CSA N285.5-22 PDF

CSA N285.5-22 PDF

Preface

This is the sixth edition of CSA N285.5, Periodic inspection of CANDU nuclear power plant containment components . It supersedes the previous editions published in 2018, 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 major changes to this edition include the following: a) Addressed submission requirements for confirmatory inspections. Revised Clause 12.3.1. b) Removed requirement for periodic inspection of ligaments in mechanical coupling. Revised Clauses 8.4.5.2 and 8.4.5.4 and Table 3. c) Added new Clause 4.6.4 to permit submission of a justification for a deviation from requirements of Standard. AHJ acceptance of deviation is required. d) Updated Table 3 to align with inaugural and periodic inspection areas and requirements as defined in Clauses 7 and 8. Revised Clauses 7.5.2, 8.1, 8.3.1.3, 8.3.3.3, 8.4.3.1, and 8.4.5.4 and Table 3. e) Introduced new Annex C guidance on inspection personnel qualification (an adaptation of CSA N285.4, Annex J). Added a definition for “proficiency demonstration”. Revised Clauses 4.1 and 6. f) Updated requirements for acceptance standards for visual examinations, indications on coated and painted surfaces, and minor condition disposition process. Revised Clauses 9.2.2.1.1, 9.2.2.1.2, and 9.2.1.4 and Table 4. g) Incorporated other changes to facilitate application and maintain harmonization across CSA N285.4, CSA N285.5, and CSA N285.7: i) Updated definitions for consistency with standardized definitions from CSA, ASME, and CSA N285.4, CSA N285.5, and CSA N285.7. Updated Clauses 3 and 8.4.3.2. ii) Added guidance note to dispositioning Clauses 9.3.2, 9.3.3, and 9.3.4 to consider adjacent and interfacing components, pipe runs, and supports in determining the need for additional examinations and corrective actions. iii) Updated Annex B to further align with Annex A of CSA N285.4. iv) Updated the “corrosion related cracking”, “relevant indication”, “allowable indication criteria”, “allowable monitoring indication criteria”, and “allowable reporting indication criteria” phrases. Revised Clauses 3, 8.3.1.3, 8.3.3, 8.4.4, 9.2.3.1.2, 9.2.3.2.2, and 9.2.4.1.4 and Figure 2. v) Incorporated changes from French verification process (revised Clause 3 and Table 4). 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 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 fibreglass 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; 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.