CSA N287.5:20 PDF

CSA N287.5:20 PDF

Preface:

This is the fourth edition of CSA N287.5, Examination and testing requirements for concrete containment structures for nuclear power plants. It supersedes the previous editions, published in 2011, 1993, and 1981.

The major changes to this edition include the following:

• The test and test frequencies for concrete materials and grout and their constituents were updated (Tables 1 and 2).
• The definitions for containment structure and containment boundary were updated to align with the other CSA N287 series standards.
• The term “class containment” was modified to align with the other CSA N287 series of Standards.
• The requirements for anchors, welds, and grouted embedments were updated to align with other CSA N287 series of Standards.
• The terms and definitions were updated to align with the common list of definitions.
• Requirements for personnel qualification were included.
• A clause on aging management was added.

The CSA N-Series Standards provide an interlinked set of requirements for the management of nuclear facilities and activities. CSA N286 provides overall direction to management to develop and implement sound management practices and controls, while the other CSA Group nuclear Standards provide technical requirements and guidance that support the management system. This Standard works in harmony with CSA N286 and does not duplicate the generic requirements of CSA N286; however, it might provide more specific direction for those requirements.

This Standard specifies examination and testing requirements that will ensure that concrete containment structures are built using techniques and work practices that meet the quality and standards commensurate with the safety principles necessary to comply with the Canadian nuclear safety philosophy.

This Standard is part of the CSA N287 series of Standards, which provides the requirements for concrete containment structures for nuclear power plants. These Standards were initiated in response to a recognition by the utilities and industries concerned with nuclear power plant structures in Canada of a need for consistent standards for the design, construction, and testing of concrete containment structures for nuclear power plants.

The CSA N287 series of Standards consists of eight Standards. The objectives of each Standard are summarized as follows:

• CSA N287.1, General requirements for concrete containment structures for nuclear power plants, specifies general requirements for the design, construction, testing, commissioning, and in-service examination and testing of concrete containment structures for nuclear power plants and is directed to the owners, designers, manufacturers, fabricators, and constructors;
• CSA N287.2, Material requirements for concrete containment structures for nuclear power plants, specifies requirements for materials used for concrete containment structures;
• CSA N287.3, Design requirements for concrete containment structures for nuclear power plants, specifies requirements for the design of concrete containment structures;
• CSA N287.4, Construction, fabrication, and installation requirements for concrete containment structures for nuclear power plants, specifies construction, fabrication, and installation requirements for concrete containment structures for nuclear power plants;
• CSA N287.5, Examination and testing requirements for concrete containment structures for nuclear power plants, specifies examination and testing requirements that apply to the work of any organization participating in the construction, fabrication, or installation of concrete containment structures for nuclear power plants;
• CSA N287.6, Pre-operational proof and leakage rate testing requirements for concrete containment structures for nuclear power plants specifies requirements for proof by demonstration, before first criticality, that the design and construction of a concrete containment structure are satisfactory with respect to quality and performance as demonstrated by achieving the specified requirements of CSA N287.6, including commissioning leakage rate target;
• CSA N287.7, In-service examination and testing requirements for concrete containment structures for nuclear power plants, specifies uniform requirements whereby, through systematic and periodic examination, the structural and leak-tight integrity of concrete containment structures can be assessed as demonstrated by achieving the specified requirements of CSA N287.7, including the operational leakage rate target; and
• CSA N287.8, Aging management for concrete containment structures for nuclear power plants, provides aging management requirements for concrete containment structures for nuclear power plants and is directed to the owners/operators, designers, manufacturers, fabricators, and constructors.

Users of this Standard are reminded that the design, manufacture, construction, commissioning, operation, and decommissioning of nuclear facilities in Canada are subject to the provisions of the Nuclear Safety and Control Act and its Regulations. Requirements additional to those specified in this Standard can be imposed by the Canadian Nuclear Safety Commission.

Scope:

1.1 This Standard specifies examination and testing requirements that apply to the work of any organization participating in the construction, fabrication, or installation of concrete containment structures, which includes, but is not limited to, the following structural and non-structural elements:

a) concrete;

b) reinforcement (pre-stressed and non-pre-stressed);

c) steel (e.g., liner, embedded parts, anchors);

d) non-metallic liners and coating systems;

e) joint sealants; and

f) elements necessary to support containment structure (e.g., foundations).

1.2 This Standard specifies personnel qualification requirements for work pertaining to the examination and testing of concrete containment structures for nuclear power plants.

1.3 This Standard is applicable to existing and new nuclear power plants. It is not the intent that the requirements of this Standard be applied retroactively to existing nuclear power plants, unless as agreed to by the authority having jurisdiction.

1.4 This Standard may be applied, as appropriate, to nuclear facilities under the jurisdiction of the Government of Canada’s Nuclear Safety and Control Act.

1.5 This Standard is used in concert with the other CSA N287 series standards, as applicable.

1.6 In this Standard, “shall” is used to express a requirement, i.e., a provision that the user is obliged to satisfy in order to comply with the Standard; “should” is used to express a recommendation or that which is advised but not required; and “may” is used to express an option or that which is permissible within the limits of the Standard. Notes accompanying clauses do not include requirements or alternative requirements; the purpose of a note accompanying a clause is to separate from the text explanatory or informative material. Notes to tables and figures are considered part of the table or figure and may be written as requirements. Annexes are designated normative (mandatory) or informative non-mandatory) to define their application.