IEC/IEEE 62582-1:2024

• Abstract:

  IEC/IEEE 62582-1:2024 contains requirements for application of the other parts of IEC/IEEE 62582 related to specific methods for condition monitoring in electrical equipment important to safety of nuclear power plants. It also includes requirements which are common to all methods. The procedures defined in IEC/IEEE 62582 are intended for detailed condition monitoring.; IEC/IEEE 62582 specifies condition monitoring methods in sufficient detail to enhance the accuracy and repeatability, and provide standard formats for reporting the results. The methods specified are applicable to electrical equipment containing polymeric materials. Some methods are especially designed for the measurement of condition of a limited range of equipment whilst others can be applied to all types of equipment for which the polymeric parts are accessible.

• Status: Published
• Publication Date: 29-Sep-2024
• ICS: 27.120.20 - Nuclear power plants. Safety
• Technical Committee: SC 45A - Instrumentation, control and electrical power systems of nuclear facilities
• Drafting Committee: WG 10 - TC 45/SC 45A/WG 10
• Current Stage: PPUB - Publication issued
• Start Date: 30-Sep-2024
• Completion Date: 30-Sep-2024

• Revises: IEC/IEEE 62582-1:2011 - Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 1: General
• Effective Date: 05-Sep-2023

Overview

IEC/IEEE 62582-1:2024 - "Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 1: General" is the introductory part of a series that sets requirements and common principles for condition monitoring of electrical equipment important to safety in nuclear power plants. The standard focuses on methods for monitoring electrical equipment containing polymeric materials, providing guidance to improve the accuracy, repeatability and reporting of condition-monitoring results. It establishes how to apply the method-specific parts of the IEC/IEEE 62582 series and defines common elements used across methods (e.g., condition indicators, destructive vs non-destructive approaches, baseline data).

Key topics and requirements

• Scope and purpose: Requirements for application of other parts of IEC/IEEE 62582 and common requirements for all condition-monitoring methods.
• Condition indicators: Chemical, physical, electrical and other indicators, plus visual and tactile observations used to evaluate the state of polymeric parts.
• Applicability: Guidance on which indicators and methods apply to different polymeric materials and equipment types (some methods target a limited range of equipment; others are broadly applicable where polymeric parts are accessible).
• Destructive vs non‑destructive monitoring: Framework for selecting test approaches consistent with equipment qualification and plant operation constraints.
• Integration with equipment qualification and ageing management: Use of condition monitoring to establish and extend qualified life, determine acceleration factors in thermal ageing, and define a “qualified condition” for condition‑based qualification.
• Standardized reporting and reproducibility: Methods are specified to enhance measurement repeatability and to provide consistent report formats for results.
• Technical background topics: Includes discussion of diffusion-limited oxidation (DLO) and theoretical/experimental considerations for ageing profiling.

Practical applications - who uses this standard

• Nuclear power plant operators and maintenance teams implementing condition-based ageing management.
• System evaluators, licensors and qualification engineers applying condition monitoring to support equipment qualification and life extension decisions.
• Asset managers and reliability engineers seeking standardized, reproducible methods for monitoring polymeric components (seals, insulation, cable jackets, etc.).
• Regulators and technical reviewers assessing demonstration of qualified condition and condition‑based qualification.

Related standards and guidance

• IEC/IEEE 60780-323 (condition‑based qualification and qualified condition)
• IEC 61513 and IEC 63046 (I&C and electrical power system requirements for NPPs)
• IAEA TECDOC-1825 and NUREG/CR-6704 (supporting research and benchmarking referenced in the standard)

IEC/IEEE 62582-1:2024 is a foundational document for implementing consistent, repeatable condition monitoring practices for safety‑important electrical equipment in nuclear power plants.

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IEC/IEEE 62582-1 ®
Edition 2.0 2024-09
REDLINE VERSION
INTERNATIONAL
STANDARD
colour
inside
Nuclear power plants – Instrumentation and control important to safety –
Electrical equipment condition monitoring methods –
Part 1: General
INTERNATIONAL
ELECTROTECHNICAL
COMMISSION
ICS 27.120.20 ISBN 978-2-8322-9819-0

– 2 – IEC/IEEE 62582-1:2024 RLV
© IEC/IEEE 2024
CONTENTS
FOREWORD . 3
INTRODUCTION . 2
1 Scope and object . 9
2 Normative references . 9
3 Terms and definitions . 9
4 Condition indicators . 10
4.1 General . 12
4.2 Chemical indicators . 13
4.3 Physical indicators . 13
4.4 Electrical indicators . 13
4.5 MiscellaneousOther indicators . 13
4.6 Visual and tactile observation . 13
5 Applicability of condition indicators to different types of organic polymeric
materials . 14
6 Destructive and non-destructive condition monitoring . 14
7 Application of condition monitoring in equipment qualification and management of
ageing . 14
7.1 General . 14
7.2 Use of condition monitoring in the establishment of qualified life . 15
7.2.1 Establishment of qualified life . 15
7.2.2 Determination of the acceleration factor in accelerated thermal ageing . 15
7.3 Use of condition monitoring in the extension of qualified life . 17
7.4 Use of condition monitoring in the establishment and assessment of
qualified condition . 17
7.5 Use of baseline data . 18
Annex A (informative) Diffusion limited oxidation (DLO) . 19
A.1 General . 19
A.2 Importance of DLO in thermal ageing . 19
A.3 Methods for profiling DLO effects . 20
A.4 Theoretical approach to DLO . 20
Bibliography . 22

Figure 1 – Example of an Arrhenius diagram . 16
Figure 2 – Influence of activation energy on qualified life, determined from artificial
accelerated thermal ageing for 42 days at 110 °C, followed by a simulated design
basis event . 16
Figure 3 – Illustration of the principle of condition-based qualification . 18
Figure A.1 – Indenter modulus profiles for EPDM seal aged at 170 °C (left) and
110 °C (right) [1] . 20

© IEC/IEEE 2024
INTERNATIONAL ELECTROTECHNICAL COMMISSION
____________
NUCLEAR POWER PLANTS –
INSTRUMENTATION AND CONTROL IMPORTANT TO SAFETY –
ELECTRICAL EQUIPMENT CONDITION MONITORING METHODS –

Part 1: General
FOREWORD
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8) Attention is drawn to the normative references cited in this publication. Use of the referenced publications is
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– 4 – IEC/IEEE 62582-1:2024 RLV
© IEC/IEEE 2024
9) Attention is drawn to the possibility that implementation of this IEC/IEEE Publication may require use of material
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© IEC/IEEE 2024
IEC/IEEE 62582-1 was prepared by subcommittee 45A: Instrumentation and control of nuclear
facilities, of IEC technical committee 45: Nuclear instrumentation, in cooperation with Nuclear
Power Engineering Committee of the IEEE Power & Energy Society , under the IEC/IEEE Dual
Logo Agreement between IEC and IEEE. It is an International Standard.
This document is published as an IEC/IEEE Dual Logo standard.
This second edition cancels and replaces the first edition published in 2011. This edition
constitutes a technical revision.
This edition includes the following significant technical changes with respect to the previous
edition:
a) Integration of experience from the work with IAEA-TECDOC-1825:2017 “Benchmark
analysis for condition monitoring test techniques of low voltage cables in nuclear power
plants. Final results of a Coordinated Research Project”.
b) Referral to IEC/IEEE 60780-323 instead of IEC 60780 and IEEE 323.
The text of this International Standard is based on the following IEC documents:
Draft Report on voting
45A/1510/CDV 45A/1537/RVC
Full information on the voting for its approval can be found in the report on voting indicated in
the above table.
The language used for the development of this International Standard is English.
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available at www.iec.ch/members_experts/refdocs. The main document types developed by IEC
are described in greater detail at www.iec.ch/publications/.
A list of all parts of IEC/IEEE 62582 series, under the general title Nuclear power plants –
Instrumentation and control important to safety – Electrical equipment condition monitoring
methods, can be found on the IEC website.
The IEC Technical Committee and IEEE Technical Committee have decided that the contents
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• revised.
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___________
A list of IEEE participants can be found at the following URL: http://standards.ieee.org/downloads/62582-1/62582-
1-2011/62582-1-2011_wg-participants.pdf.

– 6 – IEC/IEEE 62582-1:2024 RLV
© IEC/IEEE 2024
INTRODUCTION
a) Technical background, main issues and organisation of this document
This part of this IEC/IEEE 62582 series focuses on methods for condition monitoring for
management of ageing of electrical equipment installed in nuclear power plants and for
application of the concept of qualified condition.
IEC/IEEE 6258-1 is the first part of the IEC/IEEE 62582 series of standards, containing
background and guidelines for the application of methods for condition monitoring of electrical
equipment important to safety of nuclear power plants. The detailed descriptions of the methods
are given in the other parts, one part for each method. This document also includes some
elements which are common to all methods.
IEC/IEEE 62582 series is issued with a joint logo which makes it applicable to the management
of ageing of electrical equipment qualified to IEEE as well as IEC Standards.
Condition monitoring is a developing field and more methods will be added to the
IEC/IEEE 62582 series when they are considered widely applied and a good reproducibility of
the condition monitoring method can be demonstrated.
Historically, IEEE Std 323-2003 introduced the concept and role that conditionbased
qualification could be used in equipment qualification as an adjunct to qualified life. In
equipment qualification, the condition of the equipment for which acceptable performance was
demonstrated is the qualified condition. The qualified condition is the condition of equipment,
prior to the start of a design basis event, for which the equipment was demonstrated to meet
the design requirements for the specified service conditions.
IEC/IEEE 60780-323 defined condition-based qualification which is an adjunct to type testing.
The qualified condition is established by condition indicator(s) prior to the start of accident
conditions for which the equipment was demonstrated to meet the design requirements for the
specified service conditions. IEC/IEEE 60780-323 defined condition indicator.
Significant research has been performed on condition monitoring techniques and the use of
these techniques in equipment qualification as noted in NUREG/CR-6704, Vol. 2
(BNL -NUREG-52610) [1], JNES-SS-0903, 2009 [2] and IAEA-TECDOC-1825:2017 [3].
It is intended that this IEC/IEEE document be used by operators of nuclear power plants,
systems evaluators and by licensors.
b) Situation of the current standard in the structure of the IEC SC 45A standard series
IEC/IEEE 62582-1 is the third level IEC SC 45A document tackling the issue of application of
condition monitoring in equipment qualification and management of ageing of electrical I&C
equipment in nuclear power plants.
IEC/IEEE 62582-1 is to be read in association with IEC/IEEE 60780-323, which provides
general requirements for qualification of I&C systems and equipment that are used to perform
functions important to safety in NPPs and nuclear facilities.
For more details on the structure of the IEC SC 45A standard series, see item d) of this
introduction.
___________
Numbers in square brackets refer to the Bibliography.

© IEC/IEEE 2024
c) Recommendations and limitations regarding the application of this document
It is important to note that this document establishes no additional functional requirements for
safety systems.
This document discusses the general measurement technique for current condition monitoring
methods and is not meant to cover any specific technologies.
d) Description of the structure of the IEC SC 45A standard series and relationships with
other IEC documents and other bodies documents (IAEA, ISO)
The top-level document of the IEC SC 45A standard series is IEC 61513. It provides general
requirements for I&C systems and equipment that are used to perform functions important to
safety in NPPs. IEC 61513 structures the IEC SC 45A standard series.
IEC 61513 refers directly to other IEC SC 45A standards for general topics related to
categorization of functions and classification of systems, qualification, separation of systems,
defence against common cause failure, software aspects of computer-based systems, hardware
aspects of computer-based systems, and control room design. The standards referenced
directly at this second level should be considered together with IEC 61513 as a consistent
document set.
The IEC SC 45A standard series comprises a hierarchy of four levels. The top-level documents
of the IEC SC 45A standard series are IEC 61513 and IEC 63046.
IEC 61513 provides general requirements for instrumentation and control (I&C) systems and
equipment that are used to perform functions important to safety in nuclear power plants
(NPPs). IEC 63046 provides general requirements for electrical power systems of NPPs; it
covers power supply systems including the supply systems of the I&C systems.
IEC 61513 and IEC 63046 are to be considered in conjunction and at the same level. IEC 61513
and IEC 63046 structure the IEC SC 45A standard series and shape a complete framework
establishing general requirements for instrumentation, control and electrical power systems for
nuclear power plants.
IEC 61513 and IEC 63046 refer directly to other IEC SC 45A standards for general
requirements for specific topics, such as categorization of functions and classification of
systems, qualification, separation, defence against common cause failure, control room design,
electromagnetic compatibility, human factors engineering, cybersecurity, software and
hardware aspects for programmable digital systems, coordination of safety and security
requirements and management of ageing. The standards referenced directly at this second level
should be considered together with IEC 61513 and IEC 63046 as a consistent document set.
At a third level, IEC SC 45A standards not directly referenced by IEC 61513 or by IEC 63046
are standards related to specific requirements for specific equipment, technical methods, or
specific activities. Usually these documents, which make reference to second-level documents
for general topics requirements, can be used on their own.
A fourth level extending the IEC SC 45 standard series, corresponds to the Technical Reports
which are not normative.
IEC 61513 has adopted a presentation format similar to the basic safety publication IEC 61508
with an overall safety life-cycle framework and a system life-cycle framework and provides an
interpretation of the general requirements of IEC 61508-1, IEC 61508-2 and IEC 61508-4, for
the nuclear application sector. Compliance with IEC 61513 will facilitate consistency with the
requirements of IEC 61508 as they have been interpreted for the nuclear industry. In this
framework IEC 60880 and IEC 62138 correspond to IEC 61508-3 for the nuclear application
sector.
– 8 – IEC/IEEE 62582-1:2024 RLV
© IEC/IEEE 2024
IEC 61513 refers to ISO as well as to IAEA 50-C-QA (now replaced by IAEA GS-R-3) for topics
related to quality assurance (QA).
The IEC SC 45A standards series consistently implements and details the principles and basic
safety aspects provided in the IAEA code on the safety of NPPs and in the IAEA safety series,
in particular the Requirements NS-R-1, establishing safety requirements related to the design
of Nuclear Power Plants, and the Safety Guide NS-G-1.3 dealing with instrumentation and
control systems important to safety in Nuclear Power Plants. The terminology and definitions
used by SC 45A standards are consistent with those used by the IAEA.
The IEC SC 45A standards series consistently implements and details the safety and security
principles and basic aspects provided in the relevant IAEA safety standards and in the relevant
documents of the IAEA nuclear security series (NSS). In particular this includes the IAEA
requirements SSR-2/1 , establishing safety requirements related to the design of nuclear power
plants (NPPs), the IAEA safety guide SSG-30 dealing with the safety classification of structures,
systems and components in NPPs, the IAEA safety guide SSG-39 dealing with the design of
instrumentation and control systems for NPPs, the IAEA safety guide SSG-34 dealing with the
design of electrical power systems for NPPs, the IAEA safety guide SSG-51 dealing with human
factors engineering in the design of NPPs and the implementing guide NSS42-G for computer
security at nuclear facilities. The safety and security terminology and definitions used by the
SC 45A standards are consistent with those used by the IAEA.
IEC 61513 and IEC 63046 have adopted a presentation format similar to the basic safety
publication IEC 61508 with an overall life-cycle framework and a system life-cycle framework.
Regarding nuclear safety, IEC 61513 and IEC 63046 provide the interpretation of the general
requirements of IEC 61508-1, IEC 61508-2 and IEC 61508-4, for the nuclear application sector.
In this framework, IEC 60880, IEC 62138 and IEC 62566 correspond to IEC 61508-3 for the
nuclear application sector.
IEC 61513 and IEC 63046 refer to ISO 9001 as well as to IAEA GSR part 2 and IAEA GS-G-3.1
and IAEA GS-G-3.5 for topics related to quality assurance (QA).
At level 2, regarding nuclear security, IEC 62645 is the entry document for the IEC/SC 45A
security standards. It builds upon the valid high level principles and main concepts of the
generic security standards, in particular ISO/IEC 27001 and ISO/IEC 27002; it adapts them and
completes them to fit the nuclear context and coordinates with the IEC 62443 series. At level 2,
IEC 60964 is the entry document for the IEC SC 45A control rooms standards, IEC 63351 is the
entry document for the human factors engineering standards and IEC 62342 is the entry
document for the ageing management standards.
NOTE 1 It is assumed that for the design of I&C systems in NPPs that implement conventional safety functions (e.g.
to address worker safety, asset protection, chemical hazards, process energy hazards) international or national
standards would be applied.
NOTE 2 IEC TR 63400 provides a more comprehensive description of the overall structure of the IEC SC 45A
standards series and of its relationship with other standards bodies and standards.

© IEC/IEEE 2024
NUCLEAR POWER PLANTS –
INSTRUMENTATION AND CONTROL IMPORTANT TO SAFETY –
ELECTRICAL EQUIPMENT CONDITION MONITORING METHODS –

Part 1: General
1 Scope and object
This part of the IEC/IEEE 62582 series contains requirements for application of the other parts
of IEC/IEEE 62582 related to specific methods for condition monitoring in electrical equipment
important to safety of nuclear power plants. It also includes requirements which are common to
all methods. The procedures defined in IEC/IEEE 62582 are intended for detailed condition
monitoring.
IEC/IEEE 62582 specifies condition monitoring methods in sufficient detail to enhance the
accuracy and repeatability, and provide standard formats for reporting the results. The methods
specified are applicable to electrical equipment containing organic or polymeric materials. Some
methods are especially designed for the measurement of condition of a limited range of
equipment whilst others can be applied to all types of equipment for which the organic polymeric
parts are accessible.
Although the scope of IEC/IEEE 62582 is limited to the application of instrumentation and
control systems important to safety, the condition monitoring methods may can also be
applicable to other components which include organic or polymeric materials.
The different parts of IEC/IEEE 62582 are measurement standards, primarily for use in the
management of ageing in initial qualification and after installation. For the technical background
of condition monitoring methods, reference is made to other IEC standards, e.g.
IEC 60544-5 [1]. Information on the role of condition monitoring in qualification of electrical
equipment important to safety is found in IEC/IEEE Std 60780-323. General information on
management of ageing can be found in IEC 62342 [5] and IEEE 1205 [6].
NOTE The procedures defined in the IEC/IEEE 62582 are intended for detailed condition monitoring. A simplified
version of the procedures may can be appropriate for preliminary assessment of the need for detailed measurements.
2 Normative references
The following documents are referred to in the text in such a way that some or all of their content
constitutes requirements of this document. For dated references, only the edition cited applies.
For undated references, the latest edition of the referenced document (including any
amendments) applies.
IEEE Std 323:2003, IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power
Generating Stations
IEC/IEEE 60780-323, Nuclear facilities – Electrical equipment important to safety –
Qualification
IEC/IEEE 62582 (all parts), Nuclear power plants – Instrumentation and control important to
safety – Electrical equipment condition monitoring methods

– 10 – IEC/IEEE 62582-1:2024 RLV
© IEC/IEEE 2024
3 Terms and definitions
For the purposes of this document, the following terms and definitions apply.
ISO and IEC maintain terminology databases for use in standardization at the following
addresses:
• IEC Electropedia: available at https://www.electropedia.org/
• ISO Online browsing platform: available at https://www.iso.org/obp
• IEEE Standards Dictionary Online: available at http://dictionary.ieee.org
3.1
condition indicator
characteristic of a structure, system or component that can be observed, measured or trended
to infer or directly indicate the current and future ability of the structure, system or component
to function within acceptance criteria
[SOURCE: IAEA Nuclear Safety and Security Glossary, 20072022 (Interim) Edition]
3.2
condition monitoring
continuous or periodic tests, inspections, measurement or trending of the performance or
physical characteristics of structures, systems and components to indicate current or future
performance and the potential for failure
[SOURCE: IAEA Safety Glossary, 20072018 Edition, modified – note removed.]
3.3
equipment qualification
generation and maintenance of evidence to ensure that equipment will operate on demand,
under specified service conditions, to meet system performance requirements
[SOURCE: IAEA Nuclear Safety and Security Glossary, 20072022 (Interim) Edition, modified –
notes not included.]
3.4
item important to safety
item that is part of a safety group and/or whose malfunction or failure could lead to radiation
exposure of the site personnel or members of the public
[IAEA Safety Glossary, 2007 Edition]
equipment important to safety
equipment that is part of a safety group and/or whose malfunction or failure could lead to undue
radiation exposure of the site personnel or members of the public. Equipment including:
• those structures, systems and components that prevent anticipated operational occurrences
from leading to accident conditions;
• those features that are provided to mitigate the consequences of malfunction or failure of
structures, systems and components.
Note 1 to entry:
a) For usage consistent with IEC 61226 [11], equipment important to safety are as follows:
1) all I&C equipment performing Category A to Category C functions (in accordance with the IEC 61226 [11]
categorisation scheme);
2) all electrical equipment necessary to ensure emergency energy supply to this equipment in case of a loss of
normal power supply;
© IEC/IEEE 2024
3) all electrical equipment necessary to ensure ultimate energy supply in case of total loss of on-site power (if
selected as design extension condition to be mitigated).
b) For usage consistent with other IEEE documents and a Class 1E categorization; for equipment important to
safety, qualification is essential to the following:
1) electric equipment and systems that are essential to emergency reactor shutdown, containment isolation,
reactor core cooling, and containment and reactor heat removal, or;
2) electric equipment that are otherwise essential in preventing significant release of radioactive material to the
environment.
Note 2 to entry: Users of this document are advised that Class 1E is a functional term. Equipment and systems are
to be classified Class 1E only if they fulfil the functions listed in the definition. Identification of systems or equipment
as Class 1E based on anything other than their function is an improper use of the term and should be avoided.
[SOURCE: IEC/IEEE 60780-323:2016, 3.12]
3.5
tactile observation
qualitative assessment of a polymer’s condition through the physical examination of the exterior
of a material as observed by a knowledgeable person who, via experience or training, can
deduce degradation based on the hardness or softness of the material by lightly bending or
pressing a fingernail into the surface and via their knowledge and experience, or training can
deduce degradation based on the observed condition to assess if quantitative assessments are
warranted
3.6
visual observation
qualitative assessment of a polymer’s condition through the visible examination of the exterior
of material as observed by a knowledgeable person who, via experience or training, can deduce
degradation based on the observed condition to assess if quantitative assessments are
warranted
3.7
qualified condition
condition of an equipment, prior to the start of a design basis event, for which the equipment
was demonstrated to meet the design requirements for the specified service conditions. This
could include certain post accident cooling and monitoring systems that are expected to remain
operational
[SOURCE: IEC/IEEE 60780-323:2016, 3.19]
3.8
qualified life
period for which a structure, system or component has been demonstrated, through testing,
analysis or experience, to be capable of functioning within acceptance criteria during specific
operating conditions while retaining the ability to perform its safety functions in accident
conditions for a design basis accident or a design basis earthquake
[SOURCE: IAEA Nuclear Safety and Security Glossary, 20072022 (Interim) Edition]
3.9
service life
period from initial operation to final withdrawal from service of a structure, system or component
[SOURCE: IAEA Nuclear Safety and Security Glossary, 20072022 (Interim) Edition]
3.10
design basis events
postulated events used in the design to establish the acceptable performance requirements for
the structures, systems, and components

– 12 – IEC/IEEE 62582-1:2024 RLV
© IEC/IEEE 2024
[SOURCE: IEEE Standards Dictionary Online]
3.11
service conditions
actual physical states or influences during the service life of equipment, including normal
operating conditions, abnormal operating conditions, design basis event conditions and
conditions following a design basis event and design extension conditions
[SOURCE: IAEA Safety Glossary, 2007, modified, addition of “design extension conditions” and
use of term “equipment instead of “structure, system or component”]
3.12
ageing
general process in which characteristics of a system or component gradually change with time
or use
[SOURCE: IEC/IEEE 60780-323:2016, 3.2]
3.13
accelerated ageing
method of equipment testing in which the ageing associated with longer term service conditions
is simulated in a short time
Note 1 to entry: Usually, accelerated ageing attempts to simulate natural ageing effects by application of stressors
representing pre-service and service conditions, but with differences in intensity, duration and the manner of
application.
[SOURCE: IAEA Nuclear Safety and Security Glossary, 2022 (interim) Edition]
4 Condition indicators
4.1 General
Condition monitoring should only be applied if there is a known relationship between the ageing
degradation of the component monitored and the degradation of the equipment’s safety
function. This relationship should be established during equipment qualification. The
relationship should take into account any diffusion limited rate effects that occur during
accelerated ageing with high acceleration factors.
The condition indicator shall be measurable, change monotonically with time, be linked to the
functional degradation of the qualified equipment, and have a consistent trend from unaged
through the limit of the qualified pre-accident condition, and applied according to
IEC/IEEE 60780-323.
This trend should be established during the pre-ageing part of the equipment qualification.
When establishing the trend of condition indicators with ageing time, it is important that
acceleration factors (both thermal and radiation) are kept as small as practical. See Annex A
for additional information on diffusion limited oxidation (DLO).
Condition monitoring programs rely on measurable indicators that provide insight into the
overall degradation of the materials. To perform measurements of the condition of naturally
aged components, a sample shall either be taken destructively or the measurements shall be
made on the material in the field in a non-destructive way. The latter methods are preferred
since they allow the material to be studied without interrupting operation; however, it is often
difficult to perform these types of measurements directly in the field with the required degree of
repeatability and accuracy.
© IEC/IEEE 2024
In organic polymeric materials, ageing occurs that may can adversely impact the important
safety function through a range of chemical reactions, including chain scission and cross-
linking, which alter the polymeric structure. For condition monitoring programs, it becomes
imperative to find methods that, either directly or indirectly, follow the progress of these
reactions. A large number of methods exist to perform this task, which makes it difficult to
provide an overview of each individual technique. Instead, this document will focus on general
groups of methods. The overall description of these groups is provided in 4.2 through 4.6.
4.2 Chemical indicators
As mentioned above, the degradation mechanism for organic polymeric materials follows from
a series of chemical reactions in which the chemical structure of the polymer is altered. The
progressive change in the chemistry of the material provides an opportunity to monitor the
degradation throughout its ageing. Numerous techniques exist to perform this task, some which
monitor the polymer chain degradation itself and others which monitor side reactions which are
related to the degradation.
4.3 Physical indicators
Another key family of indicators includes techniques which monitor the material’s physical
properties. The degradation of organic polymeric materials manifests itself in changes to these
physical properties (i.e. tensile strength, elongation, and hardness). By measuring these
physical characteristics, it is possible to create a correlation with the aged condition of the
material.
4.4 Electrical indicators
A third category of techniques involves measuring electrical properties of the materials. Many
of these techniques were developed for polymeric materials used in electrical insulation. Within
this family there are two basic subsets of methods. The first subset involves measuring the
dielectric properties of the materials.
A second subset of methods monitors the electrical response of systems under normal
operation. In these cases, a signal is passed through the electrical system and any changes
from baseline are detected. These changes could be signs of degradation, whether through
ageing or through physical damage.
ndicators
4.5 MiscellaneousOther i
As new technologies are developed and implemented, it becomes necessary to develop
condition monitoring methods to keep pace. As such, some methods are developed specifically
for certain types of materials.
4.6 Visual and tactile observation
Visual and tactile testing methods are non-intrusive testing techniques for accessible
components. The purpose of this physical inspection method is to identify cracks,
discolouration, visible contamination of the components, the presence of chemicals or oils, and
other local damage such as swelling or deformation, to provide a qualitative assessment of the
condition of for example a cable’s jacket material that could indicate problems with the
insulation.
Visual and tactile methods may be used as a screening tool for ageing assessment and indicate
that further evaluation is necessary by applying other methods in accordance with the different
parts of IEC/IEEE 62582.
– 14 – IEC/IEEE 62582-1:2024 RLV
© IEC/IEEE 2024
5 Applicability of condition indicators to different types of organic polymeric
materials
There is currently no single condition monitoring method which is suitable for all organic or
polymeric materials. A basic requirement for inclusion in a part of the IEC/IEEE 62582 series is
that the condition indicators are sensitive to the effects of ageing. An important characteristic
of a useful condition indicator is that it shows a trend that changes monotonically with
degradation and can be correlated with the safety related performance. An indicator that does
not change for a long time and then suddenly undergoes drastic changes is not useful for
prognostic applications. This can be the case with mechanical condition monitoring on semi-
crystalline materials, e.g. cross-linked polyethylene and thermosetting resins, dependent on the
formulation.
Information on the applicability of various condition indicators to different polymeric materials
used in instrument and control equipment in nuclear power plants can be found in NUREG/CR-
7000 and in IAEA-TECDOC-1188, see Bibliography IAEA-TECDOC-1188 [12], IAEA-TECDOC-
1825 [3] and in EPRI 1022969 [14].
6 Destructive and non-destructive condition monitoring
A condition monitoring method may can be considered destructive or non-destructive,
depending on whether the measurement or the sampling of material used for the measurement
will affect operability or future ageing. Non-destructive use of condition monitoring is preferable
in field measurements but with presently available methods it is limited to a few types of
equipment, mainly cables, where the parts of the equipment of interest are accessible in the
field. In other cases, deposited samples or samples which can be replaced are needed
necessary to allow condition monitoring.
If deposited samples are available or where components can be replaced, a broader range of
condition monitoring methods can be considered, including destructive methods. In this case,
condition monitoring can be applied to all types of equipment where the ageing material –
normally organic polymeric materials used for electrical insulation, sealing, etc. can be
accessed.
7 Application of condition monitoring in equipment qualification and
management of ageing
7.1 General
Condition monitoring as part of qualification
...

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INTERNATIONAL
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Nuclear power plants – Instrumentation and control important to safety –
Electrical equipment condition monitoring methods –
Part 1: General
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IEC/IEEE 62582-1 ®
Edition 2.0 2024-09
INTERNATIONAL
STANDARD
Nuclear power plants – Instrumentation and control important to safety –

Electrical equipment condition monitoring methods –

Part 1: General
INTERNATIONAL
ELECTROTECHNICAL
COMMISSION
ICS 27.120.20 ISBN 978-2-8322-9581-6

– 2 – IEC/IEEE 62582-1:2024 © IEC/IEEE 2024
CONTENTS
FOREWORD . 3
INTRODUCTION . 5
1 Scope . 8
2 Normative references . 8
3 Terms and definitions . 9
4 Condition indicators . 11
4.1 General . 11
4.2 Chemical indicators . 12
4.3 Physical indicators . 12
4.4 Electrical indicators . 12
4.5 Other indicators . 12
4.6 Visual and tactile observation . 12
5 Applicability of condition indicators to different types of polymeric materials . 12
6 Destructive and non-destructive condition monitoring . 13
7 Application of condition monitoring in equipment qualification and management of
ageing . 13
7.1 General . 13
7.2 Use of condition monitoring in the establishment of qualified life . 13
7.2.1 Establishment of qualified life . 13
7.2.2 Determination of the acceleration factor in accelerated thermal ageing . 14
7.3 Use of condition monitoring in the extension of qualified life . 15
7.4 Use of condition monitoring in the establishment and assessment of
qualified condition . 15
7.5 Use of baseline data . 17
Annex A (informative) Diffusion limited oxidation (DLO) . 18
A.1 General . 18
A.2 Importance of DLO in thermal ageing . 18
A.3 Methods for profiling DLO effects . 19
A.4 Theoretical approach to DLO . 19
Bibliography . 21

Figure 1 – Example of an Arrhenius diagram . 14
Figure 2 – Influence of activation energy on qualified life, determined from accelerated
thermal ageing for 42 days at 110 °C, followed by a simulated design basis event . 15
Figure 3 – Illustration of the principle of condition-based qualification . 16
Figure A.1 – Indenter modulus profiles for EPDM seal aged at 170 °C (left) and
110 °C (right) [1] . 19

INTERNATIONAL ELECTROTECHNICAL COMMISSION
____________
NUCLEAR POWER PLANTS –
INSTRUMENTATION AND CONTROL IMPORTANT TO SAFETY –
ELECTRICAL EQUIPMENT CONDITION MONITORING METHODS –

Part 1: General
FOREWORD
1) The International Electrotechnical Commission (IEC) is a worldwide organization for standardization comprising
all national electrotechnical committees (IEC National Committees). The object of IEC is to promote international
co-operation on all questions concerning standardization in the electrical and electronic fields. To this end and
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IEEE Standards documents are developed within IEEE Societies and Standards Coordinating Committees of the
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IEC collaborates closely with IEEE in accordance with conditions determined by agreement between the two
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2) The formal decisions of IEC on technical matters express, as nearly as possible, an international consensus of
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3) IEC/IEEE Publications have the form of recommendations for international use and are accepted by IEC National
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5) IEC and IEEE do not provide any attestation of conformity. Independent certification bodies provide conformity
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6) All users should ensure that they have the latest edition of this publication.
7) No liability shall attach to IEC or IEEE or their directors, employees, servants or agents including individual
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8) Attention is drawn to the normative references cited in this publication. Use of the referenced publications is
indispensable for the correct application of this publication.

– 4 – IEC/IEEE 62582-1:2024 © IEC/IEEE 2024
9) Attention is drawn to the possibility that implementation of this IEC/IEEE Publication may require use of material
covered by patent rights. By publication of this standard, no position is taken with respect to the existence or
validity of any patent rights in connection therewith. IEC or IEEE shall not be held responsible for identifying
Essential Patent Claims for which a license may be required, for conducting inquiries into the legal validity or
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submission of a Letter of Assurance, if any, or in any licensing agreements are reasonable or non-discriminatory.
Users of this standard are expressly advised that determination of the validity of any patent rights, and the risk
of infringement of such rights, is entirely their own responsibility.
IEC/IEEE 62582-1 was prepared by subcommittee 45A: Instrumentation and control of nuclear
facilities, of IEC technical committee 45: Nuclear instrumentation, in cooperation with Nuclear
Power Engineering Committee of the IEEE Power & Energy Society , under the IEC/IEEE Dual
Logo Agreement between IEC and IEEE. It is an International Standard.
This document is published as an IEC/IEEE Dual Logo standard.
This second edition cancels and replaces the first edition published in 2011. This edition
constitutes a technical revision.
This edition includes the following significant technical changes with respect to the previous
edition:
a) Integration of experience from the work with IAEA-TECDOC-1825:2017 “Benchmark
analysis for condition monitoring test techniques of low voltage cables in nuclear power
plants. Final results of a Coordinated Research Project”.
b) Referral to IEC/IEEE 60780-323 instead of IEC 60780 and IEEE 323.
The text of this International Standard is based on the following IEC documents:
Draft Report on voting
45A/1510/CDV 45A/1537/RVC
Full information on the voting for its approval can be found in the report on voting indicated in
the above table.
The language used for the development of this International Standard is English.
This document was drafted in accordance with the rules given in the ISO/IEC Directives, Part 2,
available at www.iec.ch/members_experts/refdocs. The main document types developed by IEC
are described in greater detail at www.iec.ch/publications/.
A list of all parts of IEC/IEEE 62582 series, under the general title Nuclear power plants –
Instrumentation and control important to safety – Electrical equipment condition monitoring
methods, can be found on the IEC website.
The IEC Technical Committee and IEEE Technical Committee have decided that the contents
of this document will remain unchanged until the stability date indicated on the IEC website
under webstore.iec.ch in the data related to the specific document. At this date, the document
will be
• reconfirmed,
• withdrawn, or
• revised.
___________
A list of IEEE participants can be found at the following URL: http://standards.ieee.org/downloads/62582-1/62582-
1-2011/62582-1-2011_wg-participants.pdf.

INTRODUCTION
a) Technical background, main issues and organisation of this document
This part of this IEC/IEEE 62582 series focuses on methods for condition monitoring for
management of ageing of electrical equipment installed in nuclear power plants and for
application of the concept of qualified condition.
IEC/IEEE 6258-1 is the first part of the IEC/IEEE 62582 series of standards, containing
background and guidelines for the application of methods for condition monitoring of electrical
equipment important to safety of nuclear power plants. The detailed descriptions of the methods
are given in the other parts, one part for each method. This document also includes some
elements which are common to all methods.
IEC/IEEE 62582 series is issued with a joint logo which makes it applicable to the management
of ageing of electrical equipment qualified to IEEE as well as IEC Standards.
Condition monitoring is a developing field and more methods will be added to the
IEC/IEEE 62582 series when they are considered widely applied and a good reproducibility of
the condition monitoring method can be demonstrated.
IEC/IEEE 60780-323 defined condition-based qualification which is an adjunct to type testing.
The qualified condition is established by condition indicator(s) prior to the start of accident
conditions for which the equipment was demonstrated to meet the design requirements for the
specified service conditions. IEC/IEEE 60780-323 defined condition indicator.
Significant research has been performed on condition monitoring techniques and the use of
these techniques in equipment qualification as noted in NUREG/CR-6704, Vol. 2
(BNL -NUREG-52610) [1], JNES-SS-0903, 2009 [2] and IAEA-TECDOC-1825:2017 [3].
It is intended that this IEC/IEEE document be used by operators of nuclear power plants,
systems evaluators and by licensors.
b) Situation of the current standard in the structure of the IEC SC 45A standard series
IEC/IEEE 62582-1 is the third level IEC SC 45A document tackling the issue of application of
condition monitoring in equipment qualification and management of ageing of electrical I&C
equipment in nuclear power plants.
IEC/IEEE 62582-1 is to be read in association with IEC/IEEE 60780-323, which provides
general requirements for qualification of I&C systems and equipment that are used to perform
functions important to safety in NPPs and nuclear facilities.
For more details on the structure of the IEC SC 45A standard series, see item d) of this
introduction.
c) Recommendations and limitations regarding the application of this document
It is important to note that this document establishes no additional functional requirements for
safety systems.
This document discusses the general measurement technique for current condition monitoring
methods and is not meant to cover any specific technologies.
___________
Numbers in square brackets refer to the Bibliography.

– 6 – IEC/IEEE 62582-1:2024 © IEC/IEEE 2024
d) Description of the structure of the IEC SC 45A standard series and relationships with
other IEC documents and other bodies documents (IAEA, ISO)
The IEC SC 45A standard series comprises a hierarchy of four levels. The top-level documents
of the IEC SC 45A standard series are IEC 61513 and IEC 63046.
IEC 61513 provides general requirements for instrumentation and control (I&C) systems and
equipment that are used to perform functions important to safety in nuclear power plants
(NPPs). IEC 63046 provides general requirements for electrical power systems of NPPs; it
covers power supply systems including the supply systems of the I&C systems.
IEC 61513 and IEC 63046 are to be considered in conjunction and at the same level. IEC 61513
and IEC 63046 structure the IEC SC 45A standard series and shape a complete framework
establishing general requirements for instrumentation, control and electrical power systems for
nuclear power plants.
IEC 61513 and IEC 63046 refer directly to other IEC SC 45A standards for general
requirements for specific topics, such as categorization of functions and classification of
systems, qualification, separation, defence against common cause failure, control room design,
electromagnetic compatibility, human factors engineering, cybersecurity, software and
hardware aspects for programmable digital systems, coordination of safety and security
requirements and management of ageing. The standards referenced directly at this second level
should be considered together with IEC 61513 and IEC 63046 as a consistent document set.
At a third level, IEC SC 45A standards not directly referenced by IEC 61513 or by IEC 63046
are standards related to specific requirements for specific equipment, technical methods, or
activities. Usually these documents, which make reference to second-level documents for
general requirements, can be used on their own.
A fourth level extending the IEC SC 45 standard series, corresponds to the Technical Reports
which are not normative.
The IEC SC 45A standards series consistently implements and details the safety and security
principles and basic aspects provided in the relevant IAEA safety standards and in the relevant
documents of the IAEA nuclear security series (NSS). In particular this includes the IAEA
requirements SSR-2/1 , establishing safety requirements related to the design of nuclear power
plants (NPPs), the IAEA safety guide SSG-30 dealing with the safety classification of structures,
systems and components in NPPs, the IAEA safety guide SSG-39 dealing with the design of
instrumentation and control systems for NPPs, the IAEA safety guide SSG-34 dealing with the
design of electrical power systems for NPPs, the IAEA safety guide SSG-51 dealing with human
factors engineering in the design of NPPs and the implementing guide NSS42-G for computer
security at nuclear facilities. The safety and security terminology and definitions used by the
SC 45A standards are consistent with those used by the IAEA.
IEC 61513 and IEC 63046 have adopted a presentation format similar to the basic safety
publication IEC 61508 with an overall life-cycle framework and a system life-cycle framework.
Regarding nuclear safety, IEC 61513 and IEC 63046 provide the interpretation of the general
requirements of IEC 61508-1, IEC 61508-2 and IEC 61508-4, for the nuclear application sector.
In this framework, IEC 60880, IEC 62138 and IEC 62566 correspond to IEC 61508-3 for the
nuclear application sector.
IEC 61513 and IEC 63046 refer to ISO 9001 as well as to IAEA GSR part 2 and IAEA GS-G-3.1
and IAEA GS-G-3.5 for topics related to quality assurance (QA).

At level 2, regarding nuclear security, IEC 62645 is the entry document for the IEC/SC 45A
security standards. It builds upon the valid high level principles and main concepts of the
generic security standards, in particular ISO/IEC 27001 and ISO/IEC 27002; it adapts them and
completes them to fit the nuclear context and coordinates with the IEC 62443 series. At level 2,
IEC 60964 is the entry document for the IEC SC 45A control rooms standards, IEC 63351 is the
entry document for the human factors engineering standards and IEC 62342 is the entry
document for the ageing management standards.
NOTE 1 It is assumed that for the design of I&C systems in NPPs that implement conventional safety functions (e.g.
to address worker safety, asset protection, chemical hazards, process energy hazards) international or national
standards would be applied.
NOTE 2 IEC TR 63400 provides a more comprehensive description of the overall structure of the IEC SC 45A
standards series and of its relationship with other standards bodies and standards.

– 8 – IEC/IEEE 62582-1:2024 © IEC/IEEE 2024
NUCLEAR POWER PLANTS –
INSTRUMENTATION AND CONTROL IMPORTANT TO SAFETY –
ELECTRICAL EQUIPMENT CONDITION MONITORING METHODS –

Part 1: General
1 Scope
This part of the IEC/IEEE 62582 series contains requirements for application of the other parts
of IEC/IEEE 62582 related to specific methods for condition monitoring in electrical equipment
important to safety of nuclear power plants. It also includes requirements which are common to
all methods. The procedures defined in IEC/IEEE 62582 are intended for detailed condition
monitoring.
IEC/IEEE 62582 specifies condition monitoring methods in sufficient detail to enhance the
accuracy and repeatability, and provide standard formats for reporting the results. The methods
specified are applicable to electrical equipment containing polymeric materials. Some methods
are especially designed for the measurement of condition of a limited range of equipment whilst
others can be applied to all types of equipment for which the polymeric parts are accessible.
Although the scope of IEC/IEEE 62582 is limited to the application of instrumentation and
control systems important to safety, the condition monitoring methods can also be applicable
to other components which include polymeric materials.
The different parts of IEC/IEEE 62582 are measurement standards, primarily for use in the
management of ageing in initial qualification and after installation. For the technical background
of condition monitoring methods, reference is made to other IEC standards, e.g.
IEC 60544-5 [1]. Information on the role of condition monitoring in qualification of electrical
equipment important to safety is found in IEC/IEEE 60780-323. General information on
management of ageing can be found in IEC 62342 [5] and IEEE 1205 [6].
NOTE A simplified version of the procedures can be appropriate for preliminary assessment of the need for detailed
measurements.
2 Normative references
The following documents are referred to in the text in such a way that some or all of their content
constitutes requirements of this document. For dated references, only the edition cited applies.
For undated references, the latest edition of the referenced document (including any
amendments) applies.
IEC/IEEE 60780-323, Nuclear facilities – Electrical equipment important to safety –
Qualification
IEC/IEEE 62582 (all parts), Nuclear power plants – Instrumentation and control important to
safety – Electrical equipment condition monitoring methods

3 Terms and definitions
For the purposes of this document, the following terms and definitions apply.
ISO and IEC maintain terminology databases for use in standardization at the following
addresses:
• IEC Electropedia: available at https://www.electropedia.org/
• ISO Online browsing platform: available at https://www.iso.org/obp
• IEEE Standards Dictionary Online: available at http://dictionary.ieee.org
3.1
condition indicator
characteristic of a structure, system or component that can be observed, measured or trended
to infer or directly indicate the current and future ability of the structure, system or component
to function within acceptance criteria
[SOURCE: IAEA Nuclear Safety and Security Glossary, 2022 (Interim) Edition]
3.2
condition monitoring
continuous or periodic tests, inspections, measurement or trending of the performance or
physical characteristics of structures, systems and components to indicate current or future
performance and the potential for failure
[SOURCE: IAEA Safety Glossary, 2018 Edition, modified – note removed.]
3.3
equipment qualification
generation and maintenance of evidence to ensure that equipment will operate on demand,
under specified service conditions, to meet system performance requirements
[SOURCE: IAEA Nuclear Safety and Security Glossary, 2022 (Interim) Edition, modified – notes
not included.]
3.4
equipment important to safety
equipment th
...

IEC/IEEE 62582-1 ®
Edition 2.0 2024-09
NORME
INTERNATIONALE
Centrales nucléaires - Instrumentation et contrôle commande importants pour la
sûreté - Méthodes de surveillance de l'état des matériels électriques -
Partie 1: Généralités
ICS 27.120.20  ISBN 978-2-8327-1423-2

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– 22 – IEC/IEEE 62582-1:2024 © IEC/IEEE 2024
SOMMAIRE
AVANT-PROPOS . 23
INTRODUCTION . 25
1 Domaine d'application . 28
2 Références normatives . 28
3 Termes et définitions. 29
4 Indicateurs d'état . 31
4.1 Généralités . 31
4.2 Indicateurs chimiques . 32
4.3 Indicateurs physiques . 32
4.4 Indicateurs électriques . 32
4.5 Autres indicateurs . 32
4.6 Observation visuelle et tactile . 33
5 Adéquation des indicateurs d'état pour différents types de matériaux polymères . 33
6 Méthodes de surveillance d'état destructives et non destructives . 33
7 Utilisation de la surveillance d'état dans le cadre de la qualification d'équipement
et de la gestion du vieillissement . 34
7.1 Généralités . 34
7.2 Utilisation de la surveillance d'état pour la détermination de la durée de vie
qualifiée. 34
7.2.1 Détermination de la durée de vie qualifiée . 34
7.2.2 Détermination du facteur d'accélération durant le vieillissement
thermique accéléré. 34
7.3 Utilisation de la surveillance d'état pour l'extension de la durée de vie
qualifiée. 36
7.4 Utilisation de la surveillance d'état pour la détermination et l'évaluation de
l'état qualifié . 37
7.5 Utilisation de données de référence . 38
Annexe A (informative) Oxydation limitée par la diffusion (DLO) . 39
A.1 Généralités . 39
A.2 Importance de la DLO dans le vieillissement thermique . 39
A.3 Méthodes de caractérisation des effets de la DLO . 40
A.4 Approche théorique de la DLO . 41
Bibliographie . 42

Figure 1 – Exemple de diagramme d'Arrhenius . 35
Figure 2 – Influence de l'énergie d'activation sur la durée de vie qualifiée, déterminée
après une phase de vieillissement thermique accéléré de 42 jours à 110 °C, suivie de
la simulation d'un événement de dimensionnement . 36
Figure 3 – Représentation du principe de qualification par surveillance d'état . 37
Figure A.1 – Profils du module d'indentation pour un joint en EPDM soumis à un
vieillissement thermique à 170 °C (à gauche) et à 110 °C (à droite)[1] . 40

COMMISSION ÉLECTROTECHNIQUE INTERNATIONALE
____________
CENTRALES NUCLÉAIRES – INSTRUMENTATION ET
CONTRÔLE-COMMANDE IMPORTANTS POUR LA SÛRETÉ –
MÉTHODES DE SURVEILLANCE DE L'ÉTAT
DES MATÉRIELS ÉLECTRIQUES –
Partie 1: Généralités
AVANT-PROPOS
1) La Commission Électrotechnique Internationale (IEC) est une organisation mondiale de normalisation composée
de l'ensemble des comités électrotechniques nationaux (Comités nationaux de l'IEC). L'IEC a pour objet de
favoriser la coopération internationale pour toutes les questions de normalisation dans les domaines de
l'électricité et de l'électronique. À cet effet, l'IEC – entre autres activités – publie des Normes internationales,
des Spécifications techniques, des Rapports techniques, des Spécifications accessibles au public (PAS) et des
Guides (ci-après dénommés "Publication(s) de l'IEC"). Leur élaboration est confiée à des comités d'études, aux
travaux desquels tout Comité national intéressé par le sujet traité peut participer. Les organisations
internationales, gouvernementales et non gouvernementales, en liaison avec l'IEC, participent également aux
travaux.
Les normes de l'IEEE sont élaborées par les Sociétés de l'IEEE, ainsi que par les Comités de coordination des
normes du Conseil de normalisation de l'IEEE Standards Association (IEEE-SA). Ces normes sont
l'aboutissement d'un consensus, approuvé par l'American National Standards Institute (ANSI), qui rassemble des
bénévoles représentant différents points de vue et intérêts. Les participants bénévoles ne sont pas
nécessairement membres de l'IEEE et leur intervention n'est pas rétribuée. Si l'IEEE administre le déroulement
de cette procédure et définit les règles destinées à favoriser l'équité du consensus, l'IEEE lui-même n'évalue pas,
ne teste pas et ne vérifie pas l'exactitude de toute information contenue dans ses normes. L'utilisation de normes
de l'IEEE est entièrement volontaire. Les documents de l'IEEE sont disponibles à des fins d'utilisation, à condition
d'être assortis d'avis importants et de clauses de non-responsabilité (voir
http://standards.ieee.org/IPR/disclaimers.html pour plus d'informations).
L'IEC travaille en étroite collaboration avec l'IEEE, selon des conditions fixées par accord entre les deux
organisations. Cette Norme internationale double logo a été élaborée conjointement par l'IEC et l'IEEE en vertu
de cet accord.
2) Les décisions officielles de l'IEC concernant les questions techniques représentent, dans la mesure du possible,
un accord international sur les sujets étudiés, étant donné que les Comités nationaux de l'IEC intéressés sont
représentés dans chaque comité d'études. Une fois le consensus établi entre les Sociétés de l'IEEE et les
Comités de coordination des normes, les décisions officielles de l'IEEE relatives aux questions techniques sont
déterminées en fonction du vote exprimé par un groupe à la composition équilibrée, composé de parties
intéressées qui manifestent leur intérêt pour la révision des normes proposées. L'approbation finale de la norme
de l'IEEE est soumise au Conseil de normalisation de l'IEEE Standards Association (IEEE SA).
3) Les Publications IEC/IEEE se présentent sous la forme de recommandations internationales et sont agréées
comme telles par les Comités nationaux de l'IEC/Sociétés de l'IEEE. Tous les efforts raisonnables sont entrepris
afin de s'assurer de l'exactitude du contenu technique des Publications IEC/IEEE; l'IEC ou l'IEEE ne peuvent pas
être tenus responsables de l'éventuelle mauvaise utilisation ou interprétation qui en est faite par un quelconque
utilisateur final.
4) Dans le but d'encourager l'uniformité internationale, les Comités nationaux de l'IEC s'engagent, dans toute la
mesure possible, à appliquer de façon transparente les Publications de l'IEC (y compris les Publications
IEC/IEEE) dans leurs publications nationales et régionales. Toutes divergences entre toutes
Publications IEC/IEEE et toutes publications nationales ou régionales correspondantes doivent être indiquées en
termes clairs dans ces dernières.
5) L'IEC et l'IEEE eux-mêmes ne fournissent aucune attestation de conformité. Des organismes de certification
indépendants fournissent des services d'évaluation de conformité et, dans certains secteurs, accèdent aux
marques de conformité de l'IEC. L'IEC et l'IEEE ne sont responsables d'aucun des services effectués par les
organismes de certification indépendants.
6) Tous les utilisateurs doivent s'assurer qu'ils sont en possession de la dernière édition de cette publication.
7) Aucune responsabilité ne doit être imputée à l'IEC ou à l'IEEE, à ses administrateurs, employés, auxiliaires ou
mandataires, y compris ses experts particuliers et les membres de ses comités d'études et des Comités nationaux
de l'IEC, ou les bénévoles des Sociétés de l'IEEE et des Comités de coordination des normes du Conseil de
normalisation de l'IEEE Standards Association (IEEE-SA), pour tout préjudice causé en cas de dommages
corporels et matériels, ou de tout autre dommage de quelque nature que ce soit, directe ou indirecte, ou pour
supporter les coûts (y compris les frais de justice) et les dépenses découlant de la publication ou de l'utilisation
de cette Publication IEC/IEEE ou toute autre publication de l'IEC ou de l'IEEE, ou au crédit qui lui est accordé.

– 24 – IEC/IEEE 62582-1:2024 © IEC/IEEE 2024
8) L'attention est attirée sur les références normatives citées dans cette publication. L'utilisation de publications
référencées est obligatoire pour une application correcte de la présente publication.
9) L'attention est attirée sur le fait que la mise en application de cette Publication IEC/IEEE peut requérir l'utilisation
de matériels protégés par des droits de brevet. En publiant cette norme, aucun parti n'est pris concernant
l'existence ou la validité de droits de brevet y afférents. Ni l'IEC ni l'IEEE ne peuvent être tenus d'identifier les
revendications de brevet essentielles pour lesquelles une autorisation peut s'avérer nécessaire, d'effectuer des
recherches sur la validité juridique ou l'étendue des revendications des brevets, ou de déterminer le caractère
raisonnable ou non discriminatoire des termes ou conditions d'autorisation énoncés dans le cadre d'un Certificat
d'assurance, lorsque la demande d'un tel certificat a été formulée, ou contenus dans tout accord d'autorisation.
Les utilisateurs de cette norme sont expressément informés du fait que la détermination de la validité de tous
droits de propriété industrielle, ainsi que les risques qu'implique la violation de ces droits, relèvent entièrement
de leur seule responsabilité.
L'IEC/IEEE 62582-1 a été établie par le sous-comité 45A: Systèmes d'instrumentation, de
contrôle-commande et d'alimentation électrique des installations nucléaires, du comité
d'études 45 de l'IEC: Instrumentation nucléaire, en coopération avec le "Nuclear Power
Engineering Committee" de l'IEEE Power & Energy Society , selon l'accord double
logo IEC/IEEE établi entre l'IEC et l'IEEE. Il s'agit d'une Norme internationale.
Le présent document est une norme double logo IEC/IEEE.
Cette deuxième édition annule et remplace la première édition parue en 2011. Cette édition
constitue une révision technique.
Cette édition inclut les modifications techniques majeures suivantes par rapport à l'édition
précédente:
a) intégration du retour d'expérience issu des travaux sur la publication
IAEA-TECDOC-1825:2017 "Benchmark analysis for condition monitoring test techniques of
low voltage cables in nuclear power plants. Final results of a Coordinated Research Project";
b) référence à l'IEC/IEEE 60780-323 en lieu et place de l'IEC 60780 et l'IEEE 323.
La présente version bilingue (2026-08) correspond à la version anglaise monolingue publiée en
2024-09.
La version française de cette norme n'a pas été soumise au vote.
La langue employée pour l'élaboration de cette Norme internationale est l'anglais.
Ce document a été rédigé selon les Directives ISO/IEC, Partie 2, il a été développé selon les
Directives ISO/IEC, Partie 1 et les Directives ISO/IEC, Supplément IEC, disponibles sous
www.iec.ch/members_experts/refdocs. Les principaux types de documents développés par
l'IEC sont décrits plus en détail sous www.iec.ch/publications.
Une liste de toutes les parties de la série IEC/IEEE 62582, publiées sous le titre général
Centrales nucléaires – Instrumentation et contrôle-commande importants pour la sûreté –
Méthodes de surveillance de l'état des matériels électriques, se trouve sur le site web de l'IEC.
Le comité d'études de l'IEC et le comité d'études de l'IEEE ont décidé que le contenu de ce
document ne sera pas modifié avant la date de stabilité indiquée sur le site web de l'IEC sous
webstore.iec.ch dans les données relatives au document recherché. À cette date, le document
sera
• reconduit,
• supprimé, ou
• révisé.
___________
Une liste des participants IEEE est disponible à l'adresse:
http://standards.ieee.org/downloads/62582-1/62582-1-2011/62582-1-2011_wg-participants.pdf.

INTRODUCTION
a) Contexte technique, questions principales et structure du présent document
La présente partie de la série de normes IEC/IEEE 62582 traite des méthodes utilisées pour la
surveillance de l'état dans le cadre de la gestion du vieillissement des matériels électriques
installés dans les centrales nucléaires, ainsi que l'application du concept d'état qualifié.
L'IEC/IEEE 6258-1 est la première partie de la série de normes IEC/IEEE 65282. Elle contient
des informations fondamentales et des lignes directrices pour l'application des méthodes de
surveillance de l'état des matériels électriques importants pour la sûreté utilisés dans les
centrales nucléaires. Les descriptions détaillées des méthodes particulières sont fournies dans
les autres normes de la série, couvrant chacune une méthode spécifique. Le présent document
comprend aussi certains éléments qui sont communs à toutes les méthodes.
La série IEC/IEEE 62582 est publiée en double logo, ce qui la rend applicable pour la gestion
du vieillissement des matériels électriques qualifiés tant dans le cadre des normes IEEE que
dans celui des normes IEC.
La surveillance de l'état des matériels est un domaine en développement et des méthodes
supplémentaires seront ajoutées à la série IEC/IEEE 62582, lorsque ces méthodes de
surveillance seront considérées comme largement utilisées et qu'une bonne reproductibilité de
celles-ci pourra être démontrée.
L'IEC/IEEE 60780-323 définit le terme "qualification par surveillance d'état" qui est un
complément aux essais de type. L'état qualifié est établi par un ou plusieurs indicateurs d'état
avant le début des conditions accidentelles pour lesquelles la conformité du matériel aux
exigences de conception a été évaluée dans le cadre des conditions de service spécifiées.
L'IEC/IEEE 60780-323 définit le terme "indicateur d'état".
Des recherches importantes ont été réalisées sur les techniques de surveillance d'état et sur
l'utilisation de ces techniques dans le cadre de la qualification d'équipement, comme cela est
indiqué dans les documents NUREG/CR-6704, Vol. 2 (BNL -NUREG-52610) [1],
JNES-SS-0903, 2009 [2] et IAEA-TECDOC-1825:2017 [3].
Le présent document IEC/IEEE est destiné à être utilisé par les exploitants de centrales
nucléaires, les évaluateurs de systèmes et les concédants de licence.
b) Positionnement de la présente norme dans la structure de la collection de normes du
SC 45A de l'IEC
L'IEC/IEEE 62582-1 est le document de troisième niveau du SC 45A de l'IEC qui traite de la
question de l'application de la surveillance de l'état des matériels dans le cadre de la
qualification d'équipement et de la gestion du vieillissement des équipements électriques d'I&C
utilisés dans les centrales nucléaires.
L'IEC/IEEE 62582-1 doit être lue conjointement avec l'IEC/IEEE 60780-323, qui fournit les
exigences générales applicables pour la qualification des matériels et systèmes d'I&C qui sont
utilisés pour réaliser les fonctions importantes pour la sûreté dans les centrales nucléaires ainsi
que dans les installations nucléaires.
Pour plus d'informations sur la structure de la collection de normes du SC 45A de l'IEC, voir le
point d) de la présente introduction.
___________
Les chiffres entre crochets renvoient à la Bibliographie.

– 26 – IEC/IEEE 62582-1:2024 © IEC/IEEE 2024
c) Recommandations et limites relatives à l'application du présent document
Il est important de noter que le présent document n'établit pas d'exigences fonctionnelles
supplémentaires pour les systèmes de sûreté.
Le présent document traite de la technique de mesure générale pour les méthodes actuelles
de surveillance de l'état et n'a pas pour objectif de traiter de technologies particulières.
d) Description de la structure de la collection de normes du SC 45A de l'IEC et des
relations avec d'autres documents de l'IEC, et avec les documents d'autres
organisations (AIEA, ISO)
La collection de normes du SC 45A de l'IEC est structurée en quatre niveaux. Les documents
de niveau supérieur dans la collection de normes du SC 45A de l'IEC sont les normes
IEC 61513 et IEC 63046.
L'IEC 61513 établit les exigences générales relatives aux matériels et systèmes d'I&C utilisés
pour réaliser des fonctions importantes pour la sûreté des centrales nucléaires. L'IEC 63046
traite des exigences générales relatives aux systèmes d'alimentation électrique des centrales
nucléaires; elle couvre les systèmes d'alimentation électrique y compris les alimentations des
systèmes d'I&C.
Les normes IEC 61513 et IEC 63046 doivent être prises en compte ensemble et au même
niveau. Les normes IEC 61513 et IEC 63046 structurent la collection de normes du SC 45A de
l'IEC et forment un cadre complet qui établit les exigences générales relatives aux systèmes
d'I&C et d'alimentation électrique des centrales nucléaires de puissance.
Les normes IEC 61513 et IEC 63046 font directement référence à d'autres normes du SC 45A
de l'IEC qui établissent les exigences générales relatives à des sujets spécifiques, tels que la
catégorisation des fonctions et le classement des systèmes, la qualification, la séparation des
systèmes, la défense contre les défaillances de cause commune, la conception des salles de
commande, la compatibilité électromagnétique, l'ingénierie des facteurs humains, la
cybersécurité, les aspects logiciels et matériels relatifs aux systèmes numériques
programmables, la coordination des exigences de sûreté et de sécurité, et la gestion du
vieillissement. Il convient de considérer que ces normes, auxquelles il est fait référence à ce
deuxième niveau, forment, avec les normes IEC 61513 et IEC 63046, un ensemble
documentaire cohérent.
Au troisième niveau, les normes du SC 45A de l'IEC, qui ne sont pas citées en référence
directement par les normes IEC 61513 ou IEC 63046, traitent des exigences particulières de
matériels particuliers, de méthodes techniques ou d'activités. Généralement, ces documents,
qui font référence aux documents de deuxième niveau pour les exigences générales, peuvent
être utilisés de façon isolée.
Un quatrième niveau qui est une extension de la collection de normes du SC 45 de l'IEC
correspond aux rapports techniques qui ne sont pas des documents normatifs.

Les normes de la collection du SC 45A de l'IEC mettent en œuvre de manière systématique et
décrivent les principes de sûreté et de sécurité et les aspects fondamentaux donnés dans les
normes de sûreté de l'AIEA pertinentes pour les centrales nucléaires, ainsi que dans les
documents pertinents de la collection de l'AIEA pour la sécurité nucléaire (NSS). Cela concerne
en particulier le document d'exigences SSR-2/1 qui établit les exigences de sûreté relatives à
la conception des centrales nucléaires, le guide de sûreté SSG-30 qui traite du classement de
sûreté des structures, systèmes et composants des centrales nucléaires, le guide de
sûreté SSG-39 qui traite de la conception des systèmes d'instrumentation et de
contrôle-commande des centrales nucléaires, le guide de sûreté SSG-34 qui traite de la
conception des systèmes d'alimentation électrique des centrales nucléaires, le guide de
sûreté SSG-51 qui traite de l'ingénierie des facteurs humains lors de la conception des
centrales nucléaires et le guide de mise en œuvre NSS42-G qui traite de la sécurité
informatique pour les installations nucléaires. La terminologie et les définitions utilisées pour la
sûreté et la sécurité dans les normes établies par le SC 45A sont conformes à celles utilisées
par l'AIEA.
Les normes IEC 61513 et IEC 63046 ont adopté une présentation similaire à celle de la
publication fondamentale de sécurité IEC 61508, avec un cycle de vie d'ensemble et un cycle
de vie des systèmes. En ce qui concerne la sûreté nucléaire, les normes IEC 61513 et
IEC 63046 donnent l'interprétation des exigences générales de l'IEC 61508-1, de l'IEC 61508-2
et de l'IEC 61508-4 pour le secteur nucléaire. Dans ce cadre, l'IEC 60880, l'IEC 62138 et
l'IEC 62566 correspondent à la partie 3 de l'IEC 61508 pour le secteur nucléaire.
Les normes IEC 61513 et IEC 63046 font référence à la norme ISO 9001, ainsi qu'aux
documents AIEA GSR partie 2 et AIEA GS-G-3.1 et AIEA GS-G-3.5 pour ce qui concerne
l'assurance qualité (QA).
Au deuxième niveau, en ce qui concerne la sûreté nucléaire, la norme IEC 62645 est le
document chapeau des normes du SC 45A de l'IEC portant sur la cybersécurité. Elle se fonde
sur les principes pertinents de haut niveau et sur les concepts principaux des normes
génériques de sûreté, en particulier l'ISO/IEC 27001 et l'ISO/IEC 27002; elle les adapte et les
complète pour qu'ils deviennent pertinents pour le secteur nucléaire; elle est coordonnée
étroitement avec la série de normes IEC 62443. Au deuxième niveau, la norme IEC 60964 est
le document chapeau des normes du SC 45A de l'IEC applicables aux salles de commande, la
norme IEC 63351 est le document chapeau des normes du SC 45A de l'IEC applicables à
l'ingénierie des facteurs humains et la norme IEC 62342 est le document chapeau des normes
du SC 45A de l'IEC applicables à la gestion du vieillissement.
NOTE 1 On considère que pour la conception des systèmes d'I&C qui mettent en œuvre des fonctions de sûreté
conventionnelle dans les centrales nucléaires (par exemple, pour assurer la sécurité des travailleurs, la protection
des biens, la prévention contre les risques chimiques, la prévention contre les risques liés au procédé énergétique),
des Normes nationales ou internationales sont appliquées.
NOTE 2 L'IEC TR 63400 donne une description plus complète de la structure globale de la collection de normes du
SC 45A de l'IEC, ainsi que ses relations avec les autres organismes de normalisation et les autres normes.

– 28 – IEC/IEEE 62582-1:2024 © IEC/IEEE 2024
CENTRALES NUCLÉAIRES – INSTRUMENTATION ET
CONTRÔLE-COMMANDE IMPORTANTS POUR LA SÛRETÉ –
MÉTHODES DE SURVEILLANCE DE L'ÉTAT
DES MATÉRIELS ÉLECTRIQUES –
Partie 1: Généralités
1 Domaine d'application
La présente partie de la série IEC/IEEE 62582 contient les exigences pour l'application des
autres parties de l'IEC/IEEE 62582 correspondant aux méthodes de surveillance de l'état des
matériels électriques importants pour la sûreté utilisés dans les centrales nucléaires. Elle
contient aussi des exigences qui sont communes à toutes les méthodes. Les procédures
définies dans l'IEC/IEEE 62582 ont pour objectif la surveillance détaillée de l'état des matériels.
L'IEC/IEEE 62582 spécifie suffisamment en détail les méthodes de surveillance de l'état des
matériels pour améliorer l'exactitude et la répétabilité, et indique les formats normalisés à
utiliser pour rendre compte des résultats. Les méthodes spécifiées s'appliquent aux matériels
électriques qui contiennent des matériaux polymères. Certaines méthodes ont été conçues
spécifiquement pour mesurer l'état d'une gamme de matériels limitée alors que d'autres peuvent
être appliquées à tous les types de matériels pour lesquels les parties en polymère sont
accessibles.
Même si le domaine d'application de l'IEC/IEEE 62582 se limite à l'application de celles-ci aux
systèmes d'instrumentation et de contrôle-commande importants pour la sûreté, ces méthodes
de surveillance de l'état des matériels peuvent également s'appliquer à d'autres composants
qui contiennent des matériaux polymères.
Les différentes parties de l'IEC/IEEE 62582 sont des normes de mesure, qui sont
principalement destinées à être utilisées pour la gestion du vieillissement dans le cadre de la
qualification initiale et après installation. Concernant le contexte technique associé aux
méthodes de surveillance de l'état des matériels, il est fait référence à d'autres normes IEC
standards, par exemple l'IEC 60544-5 [1]. L'IEC/IEEE 60780-323 fournit des informations
concernant le rôle de la surveillance de l'état dans la qualification des matériels électriques
importants pour la sûreté. Des informations à caractère général sur la gestion du vieillissement
peuvent être trouvées dans l'IEC 62342 [5] et l'IEEE 1205 [6].
NOTE Une version simplifiée des procédures peut être appropriée pour une évaluation préliminaire de la nécessité
de réaliser des mesurages détaillés.
2 Références normatives
Les documents suivants sont cités dans le texte de sorte qu'ils constituent, pour tout ou partie
de leur contenu, des exigences du présent document. Pour les références datées, seule
l'édition citée s'applique. Pour les références non datées, la dernière édition du document de
référence s'applique (y compris les éventuels amendements).
IEC/IEEE 60780-323, Installations nucléaires – Équipements électriques importants pour la
sûreté – Qualification
IEC/IEEE 62582 (toutes les parties), Centrales nucléaires – Instrumentation et
contrôle-commande importants pour la sûreté – Méthodes de surveillance de l'état des
matériels électriques
3 Termes et définitions
Pour les besoins du présent document, les termes et définitions suivants s'appliquent.
L'ISO et l'IEC tiennent à jour des bases de données terminologiques destinées à être utilisées
en normalisation, consultables aux adresses suivantes:
• IEC Electropedia: disponible à l'adresse https://www.electropedia.org/
• ISO Online browsing platform: disponible à l'adresse https://www.iso.org/obp
• IEEE Standards Dictionary Online: disponible à l'adresse http://dictionary.ieee.org
3.1
indicateur d'état
caractéristique d'une structure, d'un système ou d'un composant qui peut être observée,
mesurée ou dont on peut suivre l'évolution pour déduire ou directement indiquer la capacité
présente et future de la structure, du système ou du composant de fonctionner conformément
aux critères d'acceptation
[SOURCE: Glossaire de la sûreté et de la sécurité nucléaires de l'AIEA, édition (provisoire) de
2022]
3.2
surveillance de l'état
tests, inspections, mesures ou suivis de l'évolution de la performance ou des caractéristiques
physiques des structures, systèmes et des composants, de façon continue ou périodique, visant
à indiquer la performance actuelle et future et le risque de défaillance
[SOURCE: Glossaire de sûreté de l'AIEA, édition 2018, modifiée – La note a été supprimée.]
3.3
qualification d'équipement
production et conservation des preuves que l'équipement fonctionnera sur commande, dans les
conditions de service spécifiées, pour répondre aux impératifs de performance du système
[SOURCE: Glossaire de la sûreté et de la sécurité nucléaires de l'AIEA, édition (provisoire) de
2022, modifiée – Des notes ont été fournies.]
3.4
équipement important pour la sûreté
équipement faisant partie d'un groupe de sûreté et/ou dont le mauvais fonctionnement ou la
défaillance pourrait entraîner une exposition indue à des rayonnements du personnel du site
ou de personnes du public. Les équipements importants pour la sûreté comprennent:
• les équipements qui empêchent les incidents de fonctionnement prévus d'aboutir à des
conditions accidentelles;
• les dispositifs prévus pour atténuer les conséquences d'un mauvais fonctionnement ou
d'une défaillance de structures, systèmes ou composants.
Note 1 à l'article:
a) Dans le cadre d'une utilisation de la présente norme en cohérence avec l'IEC 61226 [11], les équipements
importants pour la sûreté sont les suivants:
1) tous les équipements d'I&C réalisant des fonctions de catégories A à C (conformément au schéma de
catégorisation de l'IEC 61226 [11]),
2) tous les équipements électriques nécessaires pour assurer l'alimentation d'urgence en énergie de ces
équipements en cas de perte de l'alimentation de puissance normale,
3) tous les équipements électriques nécessaires pour l'alimentation en énergie ultime en cas d
...