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CSA N289.1 : 2008 : INC : UPD 1 : 2014: R201300

Superseded

Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

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GENERAL REQUIREMENTS FOR SEISMIC DESIGN AND QUALIFICATION OF CANDU NUCLEAR POWER PLANTS

Available format(s)

Hardcopy , PDF

Superseded date

09-07-2021

Language(s)

English

Published date

01-01-2013

€996.03
Excluding VAT

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

Describes the general requirements for seismic design and qualification of CANDU nuclear power plants.

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
105
ProductNote
Reconfirmed EN
PublisherName
Canadian Standards Association
Status
Superseded
SupersededBy

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
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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