CSA N289.1 : 2008 : INC : UPD 1 : 2014: R201300
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.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
Hardcopy , PDF
09-07-2021
English
01-01-2013
Important note : Users cannot be edited or removed once added to your Multi user PDF.
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Superseded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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