CSA N291 / CSA N291COM: Requirements for nuclear safety-related structures + Commenta

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CSA N291:19 (R2024) Requirements for nuclear safety-related structures + CSA N291COM:24 Commentary

| Size: 6.79 MB| Format: PDF| Quality: Original preprint| Year: 2024| pages: 73

This is the third edition of CSA N291, Requirements for nuclear safety-related structures. It supersedes the previous edition published in 2015 under the title, Requirements for safety-related structures for nuclear power plants and 2008 under the title, Requirements for safety-related structures for CANDU®nuclear power plants. The title has been changed to reflect more accurately the scope.

Note: CANDU®(CANada Deuterium Uranium) is a registered trademark of Atomic Energy of Canada Limited (AECL).

There have been many changes throughout this edition; the most significant changes are as follows:

• clarification of the scope, specifically for storage of radioactive waste material;

• addition of new clauses on testing of welding materials and rebar splice materials;

• addition of new clauses on beyond design basis and design extension conditions;

• addition of new clauses on personnel qualifications for: visual inspection, non-destructive examination, welding, concrete construction inspection, and non-metallic liner and coatings inspection.

• modification and addition of new clauses to clarify the requirements for a formal, detailed construction inspection and testing program;

• addition of new clauses on aging management; and

• updates to tests and test frequencies tables for concrete materials, concrete, and grout.

This Standard specifies requirements for the material, analysis and design, construction, fabrication, inspection, examination, and aging management of safety-related structures constructed of structural steel, reinforced concrete, and reinforced masonry. The minimum design requirements specified in this Standard follow the requirements of CSA A23.3, CSA S16, CSA S304.1, and the National Building Code of Canada. Additional requirements reference the CSA N287 series and the CSA N289 series of Standards.

This Standard provides a general definition of safety-related structures rather than a comprehensive listing of all safety-related structures. The analysis and design of structures cover static and dynamic loads, and the loads, load factors, load combinations, and safety criteria cover service loads and abnormal/environmental loads. This Standard also covers the design and analysis of irradiated fuels and radioactive waste storage structures.

The CSA N-Series of Standards provides 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 may provide more specific direction for those requirements.

The users of this Standard are reminded that an authority having jurisdiction (AHJ) such as the Canadian Nuclear Safety Commission might impose additional requirements to those specified in this Standard.

This Standard was prepared by the Subcommittee on Requirements for Nuclear Safety-Related Structures, under the jurisdiction of the Technical Committee on Concrete Containment and Safety- Related Structures for Nuclear Power Plants and the Strategic Steering Committee on Nuclear Standards, and has been formally approved by the Technical Committee.

This is the first edition of CSA N291COM, Commentary on CSA N291, Requirements for nuclear safety-related structures.

The discussion provided in this Commentary is directed toward the requirements of the third edition of CSA N291 published in March 2019, and does not address any amendments issued since this initial publication. This Commentary does not provide formal interpretations of CSA N291 and should be viewed only as an informative annotation of portions of CSA N291. It has been written in an informative (non-mandatory) language and is not intended to be adopted by users of CSA N291 or regulatory authorities as additional requirements. Significant changes between editions of CSA N291 that would benefit from commentary along with the rationale for the changes are outlined.

This Commentary responds to questions and comments raised by those who have participated in developing and implementing CSA N291. It provides a context and explanation for the structure and content of CSA N291 and outlines the governing principles and requirements. The Commentary does not cover the entire content of every clause of CSA N291.

The intent is to update this Commentary after the publication of each new edition of CSA N291 to incorporate information associated with amendments to published editions and new editions and to expand the Commentary as additional needs are identified.

This Commentary was prepared by the Subcommittee on Commentary on CSA N291 Requirements for Nuclear Safety-Related Structures, under the jurisdiction of the Technical Committee on Concrete Containment and Safety-Related Structures for Nuclear Power Plants and the Nuclear Strategic Steering Committee on Nuclear Standards, and has been formally approved by the Technical Committee.

Scope

CSA N291 provides requirements for nuclear safety-related structures. The scope of the Standard has somewhat evolved as described below.

The first edition (2008) of the Standard included within its scope the structures and components of CANDU NPPs that support, house, or protect nuclear safety systems and are required for the safe operation and shutdown of the reactor. The scope also included the facilities for the storage of irradiated fuel and other radioactive waste material. The intent of this was to be broad and all- encompassing, and to allow for the operating organization to determine the applicability of the Standard to their structure, as agreed by the authority having jurisdiction (AHJ).

Clarification of the scope with regards to radioactive waste storage structures was provided in the second edition (2015) to ensure that the users understood that the Standard applies to the storage of wet and dry irradiated fuel. The scope statement in the second edition clarified that the storage of other radioactive waste was to be included for facilities as agreed by the AHJ.

In the third edition (2019), the requirement of dry irradiated fuel was refined from a generic inclusion to include those that are required as agreed with the AHJ. Dry irradiated fuel was moved to Item e) of Clause 1.1 and included with other radioactive waste material. The use of as agreed with the AHJ means that the AHJ and the operating organization can agree to use other standards besides CSA N291 for the structures listed in Item e). Notes were added to Clause 1.1 to clarify that not all elements of the structures described in Item e) are considered safety-related, and to provide additional guidance on the storage of other radioactive waste with reference to CSA N292 with respect to high-level waste.

In the third edition, the scope of the Standard has been broadened to apply to any nuclear safety-related structures, not only those within NPPs

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