• There are no items in your cart

CSA N289.3 :2010

Superseded
Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

View Superseded by
superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

DESIGN PROCEDURES FOR SEISMIC QUALIFICATION OF NUCLEAR POWER PLANTS
Available format(s)

Hardcopy , PDF

Superseded date

07-09-2021

Language(s)

English

Published date

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Superseded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
N291-15 Requirements for safety-related structures for nuclear power plants
A23.3-14 Design of concrete structures
N285.4-14 Periodic inspection of CANDU nuclear power plant components
ACI 350.3 : 2006 SEISMIC DESIGN OF LIQUID-CONTAINING CONCRETE STRUCTURES AND COMMENTARY

View more information

Access your standards online with a subscription

Features

  • Simple online access to standards, technical information and regulations.

  • Critical updates of standards and customisable alerts and notifications.

  • Multi-user online standards collection: secure, flexible and cost effective.