of an accident.

1.2
This Standard applies to existing plants, life extensions, and new builds.

1.3
This Standard applies to equipment that enables the operator to

(a) monitor the plant safety functions post-accident, both short- and long-term; and Note: Monitoring assists the operator in selecting a strategy to restore or maintain the safety functions (control, cool, and contain).

(b) determine when conditions are developing that warrant initiating off-site emergency procedures.

1.4
At the onset of an accident, certain protective actions (e.g., reactor trip, emergency core cooling actuation, containment isolation) are designed to be performed automatically. Monitoring for the systems that perform these actions is not within the scope of this Standard.

1.5
In CSA Standards, "shall" is used to express a requirement, i.e., a provision that the user is obliged to satisfy in order to comply with the standard; "should" is used to express a recommendation or that which is advised but not required; "may" is used to express an option or that which is permissible within the limits of the standard; and "can" is used to express possibility or capability. Notes accompanying clauses do not include requirements or alternative requirements; the purpose of a note accompanying a clause is to separate from the text explanatory or informative material. Notes to tables and figures are considered part of the table or figure and may be written as requirements. Annexes are designated normative (mandatory) or informative (non-mandatory) to define their application.