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Testing procedures for seismic qualification of nuclear power plant structures, systems, and components
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| 적용범위 | Preface This is the second edition of CSA N289.4, Testing procedures for seismic qualification of nuclear power plant structures, systems, and components. It supersedes the previous edition, published in 1986 under the title Testing Procedures for Seismic Qualification of 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 includes any nuclear power plant"s systems, structures, and components. 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 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 (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; (ii) for performing seismic qualification of specified SSCs by analytical methods; and (iii) to perform evaluations of beyond design basis seismic events; (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 methods; and (e) N289.5, Seismic instrumentation requirements for nuclear reactors and nuclear facilities ? establishes the requirements for seismic instrumentation. 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 may be imposed by the CNSC. 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 and the Strategic Steering Committee on Nuclear Standards, and has been formally approved by the Technical Committee. Notes: (1) Use of the singular does not exclude the plural (and vice versa) when the sense allows. (2) Although the intended primary application of this Standard is stated in its Scope, it is important to note that it remains the responsibility of the users of the Standard to judge its suitability for their particular purpose. Scope 1.1 Structures, systems, and components requiring seismic qualification This Standard defines the processes and requirements for performing seismic qualification by testing and presents the test methods that may be used for the seismic qualification of the nuclear power plant structures, systems, and components (SSCs). Seismic qualification by testing is typically used for SSCs that will be performing both an active function and that are required to change state during or following a seismic event in order to perform a safety function, while maintaining structural and/or pressure-boundary integrity. Notes: (1) Clause 5.3 of CSA N289.1 specifies acceptable seismic qualification methodologies, including qualification by analysis, testing, or a combination thereof and qualification by similarity, depending on the nature and complexity of the SSC. (2) Some mechanical and electrical components are inherently seismically rugged and do not need to be tested to demonstrate seismic capability as discussed in Clause 5.8.5. 1.2 Specification development This Standard is intended to provide a basis for developing specifications for seismic qualification of SSCs by testing, or by a combination of analysis and testing, and to aid component purchasers, suppliers, and testing laboratories in selecting the appropriate test method(s) for performing a seismic qualification test. The specification provides the basis for the development of the test plan by the testing laboratory. 1.3 Acceptable methods This Standard presents several acceptable methods with the intent of permitting the user to make a judicious selection from among the various options. In making such a selection, the user of this Standard should choose those test methods which best recognize the characteristics of a particular SSC and the seismic environment under which it is required to perform its function. Note: It should be recognized that seismic qualification forms only a portion of the overall equipment qualification program. It is important that the qualification program for a component include consideration of all operational loadings (e.g., seismic, environmental, aging, thermal and mechanical stresses, deformation, etc.) for which the component must demonstrably meet its SSC functionality objectives. 1.4 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. |
| 국제분류(ICS)코드 | |
| 페이지수 | 68 |
| Edition |
| No. | 표준번호 | 표준명 | 발행일 | 상태 |
|---|---|---|---|---|
| 1 | CSA N289.4:22 | Testing procedures for seismic qualification of nuclear power plant structures, systems, and components | 2022-01-01 | 표준 |
| 2 | N289.4-12 (R2017) | Testing procedures for seismic qualification of nuclear power plant structures, systems, and components | 2012-01-01 | 표준 |
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