CSA N290.17-17 (R2022)

This is the first edition of CSA N290.17, Probabilistic safety assessment for nuclear power plants.

This Standard provides requirements regarding preparation and maintenance of a probabilistic safety assessment at a water-cooled nuclear power plant. It reflects Canadian regulatory requirements, operating experience of the Canadian nuclear industry, and international good practices, including requirements of the International Atomic Energy Agency, the American Society of Mechanical Engineers (ASME), and the American Nuclear Society (ANS).

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-Series Standards provide an interlinked set of requirements for the management of nuclear facilities and activities. The 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.

Scope:

1.1 Reactors and other potential sources

This Standard provides the requirements and guidance for the preparation and maintenance of a PSA at a water-cooled NPP. The radiation sources of concern include both

a) water-cooled power reactors; and

b) other potential sources of radioactive releases to the environment.

Notes:

1) This Standard may be used to provide guidance for nuclear facilities other than NPPs.

2) “Other potential sources” include, for example, wet storage bays and dry used fuel storage facilities.

1.2 New and existing reactors

This Standard applies to both new and existing water-cooled NPPs.

Notes:

1) “Existing NPPs” refers to NPPs initially licensed before 2017.

2) “New NPPs” refers to NPPs initially licensed after 2016.

3) The requirements for a new NPP might be different than the requirements for an existing NPP. This Standard notes where the requirements might be different.

1.3 Single and multi-reactor facilities

This Standard applies to NPPs with one or more water-cooled power reactors.

Notes:

1) The requirements for a single-reactor NPP might be different than the requirements for a multi-reactor NPP. This Standard notes where the requirements might be different.

2) This Standard does not provide guidance related to the aggregation of whole-site risk.

1.4 Level 1 PSA and Level 2 PSA

This Standard addresses both Level 1 PSA and Level 2 PSA.

1.5 Malevolent acts

This Standard does not address and does not apply to malevolent acts.

Note: In Canada, malevolent acts are addressed separately under the CNSC Nuclear Security Regulations.

1.6 Terminology

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.

1.7 Additional terminology

In this Standard, “shall be considered” or “shall consider” means that the user evaluates the impact and documents any decisions.