SIST EN 61772:2013
(Main)Nuclear power plants - Control rooms - Application of visual display units (VDUs)
Nuclear power plants - Control rooms - Application of visual display units (VDUs)
This International Standard supplements IEC 60964. It presents design requirements for the application of VDUs in main control rooms of nuclear power plants. For the main control room of a nuclear power plant, IEC 60964 includes general requirements for layout, user needs and verification and validation methods and these aspects are not repeated in this standard. IEC 61227, IEC 61771, IEC 62241 and IEC 61839 should also be read with this standard. This standard assists the designer in specifying VDU applications (including displays on individual workstations and larger displays for group-working or distant viewing) together with or instead of conventional (panel) displays by: - stating principles to take advantage of VDU capability; - giving examples of good practice and guiding the designer to avoid deficiencies of design. This standard contains: a) requirements for information needs: - according to information goals e.g. operation, maintenance, protection, - allowing for the necessary amount of space, e.g. location, arrangement, - using a hierarchy and/or relationships, - avoiding unnecessary information, - ensuring that information is relevant, b) requirements for good presentation such as: - clear and flicker-free display with suitable updating frequency, - enough display space and an optimal arrangement, - adequate format and symbol sizes, - pictorial, symbolic display in addition to alpha-numeric capacity, - standardized, common symbols and names, - arrangements oriented to human factor needs, e.g. population stereotypes, - use of grouping and coding methods, - use of consistent flow directions, - appropriate abstraction levels according to the needs of the different presumed users, c) methods for easy and quick access to the specific information of current interest: - by simple selection of single formats or format-sets according to information goals, - by using different kinds of menus (icons of neighbouring information) or other access techniques (last display, selection on screen, etc.) by soft keys on or off the VDU screens or cursors, - by using programmed presentation (triggered by any binary signal, such as an alarm), d) design criteria to obtain appropriate reliability of all functions necessary to achieve the specified information goals. This standard is intended for application to the design of new main control rooms in nuclear power plants designed to IEC 60964 and where this is initiated after the publication of this standard. If it is to be applied to existing control rooms or control areas designs, care should be taken as some assumptions made (such as automation level) may not apply. Where a deviation from this standard is necessary in a back-fitting application the reasons should be documented.
Kernkraftwerke - Warten - Anwendung von Sichtgeräten
Centrales nucléaires de puissance - Salles de commande - Utilisation des unités de visualisation
La CEI 61772:2009 complète la CEI 60964 et présente des exigences de conception pour l'application des unités de visualisation dans les salles de commande principales des centrales nucléaires de puissance. Aide le concepteur à spécifier les applications relatives aux unités de visualisation y compris les affichages sur les stations de travail individuelles ou sur de plus grands dispositifs d'affichage destinés au travail de groupe ou à la visualisation à distance. Les principaux changements techniques par rapport à l'édition précédente sont les suivants:
- étendre le domaine pour couvrir l'utilisation des grands écrans, et pour améliorer les recommandations concernant l'utilisation des couleurs ainsi que la couverture des applications de rénovation ou de mise à niveau;
- présenter des exemples de bonnes pratiques.
Jedrske elektrarne - Nadzorne sobe - Uporaba video prikazovalnikov (VDU)
Ta mednarodni standard dopolnjuje standard IEC 60964. Predstavlja zahteve glede načrtovanja za uporabo video prikazovalnikov (VDU) v glavnih nadzornih sobah jedrskih elektrarn. Za glavno nadzorno sobo jedrske elektrarne standard IEC 60964 vključuje splošne zahteve za postavitev, potrebe uporabnika ter metode preverjanja in potrjevanja, pri čemer se ti vidiki v zadevnem standardu ne ponavljajo. Poleg tega standarda je treba prebrati tudi standarde IEC 61227, IEC 61771, IEC 62241 in IEC 61839. Ta standard je oblikovalcu v pomoč pri ugotavljanju načinov uporabe video prikazovalnikov (vključno z zasloni na individualnih delovnih postajah in večjimi zasloni za skupinsko delo ali gledanje z večje razdalje) skupaj s konvencionalnimi (ploščatimi) zasloni ali namesto njih z naslednjim: – navajanje načel za sklicevanje na zmogljivost video prikazovalnikov; – navajanje primerov dobre prakse in vodenje oblikovalca, da se preprečijo pomanjkljivosti. Ta standard vključuje: a) zahteve za potrebe po informacijah: – v skladu s cilji glede informacij, kot so delovanje, vzdrževanje, zaščita, – omogočanje dovolj velikega prostora, tj. lokacija, ureditev, – uporaba hierarhije in/ali razmerij, – preprečevanje nepotrebnih informacij, – zagotavljanje, da so informacije pomembne, b) zahteve za dobro predstavitev, kot so: – čist in neutripajoč zaslon z ustrezno frekvenco osveževanja, – dovolj velik zaslon in optimalna razporeditev, – ustrezna velikost in mere simbola, – slikovit zaslon s simboli poleg alfanumerične zmogljivosti, – standardizirani splošni simboli in imena, – razporeditev, usmerjena v potrebe človeškega dejavnika, npr. stereotipi glede prebivalstva, – uporaba metod za združevanje v skupine in šifriranje, – uporaba ustrezne smeri pretoka, – ustrezne ravni abstrakcije podatkov v skladu s potrebami različnih predvidenih uporabnikov, c) metode za enostaven in hiter dostop do specifičnih informacij trenutnega zanimanja: – z enostavno izbiro posameznih formatov ali zbirk formatov v skladu z informacijskimi cilji, – z uporabo različnih vrst menijev (ikone sorodnih informacij) ali drugih načinov dostopa (zadnji prikaz, izbira na zaslonu itd.) z vklopljenimi ali izklopljenimi zaslonskimi tipkami, zasloni video prikazovalnikov ali kazalniki, – z uporabo programirane predstavitve (sprožene z binarnim signalom, npr. alarmom), d) merila načrtovanja za dosego ustrezne zanesljivosti vseh funkcij, potrebnih za dosego opredeljenih informacijskih ciljev. Ta standard je namenjen uporabi pri načrtovanju novih glavnih nadzornih sob jedrskih elektrarn v skladu s standardom IEC 60964, pri čemer se to začne po objavi tega standarda. V primeru njegove uporabe v obstoječih načrtih nadzornih sob ali območij, je potrebna posebna pozornost, ker nekatere navedene predpostavke (npr. stopnja avtomatizacije) morda ne veljajo. Če je potreben odklon od tega standarda pri posodabljanju, je treba vzroke zabeležiti.
General Information
Standards Content (Sample)
SLOVENSKI STANDARD
SIST EN 61772:2013
01-junij-2013
Jedrske elektrarne - Nadzorne sobe - Uporaba video prikazovalnikov (VDU)
Nuclear power plants - Control rooms - Application of visual display units (VDUs)
Kernkraftwerke - Warten - Anwendung von Sichtgeräten
Centrales nucléaires de puissance - Salles de commande - Utilisation des unités de
visualisation
Ta slovenski standard je istoveten z: EN 61772:2013
ICS:
27.120.20 Jedrske elektrarne. Varnost Nuclear power plants. Safety
SIST EN 61772:2013 en
2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega standarda ni dovoljeno.
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SIST EN 61772:2013
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SIST EN 61772:2013
EUROPEAN STANDARD
EN 61772
NORME EUROPÉENNE
February 2013
EUROPÄISCHE NORM
ICS 27.120.20
English version
Nuclear power plants -
Control rooms -
Application of visual display units (VDUs)
(IEC 61772:2009)
Centrales nucléaires de puissance - Kernkraftwerke -
Salles de commande - Warten -
Utilisation des unités de visualisation Anwendung von Sichtgeräten
(CEI 61772:2009) (IEC 61772:2009)
This European Standard was approved by CENELEC on 2013-01-14. 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, Former Yugoslav Republic of Macedonia, France, Germany,
Greece, Hungary, Iceland, Ireland, Italy, Latvia, Lithuania, Luxembourg, Malta, the Netherlands, Norway, Poland,
Portugal, Romania, Slovakia, Slovenia, Spain, Sweden, Switzerland, Turkey and the United Kingdom.
CENELEC
European Committee for Electrotechnical Standardization
Comité Européen de Normalisation Electrotechnique
Europäisches Komitee für Elektrotechnische Normung
Management Centre: Avenue Marnix 17, B - 1000 Brussels
© 2013 CENELEC - All rights of exploitation in any form and by any means reserved worldwide for CENELEC members.
Ref. No. EN 61772:2013 E
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SIST EN 61772:2013
EN 61772:2013 - 2 -
Foreword
This document (EN 61772:2013) consists of the text of IEC 61772:2009 prepared by SC 45A
"Instrumentation and control of nuclear facilities" of IEC/TC 45 "Nuclear instrumentation".
The following dates are fixed:
(dop) 2014-01-14
• latest date by which this document has to be
implemented
at national level by publication of an identical
national standard or by endorsement
(dow) 2016-01-14
• latest date by which the national standards conflicting
with this document have to be withdrawn
Attention is drawn to the possibility that some of the elements of this document may be the subject of
patent rights. CENELEC [and/or CEN] shall not be held responsible for identifying any or all such
patent rights.
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 measures in the subject-matter
covered by this standard.
Endorsement notice
The text of the International Standard IEC 61772:2009 was approved by CENELEC as a European
Standard without any modification.
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SIST EN 61772:2013
- 3 - EN 61772:2013
Annex ZA
(normative)
Normative references to international publications
with their corresponding European publications
The following documents, in whole or in part, are normatively referenced in this document and are
indispensable for its application. For dated references, only the edition cited applies. For undated
references, the latest edition of the referenced document (including any amendments) applies.
NOTE When an international publication has been modified by common modifications, indicated by (mod), the relevant EN/HD
applies.
Publication Year Title EN/HD Year
IEC 60964 2009 Nuclear power plants - Control rooms - EN 60964 2010
Design
1)
IEC 61226 2005 Nuclear power plants - Instrumentation - -
and control systems important to safety -
Classification of instrumentation
and control functions
IEC 61227 2008 Nuclear power plants - Control rooms - - -
Operator controls
IEC 61513 - Nuclear power plants - Instrumentation EN 61513 -
and control important to safety - General
requirement for systems
IEC 61771 - Nuclear power plants - Main control-room - - -
Verification and validation of design
IEC 61839 2000 Nuclear power plants - Design of control - -
rooms - Functional analysis and assignment
IEC 62241 2004 Nuclear power plants - Main control room - - -
Alarm functions and presentation
ISO 11064 Series Ergonomic design of control centres EN ISO 11064 Series
IAEA Safety 2002 Instrumentation and control systems - -
Guide NS-G-1.3 important to safety in nuclear power plants
1)
IEC 61226 is superseded by IEC 61226:2009, which is harmonised as EN 61226:2010.
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SIST EN 61772:2013
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SIST EN 61772:2013
IEC 61772
®
Edition 2.0 2009-04
INTERNATIONAL
STANDARD
NORME
INTERNATIONALE
Nuclear power plants – Control rooms – Application of visual display units
(VDUs)
Centrales nucléaires de puissance – Salles de commande – Utilisation des
unités de visualisation
INTERNATIONAL
ELECTROTECHNICAL
COMMISSION
COMMISSION
ELECTROTECHNIQUE
PRICE CODE
INTERNATIONALE
X
CODE PRIX
ICS 27.120.20 ISBN 978-2-88910-573-1
® Registered trademark of the International Electrotechnical Commission
Marque déposée de la Commission Electrotechnique Internationale
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SIST EN 61772:2013
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CONTENTS
FOREWORD.4
INTRODUCTION.6
1 Scope and object.8
2 Normative references .9
3 Terms, efinitions and abbreviations .9
4 Design requirements .10
4.1 Intended purpose and application.10
4.1.1 General .10
4.1.2 Number and location of displays .11
4.1.3 Placement to avoid daylight and lighting problems.12
4.2 Principal users .13
4.3 Failure criteria .14
4.4 System requirements.14
4.5 Information needs and application procedures.15
4.5.1 General .15
4.5.2 Back-fitting applications.16
4.5.3 New MCR design.16
5 Design and implementation of VDU formats.17
5.1 Design.17
5.2 General requirements.18
5.2.1 Presentation .18
5.2.2 Availability.18
5.2.3 Legibility.18
5.3 Accuracy .19
5.3.1 Understandability.19
5.3.2 Compatibility of VDU-formats with other man-machine interfaces .19
5.3.3 Consistency between VDU formats.19
5.4 Form of presentation .20
5.4.1 Principles .20
5.4.2 Use of symbols and graphics .21
5.4.3 Schematic and mimic displays .21
5.4.4 Formatting of information.21
6 Design and implementation of large screen displays.22
6.1 Purpose of LSD systems .22
6.2 Overview of LSD design issues .23
6.3 Placement of LSDs in the MCR .23
6.3.1 General .23
6.3.2 Placement relative to operators’ viewing areas .24
6.4 Information-content of LSD formats .25
6.4.1 General .25
6.4.2 Screen and display performance.26
6.4.3 Screen format design for LSDs .26
6.4.4 Special colour issues for LSD formats .27
6.5 Control of change of display-content on LSDs .28
7 Verification .29
8 Validation .29
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61772 © IEC:2009 – 3 –
Annex A (informative) Advantages and disadvantages of VDU-based display .30
Annex B (informative) Examples of formats, typical use and some characteristics .32
Annex C (informative) Format design and implementation basis .34
Annex D (informative) Examples of access methods .35
Annex E (informative) Verification and validation of VDU .36
Annex F (informative) Method of VDU format design presenting information on plant
conditions and equipment state.39
Figure E.1 – Format creation and verification.38
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SIST EN 61772:2013
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INTERNATIONAL ELECTROTECHNICAL COMMISSION
____________
NUCLEAR POWER PLANTS – CONTROL ROOMS –
APPLICATION OF VISUAL DISPLAY UNITS (VDUs)
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 provides no marking procedure to indicate its approval and cannot be rendered responsible for any
equipment declared to be in conformity with an IEC Publication.
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 61772 has been prepared by subcommittee 45A: Instrumentation
and control of nuclear facilities, of IEC technical committee 45: Nuclear instrumentation.
This second edition cancels and replaces the first edition published in 1995 and constitutes a
technical revision.
The main technical changes with respect to the previous edition are as follows:
– Expand the previous text to cover the use of Large Screen Displays (LSDs), to provide
improved recommendations on the use of colour, and to improve the coverage of back-fit
or upgrade applications.
– Provide references to relevant normative standards.
– Harmonise terminology according to SC 45A guidance.
– Cover experience of VDU systems design and use.
– Present examples of good practice, including methods of access to displays of current
interest.
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SIST EN 61772:2013
61772 © IEC:2009 – 5 –
The text of this standard is based on the following documents:
FDIS Report on voting
45A/728/FDIS 45A/740/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.
This publication has been drafted in accordance with the ISO/IEC Directives, Part 2.
The committee has decided that the contents of this publication will remain unchanged until
the maintenance result 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.
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SIST EN 61772:2013
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INTRODUCTION
a) Technical background, main issues and organisation of this Standard
During the work to create a standard for the design of control rooms of nuclear power plants,
it became obvious that the volume of such a standard would become very large. Therefore the
standard was split into one main standard (IEC 60964 with an annex) and some
supplementary standards. This standard is one of the supplementary standards.
It is intended that the Standard be used by operators of NPPs (utilities), designers, systems
evaluators and by licensors.
b) Situation of this Standard in the structure of the IEC SC 45A standard series
IEC 61772 is the third level IEC SC 45A document tackling the generic issue of use of VDUs
in NPPs Main Control Room.
IEC 61772 is to be read in conjunction with IEC 60964 which is the appropriate IEC SC 45A
document which provides general requirements concerning the design of Nuclear Power
Plants main control rooms. IEC 61227, IEC 61771, IEC 62241 and IEC 61839 should also be
read with this standard.
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.
To ensure that the Standard will continue to be relevant in future years, the emphasis has
been placed on issues of principle, rather than specific technologies.
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 45 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
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SIST EN 61772:2013
61772 © IEC:2009 – 7 –
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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NUCLEAR POWER PLANTS – CONTROL ROOMS –
APPLICATION OF VISUAL DISPLAY UNITS (VDUs)
1 Scope and object
This International Standard supplements IEC 60964. It presents design requirements for the
application of VDUs in main control rooms of nuclear power plants.
For the main control room of a nuclear power plant, IEC 60964 includes general requirements
for layout, user needs and verification and validation methods and these aspects are not
repeated in this standard. IEC 61227, IEC 61771, IEC 62241 and IEC 61839 should also be
read with this standard.
This standard assists the designer in specifying VDU applications (including displays on
individual workstations and larger displays for group-working or distant viewing) together with
or instead of conventional (panel) displays by:
– stating principles to take advantage of VDU capability;
– giving examples of good practice and guiding the designer to avoid deficiencies of design.
This standard contains:
a) requirements for information needs:
– according to information goals e.g. operation, maintenance, protection,
– allowing for the necessary amount of space, e.g. location, arrangement,
– using a hierarchy and/or relationships,
– avoiding unnecessary information,
– ensuring that information is relevant,
b) requirements for good presentation such as:
– clear and flicker-free display with suitable updating frequency,
– enough display space and an optimal arrangement,
– adequate format and symbol sizes,
– pictorial, symbolic display in addition to alpha-numeric capacity,
– standardized, common symbols and names,
– arrangements oriented to human factor needs, e.g. population stereotypes,
– use of grouping and coding methods,
– use of consistent flow directions,
– appropriate abstraction levels according to the needs of the different presumed users,
c) methods for easy and quick access to the specific information of current interest:
– by simple selection of single formats or format-sets according to information goals,
– by using different kinds of menus (icons of neighbouring information) or other access
techniques (last display, selection on screen, etc.) by soft keys on or off the VDU
screens or cursors,
– by using programmed presentation (triggered by any binary signal, such as an alarm),
d) design criteria to obtain appropriate reliability of all functions necessary to achieve the
specified information goals.
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61772 © IEC:2009 – 9 –
This standard is intended for application to the design of new main control rooms in nuclear
power plants designed to IEC 60964 and where this is initiated after the publication of this
standard. If it is to be applied to existing control rooms or control areas designs, care should
be taken as some assumptions made (such as automation level) may not apply.
Where a deviation from this standard is necessary in a back-fitting application the reasons
should be documented.
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 60964:2009, Nuclear power plants – Control rooms - Design
IEC 61226:2005, Nuclear power plants – Instrumentation and control systems important to
safety – Classification of instrumentation and control functions
IEC 61227:2008, Nuclear power plants – Control rooms – Operator controls
IEC 61513, Nuclear power plants – Instrumentation and control for systems important to
safety – General requirements for systems
IEC 61771, Nuclear power plants – Main control room – Verification and validation of design
IEC 61839:2000, Nuclear power plants – Design of control rooms – Functional analysis and
assignment
IEC 62241:2004, Nuclear power plants – Main control room – Alarm functions and
presentation
ISO 11064 (all parts), Ergonomic design of control centres
IAEA Safety Guide NS-G-1.3:2002, Instrumentation and control systems important to safety in
Nuclear Power Plants
3 Terms, definitions and abbreviations
For the purposes of this document, the terms, definitions and abbreviations given in
IEC 60964 apply as well as the following:
3.1
associated information
additional, or helpful information complementary to the main display content of a single format
or a format-set. The existence of this additional capability of display may be indicated by
certain icons (navigation targets, as integrated parts of the displayed information) and their
selection will lead to the display of single formats or pictorial menus or, where suitable, alpha-
numeric menus
3.2
Large Screen Display (LSD)
any form of larger display intended for group viewing, shared tasks, monitoring at a distance,
etc.
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3.3
navigation targets
areas on the display screens that provide access to other displays, when a cursor or pointer is
placed on the area and a suitable control action is taken
3.4
primary display
VDU display intended as the main (or one of the main) displays to facilitate the operator’s
main monitoring and control tasks. Primary displays need to be located more restrictively so
that the operator is able to use them effectively from the working position
3.5
secondary display
VDU display filling a supportive role, such as to promote general situation awareness, group
cooperation, casual monitoring when moving around the MCR, overall monitoring when not
occupied with more specific tasks
3.6
touch panel
soft control which uses a position detector to detect the operator's finger pointing at the label
on the VDU. Alternatively, a light pen may be used or a cursor may be moved over the VDU
format to identify a label. The label may describe an item of plant or a control action.
3.7
Visual Display Unit (VDU)
type of display incorporating a screen for presenting computer-driven images
[IEC 60964]
3.8 Abbreviations
CRT: cathode ray tube
DLP: digital light processing
LCD: liquid crystal display
LSD: large-screen display
MCR: main control room
NPP: nuclear power plant
V&V: verification and validation
VDU: visual display unit
4 Design requirements
4.1 Intended purpose and application
4.1.1 General
The design process of the VDU system shall reflect the requirements of IEC 60964.
The design process shall identify the goals of the display system, e.g. safety, availability,
operability.
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SIST EN 61772:2013
61772 © IEC:2009 – 11 –
Where a system is back-fitted to an existing plant, the extent of application of the
requirements of IEC 60964 and of this standard shall be identified.
The availability requirements shall be determined from the classification of the system in
accordance with IEC 61226 and IEC 61513.
The VDU system shall be designed so that operators can perform their tasks correctly and
promptly. Account should be taken of the relationship between the information to be
presented and any associated controls.
Consideration shall be given to control/display integration and the type of operating procedure
(event based, symptom-based or state-based).
The presentation of the relevant information shall be taken into account in the choice of the
kind
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