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CSA N287.5:20 Examination and testing requirements for concrete containment structures for nuclear power plants

standard by CSA Group, 07/01/2020

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Preface:

This is the fourth edition of CSA N287.5, Examination and testing requirements for concrete containment structures for nuclear power plants. It supersedes the previous editions, published in 2011, 1993, and 1981.

The major changes to this edition include the following: The test and test frequencies for concrete materials and grout and their constituents were updated (Tables 1 and 2). The definitions for containment structure and containment boundary were updated to align with the other CSA N287 series standards. The term "class containment" was modified to align with the other CSA N287 series of Standards. The requirements for anchors, welds, and grouted embedments were updated to align with other CSA N287 series of Standards. The terms and definitions were updated to align with the common list of definitions. Requirements for personnel qualification were included. A clause on aging management was added. The CSA N-Series Standards provide an interlinked set of requirements for the management of nuclear facilities and activities. CSA N286 provides overall direction to management to develop and implement sound management practices and controls, while the other CSA Group nuclear Standards provide technical requirements and guidance that support the management system. This Standard works in harmony with CSA N286 and does not duplicate the generic requirements of CSA N286; however, it might provide more specific direction for those requirements.

This Standard specifies examination and testing requirements that will ensure that concrete containment structures are built using techniques and work practices that meet the quality and standards commensurate with the safety principles necessary to comply with the Canadian nuclear safety philosophy.

This Standard is part of the CSA N287 series of Standards, which provides the requirements for concrete containment structures for nuclear power plants. These 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 the design, construction, and testing of concrete containment structures for nuclear power plants.

The CSA N287 series of Standards consists of eight Standards. The objectives of each Standard are summarized as follows: CSA N287.1, General requirements for concrete containment structures for nuclear power plants, specifies general requirements for the design, construction, testing, commissioning, and in-service examination and testing of concrete containment structures for nuclear power plants and is directed to the owners, designers, manufacturers, fabricators, and constructors; CSA N287.2, Material requirements for concrete containment structures for nuclear power plants, specifies requirements for materials used for concrete containment structures; CSA N287.3, Design requirements for concrete containment structures for nuclear power plants, specifies requirements for the design of concrete containment structures; CSA N287.4, Construction, fabrication, and installation requirements for concrete containment structures for nuclear power plants, specifies construction, fabrication, and installation requirements for concrete containment structures for nuclear power plants; CSA N287.5, Examination and testing requirements for concrete containment structures for nuclear power plants, specifies examination and testing requirements that apply to the work of any organization participating in the construction, fabrication, or installation of concrete containment structures for nuclear power plants; CSA N287.6, Pre-operational proof and leakage rate testing requirements for concrete 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 requirements of CSA N287.6, including commissioning leakage rate target; CSA N287.7, In-service examination and testing requirements for concrete containment structures for 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 operational leakage rate target; and CSA N287.8, Aging management for concrete containment structures for nuclear power plants, provides aging management requirements for concrete containment structures for nuclear power plants and is directed to the owners/operators, designers, manufacturers, fabricators, and constructors. 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 of the Nuclear Safety and Control Act and its Regulations. Requirements additional to those specified in this Standard can be imposed by the Canadian Nuclear Safety Commission.

Scope:

1.1
This Standard specifies examination and testing requirements that apply to the work of any organization participating in the construction, fabrication, or installation of concrete containment structures, which includes, but is not limited to, the following structural and non-structural elements:
a) concrete;
b) reinforcement (pre-stressed and non-pre-stressed);
c) steel (e.g., liner, embedded parts, anchors);
d) non-metallic liners and coating systems;
e) joint sealants; and
f) elements necessary to support containment structure (e.g., foundations).

1.2
This Standard specifies personnel qualification requirements for work pertaining to the examination and testing of concrete containment structures for nuclear power plants.

1.3
This Standard is applicable to existing and new nuclear power plants. It is not the intent that the requirements of this Standard be applied retroactively to existing nuclear power plants, unless as agreed to by the authority having jurisdiction.

1.4
This Standard may be applied, as appropriate, to nuclear facilities under the jurisdiction of the Government of Canada's Nuclear Safety and Control Act.

1.5
This Standard is used in concert with the other CSA N287 series standards, as applicable.

1.6
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 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 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. Annexes are designated normative (mandatory) or informative non-mandatory) to define their application.

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CSA N287.5:20 Examination and testing requirements for concrete containment structures for nuclear power plants

CSA N287.5:20


Examination and testing requirements for concrete containment structures for nuclear power plants

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    CSA N287.5:20

    July 2020


    Title: Examination and testing requirements for concrete containment structures for nuclear power plants

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    CSA N287.5:20

    Examination and testing requirements for concrete containment structures for nuclear power plants




    ®A trademark of the Canadian Standards Association, operating as “CSA Group”


    Published in July 2020 by CSA Group

    A not-for-profit private sector organization

    178 Rexdale Boulevard, Toronto, Ontario, Canada M9W 1R3


    To purchase standards and related publications, visit our Online Store at store.csagroup.org

    or call toll-free 1-800-463-6727 or 416-747-4044.


    ICS 27.120.20

    ISBN 978-1-4883-2943-2


    © 2020 Canadian Standards Association

    All rights reserved. No part of this publication may be reproduced in any form whatsoever without the prior permission of the publisher.


    CSA N287.5:20

    Examination and testing requirements for concrete containment

    structures for nuclear power plants


    Contents

    Technical Committee on Concrete Containment and Safety-Related Structures for Nuclear Power Plants 3


    Subcommittee on Examination and Testing Requirements for Concrete Containment Structures for Nuclear Power Plants 5


    Preface 6


    1. Scope 8


    2. Reference publications 9


    3. Definitions 11


    4. General requirements 12

      1. General 12

      2. Material requirements 12

      3. Examination and testing requirements 12

      4. Personnel qualification 13

      5. Examination and test reports 13

      6. Aging management 13


    5. Concrete 13

      1. Materials 13

        1. General 13

        2. Acceptance 14

        3. Storage and handling 14

      2. Concrete properties 14

      3. Concrete qualification and acceptance 15

      4. Measuring, mixing, and transporting equipment 15

      5. Preparations for concrete placement 15

      6. Concrete placement and finishing 16

      7. Protection and curing 16

      8. Documentation 17


    6. Reinforcement 17

      1. General 17

      2. Examination of bends 17

      3. Examination of arc-welded splices 17

        1. General 17

        2. Radiographic examination 18

        3. Alternative tests 18

      4. Examination of mechanical rebar splices 18

        1. General 19

        2. Visual examination and acceptance 19

        3. Laboratory testing and acceptance 19

        4. In-situ testing and acceptance 21


          July 2020 © 2020 Canadian Standards Association 1

          CSA N287.5:20

          Examination and testing requirements for concrete containment

          structures for nuclear power plants


      5. Documentation 21


    7. Pre-stressing systems 21

      1. General 21

      2. Anchorages and coupling anchorages 22

      3. Sheaths 22

      4. Tendons 23

      5. Grouting of bonded tendons 24

      6. Protective coating of unbonded tendons 24

      7. Documentation 24


    8. Nonmetallic liner and coating systems 24

      1. General 25

      2. Thickness measurements 25

      3. Adhesion strength test 25

      4. Documentation 25


    9. Metallic parts 26

      1. General 26

      2. Examination of welded joints 26

      3. Examination of seal welds 26

      4. Examination of welded attachments 27

      5. Examination procedures and acceptance 27

        1. Visual examination 27

        2. Radiographic examination 27

        3. Ultrasonic examination 27

        4. Magnetic particle examination 27

        5. Liquid penetrant examination 28

        6. Vacuum box examination 28

        7. Spot examination 28

      6. Documentation 29


    10. Anchorage systems 29

      1. General 29

      2. Inspection 29

      3. Testing 30

      4. Acceptance 30

      5. Documentation 30


    11. Documentation and records 30



    July 2020 © 2020 Canadian Standards Association 2

    CSA N287.5:20

    Examination and testing requirements for concrete containment

    structures for nuclear power plants


    Preface

    This is the fourth edition of CSA N287.5, Examination and testing requirements for concrete containment structures for nuclear power plants. It supersedes the previous editions, published in 2011, 1993, and 1981.

    The major changes to this edition include the following:

  • The test and test frequencies for concrete materials and grout and their constituents were updated (Tables 1 and 2).

  • The definitions for containment structure and containment boundary were updated to align with the other CSA N287 series standards.

  • The term “class containment” was modified to align with the other CSA N287 series of Standards.

  • The requirements for anchors, welds, and grouted embedments were updated to align with other CSA N287 series of Standards.

  • The terms and definitions were updated to align with the common list of definitions.

  • Requirements for personnel qualification were included.

  • A clause on aging management was added.

    The CSA N-Series Standards provide an interlinked set of requirements for the management of nuclear facilities and activities. CSA N286 provides overall direction to management to develop and implement sound management practices and controls, while the other CSA Group nuclear Standards provide technical requirements and guidance that support the management system. This Standard works in harmony with CSA N286 and does not duplicate the generic requirements of CSA N286; however, it might provide more specific direction for those requirements.


    This Standard specifies examination and testing requirements that will ensure that concrete containment structures are built using techniques and work practices that meet the quality and standards commensurate with the safety principles necessary to comply with the Canadian nuclear safety philosophy.


    This Standard is part of the CSA N287 series of Standards, which provides the requirements for concrete containment structures for nuclear power plants. These 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 the design, construction, and testing of concrete containment structures for nuclear power plants.

    The CSA N287 series of Standards consists of eight Standards. The objectives of each Standard are summarized as follows:

  • CSA N287.1, General requirements for concrete containment structures for nuclear power plants, specifies general requirements for the design, construction, testing, commissioning, and in-service examination and testing of concrete containment structures for nuclear power plants and is directed to the owners, designers, manufacturers, fabricators, and constructors;

  • CSA N287.2, Material requirements for concrete containment structures for nuclear power plants, specifies requirements for materials used for concrete containment structures;

  • CSA N287.3, Design requirements for concrete containment structures for nuclear power plants, specifies requirements for the design of concrete containment structures;

  • CSA N287.4, Construction, fabrication, and installation requirements for concrete containment structures for nuclear power plants, specifies construction, fabrication, and installation requirements for concrete containment structures for nuclear power plants;


    July 2020 © 2020 Canadian Standards Association 6

    CSA N287.5:20

    Examination and testing requirements for concrete containment

    structures for nuclear power plants


  • CSA N287.5, Examination and testing requirements for concrete containment structures for nuclear power plants, specifies examination and testing requirements that apply to the work of any organization participating in the construction, fabrication, or installation of concrete containment structures for nuclear power plants;

  • CSA N287.6, Pre-operational proof and leakage rate testing requirements for concrete 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 requirements of

    CSA N287.6, including commissioning leakage rate target;

  • CSA N287.7, In-service examination and testing requirements for concrete containment structures for 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 operational leakage rate target; and

  • CSA N287.8, Aging management for concrete containment structures for nuclear power plants, provides aging management requirements for concrete containment structures for nuclear power plants and is directed to the owners/operators, designers, manufacturers, fabricators, and constructors.


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 of the Nuclear Safety and Control Act and its Regulations. Requirements additional to those specified in this Standard can be imposed by the Canadian Nuclear Safety Commission.


This Standard was prepared by the Subcommittee on Examination and Testing Requirements for Concrete Containment Structures for Nuclear Power Plants, under the jurisdiction of the Technical Committee on Concrete Containment and Safety-Related Structures for Nuclear Power Plants 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 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 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 following information to inquiries@csagroup.org and include “Request for interpretation” in the subject line:

    1. define the problem, making reference to the specific clause, and, where appropriate, include an illustrative sketch;

    2. provide an explanation of circumstances surrounding the actual field condition; and

    3. 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 at standardsactivities.csa.ca.

  5. This Standard is subject to review within five years from the date of publication. Suggestions for its improvement will be referred to the appropriate committee. To submit a proposal for change, please send the following information to inquiries@csagroup.org and include “Proposal for change” in the subject line:

    1. Standard designation (number);

    2. relevant clause, table, and/or figure number;

    3. wording of the proposed change; and

    4. rationale for the change.


July 2020 © 2020 Canadian Standards Association 7

CSA N287.5:20

Examination and testing requirements for concrete containment

structures for nuclear power plants


CSA N287.5:20

Examination and testing requirements for concrete containment structures for nuclear power plants


1 Scope


1.1

This Standard specifies examination and testing requirements that apply to the work of any organization participating in the construction, fabrication, or installation of concrete containment structures, which includes, but is not limited to, the following structural and non-structural elements:

  1. concrete;

  2. reinforcement (pre-stressed and non-pre-stressed);

  3. steel (e.g., liner, embedded parts, anchors);

  4. non-metallic liners and coating systems;

  5. joint sealants; and

  6. elements necessary to support containment structure (e.g., foundations).


1.2

This Standard specifies personnel qualification requirements for work pertaining to the examination and testing of concrete containment structures for nuclear power plants.


1.3

This Standard is applicable to existing and new nuclear power plants. It is not the intent that the requirements of this Standard be applied retroactively to existing nuclear power plants, unless as agreed to by the authority having jurisdiction.


1.4

This Standard may be applied, as appropriate, to nuclear facilities under the jurisdiction of the Government of Canada’s Nuclear Safety and Control Act.


1.5

This Standard is used in concert with the other CSA N287 series standards, as applicable.


1.6

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 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 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.


July 2020 © 2020 Canadian Standards Association 8