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CSA N287.6 : 2011

Superseded
Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

PRE-OPERATIONAL PROOF AND LEAKAGE RATE TESTING REQUIREMENTS FOR CONCRETE CONTAINMENT STRUCTURES FOR NUCLEAR POWER PLANTS
Available format(s)

Hardcopy , PDF

Superseded date

10-10-2020

Language(s)

English, French

Published date

01-01-2016

Preface
1 Scope
2 Reference publications
3 Definitions
4 Owner/licensee responsibilities
5 General requirements
6 Proof test requirements
7 Leakage rate test requirements
8 Test specifications
9 Test procedures
10 Test report
Annexes
A (informative) - Leakage rate analysis method
B (informative) - Instrument selection guide (ISG)
C (informative) - Guidelines for evaluating prestressing
  systems using instrumented monitoring

Describes requirements for pre-operational proof and leakage rate testing of concrete containment structures of a containment system that are designated as class containment components.

DevelopmentNote
French Edition issued on 01-03-2014. (05/2014)
DocumentType
Standard
Pages
38
ProductNote
Reconfirmed EN
PublisherName
Canadian Standards Association
Status
Superseded
Supersedes

CSA N287.1:14 (R2019) General requirements for concrete containment structures for nuclear power plants
ANS 56.8 : 2002(R2016) CONTAINMENT SYSTEM LEAKAGE TESTING REQUIREMENTS
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

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