CSA N290.19:18 (R2023)
Risk-informed decision making for nuclear power plants
View Access for this document is only available for viewers in Canada
Product Details
Preface
This is the first edition of CSA N290.19, Risk-informed decision making for nuclear power plants.
This Standard provides requirements and guidance regarding the risk-informed decision making (RIDM) process employed for nuclear power plants (NPPs). It reflects Canadian regulatory requirements, operating experience of the Canadian nuclear industry, and international good practices, including those of the International Atomic Energy Agency.
Users of this Standard are reminded that the site selection, design, manufacture, construction, installation, commissioning, operation, and decommissioning of nuclear facilities in Canada are subject to the Nuclear Safety and Control Act and its Regulations. The Canadian Nuclear Safety Commission might impose additional requirements to those specified in this Standard.
The CSA N Standards provide an interlinked set of requirements for the management of nuclear facilities and activities. CSA N286 Standard provides overall direction to management to develop and implement sound management practices and controls, while the other CSA Group nuclear Standards provide technical requirements and guidance that support the management system. This Standard works in harmony with CSA N286 and does not duplicate the generic requirements of CSA N286; however, it might provide more specific direction for those requirements.
This Standard was prepared by the Subcommittee on Risk-Informed Decision Making for Nuclear Power Plants, under the jurisdiction of the Technical Committee on Reactor Safety and Risk Management and the Strategic Steering Committee on Nuclear Standards, and has been formally approved by the Technical Committee.
Scope
1.1
This Standard describes the RIDM process. This process assists in addressing, among other things, the following:
a) evaluation of options, including design;
b) decision making to support operations, maintenance, and operability assessments;
c) fitness for service criteria;
d) inspection plans for structures, systems and components (SSCs);
e) periodic safety reviews;
f) post-event (e.g., seismic event) actions;
g) resource allocation; and
h) dealing with discovery issues.
This Standard is not meant to replace existing risk management processes but rather to support the existing risk management processes.
Note: In situations where immediate actions are required, see Clauses 4.6.5.2 and 5.4.5 b).
1.2
This Standard applies to nuclear power plants.
Note: This Standard may provide guidance for nuclear facilities other than NPPs. The operators of these facilities may determine the applicability and suitability of the guidance provided by this Standard.
1.3
In this Standard, 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; and may is used to express an option or that which is permissible within the limits of the Standard.
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.
Request Copyright Permissions
