CSA N290 11-2013 Requirements for reactor heat removal capability during outage of nuclear power plants (First Edition).pdf

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22、 plantsN290.11-13N290.11-13Requirements for reactor heat removal capability during outage of nuclear power plantsDecember 2013 2013 CSA Group 1ContentsTechnical Committee on Reactor Control Systems, Safety Systems, and Instrumentation for Nuclear Power Plants 3Subcommittee on Requirements for Reacto

23、r Heat Removal Capability During Outage of Nuclear Power Plants 6Preface 71 Scope 82 Reference publications 93 Definitions 103.1 Definitions 103.2 Abbreviations 114 Functional requirements 114.1 General 114.2 Success criteria 124.2.1 Process heat sinks 124.2.2 Emergency heat sink 125 Heat sink requi

24、rements 125.1 General 125.2 Heat sink operation 145.2.1 General 145.2.2 Recall 145.2.3 Actions on failure of a heat sink 155.2.4 Heat sinks affecting other work 165.2.5 Monitoring 165.3 Instrumentation and control 165.4 Containment boundary 175.5 Loop isolation 175.5.1 General 175.5.2 Loop isolation

25、 for reactors with two cooling loops in the reactor coolant system 175.6 Reliability 175.6.1 General 175.6.2 Reliability analysis 185.6.3 Redundancy 185.6.4 Diversity 185.7 Independence and separation 185.7.1 Process heat sink independence 185.7.2 Emergency heat sink independence 185.7.3 Separation

26、195.8 Pressure-retaining SSCs 195.9 Equipment qualification 195.9.1 Environmental qualification 19N290.11-13Requirements for reactor heat removal capability during outage of nuclear power plantsDecember 2013 2013 CSA Group 25.9.2 Seismic qualification 195.9.3 Aging 195.10 Dynamic piping effects 195.

27、11 Maintenance 205.11.1 General 205.11.2 Maintenance on the primary heat sink 205.11.3 Maintenance on the standby components of the process heat sink 205.11.4 Maintenance on the emergency heat sink 215.11.5 Maintenance program 215.12 Functional testing 215.13 Documentation 215.14 Heat sink support s

28、ystem requirements 21N290.11-13Requirements for reactor heat removal capability during outage of nuclear power plantsDecember 2013 2013 CSA Group 3Technical Committee on Reactor Control Systems, Safety Systems, and Instrumentation for Nuclear Power PlantsJ. Grava CANTECH Associates Ltd, Owen Sound,

29、OntarioRepresenting General InterestChairR.K. Black TransCanada, Toronto, OntarioRepresenting Service IndustryVice-ChairB.D. Babcock North York, OntarioRepresenting General InterestM. Buckler Bruce Power, Tiverton, OntarioAssociateQ.B. Chou Canadian Power Utility Services Ltd, Toronto, OntarioRepres

30、enting Service IndustryV. Chugh AMEC NSS, Toronto, OntarioRepresenting Service IndustryJ. Coady Bruce Power L.P., Tiverton, OntarioRepresenting Owner/Operator/ProducerC.J. Conway Atomic Energy of Canada Ltd (AECL), Chalk River, OntarioRepresenting Owner/Operator/ProducerAssociateB.J. Coulas Ontario

31、Power Generation, Pickering, OntarioAssociateJ.M. Cuttler Cuttler 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, constructi

32、on, 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 o

33、f 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 s

34、ingular 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 purpo

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40、le, and/or figure number;c) wording of the proposed change; andd) rationale for the change.N290.11-13Requirements for reactor heat removal capability during outage of nuclear power plantsDecember 2013 2013 CSA Group 8N290.11-13Requirements for reactor heat removal capability during outage of nuclear

41、 power plants1 Scope1.1 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

42、 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:a) a shutdown state where subcriticality

43、is assured by physical means; orNote: 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 c

44、ondensers.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 hi

45、gh power operation.1.5 This Standard covers all systems that contribute to the transfer of heat bya) conveying heat to the ultimate heat sink;b) providing power or compressed air;c) providing inventory makeup to heat sink systems; ord) monitoring and control.Note: The combination of systems or porti

46、ons 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

47、or that N290.11-13Requirements for reactor heat removal capability during outage of nuclear power plantsDecember 2013 2013 CSA Group 9which 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

48、 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 normati

49、ve (mandatory) or informative (non-mandatory) to define their application.2 Reference publicationsThis Standard refers to the following publications, and where such reference is made, it shall be to the edition listed below, including all amendments published thereto.CSA GroupN285.0-12/N285.6 Series-12General requirements for pressure-retaining systems and components in CANDU nuclear power plants/ Material Standards for reactor components for CANDU nuclear power plantsN286-12Management system requirements for nuclear facilitiesN289.1-08General requirements for sei