CSA N290.0-11/N290.3-16 Package

Preface:

This is the first edition of CSA N290.0, General requirements for safety systems of nuclear power plants. This Standard is one of a series of standards on reactor control systems, safety systems, and instrumentation for nuclear power plants.

Scope:

1.1

This Standard covers the design, qualification, installation, operation, maintenance, inspection, and documentation of the safety systems for a water-cooled nuclear power plant.

1.2

This Standard provides the general requirements for the safety systems. This Standard is a companion document of CSA N290.2 and N290.3, which outline specific requirements.

1.3

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; 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.

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N290.3-16 Requirements for the containment system of nuclear power plants

Preface:

This is the second edition of CSA N290.3, Requirements for the containment system of nuclear power plants. It supersedes the first edition, published in 2011.

This new edition was developed in response to the lessons learned from the Fukushima accident to specifically address

a) post-accident design pressures

b) venting

c) hydrogen gas concentration control requirements

d) multi-unit stations/events

This new edition has been made to align with CNSC REGDOC-2.5.2 and CSA N290.16.

This Standard has been written as a general standard for the containment system of nuclear power plants, and establishes the nuclear safety design, qualification, installation, operation, maintenance, inspection, and documentation.

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.

This Standard is one of a series of standards on reactor control systems, safety systems, and instrumentation for nuclear power plants.

Scope:

1.1

This Standard applies to the containment system of existing and new water-cooled nuclear power plants.

Notes:

1) “Existing nuclear power plants” refers to those licensed for initial operation prior to 2011.

2) The requirements for new builds and existing plants might differ. Where requirements differ for new builds and existing plants, the difference is explicitly stated.

1.2

This Standard was written as a companion document to CSA N290.0, which outlines general requirements for safety systems.

This Standard, with its companion document, specifies requirements for the design, qualification, installation, operation, maintenance, inspection, and documentation of a containment system.

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.

1.4

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

Note: Examples can include no action, operating procedures, design features.