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N289.1-08 (R2013)

Superseded
Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.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superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

General requirements for seismic design and qualification of CANDU nuclear power plants
Available format(s)

Hardcopy , PDF

Superseded date

10-12-2020

Language(s)

English, French

Published date

01-01-2008

Preface
1 Scope
2 Reference publications
3 Definitions and abbreviations
4 Application of the CSA N289 series of Standards
5 General seismic requirements
6 Responsibilities and duties
7 Quality assurance
Annexes
A (informative) - Sample seismic classification list
B (informative) - Ground motion for engineering design
C (informative) - Seismic evaluation beyond design basis
  to demonstrate seismic ruggedness
D (informative) - Experience-based seismic qualification
  methods
E (informative) - Seismic design good practices
F (informative) - Readiness for beyond design basis seismic events

Preface This is the second edition of CSA N289.1, General requirements for seismic design and qualification of CANDU nuclear power plants. It supersedes the previous edition, published in 1980 under the title General requirements for seismic qualification of CANDU nuclear power plants. Scope 1.1 This Standard sets forth the general requirements for seismic design and qualification of CANDU nuclear power plants. 1.2 This Standard applies to all structures, systems, and components (SSCs) of CANDU nuclear power plants requiring seismic qualification based on nuclear safety considerations (see Annex A). This Standard may also be applied to other SSCs, as deemed appropriate by the owner/licensee or by regulatory agencies such as the Canadian Nuclear Safety Commission (CNSC). 1.3 This Standard was developed for nuclear power plants in regions of low to moderate seismic hazard, comparable to the levels near Canada\'s existing CANDU nuclear power plants. In regions of higher seismic hazard, the engineering required for reliable design under strong earthquake shaking is more complex, and is beyond the scope of this Standard. Therefore, while the provisions of this Standard can be applied to any nuclear power plant site, additional provisions might be required for high seismic hazard sites. 1.4 This Standard may be applied, as appropriate, to nuclear facilities under the jurisdiction of the Nuclear Safety and Control Act. 1.5 In CSA Standards, \"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; \"may\" is used to express an option or that which is permissible within the limits of the standard; and \"can\" is used to express possibility or capability. 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 N289.1, General requirements for seismic design and qualification of CANDU nuclear power plants. It supersedes the previous edition, published in 1980 under the title General requirements for seismic qualification of CANDU nuclear power plants. Scope 1.1 This Standard sets forth the general requirements for seismic design and qualification of CANDU nuclear power plants. 1.2 This Standard applies to all structures, systems, and components (SSCs) of CANDU nuclear power plants requiring seismic qualification based on nuclear safety considerations (see Annex A). This Standard may also be applied to other SSCs, as deemed appropriate by the owner/licensee or by regulatory agencies such as the Canadian Nuclear Safety Commission (CNSC). 1.3 This Standard was developed for nuclear power plants in regions of low to moderate seismic hazard, comparable to the levels near Canada\'s existing CANDU nuclear power plants. In regions of higher seismic hazard, the engineering required for reliable design under strong earthquake shaking is more complex, and is beyond the scope of this Standard. Therefore, while the provisions of this Standard can be applied to any nuclear power plant site, additional provisions might be required for high seismic hazard sites. 1.4 This Standard may be applied, as appropriate, to nuclear facilities under the jurisdiction of the Nuclear Safety and Control Act. 1.5 In CSA Standards, \"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; \"may\" is used to express an option or that which is permissible within the limits of the standard; and \"can\" is used to express possibility or capability. 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 01-12-2009. (03/2010) French Edition of GEN INS 1 issued on 01-10-2015. (11/2015)
DocumentType
Standard
Pages
63
ProductNote
Reconfirmed EN
PublisherName
Canadian Standards Association
Status
Superseded
SupersededBy
Supersedes

ASCE 43 05 : 2005 SEISMIC DESIGN CRITERIA FOR STRUCTURES, SYSTEMS, AND COMPONENTS IN NUCLEAR FACILITIES
IEEE 382-2006 IEEE Standard for Qualification of Safety-Related Actuators for Nuclear Power Generating Stations
CSA N287.1:14 (R2019) General requirements for concrete containment structures for nuclear power plants
CSA N285.0 : 2006 GENERAL REQUIREMENTS FOR PRESSURE-RETAINING SYSTEMS AND COMPONENTS IN CANDU NUCLEAR POWER PLANTS
CSA S304.1 : 2004 DESIGN OF MASONRY STRUCTURES
ASME B31.1 : 2016 POWER PIPING
CSA S16 : 2014 DESIGN OF STEEL STRUCTURES
ASME QME 1 : 2012 QUALIFICATION OF ACTIVE MECHANICAL EQUIPMENT USED IN NUCLEAR FACILITIES
ASCE 4 98 : 2000 SEISMIC ANALYSIS OF SAFETY-RELATED NUCLEAR STRUCTURES AND COMMENTARY
CSA N285.6 SERIES : 2005 MATERIAL STANDARDS FOR REACTOR COMPONENTS FOR CANDU NUCLEAR POWER PLANTS
IEEE 344-2013 IEEE Standard for Seismic Qualification of Equipment for Nuclear Power Generating Stations
N291-15 Requirements for safety-related structures for nuclear power plants
A23.3-14 Design of concrete structures
CSA S832 : 2014 SEISMIC RISK REDUCTION OF OPERATIONAL AND FUNCTIONAL COMPONENTS (OFCS) OF BUILDINGS
N290.6-16 Requirements for monitoring and display of nuclear power plant safety functions in the event of an accident
IEEE C37.98-2013 IEEE Standard for Seismic Qualification Testing of Protective Relays and Auxiliaries for Nuclear Facilities
ASME PV CODE SET : 2017 BOILER AND PRESSURE VESSEL CODE - COMPLETE SET
ASME RA-S : 2008 LEVEL 1/LARGE EARLY RELEASE FREQUENCY PROBABILISTIC RISK ASSESSMENT FOR NUCLEAR POWER PLANT APPLICATIONS

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