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This is the third edition of CSA N289.2, Ground motion determination for seismic qualification of nuclear power plants. It supersedes the previous editions, published in 2010 and 1981.
The major changes to this edition include the following:
• Clause 4 has been revised to address microearthquake monitoring and induced seismicity.
• Clause 5 has been revised and restructured to provide more details on and differentiate between seismic source characterization and ground motion models (GMMs), and to address the weights associated with both.
• Clause 6 has been revised to address seismic hazard results for near-fault sites, while considering damage potential of earthquakes, and the development of scenario earthquakes.
• A new Clause 7, on evaluation of seismic hazards considering local site conditions, has been introduced to provide a procedure to account for local conditions and for various sources of uncertainty.
• A new Clause 8, an independent peer review, has been introduced to enhance the confidence level of seismic hazard assessment and evaluations.
• A new informative annex (Annex B) has been introduced for processing earthquake motions recorded at the plant site.
• Another new informative annex (Annex C), a bibliography, has been introduced to include recent references and publications associated with the scope of this Standard.
• This Standard has been aligned with recently published CSA Group standards, CNSC Regulatory Documents, and industry documents.
Standards in the CSA N289 series of Standards are developed in response to a recognition by the utilities and industries concerned with nuclear facilities in Canada of a need for the documentation of standards applicable to the seismic design and qualification of nuclear structures, systems, and components (SSCs) of nuclear power plants. Users of this Standard should recognize that it has the force of law only when adopted by the Canadian Nuclear Safety Commission (CNSC) or the appropriate regulatory body (in countries other than Canada).
The CSA N289 series of Standards consists of five Standards. Some of the objectives of each Standard are summarized as follows:
a) CSA N289.1-18, General requirements for seismic design and qualification of nuclear power plants, provides guidelines for identifying structures and systems requiring seismic qualification based on nuclear safety considerations;
b) CSA N289.2:21, Ground motion determination for seismic qualification of nuclear power plants, determines the appropriate seismic ground motion parameters for a particular site;
c) CSA N289.3:20, Design procedures for seismic qualification of nuclear power plants, provides design requirements, criteria, and methods of analysis for
i) determining the design response spectra and ground motion time-histories to be used in the analysis;
ii) establishing design criteria for SSCs, and supports that require seismic qualification; and
iii) performing seismic analyses, including the effects of the soil-structure interaction;
d) CSA N289.4-12, Testing procedures for seismic qualification of nuclear power plant structures, systems and components, provides design requirements and methods for seismic qualification of specific components and systems by testing methods; and
e) CSA N289.5-12, Seismic instrumentation requirements for nuclear power plants and nuclear facilities, establishes the requirements for seismic instrumentation and for seismic-related inspection of structures and systems before and after a seismic event.
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 can provide more specific direction for those requirements. Users of this Standard are reminded that the design, manufacture, construction, commissioning, operation, and decommissioning of nuclear facilities in Canada are subject to the provisions of the Nuclear Safety and Control Act and its Regulations. The Canadian Nuclear Safety Commission (CNSC) can therefore impose additional requirements to those specified in this Standard.
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.
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.