Preface

This is the second edition of CSA N289.3, Design procedures for seismic qualification of nuclear power plants. It supersedes the previous edition, published in 1981 under the title Design Procedures For Seismic Qualification of CANDU Nuclear Power Plants. The title has been changed to reflect a scope change, from addressing only CANDU reactors to including any nuclear power plant.

Scope

1.1
This Standard specifies the requirements, criteria, and methods of analysis for
(a) determining the design response spectra and ground motion time-histories to be used in the analysis;
(b) establishing design criteria for SSCs, and supports that require seismic qualification; and
(c) performing seismic analyses, including the effects of the soil-structure-interaction.

1.2
This Standard applies to structures, systems, and components (SSCs) in nuclear power plants that require seismic qualification by analytical methods (see CSA N289.1). This Standard may also be applied to SSCs that might not require explicit seismic qualification as deemed appropriate by the owner/licensee or by authorities having jurisdiction.

1.3
This Standard may be applied, as appropriate, to other nuclear facilities under the jurisdiction of the Nuclear Safety and Control Act.

1.4
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 (nonmandatory) to define their application.