N290.8-15

(reaffirmed 2020)

Technical specification requirements for nuclear power plant components

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  N290.8-15

  November 2015

  
  

  Title: Technical specification requirements for nuclear power plant components

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N290.8-15

Technical specification requirements for nuclear power plant components

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N290.8-15 Technical specification requirements for nuclear power plant components

Contents

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

Subcommittee on Technical Specification Requirements for Nuclear Power Plant Components 6

Preface 8

1. Scope 10

   
   

2. Reference publications 11

   
   

3. Definitions and abbreviations 15

   1. Definitions 15

   2. Abbreviations 18

      
      

4. Preparation of technical specifications 18

   1. Procurement 18

   2. Catalogue component 19

   3. Referenced Codes, Standards, and generic specifications 19

   4. Component standardization 20

   5. Supplier capability 20

   6. Units 20

   7. Supplier submissions 20

   8. Design 21

   9. Component interaction 22

   10. Free issue material and services 22

   11. Operating organization supplied design 22

   12. QA requirements 23

   13. Documentation requirements 23

       1. List of engineering documents 23

       2. Documentation, drawings, and bills of materials 23

       3. Installation manual 23

       4. Commissioning/operating manual 23

       5. Maintenance manual 24

       6. Reports and other documents 24

       7. History file requirements 25

   14. Reliability and maintainability 25

   15. Testing 25

       1. General 25

       2. Type and production tests 26

   16. Marking and labelling 26

   17. Cleanliness and foreign material exclusion requirements 27

   18. Lifting points 27

   19. Human factors 27

   20. Fire protection and hazards 28

   21. Operating conditions 28

       1. General 28

          
          

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          N290.8-15 Technical specification requirements for nuclear power plant components

          
          

       2. Normal operating conditions 28

       3. Anticipated operating occurrence conditions 28

       4. Accident service conditions 28

       5. Design extension conditions 28

       6. Service life and duty cycle 28

       7. Vibration 28

   22. Component qualification 28

   23. Digital items 29

   24. Cyber security 29

       
       

5. Instrumentation and control components 29

   1. Application 30

   2. Design requirements 30

   3. Functional requirements 30

   4. Performance requirements 30

   5. Testing 31

1. Component qualification requirements 33

2. Valves 33

3. Pumps 33

4. Heat exchangers 34

5. Heating, ventilating, and air conditioning components (HVAC) 34

6. Other mechanical components 34

1. Electrical components 34

   1. Application 34

   2. Design requirements 35

   3. Functional requirements 35

   4. Performance requirements 36

   5. Testing requirements 36

   6. Maintenance 36

Annex A (informative) — Data sheet contents 37

Annex B (informative) — National and international Standards bodies 45

Annex C (informative) — I&C safety categories 46

Annex D (Informative) — Commercial guidance 47

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N290.8-15 Technical specification requirements for nuclear power plant components

Preface

This is the first edition of CSA N290.8, Technical specification requirements for nuclear power plant components.

This Standard is intended to ensure that technical specifications used to procure components are concise, consistent, and complete (i.e., identify all of the technical requirements and acceptance criteria). This Standard is not intended to add new requirements, codes, and standards, or interpretations to the component’s design basis.

This Standard has been written as a general standard for specifying components that will be installed in nuclear power plants. It establishes the requirements for design, procurement, installation, commissioning/testing, operation, maintenance, packaging, shipping that are to appear in the technical specifications for components.

This Standard is one of a series of standards on reactor control systems, safety systems, and instrumentation for nuclear power plants.

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 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 may provide more specific direction for those requirements.

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 Technical Specification Requirements for Nuclear Power Plant Components, under the jurisdiction of the Technical Committee on Reactor Control Systems, Safety Systems, and Instrumentation of 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.

      
      

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      N290.8-15 Technical specification requirements for nuclear power plant components

      
      

5. This Standard is subject to 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.

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N290.8-15 Technical specification requirements for nuclear power plant components

N290.8-15

Technical specification requirements for nuclear power plant components

1 Scope

1.1

This Standard

1. provides a consistent approach across the industry to produce specifications for components used in normal operation, anticipated operational occurrences (AOOs), and design basis accidents (DBAs). This Standard may be used to produce specifications for components used in design extension conditions (DECs);

2. provides a common set of attributes to be used when specifying component requirements related to plant design requirements;

3. utilizes the product specific knowledge of the industry to provide common criteria for specifying technical requirements;

4. provides a common set of attributes for use when specifying requirements for analysis, testing, design, manufacturing, and associated documentation to demonstrate components can meet their design requirements; and

5. is not intended to require update of existing specifications.

1.2

This Standard applies to all nuclear power plants (NPPs) (i.e., it is technology neutral).

1.3

This Standard applies to safety-related components and does not apply to commodity material (e.g., plate steel, conduit, etc., which have their own standalone industry specifications) services, and civil structures. This Standard may be applied to an assembly of components.

Note: This Standard may also be applied to components not in the scope of this Standard at the operating organization’s discretion.

1.4

The Standard excludes commercial considerations that could include the following:

1. liability;

2. warranty;

3. escalation;

4. insurance including policy limits, scope, and duration;

5. liquidated damages;

6. quantity of components; and

7. cancellation or termination provisions.

1.5

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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