Preface
Development of this Standard began in 1973 under the sponsorship of the Canadian Nuclear Association's Codes, Standards, and Practices Committee. In 1974 the decision was made to promulgate this document as a CSA Standard.
Standards in this series were initiated in response to a recognition by the utilities and industries concerned With nuclear structures in Canada, of a need for the documentation of standards applicable to the design, construction, and testing of concrete containment structures incorporated as components of a CANDU nuclear power plant.
The purpose of this Standard is to provide proof by demonstration, before first criticality, that the design and construction of a concrete containment structure is satisfactory with respect to quality and performance.
This Standard is one in a series of Standards, which, together, form a code. The code will comprise the Standards listed below, which are in preparation, and such additional ones as may be required from time to time:
CSA Standards
N287.1 General Requirements;
N287.2 Material Requirements;
N287.3 Design Requirements;
N287.4 Construction, Fabrication and Installation Requirements;
N287.5 Testing and Examinatibn Requirements;
N287.6 Pre-Operational Proof and Leakage Rate Testing Requirements.
In preparation of this and the above Standards, it was the decision of the Committee to make use of existing Standards, Codes, and other reference material wherever possible, noting only the exceptions applicable to concrete containment structures. Such material is listed in the reference publications.
This Standard was prepared by the Committee on Concrete Containment Structures for Nuclear Power Plants under the jurisdiction of the Sectional Committee for Nuclear Standards.
Scope
1.1
This Standard covers the requirements for proof tests and leakage rate tests of concrete containment structures of a containment system, designated as Class Containment components.
NOTE: Other components of the containment system such as the active components may be tested coincident with the tests of thi Standard, provided the intent of this Standard is observed and the requirements of CSA Standard N285.1, General and Design Requirement for CANDU Nuclear Power Plant Components, are considered.
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