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CSA N285.7-15

Periodic inspection of CANDU nuclear power plant balance of plant systems and components - First Edition

Organization:
CSA - CSA Group
Year: 2015

Abstract: Scope:

This Standard defines requirements for the periodic inspection of balance of plant pressure retaining systems, components, and supports that form part of a CANDU nuclear power plant using a risk informed in-service inspection (RI-ISI) methodology. Periodic inspection (see Annex A for additional guidance) is considered to include the fluid boundary portions of balance of plant systems, components and piping, including their supports that comprise a complete nuclear power plant, excluding the following systems or portions thereof:

a) Systems, and systems connected thereto, containing the fluid that, under normal conditions, directly transports heat from nuclear fuel, and other systems whose failure can result in a significant release of radioactive substances.

Note: These systems or portions of systems are subject to inspection in accordance with Clause 3.3. (a) in CSA N285.4.

b) Systems essential for the safe shutdown of the reactor and/or the safe cooling of the nuclear fuel in the event of a process system failure.

Note: These systems or portions of systems are subject to inspection in accordance with Clause 3.3.1(b) in CSA N285.4.

Compressors, turbines, generators, engines, and hydraulic or pneumatic cylinders are exempt from the inspection requirements of this Standard. This includes piping internal to equipment or mounted upon equipment that carries fluid from one chamber to another on the same foundation. Note: To arrive at a periodic inspection program, the user should consider the inspections, examinations, and tests performed by other programs such as pipe wall thinning, vessel inspections, equipment reliability, and maintenance programs in addition to RI-ISI. Inspections performed as part of supporting programs are not expected to be repeated in this periodic inspection program, but should be credited to this periodic inspection program to provide assurance that the program satisfies the intended purpose as described in Annex A.

This Standard addresses the following requirements

a) failure aspects;

b) classification of areas subject to inspection;

c) provision for access;

d) inspection techniques and procedures;

e) personnel qualifications;

f) frequency of inspection;

g) responsibilities;

h) documentation;

i) records;

j) evaluation of inspection results;

k) dispositioning; and

l) repair, replacement and modification requirements

The values given in SI units are the units of record for the purposes of this Standard. The values given in parentheses are for information and comparison only.

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 (nonmandatory) to define their application.

 

 

URI: https://yse.yabesh.ir/std/handle/yse/182856
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    CSA N285.7-15

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contributor authorCSA - CSA Group
date accessioned2017-09-04T17:59:48Z
date available2017-09-04T17:59:48Z
date copyright2015.01.01
date issued2015
identifier otherFVAGNFAAAAAAAAAA.pdf
identifier urihttps://yse.yabesh.ir/std/handle/yse/182856
description abstractScope:

This Standard defines requirements for the periodic inspection of balance of plant pressure retaining systems, components, and supports that form part of a CANDU nuclear power plant using a risk informed in-service inspection (RI-ISI) methodology. Periodic inspection (see Annex A for additional guidance) is considered to include the fluid boundary portions of balance of plant systems, components and piping, including their supports that comprise a complete nuclear power plant, excluding the following systems or portions thereof:

a) Systems, and systems connected thereto, containing the fluid that, under normal conditions, directly transports heat from nuclear fuel, and other systems whose failure can result in a significant release of radioactive substances.

Note: These systems or portions of systems are subject to inspection in accordance with Clause 3.3. (a) in CSA N285.4.

b) Systems essential for the safe shutdown of the reactor and/or the safe cooling of the nuclear fuel in the event of a process system failure.

Note: These systems or portions of systems are subject to inspection in accordance with Clause 3.3.1(b) in CSA N285.4.

Compressors, turbines, generators, engines, and hydraulic or pneumatic cylinders are exempt from the inspection requirements of this Standard. This includes piping internal to equipment or mounted upon equipment that carries fluid from one chamber to another on the same foundation. Note: To arrive at a periodic inspection program, the user should consider the inspections, examinations, and tests performed by other programs such as pipe wall thinning, vessel inspections, equipment reliability, and maintenance programs in addition to RI-ISI. Inspections performed as part of supporting programs are not expected to be repeated in this periodic inspection program, but should be credited to this periodic inspection program to provide assurance that the program satisfies the intended purpose as described in Annex A.

This Standard addresses the following requirements

a) failure aspects;

b) classification of areas subject to inspection;

c) provision for access;

d) inspection techniques and procedures;

e) personnel qualifications;

f) frequency of inspection;

g) responsibilities;

h) documentation;

i) records;

j) evaluation of inspection results;

k) dispositioning; and

l) repair, replacement and modification requirements

The values given in SI units are the units of record for the purposes of this Standard. The values given in parentheses are for information and comparison only.

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 (nonmandatory) to define their application.

 

 

languageEnglish
titleCSA N285.7-15num
titlePeriodic inspection of CANDU nuclear power plant balance of plant systems and components - First Editionen
typestandard
page137
statusActive
treeCSA - CSA Group:;2015
contenttypefulltext
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