CSA N287.6 : 2011(R2016)
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.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
Hardcopy , PDF
07-01-2021
English
01-01-2016
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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 |
Revision
|
| Pages |
38
|
| ProductNote |
Reconfirmed F
|
| PublisherName |
Canadian Standards Association
|
| Status |
Superseded
|
| 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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