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  • N285.0-17/N285.6 SERIES-17

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    General requirements for pressure-retaining systems and components in CANDU nuclear power plants / Material Standards for reactor components for CANDU nuclear power plants

    Available format(s):  Hardcopy, PDF

    Language(s):  French, English

    Published date:  01-01-2017

    Publisher:  Canadian Standards Association

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    Table of Contents - (Show below) - (Hide below)

    Preface
    N285.0-17, General requirements for pressure-retaining systems
               and components in CANDU nuclear power plants
    1 Scope
    2 Reference publications
    3 Definitions
    4 Effective date for standards
    5 Classification
    6 Registration
    7 Design
    8 Materials
    9 Fabrication and installation
    10 General requirements for quality assurance
    11 Examination and pressure testing
    12 Documentation
    13 In-service requirements
    14 Repairs, replacements, and modifications
    15 Pressure boundary program document
    Annexes
    Annex A (informative) - Registration numbers
    Annex B (informative) - Registration procedures for Class 1, 1C,
            2, 2C, 3, 3C, and 4 items
    Annex C (informative) - Design documentation
    Annex D (informative) - Qualification of licensee's verifiers
    Annex E (normative) - Requirements for Class 1C, 2C, and 3C
            components and supports in nuclear power plants
    Annex F (normative) - Design rules for containment
            components
    Annex G (informative) - In-service plugging by fusion welding
            of Class 1, 2, and 3 heat-exchanger tube or tubesheet holes
            with a 1 in maximum diameter
    Annex H (normative) - Reconciliation of modifications and
            as-built changes
    Annex I (informative) - Alternative process for qualification
            of Category A to F fittings for use in a nuclear Class 1,
            2, or 3 piping system
    Annex J (informative) - Pressure boundary program document
    Annex K (normative) - Alternative rules
    N285.6.1-17, Pressure tubes for use in CANDU fuel channels
    1 Scope
    2 Reference publications
    3 Definitions
    4 General requirements
    5 Ingot and ingot composition requirements
    6 Extrusion requirements
    7 Tube requirements
    8 Inspection requirements
    N285.6.2-17, Seamless zirconium alloy tubing for reactivity
                 control units
    1 Scope
    2 Reference publications
    3 General requirements
    4 Composition requirements
    5 Inspection
    N285.6.3-17, Annealed seamless zirconium alloy tubing for
                 liquid injection shutdown system (LISS) nozzles
    1 Scope
    2 Reference publications
    3 General requirements
    4 Composition requirements
    5 Inspection
    N285.6.4-17, Thin-walled, large-diameter zirconium alloy
                 tubing
    1 Scope
    2 Reference publications
    3 General requirements
    4 Composition requirements
    5 Processing requirements
    6 Final surface condition of the seam-welded and seamless tubes
    7 Inspection
    N285.6.6-17, Non-destructive examination criteria for
                 zirconium alloys
    1 Scope
    2 Reference publications
    3 Non-destructive examination (NDE) personnel qualification
    4 Visual inspection standards
    5 Radiographic standards
    6 Liquid-penetrant standards
    7 Ultrasonic standards
    8 Eddy current standards - Standard EC-1 (for pressure tubes)
    N285.6.7-17, Zirconium alloy design data
    1 Scope
    2 Reference publications
    3 General
    N285.6.8-17, Martensitic stainless steel for fuel-channel
                 end fittings
    1 Scope
    2 Reference publications
    3 Definitions
    4 Manufacturing requirements
    5 Chemical composition
    6 Mechanical properties
    7 Macroetch test
    8 Ultrasonic examination
    9 Quality of work
    10 Certification
    11 Product marking
    Annexes
    Annex A (normative) - Design data for end-fitting material
    N285.6.9-17, Materials for supports for pressure-retaining
                 items
    1 Scope
    2 Reference publications
    3 General requirements
    4 Materials
    5 Welding
    6 Examination
    7 Certification
    N285.6.10-17, Nickel-based alloy wire for fuel-channel
                  spacers
    1 Scope
    2 Reference publication
    3 General requirements
    N285.6.11-17, Zirconium alloy wire
    1 Scope
    2 Reference publications
    3 General requirements
    N285.6.12-17, Zirconium alloy bars and rods for reactivity
                  control units
    1 Scope
    2 Reference publications
    3 General requirements
    4 Composition requirements
    5 Inspection
    N285.6.13-17, Zirconium alloy sheet, strip and plate for
                  reactivity control units
    1 Scope
    2 Reference publications
    3 General requirements
    4 Composition requirements
    5 Inspection
    N285.6.14-17, Bellows attachment rings for use in
                  CANDU reactors
    1 Scope
    2 Reference publications
    3 General requirements
    4 Manufacturing requirements
    5 Composition requirements
    6 Mechanical properties
    7 Non-destructive examination
    8 Product marking

    Abstract - (Show below) - (Hide below)

    Sets up: - technical requirements for pressure boundary items of CANDU power reactors, in a format that regulatory authorities can reference; - requirements for each class of system, component, or support, consistent with the Nuclear Safety and Control Act (Act) and its Regulations; - applicable requirements of the ASME BPVC where they are appropriate to CANDU power reactors; - rules and material requirements for the design, fabrication, installation, quality assurance, and inspection of those pressure-retaining components and supports for which the ASME BPVC does not specify requirements; and - rules for the periodic inspection of pressure-retaining components in CANDU nuclear power plants.

    Scope - (Show below) - (Hide below)

    Preface This is the third edition of CSA N285.0/N285.6 Series, General requirements for pressure-retaining systems and components in CANDU nuclear power plants/Material Standards for reactor components for CANDU nuclear power plants. It supersedes the previous editions of the CSA N285.0/N285.6 Series published in 2012 and 2008, the previous editions of CSA N285.0 published in 2006, 1995, 1991, and 1981, and the previous editions of the CSA N285.6 Series published in 2005 and 1988. CSA N285.0 provides general requirements for pressure-retaining systems, components, and supports in CANDU nuclear power plants. Note: CANDU (CANada Deuterium Uranium) is a registered trademark of Atomic Energy of Canada Ltd., used under exclusive license by Candu Energy Inc., a Member of the SNC-Lavalin Group. The CSA N285 series of Standards specifies requirements applicable to nuclear power plants in Canada and references the applicable requirements of the ASME Boiler and Pressure Vessel Code (BPVC). The specific objectives of these Standards are as follows: - to establish technical requirements for pressure boundary items of CANDU power reactors, in a format that regulatory authorities can reference; - to establish requirements for each class of system, component, or support, consistent with the Nuclear Safety and Control Act (Act) and its Regulations; - to reference applicable requirements of the ASME BPVC where they are appropriate to CANDU power reactors; - to specify rules and material requirements for the design, fabrication, installation, quality assurance, and inspection of those pressure-retaining components and supports for which the ASME BPVC does not specify requirements; and - to establish rules for the periodic inspection of pressure-retaining components in CANDU nuclear power plants. The CSA N285 series consists of the following Standards and commentary document: - CSA N285.0 General requirements for pressure-retaining systems and components in CANDU nuclear power plants; - CSA N285.0.1 Commentary on N285.0-12, General requirements for pressure-retaining systems and components in CANDU nuclear power plants; Note: This commentary is an informative document and provides background, rationale, and context concerning certain clauses and requirements in CSA N285.0. - CAN/CSA-N285.1 this Standard no longer exists as a separate publication; it was incorporated into CAN/CSA-N285.0-95; - CAN/CSA-N285.2 this Standard no longer exists as a separate publication; it was incorporated as Annex I of CSA N285.0-08; - CAN/CSA-N285.3 this Standard no longer exists as a separate publication; it was incorporated as Annex J of CSA N285.0-08; - CSA N285.4 Periodic inspection of CANDU nuclear power plant components; - CAN/CSA-N285.5 Periodic inspection of CANDU nuclear power plant containment components; - CSA N285.6 Series Material Standards for reactor components for CANDU nuclear power plants (published with CSA N285.0); and Note: CSA N285.6.5 was withdrawn in the 2005 edition of the CSA N285.6 Series as the material that it covered (heat-treated Zr-2.5Nb-0.5 Cu wire for fuel-channel spacers) is no longer used for new spacers. - CSA N285.7 Periodic inspection of CANDU nuclear power plant balance of plant systems and components; - CSA N285.8 Technical requirements for in-service evaluation of zirconium alloy pressure tubes in CANDU reactors. 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. Users of this Standard are reminded that the design, fabrication, installation, commissioning, and operation of nuclear facilities in Canada are subject to the provisions of the Act and its Regulations. The Canadian Nuclear Safety Commission (CNSC) specifies regulatory and administrative requirements for pressure-retaining systems in their Regulations and regulatory documents. Where CNSC documents conflict with the requirements of this Standard, the CNSC documents take precedence. In this Standard, the CNSC is referred to as the regulatory authority. The Act and Regulations normally require the following items for a nuclear power reactor: a construction licence, an operating licence, and other licences, certificates, and permits specified by the regulatory authority. These licences and certificates can require the licensee to have the following: - registered designs for systems, components, and supports; - registered welding and brazing procedures; - an accepted overpressure protection report; - accepted code classifications, including applicable standards; - accepted record-keeping systems; - accepted quality assurance programs; and - accepted periodic inspection programs. When a licence references this Standard for another type of nuclear reactor facility, Clause 5 of CSA N285.0 should not be considered relevant unless - the facility has a defined exclusion zone; - access to the facility is controlled, permitting entry only by authorized personnel; and - the reactor is inside a containment structure that is capable of limiting releases to the environment in the event of the failure of a pressure-retaining component. -------------------------------------------------------------------------------------------------------------------------------- N285.0-17 - General requirements for pressure- retaining systems and components in CANDU nuclear power plants Scope 1.1 This Standard specifies the technical requirements for the design, procurement, fabrication, installation, modification, repair, replacement, testing, examination, and inspection of, and other work related to, pressure-retaining systems, components, and supports over the service life of a CANDU nuclear power plant. 1.2 This Standard applies to all pressure-retaining systems, including their components and supports, in a CANDU nuclear power plant. 1.3 This Standard applies to containment components, but does not apply to concrete containment structures. 1.4 This Standard does not apply to portable assemblies of pressurized items that are temporarily connected to a system or component to enable testing, venting, draining, calibration, or other maintenance activities, provided that they a) do not reduce the ability of a system to perform its design safety function; b) are under surveillance when connected and are removed upon completion of their function; and c) are constructed to Standards deemed by the licensee to be suitable for the application. Note: Safety analysis, environmental qualification programs, or seismic qualification may be used to satisfy the conditions in this Clause. 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 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 (nonmandatory) to define their application. 1.6 The values given in SI units are the units of record for the purposes of this Standard. The values given in parentheses are for information and comparison only. The units in this Standard may be converted in accordance with the ASME BPVC, Section III, NCA-1150. -------------------------------------------------------------------------------------------------------------------------------- N285.6.1-17 - Pressure tubes for use in CANDU fuel channels Scope This Standard specifies requirements for the fabrication and properties of seamless zirconium-2.5wt % niobium (Zr-2.5Nb) alloy pressure tubes for use in fuel channels in CANDU reactors. -------------------------------------------------------------------------------------------------------------------------------- N285.6.2-17 - Seamless zirconium alloy tubing for reactivity control units Scope This Standard specifies requirements for the fabrication and properties of seamless zirconium alloy tubing, Grades R60802 and R60804, with diameter to wall thickness ratios less than 80. This tubing is used for reactivity control units in CANDU reactors. -------------------------------------------------------------------------------------------------------------------------------- N285.6.3-17 - Annealed seamless zirconium alloy tubing for liquid injection shutdown system (LISS) nozzles Scope This Standard specifies requirements for the fabrication and properties of seamless zirconium-tin alloy tubing, Grade R60802 or R60804, which is suitable for use in liquid injection shutdown system (LISS) nozzles located in the moderator water in the core of a CANDU reactor. -------------------------------------------------------------------------------------------------------------------------------- N285.6.4-17 - Thin-walled, large-diameter zirconium alloy tubing Scope This Standard specifies requirements for the fabrication and properties of thin-walled, large-diameter tubing made from zirconium-tin alloys, Grade R60802 or R60804. Notes: 1) Thin-walled, large diameter tubing has a diameter to wall thickness ratio greater than 50. 2) This tubing can be used as calandria tubes and as tubes for reactivity control units in a CANDU reactor, and may be processed in the seamless or seam-welded condition. -------------------------------------------------------------------------------------------------------------------------------- N285.6.6-17 - Non-destructive examination criteria for zirconium alloys Scope 1.1 This Standard specifies requirements for non-destructive examinations (NDEs) of zirconium alloy components during manufacturing. NDE methods include visual, radiographic, liquid-penetrant, ultrasonic, and eddy current techniques. 1.2 Other standards may be used for the NDE of zirconium alloys, provided that they satisfy the requirements of this Standard. N285.6.7-17 - Zirconium alloy design data Scope This Standard specifies the physical and mechanical property data to be used in the design of the zirconium alloy components specified in the CSA N285.6 Series. -------------------------------------------------------------------------------------------------------------------------------- N285.6.8-17 - Martensitic stainless steel for fuel-channel end fittings Scope 1.1 This Standard specifies requirements for martensitic stainless steel forged blanks for the fuel-channel end fittings of a CANDU reactor. 1.2 Design data for end-fitting material are given in the following tables in Annex A: A.1 - Minimum mechanical properties A.2 - Design stress intensity values A.3 - Moduli of elasticity (Youngs Modulus) A.4 - Thermal expansion data A.5 - Thermal conductivity data -------------------------------------------------------------------------------------------------------------------------------- N285.6.9-17 - Materials for supports for pressure- retaining items Scope This Standard specifies requirements for material for the support of pressure-retaining items in CANDU nuclear power plants. The materials covered in this Standard are in addition to the materials permitted by the ASME Boiler and Pressure Vessel Code (BPVC), Section III, Division 1, NF-2000, and Code Cases. -------------------------------------------------------------------------------------------------------------------------------- N285.6.10-17 - Nickel-based alloy wire for fuel-channel spacers Scope This Standard specifies requirements for the nickel-based alloy (UNS N07750) wire used to form spacers for use between the pressure tubes and calandria tubes in the fuel channels in a CANDU reactor. -------------------------------------------------------------------------------------------------------------------------------- N285.6.11-17 - Zirconium alloy wire Scope This Standard specifies requirements for wires made from zirconium-tin alloy, Grade R60802 or R60804, used in the welding of zirconium components and in the manufacture of the spacers that are installed between pressure tubes and calandria tubes in the fuel channels in a CANDU reactor. -------------------------------------------------------------------------------------------------------------------------------- N285.6.12-17 - Zirconium alloy bars and rods for reactivity control units Scope This Standard specifies requirements for the fabrication and properties of zirconium alloy bars and rods, Grades R60802 and R60804, used for fabrication of reactivity control units in CANDU reactors. -------------------------------------------------------------------------------------------------------------------------------- N285.6.13-17 - Zirconium alloy sheet, strip and plate for reactivity control units Scope This Standard specifies requirements for the fabrication and properties of zirconium alloy sheet, strip and plate, Grades R60802 and R60804, used for fabrication of reactivity control units in CANDU reactors. -------------------------------------------------------------------------------------------------------------------------------- N285.6.14-17 - Bellows attachment rings for use in CANDU reactors Scope This Standard specifies requirements for the fabrication of centrifugal castings, chemical and mechanical properties and inspection of high strength steel, to the general requirements of ASTM A-148, which is required for bellows attachment rings (BAR) for attachment to fuel channel end fittings.

    General Product Information - (Show below) - (Hide below)

    Development Note Supersedes CSA N285.0 & CSA N285.6 SERIES. (07/2008) 2012 Edition along with GEN INS 1, 2 & 3 is still active, available in English & French. (02/2018)
    Document Type Standard
    Publisher Canadian Standards Association
    Status Current
    Supersedes

    Standards Referencing This Book - (Show below) - (Hide below)

    ASME PV CODE 5 : 2017 BOILER AND PRESSURE VESSEL CODE - NONDESTRUCTIVE EXAMINATION
    CSA C22.2 No. 63 : 1993 HOUSEHOLD REFRIGERATORS AND FREEZERS
    CSA N285.0 : 2006 GENERAL REQUIREMENTS FOR PRESSURE-RETAINING SYSTEMS AND COMPONENTS IN CANDU NUCLEAR POWER PLANTS
    ASNT SNT TC 1A : 2016 TOPICAL OUTLINES FOR QUALIFICATION OF NONDESTRUCTIVE TESTING PERSONNEL
    CSA N285.5 : 2013 PERIODIC INSPECTION OF CANDU NUCLEAR POWER PLANT CONTAINMENT COMPONENTS
    ISO 9712:2012 Non-destructive testing Qualification and certification of NDT personnel
    CSA B51 : 2014 BOILER, PRESSURE VESSEL, AND PRESSURE PIPING CODE
    ASME PV CODE 3 APP DIV 1 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - APPENDICES
    ASME PV CODE SET : 2017 BOILER AND PRESSURE VESSEL CODE - COMPLETE SET
    CSA S16 : 2014 DESIGN OF STEEL STRUCTURES
    ASME B16.34 : 2017 VALVES - FLANGED, THREADED, AND WELDING END
    CSA N285.6 SERIES : 2005 MATERIAL STANDARDS FOR REACTOR COMPONENTS FOR CANDU NUCLEAR POWER PLANTS
    ISO 6149-4:2017 Connections for fluid power and general use Ports and stud ends with ISO 261 metric threads and O-ring sealing Part 4: Dimensions, design, test methods and requirements for external hex and internal hex port plugs
    ASME PV CODE 9 : 2017 BOILER AND PRESSURE VESSEL CODE - WELDING, BRAZING, AND FUSING QUALIFICATIONS - QUALIFICATION STANDARD FOR WELDING, BRAZING, AND FUSING PROCEDURES; WELDERS; BRAZERS; AND WELDING, BRAZING, AND FUSING OPERATORS
    SAE AS 1933 : 2013 AGE CONTROLS FOR HOSE CONTAINING AGE-SENSITIVE ELASTOMERIC MATERIAL
    ASME CODE CASE NC : 2017 CODE CASES: NUCLEAR COMPONENTS
    ISO 6149-3:2006 Connections for hydraulic fluid power and general use Ports and stud ends with ISO 261 metric threads and O-ring sealing Part 3: Dimensions, design, test methods and requirements for light-duty (L series) stud ends
    SAE J 343 : 2016 TEST AND TEST PROCEDURES FOR SAE 100R SERIES HYDRAULIC HOSE AND HOSE ASSEMBLIES
    C22.2 NO. 92-15 Dehumidifiers
    ASME B16.9 : 2012 FACTORY-MADE WROUGHT BUTTWELDING FITTINGS
    ISO 6149-2:2006 Connections for hydraulic fluid power and general use Ports and stud ends with ISO 261 metric threads and O-ring sealing Part 2: Dimensions, design, test methods and requirements for heavy-duty (S series) stud ends
    CSA G40.20 G40.21 : 2013 GENERAL REQUIREMENTS FOR ROLLED OR WELDED STRUCTURAL QUALITY STEEL/STRUCTURAL QUALITY STEEL
    N285.4-14 Periodic inspection of CANDU nuclear power plant components
    ISO 6149-1:2006 Connections for hydraulic fluid power and general use Ports and stud ends with ISO 261 metric threads and O-ring sealing Part 1: Ports with truncated housing for O-ring seal
    SAE AMS 5698 : 2013 NICKEL ALLOY, CORROSION AND HEAT-RESISTANT, WIRE, 72NI - 15.5CR - 0.95CB - 2.5TI - 0.70AL - 7.0FE, NO. 1 TEMPER, PRECIPITATION HARDENABLE
    ASTM E 381 : 2017 : REDLINE Standard Method of Macroetch Testing Steel Bars, Billets, Blooms, and Forgings
    ASME CODE CASE B & PV : 2017 CODE CASES: BOILERS AND PRESSURE VESSELS
    CSA C22.2 No. 128 : 2016 VENDING MACHINES
    CSA N285.7 : 2015 Periodic inspection of CANDU nuclear power plant balance of plant systems and components
    CSA ISO 9001 : 2016 QUALITY MANAGEMENT SYSTEMS - REQUIREMENTS
    CSA N285.8 : 2015 TECHNICAL REQUIREMENTS FOR IN-SERVICE EVALUATION OF ZIRCONIUM ALLOY PRESSURE TUBES IN CANDU REACTORS
    CSA C22.2 No. 117 : 1970 ROOM AIR CONDITIONERS
    C22.2 NO. 236-15 Heating and cooling equipment (Bi-national standard with UL 1995)
    CGSB 48.9712 : 2014 NON-DESTRUCTIVE TESTING - QUALIFICATION AND CERTIFICATION OF PERSONNEL
    ASTM B 352/B352M : 2017 : REDLINE Standard Specification for Zirconium and Zirconium Alloy Sheet, Strip, and Plate for Nuclear Application
    ASME B36.10M : 2015 WELDED AND SEAMLESS WROUGHT STEEL PIPE
    ASME PV CODE 11 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR INSERVICE INSPECTION OF NUCLEAR POWER PLANT COMPONENTS
    CSA C22.2 No. 120 : 2013 REFRIGERATION EQUIPMENT
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