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N291-15

Superseded
Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

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superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

Requirements for safety-related structures for nuclear power plants
Available format(s)

Hardcopy , PDF

Superseded date

03-25-2019

Language(s)

English, French

Published date

01-01-2015

Preface
1 Scope
2 Reference publications
3 Definitions
4 General requirements
5 Materials, construction, and operating exposure
  conditions
6 Analysis and design
7 Construction inspection and in-service examination
8 Seismic analysis, design and dynamic considerations
9 Aging management
Annex A (informative) - Special provisions for impulse
        and impact effects for concrete structures
Annex B (informative) - Waiting periods for placing
        fresh concrete adjacent to hardened concrete

Preface This is the second edition of CSA N291, Requirements for safety-related structures for nuclear power plants. It supersedes the previous edition published in 2008 under the title Requirements for safety-related structures for CANDU nuclear power plants. The title has been changed to reflect a change in scope, from addressing only CANDU reactors to including all types of nuclear power plants. Note: CANDU (CANada Deuterium Uranium) is a registered trademark of Atomic Energy of Canada Limited (AECL). This Standard specifies requirements for the material, analysis & design, construction, fabrication, inspection, examination and aging management of safety-related structures constructed of structural steel, reinforced concrete, and reinforced masonry. The minimum design requirements specified in this Standard follow the requirements of CSA A23.3, CSA S16, CSA S304.1, and the National Building Code of Canada. Additional requirements reference the CSA N287 series and the CSA N289 series of Standards. This Standard provides a general definition of safety-related structures rather than a comprehensive listing of all safety-related structures. The analysis and design of structures cover static and dynamic loads, and the loads, load factors, load combinations, and safety criteria cover service loads and abnormal/environmental loads. This Standard also covers the design and analysis of irradiated fuels and radioactive waste storage facilities. 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 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 may provide more specific direction for those requirements. The users of this Standard are reminded that an authority having jurisdiction (AHJ) such as the Canadian Nuclear Safety Commission might impose additional requirements to those specified in this Standard. Scope 1.1 This Standard specifies requirements for the material, analysis and design, construction, fabrication, inspection, examination, and aging management of safety-related structures for nuclear power plants. Safety-related structures covered in this Standard are a) structures that support, house, or protect nuclear safety systems; b) components of structures that are required for the safe operation and/or safe shutdown of the reactor; c) structures for the storage of wet and dry irradiated fuel; and d) structures for the storage of radioactive waste material as agreed with the AHJ. 1.2 This Standard does not apply to concrete containment structures covered in the CSA N287 series or the pressure-retaining systems and components covered in CSA N285.0. 1.3 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.

Preface This is the second edition of CSA N291, Requirements for safety-related structures for nuclear power plants. It supersedes the previous edition published in 2008 under the title Requirements for safety-related structures for CANDU nuclear power plants. The title has been changed to reflect a change in scope, from addressing only CANDU reactors to including all types of nuclear power plants. Note: CANDU (CANada Deuterium Uranium) is a registered trademark of Atomic Energy of Canada Limited (AECL). This Standard specifies requirements for the material, analysis & design, construction, fabrication, inspection, examination and aging management of safety-related structures constructed of structural steel, reinforced concrete, and reinforced masonry. The minimum design requirements specified in this Standard follow the requirements of CSA A23.3, CSA S16, CSA S304.1, and the National Building Code of Canada. Additional requirements reference the CSA N287 series and the CSA N289 series of Standards. This Standard provides a general definition of safety-related structures rather than a comprehensive listing of all safety-related structures. The analysis and design of structures cover static and dynamic loads, and the loads, load factors, load combinations, and safety criteria cover service loads and abnormal/environmental loads. This Standard also covers the design and analysis of irradiated fuels and radioactive waste storage facilities. 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 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 may provide more specific direction for those requirements. The users of this Standard are reminded that an authority having jurisdiction (AHJ) such as the Canadian Nuclear Safety Commission might impose additional requirements to those specified in this Standard. Scope 1.1 This Standard specifies requirements for the material, analysis and design, construction, fabrication, inspection, examination, and aging management of safety-related structures for nuclear power plants. Safety-related structures covered in this Standard are a) structures that support, house, or protect nuclear safety systems; b) components of structures that are required for the safe operation and/or safe shutdown of the reactor; c) structures for the storage of wet and dry irradiated fuel; and d) structures for the storage of radioactive waste material as agreed with the AHJ. 1.2 This Standard does not apply to concrete containment structures covered in the CSA N287 series or the pressure-retaining systems and components covered in CSA N285.0. 1.3 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.

DevelopmentNote
French Edition issued on 01-11-2016. (12/2016)
DocumentType
Standard
Pages
61
PublisherName
Canadian Standards Association
Status
Superseded
SupersededBy
Supersedes

CSA N289.3 : 2010 : INC : UPD 1 : 2012 DESIGN PROCEDURES FOR SEISMIC QUALIFICATION OF NUCLEAR POWER PLANTS
N289.3-10 (R2015) Design procedures for seismic qualification of nuclear power plants
CSA N292.2 : 2007 INTERIM DRY STORAGE OF IRRADIATED FUEL
CSA N292.6:18 LONG-TERM MANAGEMENT OF RADIOACTIVE WASTE AND IRRADIATED FUEL
CSA N292.1 : 2016 WET STORAGE OF IRRADIATED FUEL AND OTHER RADIOACTIVE MATERIALS
CSA N289.1 : 2008 GENERAL REQUIREMENTS FOR SEISMIC DESIGN AND QUALIFICATION OF CANDU NUCLEAR POWER PLANTS
N289.1-08 (R2013) General requirements for seismic design and qualification of CANDU nuclear power plants
CSA N289.1 : 2008 : INC : UPD 1 : 2014: R201300 GENERAL REQUIREMENTS FOR SEISMIC DESIGN AND QUALIFICATION OF CANDU NUCLEAR POWER PLANTS
CSA N289.1 : 2008 : INC : UPD 1 : 2015 : R201300 GENERAL REQUIREMENTS FOR SEISMIC DESIGN AND QUALIFICATION OF CANDU NUCLEAR POWER PLANTS
CSA N292.2 : 2007 : R2013 INTERIM DRY STORAGE OF IRRADIATED FUEL
N287.2-17 Material requirements for concrete containment structures for nuclear power plants
CSA N289.3 :2010 DESIGN PROCEDURES FOR SEISMIC QUALIFICATION OF NUCLEAR POWER PLANTS

W59-13 Welded steel construction (metal arc welding)
CSA N287.1:14 (R2019) General requirements for concrete containment structures for nuclear power plants
ASTM C 1603 : 2016 : REDLINE Standard Test Method for Measurement of Solids in Water
CSA N287.3:14 (R2019) Design requirements for concrete containment structures for nuclear power plants
ASTM D 512 : 2012 Standard Test Methods for Chloride Ion In Water (Withdrawn 2021)
ASTM C 441 : 2005 Standard Test Method for Effectiveness of Pozzolans or Ground Blast-Furnace Slag in Preventing Excessive Expansion of Concrete Due to the Alkali-Silica Reaction
CSA S304.1 : 2004 DESIGN OF MASONRY STRUCTURES
CSA N285.5 : 2013 PERIODIC INSPECTION OF CANDU NUCLEAR POWER PLANT CONTAINMENT COMPONENTS
CSA A3000 : 2013 CEMENTITIOUS MATERIALS COMPENDIUM
CSA S16 : 2014 DESIGN OF STEEL STRUCTURES
ASTM C 1240 : 2015 : REDLINE Standard Specification for Silica Fume Used in Cementitious Mixtures
CSA N287.8 : 2015 AGING MANAGEMENT FOR CONCRETE CONTAINMENT STRUCTURES FOR NUCLEAR POWER PLANTS
CSA W48 : 2014 FILLER METALS AND ALLIED MATERIALS FOR METAL ARC WELDING
N285.0-12/N285.6 SERIES-12 General requirements for pressure-retaining systems and components in CANDU nuclear power plants/Material Standards for reactor components for CANDU nuclear power plants
ASTM C 637 : 2014 : REDLINE Standard Specification for Aggregates for Radiation-Shielding Concrete
ASTM E 70 TEST METHOD FOR PH OF AQUEOUS SOLUTIONS WITH THE GLASS ELECTRODE
SAE AMS QQ S 763D : 2013(S2015) STEEL, CORROSION RESISTANT, BARS, WIRE, SHAPES, AND FORGINGS
A23.3-14 Design of concrete structures
ASCE 7 10 : 2010 MINIMUM DESIGN LOADS FOR BUILDINGS AND OTHER STRUCTURES
N285.4-14 Periodic inspection of CANDU nuclear power plant components
AWS A5.4/A5.4M : 2012 SPECIFICATION FOR STAINLESS STEEL ELECTRODES FOR SHIELDED METAL ARC WELDING
ASTM A 421/A421M : 2015 : REDLINE Standard Specification for Stress-Relieved Steel Wire for Prestressed Concrete
AWS A5.9/A5.9M : 2012 SPECIFICATION FOR BARE STAINLESS STEEL WELDING ELECTRODES AND RODS
CSA N285.8 : 2015 TECHNICAL REQUIREMENTS FOR IN-SERVICE EVALUATION OF ZIRCONIUM ALLOY PRESSURE TUBES IN CANDU REACTORS
CSA A23.1 A23.2 : 2014 CONCRETE MATERIALS AND METHODS OF CONCRETE CONSTRUCTION/TEST METHODS AND STANDARD PRACTICES FOR CONCRETE
ASTM C 494/C494M : 2017 : REDLINE Standard Specification for Chemical Admixtures for Concrete

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