CSA N285 5-2013 Periodic inspection of CANDU nuclear power plant containment components (Fourth Edition).pdf

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1、N285.5-13Periodic inspection of CANDU nuclear power plant containment componentsLegal 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 process brings to

2、gether volunteers representing varied viewpoints and interests to achieve consensus and develop a standard. Although CSA Group administers the process and establishes rules to promote fairness in achieving consensus, it does not independently test, evaluate, or verify the content of standards.Discla

3、imer and exclusion of liabilityThis document is provided without any representations, warranties, or conditions of any kind, express or implied, including, without limitation, implied warranties or conditions concerning this documents fitness for a particular purpose or use, its merchantability, or

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18、ions of this Legal Notice.Standards Update ServiceN285.5-13July 2013Title: Periodic inspection of CANDU nuclear power plant containment 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 r

19、egister for updates to this publication is 2422416.If you require assistance, please e-mail techsupportcsagroup.org or call 416-747-2233.Visit CSA Groups policy on privacy at csagroup.org/legalto find out how we protect your personal information.ISBN 978-1-77139-173-5 2013 CSA GroupAll rights reserv

20、ed. No part of this publication may be reproduced to any form whatsoever without the prior permission of the publisher.Published in July 2013 by CSA Group A not-for-profit private sector organization 5060 Spectrum Way, Suite 100, Mississauga, Ontario, Canada L4W 5N6 To purchase standards and related

21、 publications, visit our Online Store 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”Periodic inspection of CANDU nuclear power plant containment componentsN285.5-13N285.5-13Periodic inspection of CANDU n

22、uclear power plant containment componentsJuly 2013 2013 CSA Group 1ContentsTechnical Committee on Periodic Inspection of CANDU Nuclear Power Plant Components (N285B) 4Subcommittee on Periodic Inspection of CANDU Nuclear Power Plant Containment Components 7Preface 81 Scope 102 Reference publications

23、113 Definitions 114 General requirements 154.1 Licensee responsibilities 154.2 Postulates 154.2.1 Nature of inspection 154.2.2 Prerequisites 164.2.3 Power plant operation 164.3 Components subject to inspection 164.3.1 General 164.3.2 Exemptions 164.4 Radiation exposure 164.5 Accessibility 174.5.1 Ac

24、cess for inspection 174.5.2 Access for authorized inspector 174.6 Program documents 175 Inspection methods and procedures 185.1 General 185.2 Inspection methods 185.2.1 General 185.2.2 Visual inspection 185.2.3 Surface inspection 185.2.4 Volumetric inspection 185.2.5 Thickness measurement 185.3 Insp

25、ection procedures 196 Inspection staff 206.1 Authorized inspector 206.1.1 Responsibilities 206.1.2 Certification of records 206.2 Inspection personnel 206.2.1 Training and qualification 206.2.2 Records 207 Inaugural inspection 207.1 Timing 20N285.5-13Periodic inspection of CANDU nuclear power plant

26、containment componentsJuly 2013 2013 CSA Group 27.2 Repaired/replaced components 207.3 Amendments to inspection program 207.4 Extent of inaugural inspection 217.5 Inaugural inspection area 217.6 Inaugural inspection acceptance criteria 218 Periodic inspection 218.1 General 218.2 Plastic materials 21

27、8.3 Assessment and determination of inspection methods 218.3.1 Loadings 218.3.2 Loss of material 228.3.3 Corrosion-related cracking 228.3.4 Discontinuities 238.4 Extent and areas of inspection 248.4.1 General 248.4.2 Visual inspection 248.4.3 Thickness measurement Loss of material 248.4.4 Surface an

28、d volumetric inspection for corrosion-related cracking 258.4.5 Surface and volumetric inspection for discontinuities 258.5 Identical components 278.5.1 Single reactor units or common containment systems 278.5.2 Multi-unit power plants 278.6 Inspection interval 288.6.1 General 288.6.2 Components requ

29、iring vacuum building outage for inspection 288.6.3 Components requiring dismantling for inspection 288.6.4 Multi-unit power plants 289 Evaluation of results and dispositioning 299.1 Evaluation 299.2 Acceptance criteria and records 299.2.1 Acceptance criteria General 299.2.2 Visual inspection 309.2.

30、3 Surface inspection 309.2.4 Volumetric inspection 319.2.5 Thickness measurement 319.3 Dispositioning 329.3.1 General 329.3.2 Dispositioning while reactor at power 329.3.3 Dispositioning for reactor states other than at power 3210 Repair and replacement 3310.1 General 3310.2 Periodic inspection revi

31、ew/amendment 3311 Modifications 3311.1 General 3311.2 Program amendment 33N285.5-13Periodic inspection of CANDU nuclear power plant containment componentsJuly 2013 2013 CSA Group 312 Recording requirements and reports 3312.1 General requirements 3312.2 Inspection records 3412.3 Inspection reports 34

32、12.3.1 Inaugural inspection reports 3412.3.2 Periodic inspection reports 34Annex A (informative) Periodic inspection, material property monitoring, and test programs for fibreglass reinforced plastic (FRP) containment components 44Annex B (informative) Guide for periodic inspection 53N285.5-13Period

33、ic inspection of CANDU nuclear power plant containment componentsJuly 2013 2013 CSA Group 4Technical Committee on Periodic Inspection of CANDU Nuclear Power Plant Components (N285B)D. Graham Kinectrics Inc.,Toronto, OntarioRepresenting Service Industry ChairN. van den Brekel Ontario Power Generation

34、 Inc.,Pickering, OntarioRepresenting Owner/Operator/ Producer Vice-ChairD. Scarth Kinectrics Inc.,Toronto, OntarioSecretary(Associate)N. Azer AMEC NSS,Toronto, OntarioRepresenting Service IndustryA. Blahoianu Canadian Nuclear Safety Commission (CNSC),Ottawa, OntarioAssociateT. Boyd Babcock however,

35、it may provide more specific direction for those requirements.Users of this Standard are reminded that the operation of nuclear facilities in Canada is subject to the requirements of the Nuclear Safety and Control Act and Regulations. The Canadian Nuclear Safety Commission might impose additional re

36、quirements to those specified in this Standard.This Standard was prepared by the Subcommittee on Periodic Inspection of CANDU Nuclear Power Plant Containment Components, under the jurisdiction of the Technical Committee on Periodic Inspection of CANDU Nuclear Power Plant Components and the Strategic

37、 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

38、 note that it remains the responsibility of the users of the Standard to judge its suitability for their particular purpose.3) This Standard was developed by consensus, which is defined by CSA Policy governing standardization Code of good practice for standardization as “substantial agreement. Conse

39、nsus 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 yet not be in full agreement with all clauses of this Standard.4) To submit a request for interpretation of this Stan

40、dard, please send the following information to inquiriescsagroup.organd 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 surroundi

41、ng the actual field condition; andc) 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 St

42、andards 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 committee. To submit a proposal for change, please send the following information to inquiriescsagroup.organd include “Proposa

43、l for change” in the subject line:a) Standard designation (number);b) relevant clause, table, and/or figure number;N285.5-13Periodic inspection of CANDU nuclear power plant containment componentsJuly 2013 2013 CSA Group 9c) wording of the proposed change; andd) rationale for the change.N285.5-13Peri

44、odic inspection of CANDU nuclear power plant containment componentsJuly 2013 2013 CSA Group 10N285.5-13Periodic inspection of CANDU nuclear power plant containment components1 Scope1.1 This Standard specifies requirements for the periodic inspection of containment system components, including contai

45、nment pressure suppression systems, in CANDU nuclear power plants.1.2 The inspection requirements specified in this Standard (see Annex B for additional guidance) provide assurance of the structural integrity of metallic and plastic containment system components.Note: The following are addressed by

46、other Standards or procedures as specified in Table 1:a) leak tightness and operability requirements; andb) inspection and testing requirements for concrete, embedded parts, and elastomeric seals.Periodic inspection, material property monitoring, and test programs for fiberglass reinforced plastic (

47、FRP) containment components are included in Annex A.1.3 This Standard specifies requirements fora) inspection;b) accessibility;c) inspection methods and procedures;d) personnel qualifications;e) inspection criteria;f) inspection program development;g) inspection frequency;h) evaluation of inspection

48、 results;i) disposition of defects;j) repairs;k) documentation; andl) records.1.4 In this Standard, “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 advi

49、sed but not required; “may” is used to express an option or that which is permissible within the limits of the standard; and “can” is used to express possibility or capability.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.N285.5-13Periodic inspection of CANDU nuclear power plant containment componentsJuly

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