Preface

This is the third edition of CSA N285.5, Periodic inspection of CANDU nuclear power plant containment components. It supersedes the previous editions published in 1990 and 1988.

1 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 inspection requirements specified in this Standard 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) inspection and testing requirements for concrete, embedded parts, and elastomeric seals.

1.3 This Standard specifies requirements for
(a) inspection;
(b) accessibility;
(c) inspection methods and procedures;
(d) personnel qualifications;
(e) inspection criteria;
(f) inspection program development;
(g) inspection frequency;
(h) evaluation of inspection results;
(i) disposition of defects;
(j) repairs;
(k) documentation; and
(l) records.

1.4 In CSA Standards, "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.