1、N289.4-12Testing procedures for seismic qualification of nuclear power plant structures, systems, and componentsLegal Notice for StandardsCanadian Standards Association (operating as “CSA Group”) develops standards through a consensus standards development process approved by the Standards Council o
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15、n electronic form:sLOADTHISDOCUMENTONTOACOMPUTERFORTHESOLEPURPOSEOFREVIEWINGITsSEARCHANDBROWSETHISDOCUMENTANDsPRINTTHISDOCUMENTIFITISIN0$(b) N289.2, Ground motion determination for seismic qualification of nuclear power plants determines the appropriate seismic ground motion parameters for a particu
16、lar 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 o
17、f 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 requirem
18、ents 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 desi
19、gn, 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 Stan
20、dard 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 appro
21、ved 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 Stand
22、ard to judge its suitability for their particular purpose.N289.4-12 2012 CSA Groupx August 2012(3) This Standard was developed by consensus, which is defined by CSA Policy governing standardization Code of good practice for standardization as “substantial agreement. Consensus implies much more than
23、a simple majority, but not necessarily unanimity”. It is consistent with this definition that a member may be included in the Technical Committee list and yet not be in full agreement with all clauses of this Standard.(4) To submit a request for interpretation of this Standard, please send the follo
24、wing information to inquiriescsagroup.org and include “Request for interpretation” in the subject line:(a) define the problem, making reference to the specific clause, and, where appropriate, include an illustrative sketch;(b) provide an explanation of circumstances surrounding the actual field cond
25、ition; and(c) where possible, phrase the request in such a way that a specific “yes” or “no” answer will address the issue.Committee interpretations are processed in accordance with the CSA Directives and guidelines governing standardization and are available on the Current Standards Activities page
26、 at standardsactivities.csa.ca.(5) This Standard is subject to periodic review, and suggestions for its improvement will be referred to the appropriate committee. To submit a proposal for change, please send the following information to inquiriescsagroup.org and include “Proposal for change” in the
27、subject line:(a) Standard designation (number);(b) relevant clause, table, and/or figure number;(c) wording of the proposed change; and(d) rationale for the change. 2012 CSA GroupTesting procedures for seismic qualification of nuclearpower plant structures, systems, and componentsAugust 2012 1N289.4
28、-12Testing procedures for seismic qualification of nuclear power plant structures, systems, and components1Scope1.1 Structures, systems, and components requiring seismic qualificationThis Standard defines the processes and requirements for performing seismic qualification by testing andpresents the
29、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 s
30、eismic 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 b
31、y 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 developmentThis Standard is intended to provid
32、e 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 specifi
33、cation provides the basis for the development of the test plan by the testing laboratory.1.3 Acceptable methodsThis 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 o
34、f 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 qualific
35、ation 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.
36、4 TerminologyIn 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
37、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 t
38、he table or figure and may be written as requirements.N289.4-12 2012 CSA Group2 August 2012Annexes are designated normative (mandatory) or informative (nonmandatory) to define their application.2 Reference publicationsThis publication refers to the following, and the year dates shown indicate the la
39、test issues available at the time of printing:CSA GroupN286-05 (R2011)Management system requirements for nuclear power plantsN289 series of StandardsN289.1-08General requirements for seismic design and qualification of CANDU nuclear power plantsN289.2-10Ground motion determination for seismic qualif
40、ication of nuclear power plantsN289.3-10Design procedures for seismic qualification of nuclear power plantsN289.5-12Seismic instrumentation requirements for nuclear power plants and nuclear facilitiesN290.13-05 (R2010)Environmental qualification of equipment for CANDU nuclear power plantsASME (Ameri
41、can Society of Mechanical Engineers)ASME QME-1-07Qualification of Active Mechanical Equipment Used in Nuclear Power PlantsEPRI (Electrical Power Research Institute)NP-6041-88A Methodology for Assessment of Nuclear Power Plant Seismic MarginNP-7484-93Guideline for the Seismic Technical Evaluation of
42、Replacement Items for Nuclear Power PlantsTR-104871-95Generic Seismic Technical Evaluations of Replacement Items for Nuclear Power PlantsTR-105849-08Generic Seismic Technical Evaluations of Replacement Items for Nuclear Power Plants Item-Specific EvaluationsIEEE (Institute of Electrical and Electron
43、ics Engineers)344-04IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations382-06IEEE Standard for Qualification of Safety-Related Actuators for Nuclear Power Generating Stations 2012 CSA GroupTesting procedures for seismic qualification of nuc
44、learpower plant structures, systems, and componentsAugust 2012 3C37.98-87IEEE Standard Seismic Testing of Relays3 Definitions and abbreviations3.1 DefinitionsThe following definitions shall apply in this Standard:Acceleration the most common parameter for categorizing seismic motion; it is usually e
45、xpressed in mm/s2, gals (cm/s2) or “g” units.Note: By international agreement, the value of g is 9806.65 mm/s2.Anomaly any deviation or malfunction from acceptable or expected functionality of the test specimen.Note: Examples of anomalies include failure of mounting, dislodging of sub-components, pr
46、emature interruptions during testing, or incomplete compliance with the test specification.Authority having jurisdiction (AHJ) the regulatory organization, office, or agency responsible for approving or accepting design, equipment, materials, installation, or procedures according to applicable codes
47、 and standards.Critical damping coefficient the minimum value of damping that will allow a displaced oscillator to return to its initial position without oscillation.Damping ratio () the ratio of the damping coefficient to the critical damping coefficient for a single-degree-of-freedom oscillator or
48、 a normal mode of vibration.Degrees-of-freedom (DOF) the number of independent coordinates required to define the position of all parts of a system at any instant of time.Design basis earthquake (DBE) an engineering representation of potentially severe effects at the site due to earthquake ground mo
49、tions having a selected probability of exceedance of 1 104per year, or such a probability level as is acceptable to the authority having jurisdiction.Notes: (1) DBE ground motions are usually referred to as an “earthquake”, and can take the form of a response spectrum, or time-history of acceleration, velocity, or displacement.(2) The DBE is used for the seismic qualification
