oSIST prEN IEC/IEEE 62582-1:2025
(Main)Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 1: General
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
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
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