Draft Details

1.1 General

This Standard defines requirements for the periodic inspection of pressure retaining systems, components, and supports that form part of a CANDU nuclear power plant.

Periodic inspection (see Annex A for additional guidance) is considered to include the fluid boundary portions of components and piping, including their supports that comprise

systems containing fluid that directly transports heat from nuclear fuel and other systems whose failure can result in a significant release of radioactive substance;

systems essential for the safe shutdown of the reactor or the safe cooling of the fuel, or both, in the event of a process system failure; and

other systems or components whose failure could jeopardize the integrity of the systems described in Item a) or b), or both.

In addition, for components exposed to conditions beyond the known experience base, and where such components constitute part of a vital system, the components may be considered suitable for inclusion in the periodic inspection program as supplementary periodic inspections.

1.2 Inclusions

This Standard addresses

failure aspects;

classification of areas subject to periodic inspection;

provision for access;

examination methods and procedures;

personnel qualifications;

frequency of periodic inspection;

responsibilities;

documentation;

records;

evaluation of periodic inspection results;

dispositioning; and

repair, replacement, and modification requirements.

1.3 Terminology

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.

1.4 Application of Standard

The requirements of this periodic inspection standard are applicable to the operational phase of nuclear power plant, until the fuel is removed from the entire reactor core and up to the time at which systems for cooling of the fuel are drained for the purpose of decommissioning of the reactor core.

This periodic inspection standard does contain requirements for providing access to components for pre-service and in-service examinations (part of the periodic inspection program), and hence the requirements of this standard should be taken into account during plant design and construction.

This periodic inspection standard does contain provisions for crediting of manufacturing and installation examinations as a baseline record for the periodic inspection program, and hence the requirements of this standard should be taken into account during plant construction.

This periodic inspection standard is not applicable to the decommissioning phase of the nuclear power plant life cycle.