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22、287.1-14General requirements for concrete containment structures for nuclear power plantsFebruary 2014 2014 CSA Group 1ContentsTechnical Committee on Concrete Containment and Safety-Related Structures 4Subcommittee on General Requirements for Concrete Containment Structures for Nuclear Power Plants
23、7Preface 81 Scope 102 Reference publications 113 Definitions 124 General 164.1 Classification of class containment 164.2 Application 164.3 Jurisdictional boundaries 174.4 Aging 175 Responsibilities 225.1 Owner/operators responsibility 225.1.1 Licensing and registration 225.1.2 Administration 225.1.3
24、 Quality assurance (QA) 235.1.4 Appointment of designer 235.1.5 Appointment of constructor 235.1.6 Appointment of fabricators 235.1.7 Appointment of commissioning group 235.1.8 Design/stress report 235.1.9 Specifications and drawings 235.1.10 Construction reports 235.1.11 Procurement procedures 235.
25、1.12 Construction procedures 245.1.13 Fabrication procedures 245.1.14 In-service examination and leakage rate testing 245.1.15 Test specifications and procedures 245.1.16 Filing 245.2 Designers responsibility 245.2.1 Design 245.2.2 Design documentation 245.2.3 Quality assurance (QA) 255.2.4 Design/s
26、tress report 255.2.5 Fabricators drawings 255.2.6 Schedules and procedures 255.2.7 Revisions to specifications and drawings 255.2.8 Commissioning 255.2.9 Records 25N287.1-14General requirements for concrete containment structures for nuclear power plantsFebruary 2014 2014 CSA Group 25.3 Constructors
27、 responsibility 255.3.1 Construction 255.3.2 Quality assurance (QA) 255.3.3 Proof and leakage rate tests 265.3.4 Schedules and procedures 265.3.5 Construction reports 265.4 Fabricators responsibility 265.4.1 Fabrication 265.4.2 Quality assurance (QA) 265.4.3 Drawings 265.4.4 Procedures 265.4.5 Quali
28、ty records 265.5 Material manufacturers responsibility 275.5.1 Materials 275.5.2 Quality assurance (QA) 275.5.3 Quality records 275.6 Commissioning responsibility 276 Documentation 276.1 General 276.2 Design specifications 276.3 Specifications 286.4 Drawings 286.5 Design/stress report 286.6 Fabricat
29、ors shop drawings 296.7 Construction, fabrication, and installation schedules and procedures 296.8 Construction reports 296.9 Commissioning documents 307 Commissioning 307.1 Commissioning program 307.1.1 Commissioning planning 307.1.2 Commissioning groups responsibility 307.1.3 Operating organizatio
30、ns responsibility 317.1.4 Responsibilities of other participants in the commissioning activities 317.1.5 Personnel qualifications 327.2 Commissioning documents 327.2.1 General 327.2.2 Contents of commissioning documents 327.2.3 Test procedures 337.2.4 Report 338 In-service examination and testing 33
31、8.1 Objectives of in-service examination and testing 338.2 Responsibilities of organization/personnel performing in-service examinations and LRT 348.3 In-service examinations and testing personnel qualifications 358.4 In-service examination and testing documents 369 Quality assurance (QA) 36N287.1-1
32、4General requirements for concrete containment structures for nuclear power plantsFebruary 2014 2014 CSA Group 39.1 General 369.2 Quality verification 369.3 Qualification of inspection personnel 379.3.1 General 379.3.2 Non-destructive examination personnel 379.3.3 Welding inspectors 379.3.4 Concrete
33、 construction inspectors 379.3.5 Nonmetallic liner inspectors 389.4 Quality assurance records 38Annex A (informative) Function interactions for documentation 39Annex B (informative) Information pertaining to containment systems 41Annex C (informative) Information on nuclear licensing and registratio
34、n 42Annex D (informative) Index of definitions 45N287.1-14General requirements for concrete containment structures for nuclear power plantsFebruary 2014 2014 CSA Group 4Technical Committee on Concrete Containment and Safety-Related StructuresD. Mitchell McGill University, Montral, QubecRepresenting
35、General InterestChairT.M. Nushaj Ontario Power Generation Inc., Pickering Nuclear, Pickering, OntarioRepresenting Owner/Operator/ProducerVice-ChairJ. Tcherner Mississauga, OntarioRepresenting Service IndustryVice-ChairT.S. Aziz TSAziz Consulting Inc., Mississauga, OntarioAssociateJ. Balinski AMEC Ea
36、rth however, it might provide more specific direction for those requirements.The Standards in the CSA N287 series of Standards were initiated in response to a recognition by the utilities and industries concerned with nuclear power plant structures in Canada of a need for consistent standards for th
37、e design, construction, and testing of concrete containment structures for nuclear power plants.The CSA N287 series of Standards consists of seven Standards. The objectives of each Standard are summarized as follows:a) CSA N287.1-14, General requirements for concrete containment structures for nucle
38、ar power plants, specifies general requirements for the design, construction, testing, and commissioning of concrete containment structures for nuclear power plants designated as class containment and is directed to the owners, designers, manufacturers, fabricators, and constructors of the concrete
39、components and parts;b) CSA N287.2-08, Material requirements for concrete containment structures for CANDU nuclear power plants, specifies requirements for materials used in concrete containment structures;c) CSA N287.3-14, Design requirements for concrete containment structures for nuclear power pl
40、ants, specifies requirements for the design of concrete containment structures;d) CSA N287.4-09, Construction, fabrication, and installation requirements for concrete containment structures for CANDU nuclear power plants, specifies construction, fabrication, and installation requirements that apply
41、to concrete containment structures of a containment system designated as class containment components, parts, and appurtenances for CANDU nuclear power plants;e) CSA N287.5-11, Examination and testing requirements for concrete containment structures for nuclear power plants, specifies examination an
42、d testing requirements that apply to the work of any organization participating in the construction, fabrication, or installation of parts or components of concrete containment structures for nuclear power plants;f) CSA N287.6-11, Pre-operational proof and leakage rate testing requirements for concr
43、ete containment structures for nuclear power plants, specifies requirements for proof by demonstration, before first criticality, that the design and construction of a concrete containment structure are satisfactory with respect to quality and performance as demonstrated by achieving the specified r
44、equirements of CSA N287.6, including commissioning leakage rate target; andN287.1-14General requirements for concrete containment structures for nuclear power plantsFebruary 2014 2014 CSA Group 9g) CSA N287.7-08, In-service examination and testing requirements for concrete containment structures for
45、 CANDU nuclear power plants, specifies uniform requirements whereby, through systematic and periodic examination, the structural and leak-tight integrity of concrete containment structures can be assessed as demonstrated by achieving the specified requirements of CSA N287.7, including the operationa
46、l leakage rate target.In the preparation of these Standards, it was the decision of the Committee to make use of existing Standards, Codes, and other reference material wherever possible.Users of this Standard are reminded that the design, manufacture, construction, commissioning, operation, and dec
47、ommissioning of nuclear facilities in Canada are subject to the provisions of the Nuclear Safety and Control Act, and its supporting Regulations. Thus, requirements additional to those specified in this Standard might be imposed by the Canadian Nuclear Safety Commission.This Standard was prepared by
48、 the Subcommittee on General Requirements for Concrete Containment Structures for Nuclear Power Plants, under the jurisdiction of the Technical Committee on Concrete Containment and Safety-Related Structures and the Strategic Steering Committee on Nuclear Standards, and has been formally approved by
49、 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.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
