N291-15
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
Hardcopy , PDF
03-25-2019
English, French
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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