CSA N289.4:Testing procedures for seismic qualification of nuclear power plant struct

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CSA N289.4:22 Testing procedures for seismic qualification of nuclear power plant structures, systems, and components

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This is the third edition of CSA N289.4, Testing procedures for seismic qualification of nuclear power plant structures, systems, and components. It supersedes the previous editions published in 2012 and 1986.

The major changes to this edition include the following:

a) This Standard was re-structured to consolidate all sub-clauses for the following topics: purchaser’s scope, testing lab’s scope, testing methods, and documentation.

b) The distinction of proof vs. fragility testing was elaborated and enhanced guidance was provided to remove any ambiguity.

c) More explanation was added on the differences between required response spectrum, test response spectrum, required input motion, and table input motion.

d) Requirements related to the disposition of the anomalies found during seismic testing were elaborated.

e) The requirements on seismic aging prior to the seismic testing was made consistent with international practice.

f) Application of the static side load as one of the methods of testing was elaborated.

g) Annex F was improved by clarifying several aspects, such as

i) affidavit replaced by engineer’s certification;

ii) introduction of separate tables for Category A & B valves;

iii) relief valves separated from other valves;

iv) a comprehensive list of available methods of seismic qualification;

v) clarity on use of side load testing; and

vi) clarity regarding hard mounted and line mounted components, including definitions of these terms.

h) The previous Annexes D and E have been combined into one Annex (now Annex D).

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. 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 authority having jurisdiction (in countries other than Canada).

The purpose of this Standard is to provide a basis for the development of specifications for seismic qualification by testing, and to aid purchasers, suppliers, and testing laboratories in selecting the appropriate test method(s) for performing acceptable seismic qualification tests that meet a quality and standard commensurate with the safety principles necessary to comply with the Canadian nuclear safety philosophy.

The CSA N289 Series consists of five separate Standards. Some of the objectives of each Standard are summarized as follows:

a) 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) 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) 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 structures, systems and components (SSCs), and supports that require seismic qualification; and

iii) performing seismic analyses, including the effects of the soil-structure-interaction;

d) N289.4:22, 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) N289.5-12, Seismic instrumentation requirements for nuclear reactors 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 was prepared by the Subcommittee on Testing Procedures for Seismic Qualification of Nuclear Power Plant Structures, Systems, and Components, under the jurisdiction of the Technical Committee on Seismic Design for Nuclear Power Plants and the Strategic Steering Committee on Nuclear Standards, and has been formally approved by the Technical Committee.

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