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CSA N289.5-12 (R2022)
Seismic instrumentation requirements for nuclear power plants and nuclear facilities
Preface This is the second edition of CSA N289.5, Seismic instrumentation requirements for nuclear power plants and nuclear facilities. It supersedes the previous edition, published in 1991 under the title Seismic instrumentation requirements for CANDU nuclear power plants. The title of this Standard has been changed to reflect an extension of its scope: it now addresses not only CANDU® reactors but also any other nuclear power plant and nuclear facilities. Note: CANDU (CANada Deuterium Uranium) is a registered trademark of Atomic Energy of Canada Limited (AECL). Standards in the CSA N289 Series of Standards were initiated in response to the recognition on the part of the utilities and industries concerned with nuclear facilities in Canada of a need for consistent standards for seismic design and qualification of nuclear structures, systems, and components (SSCs) of nuclear power plants. Although this compilation includes regulatory requirements (see below) in addition to those of a technical nature, users of these Standards should recognize that they have the force of law only when adopted by the Canadian Nuclear Safety Commission (CNSC) or, in countries other than Canada, the appropriate regulatory body. The CSA N289 Series consists of five Standards: a) N289.1, General requirements for seismic design and qualification of CANDU nuclear power plants — provides guidelines for identifying structures and systems requiring seismic qualification based on nuclear safety considerations; b) N289.2, Ground motion determination for seismic qualification of nuclear power plants — determines the appropriate seismic ground motion parameters for a particular site; c) N289.3, Design procedures for seismic qualification of nuclear power plants — provides design requirements and methods i) for determining the engineering representation of ground motion, ground response spectra, and floor response spectra for use in the design and seismic qualification of SSCs; and ii) for performing seismic qualification of specified SSCs by analytical methods; d) N289.4, 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; and e) N289.5, Seismic instrumentation requirements for nuclear power plants and nuclear facilities — establishes the requirements for seismic instrumentation. The CSA N-Series Standards provide an interlinked set of requirements for the management of nuclear facilities and activities. The CSA N286 Standard provides overall direction to management to develop and implement sound management practices and controls, while the other CSA 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. 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. Thus, requirements additional to those specified in this Standard might be imposed by the CNSC. This Standard was prepared by the Subcommittee on Seismic Instrumentation Requirements for Nuclear Power Plants and Nuclear Facilities, under the jurisdiction of the Technical Committee on Seismic Design and the Strategic Steering Committee on Nuclear Standards, and has been formally approved by the Technical Committee. Scope 1.1 General 1.1.1 Requirements for nuclear power plants and nuclear facilities This Standard describes the requirements for seismic instrumentation systems for nuclear power plants and nuclear facilities to monitor site-specific seismic responses. These plants and facilities include (a) existing nuclear power plants and on-site nuclear facilities (e.g., spent fuel bays, dry fuel storage) (see Clause 4); Note: "On-site" generally means within the protected area. (b) new nuclear power plants and on-site nuclear facilities (e.g., spent fuel bays, dry fuel storage) (see Clause 5); (c) new small reactors and on-site nuclear facilities (see Clause 6); (d) new enriched fuel processing, fabrication, and storage facilities (see Clause 7); and (e) new high- and intermediate-level radioactive waste storage facilities not in proximity to a nuclear power plant (see Clause 7). Notes: (1) "Existing nuclear power plants and nuclear facilities" refers to those licensed for operation prior to the publication date of this Standard. (2) The requirements for new builds and existing plants might differ. Where requirements differ for new builds and existing plants, the difference is explicitly stated. (3) "In proximity to" generally means either within the protected area or so close that the authority having jurisdiction (AHJ) judges that the instrumentation requirement in this Standard is satisfied by the instrumentation existing at the nuclear power plant. 1.1.2 Application for other nuclear facilities This Standard is not required for, but may provide guidance to, other nuclear facilities that are under the jurisdiction of the Nuclear Safety and Control Act, such as (a) existing small reactors; (b) existing high- and intermediate-level radioactive waste storage facilities not associated with a nuclear power plant; (c) nuclear substance processing facilities; (d) low-level radioactive waste storage; and (e) hospitals or nuclear research centres. The operators of the facilities listed in Items (a) through (e) may, together with the AHJ, determine the applicability and suitability of the guidance provided by this Standard. 1.1.3 Scope exclusions 1.1.3.1 Seismic trigger units Seismic trigger units (e.g., gas shut-off valves) are not considered in this Standard but can be used for specialized engineering applications. Note: Trigger units are not part of a seismic instrumentation system. 1.1.3.2 Automatic shutdown Automatic shutdown is not a seismic design requirement of this Standard; however, sufficient instrumentation of high reliability, as specified in this Standard, is needed to collect data in order to facilitate decision-making regarding continued safe operation, and the data could also be used in conjunction with other indicators to trip a reactor. Refer to Annex A. 1.2 Purpose Where required to be installed, the purpose of seismic instrumentation is to (a) measure the seismic response of the nuclear power plant or nuclear facility to the seismic ground motion; (b) provide seismic motion parameters that can be used to determine whether the seismic design basis has been exceeded; (c) generate seismic motion parameters that can be used in conjunction with inspections and testing of SSCs to determine whether the facility can continue operating; and (d) provide input for validation of the dynamic analysis, as defined in CSA N289.3, of SSCs. Notes: (1) Nuclear power plant post-seismic response procedures (see Clause 6.5 of CSA N289.1) detail the inspections and testing requirements for safe shutdown, maintenance of fuel cooling, containment integrity, and monitoring. (2) Annex A outlines criteria for seismic design basis exceedence of facility SSCs. 1.3 Terminology 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.
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