oSIST prEN IEC/IEEE 62582-3:2025

SLOVENSKI STANDARD
01-december-2025
Jedrske elektrarne - Merilna in nadzorna oprema za zagotavljanje varnosti -
Metode za spremljanje stanja električne opreme - 3. del: Raztezek pri pretrgu
Nuclear power plants - Instrumentation and control important to safety - Electrical
equipment condition monitoring methods - Part 3: Elongation at break
Kernkraftwerke - Leittechnik mit sicherheitstechnischer Bedeutung -
Zustandsüberwachung elektrischer Geräte - Teil 3: Reißdehnung
Centrales nucléaires - Instrumentation et contrôle-commande importants pour la sûreté -
Méthodes de surveillance de l'état des matériels électriques - Partie 3: Allongement à la
rupture
Ta slovenski standard je istoveten z: prEN IEC/IEEE 62582-3:2025
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 62582-3
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
3: Elongation at break
(IEC/IEEE 62582-3:2024)
Centrales nucléaires - Instrumentation et contrôle- Kernkraftwerke - Leittechnik mit sicherheitstechnischer
commande importants pour la sûreté - Méthodes de Bedeutung - Zustandsüberwachung elektrischer Geräte -
surveillance de l'état des matériels électriques - Partie 3: Teil 3: Reißdehnung
Allongement à la rupture (IEC/IEEE 62582-3:2024)
(IEC/IEEE 62582-3:2024)
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 62582-3:2024.

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: 82118 Ref. No. prEN IEC/IEEE 62582-3:2025 E

European foreword
This document (prEN IEC/IEEE 62582-3:2025) consists of the text of document IEC/IEEE 62582-
3:2024, 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.

IEC/IEEE 62582-3 ®
Edition 2.0 2024-07
INTERNATIONAL
STANDARD
NORME
INTERNATIONALE
Nuclear power plants – Instrumentation and control important to safety –

Electrical equipment condition monitoring methods –

Part 3: Elongation at break
Centrales nucléaires – Instrumentation et contrôle-commande importants pour

la sûreté – Méthodes de surveillance de l'état des matériels électriques –

Partie 3: Allongement à la rupture

INTERNATIONAL
ELECTROTECHNICAL
COMMISSION
COMMISSION
ELECTROTECHNIQUE
INTERNATIONALE
ICS 27.120.20 ISBN 978-2-8322-9054-5

– 2 – IEC/IEEE 62582-3:2024 © IEC/IEEE 2024
CONTENTS
FOREWORD . 4
INTRODUCTION . 6
1 Scope . 8
2 Normative references . 8
3 Terms and definitions . 8
4 General description . 9
5 Applicability and reproducibility . 9
6 Measurement procedure . 10
6.1 Stabilisation of the polymeric materials . 10
6.2 Sampling. 10
6.2.1 General . 10
6.2.2 Sample requirements . 10
6.3 Specimen preparation . 10
6.3.1 General . 10
6.3.2 Dumb-bell specimens . 11
6.3.3 Tubular specimens . 11
6.3.4 O-ring specimens . 11
6.4 Instrumentation . 11
6.4.1 Tensile test machine . 11
6.4.2 Calibration . 12
6.4.3 Use of extensometers . 12
6.5 Tensile elongation measurement method . 12
6.5.1 Conditioning . 12
6.5.2 Dimensions of test specimens . 12
6.5.3 Clamping . 13
6.5.4 Testing speed . 13
6.5.5 Recording data . 13
6.5.6 Calculation of results . 13
6.6 Measurement report . 15
Annex A (informative) Shape and dimensions of test specimens . 16
A.1 Preparation of dumb-bell specimens . 16
A.2 Tubular specimens . 16
A.3 O-ring specimens . 18
Annex B (informative) Preparation of test specimens from cable samples . 19
B.1 General . 19
B.2 Preparation of specimens from large diameter cables . 19
B.3 Preparation of specimens from small diameter cables . 19
B.4 Preparation of test specimens from bonded material . 20
Annex C (informative) Typical load versus elongation curves . 21
Annex D (normative) Dies for cutting dumb-bell specimens . 23
Annex E (informative) Example of a measurement report from tensile elongation
measurements . 24
Bibliography . 25

Figure A.1 – Shape of dumb-bell specimens . 16

IEC/IEEE 62582-3:2024 © IEC/IEEE 2024 – 3 –
Figure A.2 – Fitting end tabs to tubular specimens . 17
Figure A.3 – Fitting soft inserts to tubular specimens . 18
Figure A.4 – Mounting of O-ring specimens in the test machine . 18
Figure C.1 – Typical load-elongation curves . 21
Figure C.2 – Typical load-time curve with a slipping specimen . 22
Figure D.1 – Suitable cutters for dumb-bell specimens . 23

Table 1 – Testing speeds for elongation measurements . 13
Table A.1 – Recommended dimensions for dumb-bell specimens . 16

– 4 – IEC/IEEE 62582-3:2024 © IEC/IEEE 2024
INTERNATIONAL ELECTROTECHNICAL COMMISSION
____________
NUCLEAR POWER PLANTS –
INSTRUMENTATION AND CONTROL IMPORTANT TO SAFETY –
ELECTRICAL EQUIPMENT CONDITION MONITORING METHODS –

Part 3: Elongation at break
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
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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
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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
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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.

IEC/IEEE 62582-3:2024 © IEC/IEEE 2024 – 5 –
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 62582-3 was prepared by subcommittee 45A: Instrumentation and control of nuclear
facilities, of IEC technical committee 45: Nuclear instrumentation, in cooperation with the
Nuclear Power Engineering Committee of the Power & Energy Society of the IEEE , 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 2012. This edition
constitutes a technical revision.
This edition includes the following technical changes with respect to the previous edition:
a) Updated best practices relating to condition monitoring using the tensile elongation method.
b) Updated bibliography, references and context.
The text of this International Standard is based on the following IEC documents:
Draft Report on voting
45A/1524/FDIS 45A/1538/RVD
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 the 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 committee has 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/62582-3/62582-
3-2012/62582-3-2012_wg-participants.pdf.

– 6 – IEC/IEEE 62582-3:2024 © IEC/IEEE 2024
INTRODUCTION
a) Technical background, main issues and organisation of the standard
This part of this IEC/IEEE standard specifically focuses on elongation at break methods for
condition monitoring for the management of ageing of electrical equipment installed in nuclear
power plants. The method is primarily suited to samples taken from equipment that are based
on polymeric materials.
This part of IEC/IEEE 62582 is the third part of the IEC/IEEE 62582 series. It contains detailed
descriptions of condition monitoring based on elongation at break measurements.
The IEC/IEEE 62582 series is issued with a joint logo which makes it applicable to management
of ageing of electrical equipment qualified to IEEE as well as IEC Standards.
IEC/IEEE 60780-323 defined term 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), JNES-SS-0903, 2009 and IAEA-TECDOC-1825:2017.
It is intended that this IEC/IEEE standard be used by test laboratories, operators of nuclear
power plants, systems evaluators and licensors.
b) Situation of the current standard in the structure of the IEC SC 45A standard series
Part 3 of IEC/IEEE 62582 is the third level IEC SC 45A document tackling the specific issue of
application and performance of elongation at break measurements in management of ageing of
electrical instrument and control equipment in nuclear power plants.
Part 3 of IEC/IEEE 62582 is to be read in association with Part 1 of IEC/IEEE 62582, which
provides requirements for application of methods for condition monitoring of electrical
equipment important to safety of nuclear power plants.
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 standard
It is important to note that this document establishes no additional functional requirements for
safety systems.
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/IEEE 62582-3:2024 © IEC/IEEE 2024 – 7 –
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 64000 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 62582-3:2024 © IEC/IEEE 2024
NUCLEAR POWER PLANTS –
INSTRUMENTATION AND CONTROL IMPORTANT TO SAFETY –
ELECTRICAL EQUIPMENT CONDITION MONITORING METHODS –

Part 3: Elongation at break
1 Scope
This part of IEC/IEEE 62582 contains methods for condition monitoring of organic and polymeric
materials in instrumentation and control systems using tensile elongation techniques in the
detail necessary to produce accurate and reproducible measurements. This document includes
the requirements for selection of samples, the measurement system and conditions, and the
reporting of the measurement results.
The different parts of IEC/IEEE 62582 are measurement standards, primarily for use in the
management of ageing in initial qualification and after installation. IEC/IEEE 62582-1 includes
requirements for the application of the other parts of IEC/IEEE 62582 and some elements which
are common to all methods. Information on the role of condition monitoring in qualification of
equipment important to safety is found in IEC/IEEE 60780-323.
This document is applicable to non-energised equipment.
2 Normative references
There are no normative references in this document.
3 Terms and definitions
For the purposes of this document, the following terms and definitions apply.
ISO, IEC and IEEE maintain terminological databases for use in standardization at the following
addresses:
• IEC Electropedia: available at http://www.electropedia.org/
• ISO Online browsing platform: available at http://www.iso.org/obp
• IEEE Standards Dictionary Online: available at http://dictionary.ieee.org
3.1
elongation
E
tensile strain, expressed as a percentage of the test length, produced in the piece by a tensile
stress
[SOURCE: ISO 37:2017, 3.2]
3.2
elongation at break
E
b
tensile strain in the test length at the breaking point
[SOURCE: ISO 37:2017, 3.5]
IEC/IEEE 62582-3:2024 © IEC/IEEE 2024 – 9 –
3.3
nominal elongation at break
tensile strain, expressed as a percentage of the specimen length between the grips, produced
in the specimen at the breaking point
3.4
gauge length
L
initial distance between the gauge marks on the central part of the test specimen. It is expressed
in millimetres (mm)
Note 1 to entry: See figures of the test specimens in the relevant part of ISO 527.
[SOURCE: ISO 527-1:2019, 3.1]
3.5
test speed
rate of separation of the gripping jaws
Note 1 to entry: It is expressed in millimetres per minute (mm/min).
[SOURCE: ISO 527-1:2019, 3.5]
4 General description
This document provides requirements for the condition monitoring of organic and polymeric
materials using tensile elongation techniques whereby a test specimen is extended along its
longitudinal axis at constant speed until the specimen breaks. During the test, the load
sustained on the specimen and its elongation are measured. For this standard, elongation at
break is the measured parameter.
NOTE Elongation at break rather than tensile strength is used because for some polymeric materials, particularly
thermoplastics, the strength can remain consistently equal to the yield strength after ageing even when the elongation
has decreased to < 50 % absolute.
5 Applicability and reproducibility
The tensile elongation method described in this document is related to the long chain molecular
structure of the polymer. As degradation proceeds, changes in the molecular structure occur as
a result of cross-linking, chain scission, oxidation and other degradation mechanisms. These
changes usually decrease the elongation at break.
The tensile elongation method described in this document is primarily suited to samples taken
from equipment that are based on polymeric materials. The method is generally not suitable for
fibre reinforced polymeric materials or resins such as epoxides.
The tensile elongation method described in this document cannot be used in the field in the
nuclear power plant but uses samples taken from the plant, which are then measured in the
laboratory. Each tensile elongation measurement in the laboratory can take between 5 min and
10 min to complete.
NOTE Round robin
...