Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 1: General

See the scope of IEC/IEEE 62582-1:2024. Adoption is to be implemented without modification.

Kernkraftwerke - Leittechnik mit sicherheitstechnischer Bedeutung - Zustandsüberwachung elektrischer Geräte - Teil 1: Allgemeines

Centrales nucléaires - Instrumentation et contrôle-commande important pour la sûreté - Méthodes de surveillance de l’état des matériels électriques - Partie 1: Généralités

Jedrske elektrarne - Merilna in nadzorna oprema za zagotavljanje varnosti - Metode za spremljanje stanja električne opreme - 1. del: Splošno

General Information

Status
Not Published
Public Enquiry End Date
31-Dec-2025
Technical Committee
Current Stage
4020 - Public enquire (PE) (Adopted Project)
Start Date
16-Oct-2025
Due Date
05-Mar-2026
Draft
oSIST prEN IEC/IEEE 62582-1:2025
English language
24 pages
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Standards Content (Sample)


SLOVENSKI STANDARD
01-december-2025
Jedrske elektrarne - Merilna in nadzorna oprema za zagotavljanje varnosti -
Metode za spremljanje stanja električne opreme - 1. del: Splošno
Nuclear power plants - Instrumentation and control important to safety - Electrical
equipment condition monitoring methods - Part 1: General
Kernkraftwerke - Leittechnik mit sicherheitstechnischer Bedeutung -
Zustandsüberwachung elektrischer Geräte - Teil 1: Allgemeines
Centrales nucléaires - Instrumentation et contrôle-commande important pour la sûreté -
Méthodes de surveillance de l’état des matériels électriques - Partie 1: Généralités
Ta slovenski standard je istoveten z: prEN IEC/IEEE 62582-1:2025
ICS:
27.120.20 Jedrske elektrarne. Varnost Nuclear power plants. Safety
2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega standarda ni dovoljeno.

EUROPEAN STANDARD DRAFT
prEN IEC/IEEE 62582-1
NORME EUROPÉENNE
EUROPÄISCHE NORM
October 2025
ICS 27.120.20 -
English Version
Nuclear power plants - Instrumentation and control important to
safety - Electrical equipment condition monitoring methods - Part
1: General
(IEC/IEEE 62582-1:2024)
Centrales nucléaires - Instrumentation et contrôle- Kernkraftwerke - Leittechnik mit sicherheitstechnischer
commande important pour la sûreté - Méthodes de Bedeutung - Zustandsüberwachung elektrischer Geräte -
surveillance de l'état des matériels électriques - Partie 1: Teil 1: Allgemeines
Généralités (IEC/IEEE 62582-1:2024)
(IEC/IEEE 62582-1:2024)
This draft European Standard is submitted to CENELEC members for enquiry.
Deadline for CENELEC: 2026-01-02.

The text of this draft consists of the text of IEC/IEEE 62582-1:2024.

If this draft becomes a European Standard, CENELEC members are bound to comply with the CEN/CENELEC Internal Regulations which
stipulate the conditions for giving this European Standard the status of a national standard without any alteration.

This draft European Standard was established by CENELEC in three official versions (English, French, German).
A version in any other language made by translation under the responsibility of a CENELEC member into its own language and notified to
the CEN-CENELEC Management Centre has the same status as the official versions.

CENELEC members are the national electrotechnical committees of Austria, Belgium, Bulgaria, Croatia, Cyprus, the Czech Republic,
Denmark, Estonia, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Latvia, Lithuania, Luxembourg, Malta, the
Netherlands, Norway, Poland, Portugal, Republic of North Macedonia, Romania, Serbia, Slovakia, Slovenia, Spain, Sweden, Switzerland,
Türkiye and the United Kingdom.

Recipients of this draft are invited to submit, with their comments, notification of any relevant patent rights of which they are aware and to
provide supporting documentation.

Warning : This document is not a European Standard. It is distributed for review and comments. It is subject to change without notice and
shall not be referred to as a European Standard.

European Committee for Electrotechnical Standardization
Comité Européen de Normalisation Electrotechnique
Europäisches Komitee für Elektrotechnische Normung
CEN-CENELEC Management Centre: Rue de la Science 23, B-1040 Brussels
© 2025 CENELEC All rights of exploitation in any form and by any means reserved worldwide for CENELEC Members.
Project: 82116 Ref. No. prEN IEC/IEEE 62582-1:2025 E

European foreword
This document (prEN IEC/IEEE 62582-1:2025) consists of the text of document IEC/IEEE 62582-
1:2024, prepared by IEC/SC 45A “Instrumentation, control and electrical power systems of nuclear
facilities” of IEC/TC 45 "Nuclear instrumentation".
This document is currently submitted to the Enquiry.
The following dates are proposed:
• latest date by which the existence of this document (doa) dav + 6 months
has to be announced at national level
• latest date by which this document has to be (dop) dav + 12 months
implemented at national level by publication of an
identical national standard or by endorsement
• latest date by which the national standards (dow) dav + 36 months
conflicting with this document have to be withdrawn (to be confirmed or
modified when voting)
As stated in the nuclear safety directive 2009/71/EURATOM, Chapter 1, Article 2, item 2, Member States
are not prevented from taking more stringent safety measures in the subject-matter covered by the
Directive, in compliance with Community law.
In a similar manner, this document does not prevent Member States from taking more stringent nuclear
safety and/or security measures in the subject-matter covered by this document.
Annex ZA
(normative)
Normative references to international publications
with their corresponding European publications
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.
NOTE 1 Where an International Publication has been modified by common modifications, indicated by (mod),
the relevant EN/HD applies.
NOTE 2 Up-to-date information on the latest versions of the European Standards listed in this annex is available
here: www.cencenelec.eu.
Publication Year Title EN/HD Year
IEC/IEEE 60780- - Nuclear facilities - Electrical equipment EN 60780-323 -
323 important to safety - Qualification
IEC/IEEE 62582 series Nuclear power plants - Instrumentation and - -
control important to safety - Electrical
equipment condition monitoring methods

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

IEC/IEEE 62582-1:2024 © IEC/IEEE 2024 – 3 –
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
in addition to other activities, IEC publishes International Standards, Technical Specifications, Technical Reports,
Publicly Available Specifications (PAS) and Guides (hereafter referred to as "IEC document(s)"). Their
preparation is entrusted to technical committees; any IEC National Committee interested in the subject dealt with
may participate in this preparatory work. International, governmental and non-governmental organizations liaising
with the IEC also participate in this preparation.
IEEE Standards documents are developed within IEEE Societies and Standards Coordinating Committees of the
IEEE Standards Association (IEEE SA) Standards Board. IEEE develops its standards through a consensus
development process, approved by the American National Standards Institute, which brings together volunteers
representing varied viewpoints and interests to achieve the final product. Volunteers are not necessarily members
of IEEE and serve without compensation. While IEEE administers the process and establishes rules to promote
fairness in the consensus development process, IEEE does not independently evaluate, test, or verify the
accuracy of any of the information contained in its standards. Use of IEEE Standards documents is wholly
voluntary. IEEE documents are made available for use subject to important notices and legal disclaimers (see
https://standards.ieee.org/ipr/disclaimers.html for more information).
IEC collaborates closely with IEEE in accordance with conditions determined by agreement between the two
organizations. This Dual Logo International Standard was jointly developed by the IEC and IEEE under the terms
of that agreement.
2) The formal decisions of IEC on technical matters express, as nearly as possible, an international consensus of
opinion on the relevant subjects since each technical committee has representation from all interested IEC
National Committees. The formal decisions of IEEE on technical matters, once consensus within IEEE Societies
and Standards Coordinating Committees has been reached, is determined by a balanced ballot of materially
interested parties who indicate interest in reviewing the proposed standard. Final approval of the IEEE standards
document is given by the IEEE Standards Association (IEEE SA) Standards Board.
3) IEC/IEEE Publications have the form of recommendations for international use and are accepted by IEC National
Committees/IEEE Societies in that sense. While all reasonable efforts are made to ensure that the technical
content of IEC/IEEE Publications is accurate, IEC or IEEE cannot be held responsible for the way in which they
are used or for any misinterpretation by any end user.
4) In order to promote international uniformity, IEC National Committees undertake to apply IEC Publications
(including IEC/IEEE Publications) transparently to the maximum extent possible in their national and regional
publications. Any divergence between any IEC/IEEE Publication and the corresponding national or regional
publication shall be clearly indicated in the latter.
5) IEC and IEEE do not provide any attestation of conformity. Independent certification bodies provide conformity
assessment services and, in some areas, access to IEC marks of conformity. IEC and IEEE are not responsible
for any services carried out by independent certification bodies.
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
experts and members of technical committees and IEC National Committees, or volunteers of IEEE Societies and
the Standards Coordinating Committees of the IEEE Standards Association (IEEE SA) Standards Board, for any
personal injury, property damage or other damage of any nature whatsoever, whether direct or indirect, or for
costs (including legal fees) and expenses arising out of the publication, use of, or reliance upon, this IEC/IEEE
Publication or any other IEC or IEEE Publications.
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
scope of Patent Claims or determining whether any licensing terms or conditions provided in connection with
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.

IEC/IEEE 62582-1:2024 © IEC/IEEE 2024 – 5 –
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).

IEC/IEEE 62582-1:2024 © IEC/IEEE 2024 – 7 –
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) a
...

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