CSA N290.11:13

(reaffirmed 2019)

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

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  Standards Update Service

  CSA N290.11:13

  December 2013

  
  

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

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CSA N290.11:13

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

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CSA N290.11:13

Requirements for reactor heat removal capability during outage of

nuclear power plants

Contents

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

Subcommittee on Requirements for Reactor Heat Removal Capability During Outage of Nuclear Power Plants 6

Preface 7

1. Scope 8

   
   

2. Reference publications 9

   
   

3. Definitions 10

   1. Definitions 10

   2. Abbreviations 11

      
      

4. Functional requirements 11

   1. General 11

   2. Success criteria 12

      1. Process heat sinks 12

      2. Emergency heat sink 12

         
         

5. Heat sink requirements 12

   1. General 12

   2. Heat sink operation 14

      1. General 14

      2. Recall 14

      3. Actions on failure of a heat sink 15

      4. Heat sinks affecting other work 16

      5. Monitoring 16

   3. Instrumentation and control 16

   4. Containment boundary 17

   5. Loop isolation 17

      1. General 17

      2. Loop isolation for reactors with two cooling loops in the reactor coolant system 17

   6. Reliability 17

      1. General 17

      2. Reliability analysis 18

      3. Redundancy 18

      4. Diversity 18

   7. Independence and separation 18

      1. Process heat sink independence 18

      2. Emergency heat sink independence 18

      3. Separation 19

   8. Pressure-retaining SSCs 19

   9. Equipment qualification 19

      1. Environmental qualification 19

         
         

         December 2013 © 2013 Canadian Standards Association 1

         CSA N290.11:13

         Requirements for reactor heat removal capability during outage of

         nuclear power plants

         
         

      2. Seismic qualification 19

      3. Aging 19

   10. Dynamic piping effects 19

   11. Maintenance 20

       1. General 20

       2. Maintenance on the primary heat sink 20

       3. Maintenance on the standby components of the process heat sink 20

       4. Maintenance on the emergency heat sink 21

       5. Maintenance program 21

   12. Functional testing 21

   13. Documentation 21

   14. Heat sink support system requirements 21

December 2013 © 2013 Canadian Standards Association 2

CSA N290.11:13

Requirements for reactor heat removal capability during outage of

nuclear power plants

Preface

This is the first edition of CSA N290.11, Requirements for reactor heat removal capability during outage of 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.

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 has been 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.

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December 2013 © 2013 Canadian Standards Association 7

CSA N290.11:13

Requirements for reactor heat removal capability during outage of

nuclear power plants

CSA N290.11:13

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 defueled core state.

1.3

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.

1.4

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 re- established as part of the plan to proceed to sustained high power operation.

1.5

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”.

1.6

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

December 2013 © 2013 Canadian Standards Association 8