CSA N289.2
Ground motion determination for seismic qualification of nuclear power plants
Organization: | CSA |
Publication Date: | 1 January 2021 |
Status: | active |
Page Count: | 62 |
scope:
This Standard describes the investigations required to obtain the seismological and geological information necessary to determine the seismic ground motion that will be used in seismic qualification of safety-related nuclear power plant structures, systems, and components (SSCs), and the potential for secondary earthquake effects (e.g., tsunami, seiche, volcanism, slope instability, surface faults, surface instability, and dam failures) that can have a direct or indirect effect on plant safety or operation.
Notes:
1) This Standard establishes the basis for a family of seismic hazard results that can be used as input to CSA N289 Series of Standards. This Standard does not specify
a) ground motion parameters to be used in design;
b) probability level; or
c) degree of confidence to be achieved.
2) The investigations specified in this Standard should be updated periodically to reflect gained knowledge and modern requirements. The investigations may be conducted independently or as part of the periodic safety review (refer to REGDOC-2.3.3, CSA N289.1, and CSA N290.18).
This Standard was developed for the determination of ground motions for Eastern North American 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 Specific Safety Guide SSG-9, and relevant codes of other countries.
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.
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.