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CSA N285.7:21 Periodic inspection of CANDU nuclear power plant balance of plant systems and components

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Preface:

This is the second edition of CSA N285.7, Periodic inspection of CANDU nuclear power plant balance of plant systems and components. It supersedes the previous edition published in 2015.

This Standard is one of a series of Standards intended to provide uniform requirements for CANDU nuclear power plants.
Note: CANDU (CANada Deuterium Uranium) is a registered trademark of Atomic Energy of Canada Limited (AECL).

This Standard provides requirements for the periodic inspection of balance of plant systems and components.
The major changes to this edition include the following:
a) an update to the definitions, specifically the definitions related to "inspection" and "examination", affecting most clauses;
b) general harmonization with CSA N285.4-19 and N285.5-18;
c) revisions to Annexes B, C, and D for clarity of requirements based on application of risk informed rules to select locations for periodic inspection;
d) improved clarity of pre-screening requirements for raw water systems to account for in-service inspection programs, availability of back-up systems and independent trains, evaluation of external events, and internal flooding probabilistic safety assessments (IFPSA);
e) clarified timeline for notifying the authority having jurisdiction (AHJ) and obtaining AHJ acceptance of dispositions (Clause 7.8);
f) clarified periodic inspection requirements for replaced components (Clause 8);
g) added reporting requirements for confirmatory inspections (Clause 10.3);
h) clarified requirements to defining a weld examination area that include a reasonable amount of base metal (Clause 13.1.2.3);
i) clarified examination requirements for mechanical couplings, including removal of requirement to examine threaded ligaments (Clause 13.4.2);
j) added guidance on approach to evaluation of examination results and use of acceptance standards (Clause A.2); and
k) added provisions for use of non-destructive examination personnel certified to other than CGSB standards (new Annex G).

The CSA N-Series of Standards provides 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.

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 may impose additional requirements to those specified in this Standard.

Portions of this Standard have been developed using the Risk Informed In-service Inspection (RI-ISI) methodologies and definitions from ASME BPVC Section XI with 2011 Addenda, Code Case N-578-1, ASME RA-Sa-2009 and EPRI RI-ISI TR-112657 Rev B-A. Excerpts are reprinted with permission from The American Society of Mechanical Engineers, Electric Power Research Institute, Inc., and International Atomic Energy Agency.

Scope:

1.1
This Standard defines requirements for the periodic inspection of balance of plant pressure-retaining systems, components, and supports that form part of a CANDU nuclear power plant using a risk informed in-service inspection (RI-ISI) methodology. Periodic inspection (see Annex A for additional guidance) is considered to include the fluid boundary portions of balance of plant systems, components, and piping, including their supports that comprise a complete nuclear power plant, excluding the following systems or portions thereof:
a) Systems, and systems connected thereto, containing the fluid that, under normal conditions, directly transports heat from nuclear fuel, and other systems whose failure can result in a significant release of radioactive substances.
Note: These systems or portions of systems are subject to periodic inspection in accordance with Clause 3.3.1 a) in CSA N285.4.
b) Systems essential for the safe shutdown of the reactor and/or the safe cooling of the nuclear fuel in the event of a process system failure.
Note: These systems or portions of systems are subject to periodic inspection in accordance with Clause 3.3.1 b) in CSA N285.4.

Compressors, turbines, generators, engines, internal components of vessels and heat exchangers, and hydraulic or pneumatic cylinders are exempt from the periodic inspection requirements of this Standard. This includes piping internal to equipment or mounted upon equipment that carries fluid from one chamber to another on the same foundation.
Note: To arrive at a periodic inspection program, the user should consider the examinations and tests performed by other programs such as pipe wall thinning, vessel examinations, equipment reliability, and maintenance programs in addition to RI-ISI. Examinations performed as part of supporting programs are not expected to be repeated in this periodic inspection program, but should be credited to this periodic inspection program to provide assurance that the program satisfies the intended purpose as described in Annex A.

1.2
This Standard addresses the following requirements:
a) failure aspects;
b) classification of areas subject to periodic inspection;
c) provision for access;
d) examination techniques and procedures;
e) personnel qualifications;
f) frequency of periodic inspection;
g) responsibilities;
h) documentation;
i) records;
j) evaluation of periodic inspection results;
k) dispositioning; and
l) repair, replacement, and modification requirements.

1.3
The values given in SI units are the units of record for the purposes of this Standard. The values given in parentheses are for information and comparison only.

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 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 N285.7:21, Periodic inspection of CANDU nuclear power plant balance of plant systems and components

CSA N285.7:21


Periodic inspection of CANDU nuclear power plant balance of plant systems and components

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    CSA N285.7:21

    February 2021


    Title: Periodic inspection of CANDU nuclear power plant balance of plant systems and components

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CSA N285.7:21

Periodic inspection of CANDU nuclear power plant balance of plant systems and components




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Published in February 2021 by CSA Group A not-for-profit private sector organization

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ICS 27.120.20

ISBN 978-1-4883-3393-4


© 2021 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.

Contents

Technical Committee on Periodic Inspection of Nuclear Power Plant Components 4


Preface 7


  1. Scope 9


  2. Reference publications 10


  3. Definitions 11


  4. General requirements 15

    1. Prerequisites 15

      1. Nature of periodic inspection 15

      2. Operation and maintenance 16

      3. Power plant operation 16

    2. Hazards 16

    3. Radiation exposure 16

    4. Program documents 16

    5. Operating organization’s responsibility 17

    6. Accessibility 18

      1. Access for periodic inspection 18

      2. Existing plants 18


  5. Examination methods, qualification, and procedures 18

    1. Examination methods 18

    2. Examination procedures 19

      5.2.10 Volumetric methods 20

      5.3 Inspection qualification 21


  6. Examination personnel and qualifications 21

    1. Training and certification 21

    2. Qualification 21

    3. Records 22


  7. Evaluation of examination results 22

    1. Evaluation 22

    2. General acceptance standards 22

    3. Visual examination 22

    4. Surface examination 23

    5. Volumetric examination 23

    6. Dimensional examination 23

    7. Integrative examination 23

    8. Dispositioning 24

      1. General 24

      2. Dispositioning while reactor at power 24

      3. Dispositioning while reactor not at power 24

      4. Dispositioning of minor conditions 25

  8. Repairs and replacements 25


  9. Modifications 26


  10. Recording requirements and reports 26

    1. General requirements 26

    2. Periodic inspection records 27

    3. Periodic inspection reports 27


      10.3.1

      Inaugural inspection reports

      27

      10.3.2

      Periodic inspection reports

      27


  11. Periodic inspection regions 28

    1. Systems 28

      1. Systems subject to periodic inspection 28

      2. Extent of systems subject to periodic inspection 28

    2. Grouping of systems and components 28

    3. Consequence and potential of failure assessments 28

      1. Consequence of failure assessment 28

      2. Potential of failure assessment 28

    4. Segment risk categorization 29

    5. Element assessment and selection 29

    6. Change-in-risk assessment 29


  12. Periodic inspection intervals 30

    1. Operating systems 30

          1. Inaugural inspection 31

          2. Dormant systems 31


  13. Periodic and inaugural inspections 31

    1. General requirements 31

      1. General 31

      2. Extent of periodic inspection 31

      3. Periodic inspection for corrosion and erosion 32

    2. Piping 33

      1. General requirements 33

      2. Extent of periodic inspection and sample size 33

      3. Periodic inspection intervals 34

      4. Examination methods and procedures 34

      5. Evaluation of results and dispositioning 35

      6. Records and reports 35

    3. Vessels 35

      1. General requirements 35

      2. Extent of periodic inspection and sample size 35

      3. Periodic inspection intervals 36

      4. Examination methods and procedures 37

      5. Evaluation of results and dispositioning 37

      6. Records and reports 37

    4. Mechanical couplings 37

      1. General requirements 37

      2. Extent of periodic inspection and sample size 37

      3. Inspection intervals 39

      4. Examination methods and procedures 39

      5. Evaluation of results and dispositioning 39

      6. Records and reports 39

    5. Pumps 39

      1. General requirements 39

      2. Extent of inspection and sample size 39

      3. Periodic inspection intervals 40

      4. Examination methods and procedures 41

      5. Evaluation of results and dispositioning 41

      6. Records and reports 41

    6. Valves 41

      1. General requirements 41

      2. Extent of periodic inspection and sample size 41

      3. Periodic inspection intervals 42

      4. Examination methods and procedures 42

      5. Evaluation of results and dispositioning 43

      6. Records and reports 43

    7. Supports 43

      1. General requirements 43

      2. Extent of periodic inspection and sample size 43

      3. Periodic inspection intervals 45

      4. Examination methods and procedures 45

      5. Evaluation of results and dispositioning 45

      6. Records and reports 45

    8. Rotating machinery 45

      1. General requirements 45

      2. Extent of periodic inspection and sample size 46

      3. Periodic inspection intervals 46

      4. Examination methods and procedures 46

      5. Evaluation of results and dispositioning 47

      6. Records and reports 47


Annex A (informative) — Guide for periodic inspection 56

Annex B (normative) — Pre-screening process 59

Annex C (normative) — Consequence of failure assessment 66

Annex D (normative) — Potential of failure assessment 76

Annex E (normative) — Risk categorization, sample size determination, and element selection 152

Annex F (informative) — Rationale for grouping identical elements 155

Annex G (informative) — Guidance on obtaining AHJ acceptance of non-destructive examination personnel certified to an operating organization-specified standard 160

Preface

This is the second edition of CSA N285.7, Periodic inspection of CANDU nuclear power plant balance of plant systems and components. It supersedes the previous edition published in 2015.


This Standard is one of a series of Standards intended to provide uniform requirements for CANDU® nuclear power plants.

Note: CANDU (CANada Deuterium Uranium) is a registered trademark of Atomic Energy of Canada Limited (AECL).


This Standard provides requirements for the periodic inspection of balance of plant systems and components.


The major changes to this edition include the following:

  1. an update to the definitions, specifically the definitions related to “inspection” and “examination”, affecting most clauses;

  2. general harmonization with CSA N285.4-19 and N285.5-18;

  3. revisions to Annexes B, C, and D for clarity of requirements based on application of risk informed rules to select locations for periodic inspection;

  4. improved clarity of pre-screening requirements for raw water systems to account for in-service inspection programs, availability of back-up systems and independent trains, evaluation of external events, and internal flooding probabilistic safety assessments (IFPSA);

  5. clarified timeline for notifying the authority having jurisdiction (AHJ) and obtaining AHJ acceptance of dispositions (Clause 7.8);

  6. clarified periodic inspection requirements for replaced components (Clause 8);

  7. added reporting requirements for confirmatory inspections (Clause 10.3);

  8. clarified requirements to defining a weld examination area that include a reasonable amount of base metal (Clause 13.1.2.3);

  9. clarified examination requirements for mechanical couplings, including removal of requirement to examine threaded ligaments (Clause 13.4.2);

  10. added guidance on approach to evaluation of examination results and use of acceptance standards (Clause A.2); and

  11. added provisions for use of non-destructive examination personnel certified to other than CGSB standards (new Annex G).


    The CSA N-Series of Standards provides 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.


    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 may impose additional requirements to those specified in this Standard.


    Portions of this Standard have been developed using the Risk Informed In-service Inspection (RI-ISI) methodologies and definitions from ASME BPVC Section XI with 2011 Addenda, Code Case N-578-1, ASME RA-Sa-2009 and EPRI RI-ISI TR-112657 Rev B-A. Excerpts are reprinted with permission from The American Society of Mechanical Engineers, Electric Power Research Institute, Inc., and International Atomic Energy Agency.

    In order to facilitate adoption by the authority having jurisdiction, this Standard includes some regulatory provisions.


    This Standard was prepared by the Technical Committee on Periodic Inspection of Nuclear Power Plant Components, under the jurisdiction of 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.

CSA N285.7:21

Periodic inspection of CANDU nuclear power plant balance of plant systems and components


1 Scope


1.1

This Standard defines requirements for the periodic inspection of balance of plant pressure-retaining systems, components, and supports that form part of a CANDU nuclear power plant using a risk informed in-service inspection (RI-ISI) methodology. Periodic inspection (see Annex A for additional guidance) is considered to include the fluid boundary portions of balance of plant systems, components, and piping, including their supports that comprise a complete nuclear power plant, excluding the following systems or portions thereof:

  1. Systems, and systems connected thereto, containing the fluid that, under normal conditions, directly transports heat from nuclear fuel, and other systems whose failure can result in a significant release of radioactive substances.

    Note: These systems or portions of systems are subject to periodic inspection in accordance with Clause 3.3.1 a) in CSA N285.4.

  2. Systems essential for the safe shutdown of the reactor and/or the safe cooling of the nuclear fuel in the event of a process system failure.

Note: These systems or portions of systems are subject to periodic inspection in accordance with Clause 3.3.1 b) in CSA N285.4.


Compressors, turbines, generators, engines, internal components of vessels and heat exchangers, and hydraulic or pneumatic cylinders are exempt from the periodic inspection requirements of this Standard. This includes piping internal to equipment or mounted upon equipment that carries fluid from one chamber to another on the same foundation.

Note: To arrive at a periodic inspection program, the user should consider the examinations and tests performed by other programs such as pipe wall thinning, vessel examinations, equipment reliability, and maintenance programs in addition to RI-ISI. Examinations performed as part of supporting programs are not expected to be repeated in this periodic inspection program, but should be credited to this periodic inspection program to provide assurance that the program satisfies the intended purpose as described in Annex A.


1.2

This Standard addresses the following requirements:

  1. failure aspects;

  2. classification of areas subject to periodic inspection;

  3. provision for access;

  4. examination techniques and procedures;

  5. personnel qualifications;

  6. frequency of periodic inspection;

  7. responsibilities;

  8. documentation;