Historical
CSA N289.2-2010 (R2015)
N289.2-10 (R2015) - Ground motion determination for seismic qualification of nuclear power plants
Preface
This is the second edition of CSA N289.2, Ground motion determination for seismic qualification of nuclear power plants. It supersedes the previous edition, published in 1981 under the title Ground Motion Determination 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 describes the investigations required to obtain the seismological and geological information necessary to determine, for a proposed or existing nuclear power plant site, the seismic ground motion that will be used in seismic qualification of safety-related plant structures and systems, and the potential for seismically induced phenomena that can have a direct or indirect effect on plant safety or operation. Note: CSA N289.2 establishes the basis for a family of seismic hazard results that can be used as input to CSA N289.3. CSA N289.2 does not specify (a) ground motion parameters to be used in design; (b) probability level; or (c) degree of confidence to be achieved.1.2 This Standard was developed for the determination of ground motions for regions of low to moderate seismic hazard, comparable to the levels near Canada's existing nuclear power plants. In regions of higher seismic hazard, the assessment of strong earthquake shaking can be more complex due to near-fault and other effects that are beyond the scope of this Standard. Therefore, while the provisions of this Standard can be applied to any nuclear power plant site, additional provisions might be required for high seismic hazard sites. Note: Guidance regarding additional provisions for high seismic hazard sites may be obtained from IAEA Safety Standards Series No. NS-G-3.3, and relevant codes of other countries.
1.3 This Standard may be applied, as appropriate, to other nuclear facilities under the jurisdiction of the Government of Canada's 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.
CONTENT PROVIDER
CSA America, Inc. [csa]
CSA America, Inc. [csa]