1、N289.5-12Seismic instrumentation requirements for nuclear power plants and nuclear facilitiesLegal Notice for StandardsCanadian Standards Association (operating as “CSA Group”) develops standards through a consensus standards development process approved by the Standards Council of Canada. This proc
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15、LOADTHISDOCUMENTONTOACOMPUTERFORTHESOLEPURPOSEOFREVIEWINGITsSEARCHANDBROWSETHISDOCUMENTANDsPRINTTHISDOCUMENTIFITISIN0$(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
16、, 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
17、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 testin
18、g; 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
19、 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 duplica
20、te 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
21、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
22、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
23、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.N289.5-12 2012 CSA Groupx August 2012(3) This Standard was developed by consensus, which is defin
24、ed by CSA Policy governing standardization Code of good practice for standardization as “substantial agreement. Consensus implies much more than 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
25、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 following information to inquiriescsagroup.org and include “Request for interpretation” in the subject line:(a) define the problem, making reference to the spec
26、ific clause, and, where appropriate, include an illustrative sketch;(b) provide an explanation of circumstances surrounding the actual field condition; 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 pr
27、ocessed in accordance with the CSA Directives and guidelines governing standardization and are available on the Current Standards Activities page at standardsactivities.csa.ca.(5) This Standard is subject to periodic review, and suggestions for its improvement will be referred to the appropriate com
28、mittee. To submit a proposal for change, please send the following information to inquiriescsagroup.org and include “Proposal for change” in the subject line:(a) Standard designation (number);(b) relevant clause, table, and/or figure number;(c) wording of the proposed change; and(d) rationale for th
29、e change. 2012 CSA GroupSeismic instrumentation requirements fornuclear power plants and nuclear facilitiesAugust 2012 1N289.5-12Seismic instrumentation requirements for nuclear power plants and nuclear facilities0Introduction0.1 ObjectiveThis Standard provides a basis for specifying requirements fo
30、r seismic instrumentation. The recorded data of seismic activity will be used to compare actual and predicted responses, and to assess the need for further detailed inspections. This Standard aids owners of nuclear power plants and nuclear facilities in the determination of the extent and nature of
31、instrumentation to be installed. It also is intended to aid owners and equipment suppliers by specifying instrumentation commensurate with Canadian nuclear safety principles.Note: See Table 1 for a summary of the requirements for, and the number and locations of, accelerometers for various nuclear f
32、acilities.0.2 ApplicationUsers of this Standard will apply only one clause from Clauses 4 to 7 depending on the type of facility. Unless specifically stated otherwise, all other clauses and annexes in this Standard apply to all facilities listed in Clause 1.1, regardless of type.Note: For example, o
33、wners of new nuclear power plants and new on-site nuclear facilities would apply Clauses 1 to 3, 5, and 8 to 10.1Scope1.1 General1.1.1 Requirements for nuclear power plants and nuclear facilitiesThis Standard describes the requirements for seismic instrumentation systems for nuclear power plants and
34、 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
35、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 radioactiv
36、e 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 di
37、ffer. Where requirements differ for new builds and existing plants, the difference is explicitly stated.N289.5-12 2012 CSA Group2 August 2012(3) “In proximity to” generally means either within the protected area or so close that the authority having jurisdiction (AHJ) judges that the instrumentation
38、 requirement in this Standard is satisfied by the instrumentation existing at the nuclear power plant.1.1.2 Application for other nuclear facilitiesThis Standard is not required for, but may provide guidance to, other nuclear facilities that are under the jurisdiction of the Nuclear Safety and Contr
39、ol 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 ope
40、rators 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 exclusions1.1.3.1 Seismic trigger unitsSeismic trigger units (e.g., gas shut-off valves) are not considered in this S
41、tandard but can be used for specialized engineering applications.Note: Trigger units are not part of a seismic instrumentation system.1.1.3.2 Automatic shutdownAutomatic shutdown is not a seismic design requirement of this Standard; however, sufficient instrumentation of high reliability, as specifi
42、ed 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 PurposeWhere required to be installed, the purpose of seismic instrum
43、entation 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
44、 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) de
45、tail 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 TerminologyIn CSA standards, “shall” is used to express a requirement, i.e., a pr
46、ovision 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 d
47、o 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 normat
48、ive (mandatory) or informative (nonmandatory) to define their application. 2012 CSA GroupSeismic instrumentation requirements fornuclear power plants and nuclear facilitiesAugust 2012 32 Reference publicationsThis publication refers to the following, and the year dates shown indicate the latest issu
49、es available at the time of printing:CSA GroupN286-05Management 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 qualification of nuclear power plantsN289.3-10Design procedures for seismic qualification of nuclear power plantsN289.4-12T
