Nuclear power plants - Instrumentation and control important to safety - Management of ageing of electrical cabling systems (IEC 62465:2010)

This International Standard provides strategies, technical requirements, and recommended
practices for the management of normal ageing of cabling systems that are important to
safety in nuclear power plants. The main requirements are presented in the body of this
International Standard followed by a number of informative annexes with examples of cable
testing techniques, procedures, and equipment that are available for the nuclear industry to
use to ensure that ageing degradation will not impact plant safety.
This International Standard covers cables and their accessories (e.g., connectors) installed in
nuclear power plants (inside and outside the containment). It provides requirements to
perform cable testing for the purposes of predictive maintenance, troubleshooting, ageing
management, and assurance of plant safety. It is concerned with Instrumentation and Control
(I&C) cables, signal cables, and power cables of voltages less than 1 kV. More specifically,
this International Standard focuses on in-situ testing techniques that have been established
for determining problems in cable conductors (i.e., copper wire) and, to a lesser extent, on
insulation material (i.e., polymer). It follows the IEC 62342 standard on “Management of
Ageing” that was prepared to provide general guidelines for management of ageing of I&C
components in nuclear power plants, including cables. It should be pointed out that cable
testing technologies are evolving and new methods are becoming available that are not
covered in this International Standard. More specifically, this International Standard covers
typical cable testing methods that have been in use in the nuclear power industry over the last
decade. It should also be pointed out that a single cable testing technique is unlikely to
provide conclusive results, and a reliable diagnosis normally requires a combination of
techniques.

Kernkraftwerke - Leittechnische Systeme mit sicherheitstechnischer Bedeutung - Alterungsmanagement von elektrischen Kabeln (IEC 62465:2010)

Centrales nucléaires de puissance - Instrumentation et contrôle-commande importants pour la sûreté - Gestion du vieillissement des systèmes de câbles électriques (IEC 62465:2010)

La CEI 62465:2010 fournit des stratégies, des exigences techniques et des pratiques recommandées pour la gestion du vieillissement normal des systèmes de câbles qui sont importants pour la sûreté en centrale nucléaire. Les exigences principales sont présentées dans le corps de la norme qui est suivi d'un certain nombre d'annexes informatives présentant des exemples de techniques, de procédures et de matériels pour l'essai des câbles qui sont disponibles pour garantir à l'industrie nucléaire que les dégradations liées au vieillissement n'impactent pas la sûreté des installations.
Cette publication indique qu'elle contient des couleurs qui
sont considérées comme utiles à une bonne compréhension de son  
contenu.

Jedrske elektrarne - Merilna in nadzorna oprema za zagotavljanje varnosti - Upravljanje staranja električnih kablov (IEC 62465:2010)

Ta mednarodni standard vsebuje strategije, tehnične zahteve in priporočene prakse za upravljanje normalnega staranja kablov, ki so pomembni za varnost v jedrskih elektrarnah. Glavne zahteve so predstavljene v osnovnem besedilu tega mednarodnega standarda, sledijo pa mu številne informativne priloge s primeri tehnik, postopkov in opreme za preskušanje kablov, ki se uporabljajo v jedrski industriji, da se zagotovi, da staranje kablov ne vpliva na varnost elektrarne.
Ta mednarodni standard zajema kable in njihove dodatke (npr. konektorje), nameščene v jedrskih elektrarnah (znotraj in zunaj nadzora). Podaja zahteve za preskušanje kablov med predvidenim vzdrževanjem, odpravljanjem napak, upravljanjem staranja in zagotavljanjem varnosti elektrarne. Uporablja se za kable merilne in nadzorne opreme, signalne kable in napajalne kable z napetostjo manj kot 1 kV. Natančneje, ta mednarodni standard se osredotoča na tehnike preskušanja na mestu uporabe, s katerimi se prepoznava težave v kabelskih vodnikih (tj. bakrene žice) in v manjši meri na izolacijskem materialu (tj. polimeri). Sledi standardu IEC 62342 o »upravljanju staranja«, v katerem so podane splošne smernice za upravljanje staranja merilnih in nadzornih komponent v jedrskih elektrarnah, vključno s kabli. Poudariti je treba, da se tehnologije za preskušanje kablov razvijajo, tako da so na voljo tudi nove metode, ki niso zajete v tem mednarodnem standardu. Natančneje, ta mednarodni standard zajema tipične metode preskušanja kablov, ki so se uporabljale v jedrski industriji v zadnjem desetletju.
Pomembno je tudi poudariti, da ena sama tehnika preskušanja kablov verjetno ne more zagotoviti dokončnih rezultatov, ampak je za zanesljivo diagnozo običajno potrebna kombinacija več tehnik.

General Information

Status
Published
Publication Date
11-Aug-2019
Technical Committee
Current Stage
6060 - National Implementation/Publication (Adopted Project)
Start Date
05-Jul-2019
Due Date
09-Sep-2019
Completion Date
12-Aug-2019

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SLOVENSKI STANDARD
SIST EN IEC 62465:2019
01-september-2019
Jedrske elektrarne - Merilna in nadzorna oprema za zagotavljanje varnosti -
Upravljanje staranja električnih kablov (IEC 62465:2010)

Nuclear power plants - Instrumentation and control important to safety - Management of

ageing of electrical cabling systems (IEC 62465:2010)
Kernkraftwerke - Leittechnische Systeme mit sicherheitstechnischer Bedeutung -
Alterungsmanagement von elektrischen Kabeln (IEC 62465:2010)

Centrales nucléaires de puissance - Instrumentation et contrôle-commande importants

pour la sûreté - Gestion du vieillissement des systèmes de câbles électriques (IEC

62465:2010)
Ta slovenski standard je istoveten z: EN IEC 62465:2019
ICS:
27.120.20 Jedrske elektrarne. Varnost Nuclear power plants. Safety
29.060.20 Kabli Cables
SIST EN IEC 62465:2019 en

2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega standarda ni dovoljeno.

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SIST EN IEC 62465:2019
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SIST EN IEC 62465:2019
EUROPEAN STANDARD EN IEC 62465
NORME EUROPÉENNE
EUROPÄISCHE NORM
June 2019
ICS 27.120.20
English Version
Nuclear power plants - Instrumentation and control important to
safety - Management of ageing of electrical cabling systems
(IEC 62465:2010)

Centrales nucléaires de puissance - Instrumentation et Kernkraftwerke - Leittechnische Systeme mit

contrôle-commande importants pour la sûreté - Gestion du sicherheitstechnischer Bedeutung - Alterungsmanagement

vieillissement des systèmes de câbles électriques von elektrischen Kabeln
(IEC 62465:2010) (IEC 62465:2010)

This European Standard was approved by CENELEC on 2019-06-17. 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.

Up-to-date lists and bibliographical references concerning such national standards may be obtained on application to the CEN-CENELEC

Management Centre or to any CENELEC member.

This European Standard exists 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,

Turkey and the United Kingdom.
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

© 2019 CENELEC All rights of exploitation in any form and by any means reserved worldwide for CENELEC Members.

Ref. No. EN IEC 62465:2019 E
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SIST EN IEC 62465:2019
EN IEC 62465:2019 (E)
European foreword

This document (EN IEC 62465:2019) consists of the text of IEC 62465:2010 prepared by IEC/SC

45A: "Instrumentation, control and electrical power systems of nuclear facilities", of IEC/TC 45:

"Nuclear instrumentation".
The following dates are fixed:
• latest date by which this document has to be (dop) 2020-06-17
implemented at national level by publication of an
identical national standard or by endorsement
• latest date by which the national standards (dow) 2022-06-17
conflicting with this document have to be
withdrawn

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 European standard does

not prevent Member States from taking more stringent nuclear safety and/or security measures in the

subject-matter covered by this standard.

Attention is drawn to the possibility that some of the elements of this document may be the subject of

patent rights. CENELEC shall not be held responsible for identifying any or all such patent rights.

Endorsement notice

The text of the International Standard IEC 62465:2010 was approved by CENELEC as a European

Standard without any modification.
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SIST EN IEC 62465:2019
EN IEC 62465:2019 (E)
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 When 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.cenelec.eu.
Publication Year Title EN/HD Year
IEC 60780 - Nuclear power plants - Electrical - -
equipment of the safety system -
Qualification
IEC 62342 - Nuclear power plants - Instrumentation - -
and control systems important to safety -
Management of ageing
IEC 62385 - Nuclear power plants - Instrumentation - -
and control important to safety - Methods
for assessing the performance of safety
system instrument channels
IEC/TR 62096 - Nuclear power plants - Instrumentation - -
and control - Guidance for the decision on
modernization
IEC/TR 62392 - Suitability of typical electrical insulating - -
material (EIM) for polymer recycling

IEC 60780:1998 is superseded by IEC/IEEE 60780-323:2016, which is endorsed as EN 60780-323:2017.

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SIST EN IEC 62465:2019
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SIST EN IEC 62465:2019
IEC 62465
Edition 1.0 2010-05
INTERNATIONAL
STANDARD
NORME
INTERNATIONALE
colour
inside
Nuclear power plants –
Instrumentation and control important to safety – Management of ageing of
electrical cabling systems
Centrales nucléaires de puissance –
Instrumentation et contrôle-commande importants pour la sûreté – Gestion du
vieillissement des systèmes de câbles électriques
INTERNATIONAL
ELECTROTECHNICAL
COMMISSION
COMMISSION
ELECTROTECHNIQUE
PRICE CODE
INTERNATIONALE
CODE PRIX
ICS 27.120.20 ISBN 978-2-88910-915-9
® Registered trademark of the International Electrotechnical Commission
Marque déposée de la Commission Electrotechnique Internationale
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SIST EN IEC 62465:2019
– 2 – 62465 © IEC:2010
CONTENTS

FOREWORD...........................................................................................................................4

INTRODUCTION.....................................................................................................................6

1 Scope...............................................................................................................................8

2 Normative references .......................................................................................................8

3 Terms and definitions .......................................................................................................8

4 Technical background.....................................................................................................11

4.1 General .................................................................................................................11

4.2 Cable types ...........................................................................................................11

4.3 Reasons for cable ageing management .................................................................12

4.4 Cable stressors .....................................................................................................12

4.5 Cable testing techniques .......................................................................................13

5 Cable testing requirements.............................................................................................13

5.1 General .................................................................................................................13

5.2 Test methods ........................................................................................................14

5.3 Application of cable testing requirements ..............................................................14

5.4 Test interval ..........................................................................................................14

5.5 Test location .........................................................................................................14

5.6 Calibration of cable testing equipment...................................................................14

5.7 Test results ...........................................................................................................14

5.8 Validation of test methods .....................................................................................14

5.9 Software and test tool validation............................................................................15

5.10 Qualification of test personnel ...............................................................................15

6 Acceptable means for cable testing ................................................................................15

7 Testing of end devices....................................................................................................15

8 Relationship between initial qualification and cable ageing management ........................16

9 Example of a nuclear power plant practice for cable ageing management.......................16

10 Cable testing for long-term operation..............................................................................16

Annex A (informative) Typical components of an electrical cable .........................................17

Annex B (informative) Cable testing techniques ...................................................................20

Annex C (informative) Description of TDR test .....................................................................22

Annex D (informative) Electrical measurement of NIS cables and detectors .........................26

Annex E (informative) Example of a nuclear power plant practice for cable ageing

management.........................................................................................................................28

Bibliography..........................................................................................................................31

Figure A.1 – Example of cables covered by this International Standard.................................18

Figure C.1 – Principle of TDR test of an open cable..............................................................22

Figure C.2 – Principle of TDR test of a short cable................................................................23

Figure C.3 – Simplified TDR traces for a cable with a passive load .......................................23

Figure C.4 – TDR test setup .................................................................................................24

Figure C.5 – RTD cabling and corresponding TDR signature ................................................25

Figure D.1 – I-V curve...........................................................................................................27

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SIST EN IEC 62465:2019
62465 © IEC:2010 – 3 –

Figure E.1 – Photo of baskets in which samples of 1E cables are deposited and placed

in the plant for periodic removal and testing..........................................................................29

Figure E.2 – Schematic of test interval for mechanical tests..................................................30

Table 1 – Examples of stressors with potential to damage cables .........................................13

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SIST EN IEC 62465:2019
– 4 – 62465 © IEC:2010
INTERNATIONAL ELECTROTECHNICAL COMMISSION
____________
NUCLEAR POWER PLANTS –
INSTRUMENTATION AND CONTROL IMPORTANT TO SAFETY –
MANAGEMENT OF AGEING OF ELECTRICAL CABLING SYSTEMS
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

Publication(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. IEC collaborates closely

with the International Organization for Standardization (ISO) in accordance with conditions determined by

agreement between the two organizations.

2) The formal decisions or agreements 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.

3) IEC Publications have the form of recommendations for international use and are accepted by IEC National

Committees in that sense. While all reasonable efforts are made to ensure that the technical content of IEC

Publications is accurate, IEC 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

transparently to the maximum extent possible in their national and regional publications. Any divergence

between any IEC Publication and the corresponding national or regional publication shall be clearly indicated in

the latter.

5) IEC itself does not provide any attestation of conformity. Independent certification bodies provide conformity

assessment services and, in some areas, access to IEC marks of conformity. IEC is 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 its directors, employees, servants or agents including individual experts and

members of its technical committees and IEC National Committees 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 Publication or any other IEC

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.

9) Attention is drawn to the possibility that some of the elements of this IEC Publication may be the subject of

patent rights. IEC shall not be held responsible for identifying any or all such patent rights.

International Standard IEC 62465 has been prepared by subcommittee 45A: Instrumentation

and control of nuclear facilities, of IEC technical committee 45: Nuclear instrumentation.

The text of this International Standard is based on the following documents:
FDIS Report on voting
45A/795/FDIS 45A/803/RVD

Full information on the voting for the approval of this International Standard can be found in

the report on voting indicated in the above table.

This publication has been drafted in accordance with the ISO/IEC Directives, Part 2.

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SIST EN IEC 62465:2019
62465 © IEC:2010 – 5 –

The committee has decided that the contents of this publication will remain unchanged until

the stability date indicated on the IEC web site under "http://webstore.iec.ch" in the data

related to the specific publication. At this date, the publication will be
• reconfirmed,
• withdrawn,
• replaced by a revised edition, or
• amended.

IMPORTANT – The 'colour inside' logo on the cover page of this publication indicates

that it contains colours which are considered to be useful for the correct

understanding of its contents. Users should therefore print this document using a

colour printer.
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SIST EN IEC 62465:2019
– 6 – 62465 © IEC:2010
INTRODUCTION
a) Technical background, main issues and organisation of the Standard

With the majority of nuclear power plants over 20 years old, the management of ageing of

instrumentation and associated electrical cabling systems is currently a relevant topic,

especially for those plants that have extended their operating licenses or are considering this

option. This International Standard is intended to be used by operators of nuclear power

plants (utilities), systems evaluators, and by licensors.

b) Situation of the current Standard in the structure of the IEC SC 45A standard series

IEC 62465 is the third level IEC SC 45A document tackling the specific issue of management

of ageing of electrical cabling systems in nuclear power plants for Instrumentation and Control

(I&C) systems important to safety.

IEC 62342 is the second level chapeau standard of SC 45A covering the domain of the

management of ageing of nuclear instrumentation systems used in nuclear power plants to

perform functions important to safety. IEC 62342 is the introduction to a series of standards to

be developed by IEC SC 45A covering the management of ageing of specific I&C systems or

components such as electrical cabling systems (IEC 62465), sensors, and transmitters.

IEC 62465 is to be read in association with IEC 62342 and IEC 62096, which is the

appropriate IEC SC 45A Technical Report that provides guidance on the decision for

modernization when management of ageing techniques are no longer successful.

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 International Standard establishes no additional functional

requirements for safety systems. Ageing mechanisms have to be prevented and thus detected

by performance measurements. Aspects for which special recommendations have been
provided in this International Standard are:

• criteria for evaluation of ageing of electrical cabling systems in nuclear power plants;

• steps to be followed to establish cable testing requirements for an ageing management

program for nuclear power plant electrical cabling systems; and

• relationship between on-going qualification analysis and ageing management programs

with regards to electrical cabling systems.

It is recognized that testing and monitoring techniques used to evaluate the ageing condition

of nuclear power plants’ electrical cabling systems are continuing to develop at a rapid pace

and that it is not possible for a standard such as IEC 62465 to include references to all

modern technologies and techniques. However, a number of techniques have been mentioned

within this International Standard and are described in Annexes B, C and D.

To ensure that this International Standard will continue to be relevant in future years, the

emphasis has been placed on issues of principle, rather than specific technologies.

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SIST EN IEC 62465:2019
62465 © IEC:2010 – 7 –

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.

At a third level, IEC SC 45A standards not directly referenced by IEC 61513 are standards

related to specific equipment, technical methods, or specific activities. Usually these

documents, which make reference to second-level documents for general topics, can be used

on their own.

A fourth level extending the IEC SC 45A 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.

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.
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SIST EN IEC 62465:2019
– 8 – 62465 © IEC:2010
NUCLEAR POWER PLANTS –
INSTRUMENTATION AND CONTROL IMPORTANT TO SAFETY –
MANAGEMENT OF AGEING OF ELECTRICAL CABLING SYSTEMS
1 Scope

This International Standard provides strategies, technical requirements, and recommended

practices for the management of normal ageing of cabling systems that are important to

safety in nuclear power plants. The main requirements are presented in the body of this

International Standard followed by a number of informative annexes with examples of cable

testing techniques, procedures, and equipment that are available for the nuclear industry to

use to ensure that ageing degradation will not impact plant safety.

This International Standard covers cables and their accessories (e.g., connectors) installed in

nuclear power plants (inside and outside the containment). It provides requirements to

perform cable testing for the purposes of predictive maintenance, troubleshooting, ageing

management, and assurance of plant safety. It is concerned with Instrumentation and Control

(I&C) cables, signal cables, and power cables of voltages less than 1 kV. More specifically,

this International Standard focuses on in-situ testing techniques that have been established

for determining problems in cable conductors (i.e., copper wire) and, to a lesser extent, on

insulation material (i.e., polymer). It follows the IEC 62342 standard on “Management of

Ageing” that was prepared to provide general guidelines for management of ageing of I&C

components in nuclear power plants, including cables. It should be pointed out that cable

testing technologies are evolving and new methods are becoming available that are not

covered in this International Standard. More specifically, this International Standard covers

typical cable testing methods that have been in use in the nuclear power industry over the last

decade. It should also be pointed out that a single cable testing technique is unlikely to

provide conclusive results, and a reliable diagnosis normally requires a combination of

techniques.
2 Normative references

The following referenced documents are indispensable for the application 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 60780, Nuclear power plants – Electrical equipment of the safety system – Qualification

IEC/TR 62096, Nuclear power plants – Instrumentation and control important to safety –

Guidance for the decision on modernization

IEC 62342, Nuclear power plants – Instrumentation and control systems important to safety –

Management of ageing

IEC 62385, Nuclear power plants – Instrumentation and control important to safety – Methods

for assessing the performance of safety system instrument channels

IEC/TR 62392, Suitability of typical electrical insulating material (EIM) for polymer recycling

3 Terms and definitions
For the purposes of this document, the following terms and definitions apply.
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SIST EN IEC 62465:2019
62465 © IEC:2010 – 9 –
3.1
accelerated ageing

accelerated process designed to simulate an advanced life condition in a short period of time.

It is the process of subjecting an equipment or a component to stress conditions in

accordance with known measurable physical or chemical laws of degradation in order to

render its physical and electrical properties similar to those it would have at an advanced age

operating under expected operational conditions.
[IEC 60780]
3.2
ageing assessment

evaluation of appropriate information for determining the effects of ageing on the current and

future ability of systems, structures, and components to function within acceptance criteria in

all operating conditions (e.g., in normal conditions and after design basis events)

3.3
ageing management

engineering, operations, and maintenance actions to control within acceptable limits ageing

degradation of structures, systems, or components
[IAEA Safety Glossary, 2007 edition]
3.4
cable deposit (cable depot)

selection of cable samples placed inside a nuclear power plant for condition monitoring or

removal for testing
3.5
cable indenter

means for testing the indenter modulus of a cable’s insulation or jacket material

3.6
cabling system

system of cables, including the conductor, shielding, splices, insulation material, and the

cable accessories (e.g., connectors)
3.7
Design Basis Accident
DBA

accident conditions against which a facility is designed according to established design

criteria, and for which the damage to the fuel and the release of radioactive material are kept

within authorized limits
[IAEA Safety Glossary, 2007 edition]
3.8
environmental monitoring

monitoring of severities of ambient environmental parameters (e.g., temperature and radiation

dose)
3.9
environmental stress

factor influencing at least one ageing mechanism of the cabling system which is not caused

by the change of its physical state
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SIST EN IEC 62465:2019
– 10 – 62465 © IEC:2010
3.10
equipment qualification

generation and maintenance of evidence to ensure that equipment will operate on demand,

under specified service conditions, to meet system performance requirements
[IAEA Safety Glossary, 2007 edition]
3.11
high-stress area (hot spot)

limited part of cable subject to more severe environmental stress (irradiation, temperature,

mechanical constraints). Areas often localized within a nuclear power plant where

temperatures and/or radiation dose rates are higher than expected.
3.12
in-situ cable test

testing that is performed without removing the cabling system from its normal installed

position in the plant
3.13
Insulation Resistance (IR) measurement

measurement of resistance between a conductor and ground or between any two electrical

conductors
3.14
I-V curve

plot of the relationship between Current (I) and Voltage (V) for a neutron detector

3.15
LCR measurement

measurement of Inductance (L), Capacitance (C), and Resistance (R) of a cabling system

3.16
Loop Current Step Response (LCSR) test

method for measurement of response time of temperature sensors and for separating sensor

problems from cable problems
3.17
noise analysis technique

method for in-situ response time testing of sensors, detectors, and transmitters and for on-line

detection of blockages, voids, a
...

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