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

IEC/IEEE 62582-1:2011 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.

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

La CEI/IEEE 62582-1:2011 contient des exigences concernant l'application des autres parties de la CEI/IEEE 62582 correspondant aux méthodes de surveillance de l'état des matériels électriques importants pour la sûreté des centrales nucléaires de puissance. Elle contient aussi des exigences qui sont communes à toutes les méthodes.

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IEC/IEEE 62582-1:2011 - Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 1: General
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IEC/IEEE 62582-1
Edition 1.0 2011-08
INTERNATIONAL
STANDARD
NORME
INTERNATIONALE
Nuclear power plants – Instrumentation and control important to safety –
Electrical equipment condition monitoring methods –
Part 1: General
Centrales nucléaires de puissance – Instrumentation et contrôle-commande
importants pour la sûreté – Méthodes de surveillance de l’état des matériels
électriques –
Partie 1: Généralités
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IEC/IEEE 62582-1
Edition 1.0 2011-08
INTERNATIONAL
STANDARD
NORME
INTERNATIONALE
Nuclear power plants – Instrumentation and control important to safety –
Electrical equipment condition monitoring methods –
Part 1: General
Centrales nucléaires de puissance – Instrumentation et contrôle-commande
importants pour la sûreté – Méthodes de surveillance de l’état des matériels
électriques –
Partie 1: Généralités
INTERNATIONAL
ELECTROTECHNICAL
COMMISSION
COMMISSION
ELECTROTECHNIQUE
INTERNATIONALE
PRICE CODE
N
CODE PRIX
ICS 27.120.20 ISBN 978-2-88912-668-2

– 2 – 62582-1  IEC/IEEE:2011
CONTENTS
FOREWORD . 3
INTRODUCTION . 5
1 Scope and object . 7
2 Normative references . 7
3 Terms and definitions . 7
4 Condition indicators . 8
4.1 General . 8
4.2 Chemical indicators . 9
4.3 Physical indicators . 9
4.4 Electrical indicators . 9
4.5 Miscellaneous Indicators . 9
5 Applicability of condition indicators to different types of organic materials . 9
6 Destructive and non-destructive condition monitoring . 10
7 Application of condition monitoring in equipment qualification and management of
ageing . 10
7.1 General . 10
7.2 Use of condition monitoring in the establishment of qualified life . 10
7.2.1 Establishment of qualified life . 10
7.2.2 Determination of acceleration factor in accelerated thermal ageing. 10
7.3 Use of condition monitoring in the extension of qualified life . 12
7.4 Use of condition monitoring in the establishment and assessment of qualified
condition . 12
7.5 Use of baseline data . 13
Bibliography . 14

Figure 1 – Example of an Arrhenius diagram. 11
Figure 2 – Influence of activation energy on qualified life, determined from artificial
thermal ageing for 42 days at 110 °C, followed by simulated design basis event . 12
Figure 3 – Illustration of condition-based qualification . 13

62582-1  IEC/IEEE:2011 – 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
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.
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
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IEC collaborates closely with IEEE in accordance with conditions determined by agreement between the two
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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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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
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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
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5) IEC and IEEE do not provide any attestation of conformity. Independent certification bodies provide conformity
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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.
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.

– 4 – 62582-1  IEC/IEEE:2011
International Standard IEC/IEEE 62582-1 has been 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.
This publication is published as an IEC/IEEE Dual Logo standard.
The text of this standard is based on the following IEC documents:
FDIS Report on voting
45A/840/FDIS 45A/849/RVD
Full information on the voting for the approval of this standard can be found in the report on
voting indicated in the above table.
International standards are drafted in accordance with the rules given in the ISO/IEC
Directives, Part 2.
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 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.
—————————
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. .

62582-1  IEC/IEEE:2011 – 5 –
INTRODUCTION
a) Technical background, main issues and organisation of this standard
This part of this IEC/IEEE standard specifically 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.
This part of IEC/IEEE 62582 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 part also includes
some elements which are common to all methods.
IEC/IEEE 62582 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 when they are considered widely applied and a good reproducibility of the
condition monitoring method can be demonstrated.
Historically, IEEE Std 323-2003 introduced 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) and JNES-SS-0903, 2009.
It is intended that this IEC/IEEE Standard 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
Part 1 of IEC/IEEE 62582 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 equipments in nuclear power plants.
Part 1 of IEC/IEEE 62582 is to be read in association with IEC 60780 and IEEE 323, which
provide 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 standard
It is important to note that this Standard establishes no additional functional requirements for
safety systems.
The Standard discusses the general measurement technique for current condition monitoring
methods and is not meant to cover any specific technologies.

– 6 – 62582-1  IEC/IEEE:2011
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.

62582-1  IEC/IEEE:2011 – 7 –
NUCLEAR POWER PLANTS –
INSTRUMENTATION AND CONTROL IMPORTANT TO SAFETY –
ELECTRICAL EQUIPMENT CONDITION MONITORING METHODS –

Part 1: General
1 Scope and object
This part of IEC/IEEE 62582 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.
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 organic or 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
organic 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 may be applicable also
to other components which include organic or 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 technical background
of condition monitoring methods, reference is made to other IEC standards, e.g. IEC 60544-5.
Information on the role of condition monitoring in qualification of equipment important to
safety is found in IEEE Std 323. General information on management of ageing can be found
in IEC 62342 and IEEE 1205.
NOTE The procedures defined in the IEC/IEEE 62582 are intended for detailed condition monitoring. A simplified
version of the procedures may be appropriate for preliminary assessment of the need for detailed measurements.
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.
IEEE Std 323:2003, IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power
Generating Stations
3 Terms and definitions
For the purposes of this document, the following terms and definitions apply.
3.1
condition indicator
characteristic of a structure, system or component that can be observed, measured or trended
to infer or directly indicate the current and future ability of the structure, system or component
to function within acceptance criteria
[IAEA Safety Glossary, 2007 Edition]

– 8 – 62582-1  IEC/IEEE:2011
3.2
condition monitoring
continuous or periodic tests, inspections, measurement or trending of the performance or
physical characteristics of structures, systems and components to indicate current or future
performance and the potential for failure
[IAEA Safety Glossary, 2007 Edition]
3.3
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]
3.4
item important to safety
item that is part of a safety group and/or whose malfunction or failure could lead to radiation
exposure of the site personnel or members of the public
[IAEA Safety Glossary, 2007 Edition]
3.5
qualified condition
condition of an 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
3.6
qualified life
period for which a structure, system or component has been demonstrated, through testing,
analysis or experience, to be capable of functioning within acceptance criteria during specific
operating conditions while retaining the ability to perform its safety functions in a design basis
accident or earthquake
[IAEA Safety Glossary, 2007 Edition]
3.7
service life
period from initial operation to final withdrawal from service of a structure, system or
component
[IAEA Safety Glossary, 2007 Edition]
4 Condition indicators
4.1 General
Condition monitoring should only be applied if there is a known relationship between the
ageing degradation of the component monitored and the degradation of the equipment’s
safety function. This relationship should be established during equipment qualification. The
relationship should take into account any diffusion limited rate effects that occur during
accelerated ageing with high acceleration factors.
Condition monitoring programs rely on measurable indicators that provide insight into the
overall degradation of the materials. To perform measurements of the condition of naturally
aged components, a sample shall either be taken destructively or the measurements shall be
made on the material in the field in a non-destructive way. The latter methods are preferred
since they allow the material to be studied without interrupting operation; however, it is often

62582-1  IEC/IEEE:2011 – 9 –
difficult to perform these types of measurements directly in the field with the required degree
of repeatability and accuracy.
In organic materials, ageing occurs that may adversely impact the important safety function
through a range of chemical reactions, including chain scission and cross-linking, which alter
the polymeric structure. For condition monitoring programs, it becomes imperative to find
methods that, either directly or indirectly, follow the progress of these reactions. A large
number of methods exist to perform this task, which makes it difficult to provide an overview
of each individual technique. Instead, this standard will focus on general groups of methods.
The overall description of these groups is provided below.
4.2 Chemical indicators
As mentioned above, the degradation mechanism for organic materials follows from a series
of chemical reactions in which the chemical structure of the polymer is altered. The
progressive change in the chemistry of the material provides an opportunity to monitor the
degradation throughout its ageing. Numerous techniques exist to perform this task, some
which monitor the polymer chain degradation itself and others which monitor side reactions
which are related to the degradation.
4.3 Physical indicators
Another key family of indicators includes techniques which monitor the material’s physical
properties. The degradation of organic materials manifests itself in changes to these physical
properties (i.e. tensile strength, elongation, and hardness). By measuring these physical
characteristics, it is possible to create a correlation with the aged condition of the material.
4.4 Electrical indicators
A third category of techniques involves measuring electrical properties of the materials. Many
of these techniques were developed for polymeric materials used in electrical insulation.
Within this family there are two basic subsets of methods. The first subset involves measuring
the dielectric properties of the materials.
A second subset of methods monitors the electrical response of systems under normal
operation. In these cases, a signal is passed through the electrical system and any changes
from baseline are detected. These changes could be signs of degradation, whether through
ageing or through physical damage.
4.5 Miscellaneous Indicators
As new technologies are developed and implemented, it becomes necessary to develop
condition monitoring methods to keep pace. As such, some methods are developed
specifically for certain types of materials.
5 Applicability of condition indicators to different types of organic materials
There is currently no single condition monitoring method which is suitable for all organic or
polymeric materials. A basic requirement for inclusion in a part of IEC/IEEE 62582 is that the
condition indicators are sensitive to the effects of ageing. An important characteristic of a
useful condition indicator is that it shows a trend that changes monotonically with degradation
and can be correlated with the safety related performance. An indicator that does not change
for a long time and then suddenly undergoes drastic changes is not useful for prognostic
applications. This can be the case with mechanical condition monitoring on semi-crystalline
materials, e.g. cross-linked polyethylene and thermosetting resins, dependant on the
formulation.
– 10 – 62582-1  IEC/IEEE:2011
Information on the applicability of various condition indicators to different polymeric materials
used in instrument and control equipments in nuclear power plants can be found in
NUREG/CR-7000 and in IAEA-TECDOC-1188, see Bibliography.
6 Destructive and non-destructive condition monitoring
A condition monitoring method may be considered destructive or non-destructive, depending
on whether the measurement or the sampling of material used for the measurement will affect
operability or future ageing. Non-destructive use of condition monitoring is preferable in field
measurements but with presently available methods it is limited to a few types of equipment,
mainly cables, where the parts of the equipment of interest are accessible in the field. In other
cases deposited samples or samples which can be replaced are needed to allow condition
monitoring.
If deposited samples are available or where components can be replaced, a broader range of
condition monitoring methods can be considered, including destructive methods. In this case,
condition monitoring can be applied to all types of equipment where the ageing material –
normally organic materials used for electrical insulation, sealing etc. – can be accessed.
7 Application of condition monitoring in equipment qualification and
management of ageing
7.1 General
Condition monitoring as part of qualification and management of ageing of electrical
equipment in nuclear power plants can have one or a combination of the following aims :
• determination of acceleration factors for the establishment of qualified life from artificial
laboratory ageing;
• extension of qualified life;
• establishment of qualified condition;
• periodic assessment of equipment condition after installation for comparison with qualified
condition.
Condition monitoring can also be used for determining whether the degradation of age
sensitive materials in equipment is within specific limits. These limits are those for which it
has been established that the effects on operability in specified service conditions and design
basis events are negligible.
7.2 Use of condition monitoring in the establishment of qualified life
7.2.1 Establishment of qualified life
The qualified life of an equipment is generally established by accelerated ageing of samples
in a laboratory, followed by verification of their capability to function within acceptance criteria
during a simulated design basis event. The acceleration factor is the ratio between the rate of
degradation under the laboratory simulation and in normal operating conditions in the field.
Condition monitoring is used to establish activation energies for calculation of the acceleration
factor in accelerated thermal ageing.
7.2.2 Determination of acceleration factor in accelerated thermal ageing
The acceleration factor F in accelerated thermal ageing is normally calculated by application
of the Arrhenius equation as follows:

62582-1  IEC/IEEE:2011 – 11 –
 
E 1 1
− −
 
t
k T T
1 2 1

F= = e (1)
t
where t and t are the times to reach a certain level of degradation at the temperatures T
1 2 1
and T (in kelvins); E is the activation energy and k is the Boltzmann constant.
−E / kT
NOTE The Arrhenius equation r= Ae is a formula for the temperature dependence of the rate r of a
–1
chemical reaction. A is a pre-factor (in case of first order reactions called the frequency factor with the unit s ), E
–4 –1
is the activation energy (here with the unit eV), k is the Boltzmann constant (0,861 7 ∙ 10 eV ∙ K ) and T is the
temperature (in K). The activation energy is defined as the energy that must be overcome in order for a chemical
reaction to occur.
The activation energy of a material is normally calculated from the results of measurements of
a condition indicator as a function of time at different temperatures. The pairs of values of
temperature and time to reach a certain level of degradation are plotted in an Arrhenius
diagram, where the inverse of temperatures (in K) are plotted on a linear scale on the
abscissa and the time t is plotted on a logarithmic scale on the ordinate. An example is shown
in Figure 1.
100 000
10 000
1 000
0,002 5 0,002 7 0,002 9 0,003 1 0,003 3 0,003 5
–1
1/T  (K )
IEC  1958/11
Figure 1 – Example of an Arrhenius diagram
A straight line between the points indicates that there is an Arrhenius behaviour of the
dependency between rate of degradation and temperature. The activation energy E (in eV) is
calculated from the slope of the line.
The acceleration factor and, consequently, the qualified life is sensitive to the value of the
activation energy. Inaccuracy in determination of the activation energy has a very significant
influence on the acceleration factor and consequently on the qualified life based on tests
including artificial accelerated thermal ageing. This is illustrated in Figure 2.
t  (h)
– 12 – 62582-1  IEC/IEEE:2011

E–10 % E–7,5 % E–5 % E–2,5 % E EE++2,2,5 %5 % E+5 % E+7,5 % E+10 %
Activation energy
IEC  1959/11
o
NOTE The normal service temperature is 50 C. E=0,9 eV.
Figure 2 – Influence of activation energy on qualified life, determined from artificial
thermal ageing for 42 days at 110 °C, followed by simulated design basis event
The example illustrates the need for high accuracy and repeatability of the condition
monitoring methods used in measurements for the determination of activation energies.
7.3 Use of condition monitoring in the extension of qualified life
A high degree of conservatism is normally used in the establishment of qualified life during
initial qualification testing. The conservatism takes into account uncertainties in the prediction
of the field environmental conditions, uncertainties in the acceleration factors used for
determination of the qualified life from simulated laboratory ageing, uncertainties in
demonstrating satisfactory performance, normal variations in commercial production, and
uncertainties in measurement and test equipment. Due to the conservatism and limitation of
time available, combined with use of moderate acceleration factors in simulated laboratory
ageing, initial qualification can result in an established qualified life which may be far from the
service life that can be tolerated before a design basis event. Methods for extension of
qualified life usually include monitoring of the condition of representative samples of installed
equipment.
7.4 Use of condition monitoring in the establishment and assessment of qualified
condition
Condition based qualification is included in IEEE 323-2003 as a complement or alternative to
qualified life.
Condition based qualification is based on establishment of the values of appropriate condition
indicators at the end of ageing prior to design basis event testing. These values represent the
qualified condition. The benefit of using condition based qualification as a complement or
alternative to qualified life is considerably enhanced if the trends (variation with time) of the
values of the condition indicators are established during ageing, e.g. by performing the
artificial ageing incrementally and measuring the values of the condition indicators at each
increment. After installation, identical measurements of the condition of representative
samples are carried out periodically and compared with the qualified condition. The principle
is illustrated in Figure 3.
Qualified life  (years)
62582-1  IEC/IEEE:2011 – 13 –

Condition development during artificial ageing

Condition development of installed specimen
Qualified condition
t tt t
1 22 3
Time
t Time at which condition monitoring is carried out
i
IEC  1960/11
Figure 3 – Illustration of condition-based qualification
The qualified condition can be established as part of the initial qualification testing. If the
initial qualification has been performed with the target to establish a qualified life only and no
condition monitoring has been included, it may be possible to establish the qualified condition
afterwards without repeating the design basis event testing. If identical samples of equipment
are available which are new or have been stored in environmentally controlled conditions, the
qualified condition can be established by repeating the ageing used in the original initial
qualification testing and determining the values of appropriate condition indicators (during
and) at the end of this ageing.
The measurements after installation may be made by other personnel, instrumentation and in
other laboratories than those used when the qualified condition was established. This puts a
high demand on the specification of the condition monitoring methods used and the
documentation and repeatability of the measurements. It is important that quite small changes
in the value of the condition indicator can be detected. This requires a high degree of
accuracy in the condition monitoring method.
7.5 Use of baseline data
Condition monitoring can be useful for evaluating the limits of degradation, below which the
functionality in service conditions and simulated design basis events is generally known not to
be significantly affected.
The general usefulness of available data on values of condition indicators, for which
operability in simulated design basis events has been demonstrated, depends on the
repeatability and accuracy of the methods used and how well the condition monitoring has
been defined and reported.
Condition indicator value
– 14 – 62582-1  IEC/IEEE:2011
Bibliography
IEC 60544-5, Electrical insulating materials – Determination of the effects of ionizing radiation
– Part 5: Procedures for assessment of ageing in service
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
IEEE Std 1205, IEEE Guide for Assessing, Monitoring, and Mitigating Aging Effects on
Class 1E Equipment Used in Nuclear Power Generating Stations
NUREG/CR-6704, Vol. 2 (BNL -NUREG-52610), Assessment of Environmental Qualification
Practices and Condition Monitoring Techniques for Low-Voltage Electric Cables, Condition
Monitoring Test Results
JNES-SS-0903:2009, The final report of the project “Assessment of cable ageing for nuclear
power plant”. T. Yamamoto & T. Minikawa, Japan Nuclear Energy Safety Organisation,
Nuclear Energy System Safety Division
NUREG/CR-7000, Essential Elements of an Electric Cable Condition Monitoring Program
IAEA-TECDOC-1188:2000, Assessment and management of ageing of major nuclear power
plant components important to safety: In-containment instrumentation and control cables,
IAEA, Vienna
___________
– 16 – 62582-1  CEI/IEEE:2011
SOMMAIRE
AVANT-PROPOS . 17
INTRODUCTION . 19
1 Domaine d'application et objet . 21
2 Références normatives . 21
3 Termes et définitions . 21
4 Indicateurs d’état . 23
4.1 Généralités. 23
4.2 Indicateurs chimiques . 23
4.3 Indicateurs physiques . 23
4.4 Indicateurs électriques . 23
4.5 Indicateurs divers . 24
5 Possibilités d’utiliser les indicateurs d’état pour différents types de matériaux
organiques . 24
6 Surveillance d’état destructive et non destructive . 24
7 Utilisation de la surveillance d’état dans le cadre de la qualification des
équipements et de la gestion du vieillissement . 24
7.1 Général . 24
7.2 Utilisation de la surveillance d’état pour déterminer la durée de vie certifiée . 25
7.2.1 Détermination de la durée de vie certifiée . 25
7.2.2 Détermination du facteur d’accélération en vieillissement thermique
accéléré . 25
7.3 Utilisation de la surveillance d’état pour l’extension de la durée de vie
certifiée . 27
7.4 Utilisation de la surveillance d’état pour la détermination et l’évaluation de
l’état qualifié . 27
7.5 Utilisation de données de base . 28
Bibliographie . 29

Figure 1 – Exemple de diagramme d’Arrhenius . 26
Figure 2 – Influence de l’énergie d’activation sur la durée de vie certifiée, déterminée
après une phase de vieillissement thermique artificiel de 42 jours à 110 °C, suivie de
la simulation d’un évènement de dimensionnement . 26
Figure 3 – Illustration de la qualification basée sur la surveillance d’état . 28

62582-1  CEI/IEEE:2011 – 17 –
COMMISSION ÉLECTROTECHNIQUE INTERNATIONALE
____________
CENTRALES NUCLÉAIRES DE PUISSANCE –
INSTRUMENTATION ET CONTRÔLE-COMMANDE
IMPORTANTS POUR LA SÛRETÉ –
MÉTHODES DE SURVEILLANCE DE
L’ÉTAT DES MATÉRIELS ÉLECTRIQUES –

Partie 1: Généralités
AVANT-PROPOS
1) La Commission Electrotechnique Internatio
...

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