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18、ards Update ServiceN290.8-15November 2015Title: Technical specification requirements for nuclear power plant componentsTo register for e-mail notification about any updates to this publication go to shop.csa.ca click on CSA Update ServiceThe List ID that you will need to register for updates to this
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21、re at shop.csa.caor call toll-free 1-800-463-6727 or 416-747-4044.TMA trade-mar k of the Canadian S tandards Association, operating as “CSA Group”Technical specificationrequirements for nuclear powerplant componentsN290.8-15N290.8-15Technical specification requirements for nuclear power plant compon
22、entsNovember 2015 2015 CSA Group 1ContentsTechnical Committee on Reactor Control Systems, Safety Systems, and Instrumentation for NuclearPower Plants 3Subcommittee on Technical Specification Requirements for Nuclear Power Plant Components 6Preface 81 Scope 102 Reference publications 113 Definitions
23、and abbreviations 153.1 Definitions 153.2 Abbreviations 184 Preparation of technical specifications 184.1 Procurement 184.2 Catalogue component 194.3 Referenced Codes, Standards, and generic specifications 194.4 Component standardization 204.5 Supplier capability 204.6 Units 204.7 Supplier submissio
24、ns 204.8 Design 214.9 Component interaction 224.10 Free issue material and services 224.11 Operating organization supplied design 224.12 QA requirements 234.13 Documentation requirements 234.13.1 List of engineering documents 234.13.2 Documentation, drawings, and bills of materials 234.13.3 Installa
25、tion manual 234.13.4 Commissioning/operating manual 234.13.5 Maintenance manual 244.13.6 Reports and other documents 244.13.7 History file requirements 254.14 Reliability and maintainability 254.15 Testing 254.15.1 General 254.15.2 Type and production tests 264.16 Marking and labelling 264.17 Cleanl
26、iness and foreign material exclusion requirements 274.18 Lifting points 274.19 Human factors 274.20 Fire protection and hazards 284.21 Operating conditions 284.21.1 General 28N290.8-15Technical specification requirements for nuclear power plant componentsNovember 2015 2015 CSA Group 24.21.2 Normal o
27、perating conditions 284.21.3 Anticipated operating occurrence conditions 284.21.4 Accident service conditions 284.21.5 Design extension conditions 284.21.6 Service life and duty cycle 284.21.7 Vibration 284.22 Component qualification 284.23 Digital items 294.24 Cyber security 295 Instrumentation and
28、 control components 295.1 Application 305.2 Design requirements 305.3 Functional requirements 305.4 Performance requirements 305.5 Testing 316 Mechanical components 316.1 Application 316.2 Design requirements 316.3 Functional requirements 326.4 Performance requirements 336.5 Testing requirements 336
29、.6 Component qualification requirements 336.7 Valves 336.8 Pumps 336.9 Heat exchangers 346.10 Heating, ventilating, and air conditioning components (HVAC) 346.11 Other mechanical components 347 Electrical components 347.1 Application 347.2 Design requirements 357.3 Functional requirements 357.4 Perf
30、ormance requirements 367.5 Testing requirements 367.6 Maintenance 36Annex A (informative) Data sheet contents 37Annex B (informative) National and international Standards bodies 45Annex C (informative) I however, it mayprovide more specific direction for those requirements.Users of this Standard are
31、 reminded that the design, manufacture, construction, commissioning,operation, and decommissioning of nuclear facilities in Canada are subject to the provisions of theNuclear Safety and Control Act and its supporting Regulations.This Standard was prepared by the Subcommittee on Technical Specificati
32、on Requirements for NuclearPower Plant Components, under the jurisdiction of the Technical Committee on Reactor ControlSystems, Safety Systems, and Instrumentation of Nuclear Power Plants and the Strategic SteeringCommittee on Nuclear Standards, and has been formally approved by the Technical Commit
33、tee.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 itremains the responsibility of the users of the Standard to judge its suitability fo
34、r their particular purpose.3) This Standard was developed by consensus, which is defined by CSA Policy governing standardization Codeof good practice for standardization as “substantial agreement. Consensus implies much more than a simplemajority, but not necessarily unanimity”. It is consistent wit
35、h this definition that a member may be included inthe 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 following information toinquiriescsagroup.org and include “Request for interpr
36、etation” in the subject line:a) define the problem, making reference to the specific clause, and, where appropriate, include anillustrative sketch;b) provide an explanation of circumstances surrounding the actual field condition; andc) where possible, phrase the request in such a way that a specific
37、 “yes” or “no” answer will address theissue.Committee interpretations are processed in accordance with the CSA Directives and guidelines governingstandardization and are available on the Current Standards Activities page at standardsactivities.csa.ca.N290.8-15Technical specification requirements for
38、 nuclear power plant componentsNovember 2015 2015 CSA Group 95) This Standard is subject to subject to review five years from the date of publication. Suggestions for itsimprovement will be referred to the appropriate committee. To submit a proposal for change, please send thefollowing information t
39、o 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; andd) rationale for the change.N290.8-15Technical specification requirements for nuclear power plant compo
40、nentsNovember 2015 2015 CSA Group 10N290.8-15Technical specification requirements fornuclear power plant components1 Scope1.1This Standarda) provides a consistent approach across the industry to produce specifications for components usedin normal operation, anticipated operational occurrences (AOOs)
41、, and design basis accidents(DBAs). This Standard may be used to produce specifications for components used in designextension conditions (DECs);b) provides a common set of attributes to be used when specifying component requirements relatedto plant design requirements;c) utilizes the product specif
42、ic knowledge of the industry to provide common criteria for specifyingtechnical requirements;d) provides a common set of attributes for use when specifying requirements for analysis, testing,design, manufacturing, and associated documentation to demonstrate components can meet theirdesign requiremen
43、ts; ande) is not intended to require update of existing specifications.1.2This Standard applies to all nuclear power plants (NPPs) (i.e., it is technology neutral).1.3This Standard applies to safety-related components and does not apply to commodity material (e.g.,plate steel, conduit, etc., which h
44、ave their own standalone industry specifications) services, and civilstructures. This Standard may be applied to an assembly of components.Note: This Standard may also be applied to components not in the scope of this Standard at the operatingorganizations discretion.1.4The Standard excludes commerc
45、ial considerations that could include the following:a) liability;b) warranty;c) escalation;d) insurance including policy limits, scope, and duration;e) liquidated damages;f) quantity of components; andg) cancellation or termination provisions.1.5In this Standard,“shall” is used to express a requirem
46、ent, i.e., a provision that the user is obliged tosatisfy in order to comply with the Standard; “should” is used to express a recommendation or thatN290.8-15Technical specification requirements for nuclear power plant componentsNovember 2015 2015 CSA Group 11which is advised but not required; and “m
47、ay” is used to express an option or that which is permissiblewithin the limits of the Standard.Notes accompanying clauses do not include requirements or alternative requirements; the purpose of anote accompanying a clause is to separate from the text explanatory or informative material.Notes to tabl
48、es and figures are considered part of the table or figure and may be written asrequirements.Annexes are designated normative (mandatory) or informative (non-mandatory) to define theirapplication.2 Reference publicationsThis Standard refers to the following publications, and where such reference is m
49、ade, it shall be to theedition listed below, including all amendments published thereto.CSA GroupB51-14Boiler, pressure vessel, and pressure piping codeC22.2 SeriesCanadian Electrical Code, Part IIN285.0-12General requirements for pressure retaining systems and components in CANDU nuclear power plantsN286-12Management system requirements for nuclear facilitiesN289 SeriesSeismic design for nuclear power plantsN290.7-14Cyber security for nuclear power plants and small reactor facilitiesN290.12-14Human factors in design for nuclear power plantsN290.13-05Enviro
