CSA N293:23

Preface

This is the fifth edition of CSA N293, Fire protection for nuclear power plants. It supersedes the previous editions published in 2012, 2007, 1995, and 1987. This edition of CSA N293 includes changes arising from new knowledge, operating experience, and comments from users of the Standard. It also incorporates the information from CSA N293S1 on small modular reactors. The Standard has been restructured from its previous edition to allow for improved usability, accessibility, and removal of duplicated requirements. An asterisk (*) as the first character of a clause title or at the beginning of a paragraph indicates that there is guidance or rationale related to that item in Annex A. 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 Regulations. The Canadian Nuclear Safety Commission might impose requirements additional 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. CSA N286 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 may provide more specific direction for those requirements. This Standard was prepared by the New Edition Task Force, under the jurisdiction of the Technical Committee on Fire Protection for Nuclear Power Plants and the Strategic Steering Committee on Nuclear Standards, and has been formally approved by the Technical Committee.

Scope

1.1 *Inclusions

This Standard provides the minimum fire protection requirements for the design, construction, commissioning, operation, and decommissioning of nuclear power plants (NPPs) and small modular reactors (SMRs), including structures, systems, and components (SSCs) that directly support the NPP/SMR and the protected area. Notes: 1) Where requirements do not state specific applicability to NPPs or SMRs, the requirements apply to both types of nuclear facilities. 2) When a clause in this Standard includes a subsection for NPPs and a subsection for SMRs, the requirements for SMRs are separate from the requirements for all other NPPs. In all other cases throughout this Standard, the term ?NPP? is inclusive of SMRs.

1.2 *Exclusions

External events, such as an aircraft crash or terrorist attack, are outside the scope of this Standard.

1.3 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.

1.4 Units of measurement

The values given in SI units are the units of record for the purposes of this Standard. The values given in parentheses are for information and comparison only.