oSIST prEN IEC/IEEE 62582-4:2025

SLOVENSKI STANDARD
01-december-2025
Jedrske elektrarne - Merilna in nadzorna oprema za zagotavljanje varnosti -
Metode za spremljanje stanja električne opreme - 4. del: Tehnike indukcijske
oksidacije
Nuclear power plants - Instrumentation and control important to safety - Electrical
equipment condition monitoring methods - Part 4: Oxidation induction techniques
Kernkraftwerke - Leittechnik mit sicherheitstechnischer Bedeutung -
Zustandsüberwachung elektrischer Geräte - Teil 4: Oxidationsmethoden
Centrales nucléaires de puissance - Instrumentation et contrôle-commande importants
pour la sûreté - Méthodes de surveillance de l’état des matériels électriques - Partie 4:
Techniques d’induction à l’oxydation
Ta slovenski standard je istoveten z: prEN IEC/IEEE 62582-4:2025
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 62582-4
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
4: Oxidation induction techniques
(IEC/IEEE 62582-4:2022)
Centrales nucléaires de puissance - Instrumentation et Kernkraftwerke - Leittechnik mit sicherheitstechnischer
contrôle-commande importants pour la sûreté - Méthodes Bedeutung - Zustandsüberwachung elektrischer Geräte -
de surveillance de l'état des matériels électriques - Partie 4: Teil 4: Oxidationsmethoden
Techniques d'induction à l'oxydation (IEC/IEEE 62582-4:2022)
(IEC/IEEE 62582-4:2022)
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 62582-4:2022.

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: 82119 Ref. No. prEN IEC/IEEE 62582-4:2025 E

European foreword
This document (prEN IEC/IEEE 62582-4:2025) consists of the text of document IEC/IEEE 62582-
4:2022, 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 62582-4 ®
Edition 2.0 2022-11
INTERNATIONAL
STANDARD
NORME
INTERNATIONALE
colour
inside
Nuclear power plants – Instrumentation and control important to safety –

Electrical equipment condition monitoring methods –

Part 4: Oxidation induction techniques

Centrales nucléaires de puissance – Instrumentation et contrôle-commande

importants pour la sûreté – Méthodes de surveillance de l’état des matériels

électriques –
Partie 4: Techniques d’induction à l’oxydation

INTERNATIONAL
ELECTROTECHNICAL
COMMISSION
COMMISSION
ELECTROTECHNIQUE
INTERNATIONALE
ICS 27.120.20 ISBN 978-2-8322-5841-5

– 2 – IEC/IEEE 62582-4:2022 © IEC/IEEE 2022
CONTENTS
FOREWORD . 4
INTRODUCTION . 7
1 Scope . 9
2 Normative references . 9
3 Terms and definitions . 9
4 Abbreviated terms and acronyms . 10
5 General description . 10
6 Applicability and reproducibility . 10
7 Measurement procedure . 11
7.1 Stabilisation of the polymeric materials . 11
7.2 Sampling. 11
7.2.1 General . 11
7.2.2 Sample requirements . 11
7.2.3 Precautions . 11
7.3 Sample preparation . 12
7.4 Instrumentation . 12
7.5 Calibration . 12
7.6 OIT measurement method . 12
7.6.1 Measurement procedure . 12
7.6.2 Temperature profile . 13
7.6.3 Gas flow . 14
7.6.4 Determining the value of oxidation onset . 14
7.6.5 Reporting . 15
7.7 OITP measurement method . 16
7.7.1 Measurement procedure . 16
7.7.2 Temperature profile . 16
7.7.3 Gas flow . 16
7.7.4 Determining the value of oxidation onset . 17
7.7.5 Reporting . 17
Annex A (informative)  Interpretation of thermogram . 19
A.1 Interpretation of OIT thermograms . 19
A.2 Interpretation of OITP thermograms . 22
Annex B (informative)  Example of a measurement report from OITP and OIT . 24
B.1 OITP measurements . 24
B.2 OIT measurements . 26
Annex C (informative)  Influence of set temperature on the OIT value . 28
Bibliography . 29

Figure 1 – OIT measurement – Schematic of temperature and gas profile and
corresponding heat flow . 13
Figure 2 – Schematic showing the types of baselines (flat, sloping, endothermic dip,
melting endotherm) observed for OIT and OITP measurements . 14
Figure 3 – Schematic showing definition of onset value for OIT and OITP
measurements . 15

IEC/IEEE 62582-4:2022 © IEC/IEEE 2022 – 3 –
Figure 4 – Schematic of the temperature for OITP measurements and the
corresponding heat flow . 16
Figure A.1 – Example of an OIT plot with clear baseline and onset . 19
Figure A.2 – Example of OIT plot with multiple onsets. 20
Figure A.3 – Example of OIT plot where the baseline is difficult to define . 21
–1
Figure A.4 – Example of OIT plot where heat flow is too low to use standard 0,1 W∙g
threshold . 21
Figure A.5 – Example of an OITP plot with a well-defined baseline and onset . 22
Figure A.6 – Example of an OITP plot for a semi-crystalline material showing a melting
endotherm prior to the oxidation onset . 23
Figure A.7 – Example of an OITP plot showing an endothermic dip immediately prior to
the oxidation onset . 23
Figure B.1 – Example of OITP test plot . 25
Figure B.2 – Example of OIT test plot . 27
Figure C.1 – Example of the influence of set temperature on the OIT value . 28

Table B.1 – Example of a measurement report from OITP . 24
Table B.2 – Example of a measurement report from OIT . 26

– 4 – IEC/IEEE 62582-4:2022 © IEC/IEEE 2022
INTERNATIONAL ELECTROTECHNICAL COMMISSION
____________
NUCLEAR POWER PLANTS – INSTRUMENTATION AND CONTROL
IMPORTANT TO SAFETY – ELECTRICAL EQUIPMENT
CONDITION MONITORING METHODS –

Part 4: Oxidation induction techniques

FOREWORD
1) The International Electrotechnical Commission (IEC) is a worldwide organization for standardization comprising
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IEC/IEEE 62582-4:2022 © IEC/IEEE 2022 – 5 –
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of infringement of such rights, is entirely their own responsibility.
IEC/IEEE 62582-4 was prepared by subcommittee 45A: Instrumentation, control and electrical
power systems of nuclear facilities, of IEC technical committee 45: Nuclear instrumentation, in
cooperation with Nuclear Power Engineering Committee 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 2011. This edition
constitutes a technical revision.
This edition includes the following significant technical changes with respect to the previous
edition:
a) Consideration of publication of IEC/IEEE 60780-323;
b) An example added in Annex B and update;
c) Annex C added.
The text of this International Standard is based on the following IEC documents:
Draft Report on voting
45A/1435/FDIS 45A/1445/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/standardsdev/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.

– 6 – IEC/IEEE 62582-4:2022 © IEC/IEEE 2022
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IEC/IEEE 62582-4:2022 © IEC/IEEE 2022 – 7 –
INTRODUCTION
a) Technical background, main issues and organisation of this standard
This part of IEC/IEEE 62582 specifically focuses on oxidation induction methods for condition
monitoring for the management of ageing of electrical equipment installed in nuclear power
plants. The methods are primarily suited to samples taken from materials that are polyolefin-
based, but they can also be used for some materials based on ethylene-propylene polymers
and for some ethylene vinyl acetate materials.
This part 4 of IEC/IEEE 62582 is the fourth part of the IEC/IEEE 62582 series.
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.
IEC/IEEE 60780-323 includes the concept and role that condition based 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.
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 document 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
IEC/IEEE 62582-4 is the third level IEC SC 45A document tackling the specific issue of
application and performance of oxidation induction measurements in the management of ageing
of electrical instrument and control equipment in nuclear power plants.
IEC/IEEE 62582-4 is to be read in association with IEC/IEEE 62582-1, which provides
background and guidelines for the 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 SC45A 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.

– 8 – IEC/IEEE 62582-4:2022 © IEC/IEEE 2022
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 NSS17 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.

IEC/IEEE 62582-4:2022 © IEC/IEEE 2022 – 9 –
NUCLEAR POWER PLANTS – INSTRUMENTATION AND CONTROL
IMPORTANT TO SAFETY – ELECTRICAL EQUIPMENT
CONDITION MONITORING METHODS –

Part 4: Oxidation induction techniques

1 Scope
This part of IEC/IEEE 62582 specifies methods for condition monitoring of organic and
polymeric materials in instrumentation and control systems using oxidation induction techniques
in the detail necessary to produce accurate and reproducible measurements. It includes the
requirements for sample preparation, 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 the IEC/IEEE 62582 series and some
elements which are common to all methods. Information on the role of condition monitoring in
the qualification of equipment important to safety is found in IEC/IEEE 60780-323.
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
...