CSA N289.3 :2010
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
View Superseded by
DESIGN PROCEDURES FOR SEISMIC QUALIFICATION OF NUCLEAR POWER PLANTS
Hardcopy , PDF
09-07-2021
English
01-01-2015
Preface
1 Scope
2 Reference publications
3 Definitions and abbreviations
4 Application of seismic ground motion to engineering
design
5 Seismic analysis of foundations
6 Seismic qualification by analytical methods
7 Seismic design criteria
8 Seismic evaluation beyond design basis to demonstrate
seismic ruggedness
9 Other seismically induced phenomena
10 Documentation
11 Quality assurance
Annexes
A (informative) - Buried pipes and conduits
Describes the requirements, criteria, and methods of analysis for: (a) determining the design response spectra and ground motion time-histories to be used in the analysis; (b) establishing design criteria for SSCs, and supports that require seismic qualification; and (c) performing seismic analyses, including the effects of the soil-structure-interaction.
| DocumentType |
Standard
|
| Pages |
0
|
| 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Superseded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 |
| CSA N287.3:14 (R2019) | Design requirements for concrete containment structures for nuclear power plants |
| CSA S304.1 : 2004 | DESIGN OF MASONRY STRUCTURES |
| ASME B31.1 : 2016 | POWER PIPING |
| CSA S16 : 2014 | DESIGN OF STEEL STRUCTURES |
| CSA N286.7 : 2016 | QUALITY ASSURANCE OF ANALYTICAL, SCIENTIFIC, AND DESIGN COMPUTER PROGRAMS |
| ASME PV CODE 2 SET : 2013 | ASME BOILER AND PRESSURE VESSEL CODE (BPVC) - MATERIALS (SET) |
| ASCE 4 98 : 2000 | SEISMIC ANALYSIS OF SAFETY-RELATED NUCLEAR STRUCTURES AND COMMENTARY |
| 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 |
| ACI 350.3 : 2006 | SEISMIC DESIGN OF LIQUID-CONTAINING CONCRETE STRUCTURES AND COMMENTARY |
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