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CSA N285.7:21 Periodic inspection of CANDU nuclear power plant balance of plant systems and components
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CSA N285.7:21
February 2021
Title: Periodic inspection of CANDU nuclear power plant balance of plant systems and components
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CSA N285.7:21
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ICS 27.120.20
ISBN 978-1-4883-3393-4
© 2021 Canadian Standards Association
All rights reserved. No part of this publication may be reproduced in any form whatsoever without the prior permission of the publisher.
Technical Committee on Periodic Inspection of Nuclear Power Plant Components 4
Preface 7
Scope 9
Reference publications 10
Definitions 11
General requirements 15
Prerequisites 15
Nature of periodic inspection 15
Operation and maintenance 16
Power plant operation 16
Hazards 16
Radiation exposure 16
Program documents 16
Operating organization’s responsibility 17
Accessibility 18
Access for periodic inspection 18
Existing plants 18
Examination methods, qualification, and procedures 18
Examination methods 18
Examination procedures 19
5.2.10 Volumetric methods 20
5.3 Inspection qualification 21
Examination personnel and qualifications 21
Training and certification 21
Qualification 21
Records 22
Evaluation of examination results 22
Evaluation 22
General acceptance standards 22
Visual examination 22
Surface examination 23
Volumetric examination 23
Dimensional examination 23
Integrative examination 23
Dispositioning 24
General 24
Dispositioning while reactor at power 24
Dispositioning while reactor not at power 24
Dispositioning of minor conditions 25
Repairs and replacements 25
Modifications 26
Recording requirements and reports 26
General requirements 26
Periodic inspection records 27
Periodic inspection reports 27
10.3.1 | Inaugural inspection reports | 27 |
10.3.2 | Periodic inspection reports | 27 |
Periodic inspection regions 28
Systems 28
Systems subject to periodic inspection 28
Extent of systems subject to periodic inspection 28
Grouping of systems and components 28
Consequence and potential of failure assessments 28
Consequence of failure assessment 28
Potential of failure assessment 28
Segment risk categorization 29
Element assessment and selection 29
Change-in-risk assessment 29
Periodic inspection intervals 30
Operating systems 30
Inaugural inspection 31
Dormant systems 31
Periodic and inaugural inspections 31
General requirements 31
General 31
Extent of periodic inspection 31
Periodic inspection for corrosion and erosion 32
Piping 33
General requirements 33
Extent of periodic inspection and sample size 33
Periodic inspection intervals 34
Examination methods and procedures 34
Evaluation of results and dispositioning 35
Records and reports 35
Vessels 35
General requirements 35
Extent of periodic inspection and sample size 35
Periodic inspection intervals 36
Examination methods and procedures 37
Evaluation of results and dispositioning 37
Records and reports 37
Mechanical couplings 37
General requirements 37
Extent of periodic inspection and sample size 37
Inspection intervals 39
Examination methods and procedures 39
Evaluation of results and dispositioning 39
Records and reports 39
Pumps 39
General requirements 39
Extent of inspection and sample size 39
Periodic inspection intervals 40
Examination methods and procedures 41
Evaluation of results and dispositioning 41
Records and reports 41
Valves 41
General requirements 41
Extent of periodic inspection and sample size 41
Periodic inspection intervals 42
Examination methods and procedures 42
Evaluation of results and dispositioning 43
Records and reports 43
Supports 43
General requirements 43
Extent of periodic inspection and sample size 43
Periodic inspection intervals 45
Examination methods and procedures 45
Evaluation of results and dispositioning 45
Records and reports 45
Rotating machinery 45
General requirements 45
Extent of periodic inspection and sample size 46
Periodic inspection intervals 46
Examination methods and procedures 46
Evaluation of results and dispositioning 47
Records and reports 47
Annex A (informative) — Guide for periodic inspection 56
Annex B (normative) — Pre-screening process 59
Annex C (normative) — Consequence of failure assessment 66
Annex D (normative) — Potential of failure assessment 76
Annex E (normative) — Risk categorization, sample size determination, and element selection 152
Annex F (informative) — Rationale for grouping identical elements 155
Annex G (informative) — Guidance on obtaining AHJ acceptance of non-destructive examination personnel certified to an operating organization-specified standard 160
This is the second edition of CSA N285.7, Periodic inspection of CANDU nuclear power plant balance of plant systems and components. It supersedes the previous edition published in 2015.
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 requirements for the periodic inspection of balance of plant systems and components.
The major changes to this edition include the following:
an update to the definitions, specifically the definitions related to “inspection” and “examination”, affecting most clauses;
general harmonization with CSA N285.4-19 and N285.5-18;
revisions to Annexes B, C, and D for clarity of requirements based on application of risk informed rules to select locations for periodic inspection;
improved clarity of pre-screening requirements for raw water systems to account for in-service inspection programs, availability of back-up systems and independent trains, evaluation of external events, and internal flooding probabilistic safety assessments (IFPSA);
clarified timeline for notifying the authority having jurisdiction (AHJ) and obtaining AHJ acceptance of dispositions (Clause 7.8);
clarified periodic inspection requirements for replaced components (Clause 8);
added reporting requirements for confirmatory inspections (Clause 10.3);
clarified requirements to defining a weld examination area that include a reasonable amount of base metal (Clause 13.1.2.3);
clarified examination requirements for mechanical couplings, including removal of requirement to examine threaded ligaments (Clause 13.4.2);
added guidance on approach to evaluation of examination results and use of acceptance standards (Clause A.2); and
added provisions for use of non-destructive examination personnel certified to other than CGSB standards (new Annex G).
The CSA N-Series of Standards provides 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 may impose additional requirements to those specified in this Standard.
Portions of this Standard have been developed using the Risk Informed In-service Inspection (RI-ISI) methodologies and definitions from ASME BPVC Section XI with 2011 Addenda, Code Case N-578-1, ASME RA-Sa-2009 and EPRI RI-ISI TR-112657 Rev B-A. Excerpts are reprinted with permission from The American Society of Mechanical Engineers, Electric Power Research Institute, Inc., and International Atomic Energy Agency.
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.
Notes:
Use of the singular does not exclude the plural (and vice versa) when the sense allows.
Although the intended primary application of this Standard is stated in its Scope, it is important to note that it remains the responsibility of the users of the Standard to judge its suitability for their particular purpose.
This Standard was developed by consensus, which is defined by CSA Policy governing standardization — Code of good practice for standardization as “substantial agreement. Consensus implies much more than a simple majority, but not necessarily unanimity”. It is consistent with this definition that a member may be included in the Technical Committee list and yet not be in full agreement with all clauses of this Standard.
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CSA N285.7:21
1 Scope
1.1
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:
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 periodic inspection in accordance with Clause 3.3.1 a) in CSA N285.4.
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 periodic inspection in accordance with Clause 3.3.1 b) in CSA N285.4.
Compressors, turbines, generators, engines, internal components of vessels and heat exchangers, and hydraulic or pneumatic cylinders are exempt from the periodic 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 examinations and tests performed by other programs such as pipe wall thinning, vessel examinations, equipment reliability, and maintenance programs in addition to RI-ISI. Examinations 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.
1.2
This Standard addresses the following requirements:
failure aspects;
classification of areas subject to periodic inspection;
provision for access;
examination techniques and procedures;
personnel qualifications;
frequency of periodic inspection;
responsibilities;
documentation;