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CSA N290.11:21 Requirements for reactor heat removal capability during outage of nuclear power plants

standard by CSA Group, 07/01/2021

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Preface

This is the second edition of CSA N290.11, Requirements for reactor heat removal capability during outage of nuclear power plants . It supersedes the previous edition published in 2013. The following are the major changes to this edition: a) updated requirements and specifications for the back-up heat sink and the protection it is to provide; b) provided additional clarification in areas identified by users; and c) improved alignment with current industry standards. 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 can 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.

Scope

1.1 This Standard covers the design, qualification, installation, commissioning, operation, maintenance, testing, inspection, and documentation requirements for systems providing heat removal from the reactor core to the ultimate heat sink(s) for water-cooled nuclear power plants during outages.

1.2 This Standard covers only fuel cooling within the reactor core and does not cover spent fuel pool cooling, off-reactor fuelling operations, or the completely defueled core state.

1.3 This Standard covers all systems that contribute to the transfer of heat by a) conveying heat to the ultimate heat sink; b) providing power or compressed air; c) providing inventory makeup to heat sink systems; or d) monitoring and control. Note: The combination of systems or portions of systems that contribute to these functions are referred to in this Standard as "heat sinks".

1.4 The term outage refers to the following reactor states: a) a shutdown state where subcriticality is assured by physical means; or Note: For CANDU reactors, this refers to a guaranteed shutdown state. b) critical or sub-critical at any power where the normal (at high power) heat sinks are not the primary heat sinks. Note: Examples of high power heat sinks include steaming of boilers to turbine or condensers.

1.5 This Standard does not cover requirements for design extension conditions (DEC). Requirements and principles for maintaining fuel cooling for outages during DECs, including requirements for emergency cooling water and power supplies, are covered in CSA N290.16.

1.6 For the purposes of this Standard, the outage commences when the normal (at high power) heat sinks are no longer the primary heat sinks. The outage is considered to be terminated when the normal (at high power) heat sinks are reestablished as part of the plan to proceed to sustained high power operation.

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 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 N290.11:21, Requirements for reactor heat removal capability during outage of nuclear power plants

CSA N290.11:21


Requirements for reactor heat removal capability during outage of nuclear power plants

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    CSA N290.11:21

    July 2021


    Title: Requirements for reactor heat removal capability during outage of nuclear power plants

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CSA N290.11:21

Requirements for reactor heat removal capability during outage of nuclear power plants




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ICS 27.120

ISBN 978-1-4883-3631-7


© 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 Reactor Control Systems, Safety Systems, and Instrumentation of Nuclear Power Plants 3


Subcommittee on Requirements for Reactor Heat Removal Capability during Outage of Nuclear Power Plants 5


Preface 6


  1. Scope 8


  2. Reference publications 9


  3. Definitions 10

    1. Definitions 10

    2. Abbreviations 12


  4. Functional requirements 12

    1. General 12

    2. Success criteria 13

      1. Process heat sinks 13

      2. Emergency heat sink 13


  5. Heat sink requirements 13

    1. General 13

    2. Heat sink operation 15

      1. General 15

      2. Recall 15

      3. Actions on failure of a heat sink 16

      4. Heat sinks affecting other work 17

      5. Monitoring 17

    3. Instrumentation and control 17

    4. Loop isolation 18

      1. General 18

      2. Loop isolation for reactors with two cooling loops in the reactor coolant system 18

    5. Reliability 18

      1. General 18

      2. Redundancy 19

      3. Diversity 19

    6. Independence and separation 19

      1. Process heat sink independence 19

      2. Emergency heat sink independence 20

      3. Separation 20

    7. Equipment qualification 20

      1. Process heat sink 20

      2. Emergency heat sink 20

      3. Seismic qualification 20

      4. Aging 21

    8. Dynamic piping effects 21

    9. Maintenance 21

      1. General 21

      2. Maintenance on the primary heat sink 21

      3. Maintenance on the standby components of the process heat sink 21

      4. Maintenance on the emergency heat sink 22

      5. Maintenance program 22

    10. Functional testing 22

    11. Documentation 22

    12. Heat sink support system requirements 23


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


L. C. Luckhardt Baker Hughes — Dresser, Dundas, Ontario, Canada Category: Service Industry

Chair


N. Mesmous Canadian Nuclear Safety Commission (CNSC), Ottawa, Ontario, Canada

Category: Government and/or Regulatory Authority

Vice-Chair


R. Clavero Kinectrics Inc.,

Toronto, Ontario, Canada

Category: Service Industry

Vice-Chair


M. Buckler Bruce Power,

Tiverton, Ontario, Canada

Non-voting


B. Chan Technical Standards & Safety Authority, Toronto, Ontario, Canada

Category: Government and/or Regulatory Authority


Q. B. Chou Canadian Power Utility Services Ltd. (CPUS), Toronto, Ontario, Canada

Non-voting



D. Garrick Canadian Nuclear Laboratories Limited (CNL), Chalk River, Ontario, Canada

Category: Owner/Operator/Producer


S. Gateman Bruce Power,

Tiverton, Ontario, Canada

Non-voting


L. Gilbert Bruce Power,

Tiverton, Ontario, Canada

Category: Owner/Operator/Producer


S. Gyepi-Garbrah Canadian Nuclear Safety Commission (CNSC),

Ottawa, Ontario, Canada

Non-voting


R. Henry Kinectrics Inc.,

Toronto, Ontario, Canada

Non-voting

R. Ion MeV200 Consulting Inc., Mississauga, Ontario, Canada

Non-voting


W. K. Lam Toronto, Ontario, Canada

Category: Government and/or Regulatory Authority


P. Lawrence Kinectrics Inc.,

Pickering, Ontario, Canada

Non-voting


C. Lorencez Candu Owners Group, Toronto, Ontario, Canada Category: General Interest


J. Luxat McMaster University, Hamilton, Ontario, Canada Category: General Interest


D. Mullin NB Power Corporation,

Lepreau, New Brunswick, Canada

Category: Owner/Operator/Producer


M. K. O’Neill Ian Martin Limited, Scarborough, Ontario, Canada

Non-voting



Y. Parlatan Ontario Power Generation Inc., Pickering, Ontario, Canada

Category: Owner/Operator/Producer


P. Santamaura SNC-Lavalin Nuclear Inc., Mississauga, Ontario, Canada Category: Service Industry


A. Tokuhiro Ontario Tech University, Oshawa, Ontario, Canada Category: General Interest


J. Lee CSA Group,

Toronto, Ontario, Canada

Project Manager

Subcommittee on Requirements for Reactor Heat Removal Capability during Outage of Nuclear Power Plants


M. Buckler Bruce Power,

Tiverton, Ontario, Canada

Chair


J. Johns Bruce Power,

Tiverton, Ontario, Canada

Vice-Chair


L. Gilbert Bruce Power,

Tiverton, Ontario, Canada


H. Hasanein Kinectrics Inc.,

Toronto, Ontario, Canada


R. Henry Kinectrics Inc.,

Toronto, Ontario, Canada


B. Lekakh SNC-Lavalin Nuclear Inc., Mississauga, Ontario, Canada


G. Martin Ontario Power Generation Inc. Darlington NGS, Bowmanville, Ontario, Canada


M. Ohn Canadian Nuclear Safety Commission, Ottawa, Ontario, Canada


R. Prime NB Power Nuclear Corporation, Lepreau, New Brunswick, Canada


J. Lee CSA Group,

Toronto, Ontario, Canada

Project Manager

Preface

This is the second edition of CSA N290.11, Requirements for reactor heat removal capability during outage of nuclear power plants. It supersedes the previous edition published in 2013.

The following are the major changes to this edition:

  1. updated requirements and specifications for the back-up heat sink and the protection it is to provide;

  2. provided additional clarification in areas identified by users; and

  3. improved alignment with current industry standards.

    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 can 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 Requirements for Reactor Heat Removal Capability during Outage of Nuclear Power Plants, 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.

    5. This Standard is subject to review within five years from the date of publication and 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 N290.11:21

Requirements for reactor heat removal capability during outage of nuclear power plants


1 Scope


1.1

This Standard covers the design, qualification, installation, commissioning, operation, maintenance, testing, inspection, and documentation requirements for systems providing heat removal from the reactor core to the ultimate heat sink(s) for water-cooled nuclear power plants during outages.


1.2

This Standard covers only fuel cooling within the reactor core and does not cover spent fuel pool cooling, off-reactor fuelling operations, or the completely defuelled core state.


1.3

This Standard covers all systems that contribute to the transfer of heat by

  1. conveying heat to the ultimate heat sink;

  2. providing power or compressed air;

  3. providing inventory makeup to heat sink systems; or

  4. monitoring and control.

Note: The combination of systems or portions of systems that contribute to these functions are referred to in this Standard as “heat sinks”.


1.4

The term “outage” refers to the following reactor states:

  1. a shutdown state where subcriticality is assured by physical means; or

    Note: For CANDU reactors, this refers to a guaranteed shutdown state.

  2. critical or sub-critical at any power where the normal (at high power) heat sinks are not the primary heat sinks.

Note: Examples of high power heat sinks include steaming of boilers to turbine or condensers.


1.5

This Standard does not cover requirements for design extension conditions (DEC). Requirements and principles for maintaining fuel cooling for outages during DECs, including requirements for emergency cooling water and power supplies, are covered in CSA N290.16.


1.6

For the purposes of this Standard, the outage commences when the normal (at high power) heat sinks are no longer the primary heat sinks.