N290.20:21

Aging management requirements for nuclear power plants

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  N290.20:21

  March 2021

  
  

  Title: Aging management requirements for nuclear power plants

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N290.20:21

Aging management requirements for nuclear power plants

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ICS 27.120

ISBN 978-1-4883-2995-1

© 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.

N290.20:21 Aging management requirements for nuclear power plants

Contents

Technical Committee on Reactor Control Systems, Safety Systems, and Instrumentation for Nuclear Power Plants 3

Subcommittee on Aging Management Requirements for Nuclear Power Plants 6

Preface 8

1. Scope 9

   
   

2. Reference publications 10

   
   

3. Definitions and abbreviations 12

   1. Definitions 12

   2. Abbreviations 16

      
      

4. Systematic approach to aging management 17

   1. AM program 17

      1. General 17

      2. AM program requirements 18

      3. Systematic approach to aging management 20

   2. Scoping, screening, and selection of SSCs 22

      1. General 22

      2. Scoping 22

      3. Screening 25

      4. Selection 27

      5. Data and records 28

   3. SSC assessment and aging review 28

      1. Assessment of a SSC’s aging 28

      2. Assessment of degradation mechanisms and obsolescence 29

      3. Assessment of preventive actions 29

      4. Limits to acceptable degradation 29

      5. Operational factors 29

      6. Review of applicable operating history and experience 29

      7. Review of information sources 30

      8. Evaluation of physical condition of SSCs 30

      9. SSC condition classification 30

   4. AM plans 31

      1. General 31

      2. Addressing attributes 31

      3. Other NPP programs 31

   5. Periodic reviews and improvements 31

      1. General 31

      2. AM program 32

      3. AM plans 32

   6. Program and plans improvement and action resolution 33

      1. Process 33

      2. Performance indicators 33

         
         

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         N290.20:21 Aging management requirements for nuclear power plants

         
         

   7. Obsolescence management 33

      1. General 33

      2. Obsolescence management 34

         
         

5. Aging management during the life cycle of a NPP 34

   1. General 34

      1. Proactive strategy for aging management 34

      2. Transition between life cycle phases 34

      3. Safety analysis 35

      4. Review and update of safety analysis 35

   2. Design phase 36

      1. General 36

      2. Aging management elements 37

   3. Construction phase 38

      1. General 38

      2. Construction 38

      3. Delayed construction 38

      4. Data collection and records 39

   4. Commissioning phase 39

      1. General 39

      2. Aging management activities 39

      3. Data collection and records 39

   5. Operation phase 40

      1. General 40

      2. Long-term operation 40

      3. Extended shutdown 41

   6. Decommissioning phase 42

      
      

6. Documentation and records 42

   1. General 42

      1. Documentation and records management 42

      2. Stakeholder input 43

   2. Records supporting AM attributes 43

   3. Records of AM plan actions 44

Annex A (informative) — Sample methodology for aging evaluation 45 Annex B (normative) — Generic attributes of an effective AM program 47 Annex C (informative) — Sample SSC condition classification 49

Annex D (informative) — Examples of good practices for management of obsolescence 50

Annex E (informative) — Criteria for scoping, screening, and selection of SSCs specific to the transition to decommissioning life cycle phase 51

Annex F (informative) — Examples of support program inputs and outputs associated with the AM program 54

Annex G (informative) — Aging management activities and typical inputs and outputs at all life cycle phases of the NPP 57

Annex H (informative) — Guidance for use of a graded approach to aging management 62

Annex I (informative) — Bibliography 64

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N290.20:21 Aging management requirements for nuclear power plants

Preface

This is the first edition of CSA N290.20, Aging management requirements for nuclear power plants.

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 reflects the operating experience of the Canadian nuclear power industry.

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 supporting Regulations.

This Standard was prepared by the Subcommittee on Aging Management Requirements for Nuclear Power Plants, under the jurisdiction of the Technical Committee on Reactor Control Systems, Safety Systems, and Instrumentation 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.

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   4. rationale for the change.

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N290.20:21 Aging management requirements for nuclear power plants

N290.20:21

Aging management requirements for nuclear power plants

1 Scope

1.1

This Standard specifies requirements and guidance for the aging management of nuclear power plants (NPPs). Specifically, this Standard addresses the aging management of

1. structures, systems, and components (SSCs) that are important to safety; and

2. SSCs that, in the case of failure, would prevent SSCs important to safety from performing their safety function.

Note: Other nuclear facilities may apply this Standard using a graded approach commensurate with risk.

1.2

This Standard addresses the integration of NPP programs to support aging management.

1.3

This Standard applies to the following life cycle phases of the NPP:

1. design;

2. construction (including procurement, fabrication and installation, delayed construction, storage, and transportation activities);

3. commissioning;

4. operation (including long-term operation and extended shutdown, if applicable); and

5. decommissioning.

1.4

This Standard addresses two aspects of aging management of SSCs: physical aging and non-physical aging (obsolescence).

1.5

This Standard excludes management of obsolescence that is due to non-equipment-related drivers. Note: For example, changes to current regulations, codes and standards, or loss of staff knowledge due to workforce changes.

1.6

This Standard does not address the broader topic of asset management.

Note: Although asset management is not addressed in this Standard, the concepts and guidance may be adapted and used for establishing strategies to optimize the management of facility assets.

1.7

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

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