Preface
This is the fifth edition of CSA N285.5, Periodic inspection of CANDU nuclear power plant containment components. It supersedes the previous editions published in 2013, 2008, 1990, and 1988.
This Standard is one of a series of Standards intended to provide uniform requirements for CANDU®nuclear power plants.
Note: CANDU (CANada Deuterium Uranium) is a registered trademark of Atomic Energy of Canada Limited (AECL).
This Standard provides uniform rules for the periodic inspection of containment components, including containment pressure suppression systems in CANDU nuclear power plants. It has been revised and updated to account for new knowledge and experience gained from CANDU research and operations, advances in technology, and changes to the regulatory framework in Canada.
The CSA N-Series of 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.
Users of this Standard are reminded that the operation of nuclear facilities in Canada is subject to the requirements of the Nuclear Safety and Control Act and Regulations. The Canadian Nuclear Safety Commission might impose additional requirements to those specified in this Standard.
In order to facilitate adoption by the authority having jurisdiction, this Standard includes some regulatory provisions.
This Standard was prepared by the Technical Committee on Periodic Inspection of CANDU Nuclear Power Plant Components under the jurisdiction of the Strategic Steering Committee on Nuclear Standards, and has been formally approved by the Technical Committee.
Scope
1.1
This Standard specifies requirements for the periodic inspection of containment system components, including containment pressure suppression systems, in CANDU nuclear power plants.
1.2
The periodic inspection requirements specified in this Standard (see Annex B for additional guidance) provide assurance of the structural integrity of metallic and plastic containment system components.
Note: The following are addressed by other Standards or procedures as specified in Table 1:
a) leak tightness and operability requirements; and
b) examination and testing requirements for concrete, embedded parts, and elastomeric seals.
Periodic inspection, material property monitoring, and test programs for fibre glass reinforced plastic (FRP) containment components are included in Annex A.
1.3
This Standard specifies requirements for
a) periodic inspection;
b) accessibility;
c) examination methods and procedures;
d) personnel qualifications;
e) examination criteria;
f) periodic inspection program development;
g) periodic inspection frequency;
h) evaluation of periodic inspection results;
i) dispositioning of defects;
j) repairs;
k) documentation; and
l) records.
1.4
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; may is used to express an option or that which is permissible within the limits of the standard; and can is used to express possibility or capability.
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.
