IEC 60964:2009
(Main)Nuclear power plants - Control rooms - Design
Nuclear power plants - Control rooms - Design
IEC 60964:2009 provides functional design requirements to be used in the design of the main control room of a nuclear power plant to meet operational and safety requirements. Also provides functional interface requirements which relate to control room staffing, operating procedures, and the training programmes which, together with the human-machine interface, constitute the control room system. This new edition takes into account the fact that software engineering techniques advanced significantly in the intervening years and introduces consistency with the latest revisions of relevant IAEA documents.
Centrales nucléaires de puissance - Salles de commande - Conception
La CEI 60964:2009 établit des exigences fonctionnelles pour la conception des salles de commande des centrales nucléaires de puissance afin de respecter les exigences de conduite et de sûreté. Présente aussi les exigences d'interface fonctionnelles en rapport avec la structure de l'équipe de salle de commande, les procédures de conduite et le programme de formation qui sont en association avec l'interface homme-machine, les constituants du système de salle de commande. Cette nouvelle édition prend en compte le fait que les techniques de génie logiciel ont progressé de façon significative ces dernières années et introduit de la cohérence avec les dernières révisions des documents de l'AIEA pertinents.
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Standards Content (Sample)
IEC 60964
®
Edition 2.0 2009-02
INTERNATIONAL
STANDARD
NORME
INTERNATIONALE
Nuclear power plants – Control rooms – Design
Centrales nucléaires de puissance – Salles de commande – Conception
IEC 60964:2009
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IEC 60964
®
Edition 2.0 2009-02
INTERNATIONAL
STANDARD
NORME
INTERNATIONALE
Nuclear power plants – Control rooms – Design
Centrales nucléaires de puissance – Salles de commande – Conception
INTERNATIONAL
ELECTROTECHNICAL
COMMISSION
COMMISSION
ELECTROTECHNIQUE
PRICE CODE
INTERNATIONALE
W
CODE PRIX
ICS 27.120.20 ISBN 978-2-88910-353-9
® Registered trademark of the International Electrotechnical Commission
Marque déposée de la Commission Electrotechnique Internationale
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– 2 – 60964 © IEC:2009
CONTENTS
FOREWORD.4
INTRODUCTION.6
1 Scope and object.8
2 Normative references .8
3 Terms and definitions .9
4 Standard use.12
5 Design principles for the main control room .16
5.1 Main objectives of the main control room.16
5.2 Functional design objectives of the main control room.16
5.3 Safety principles.16
5.4 Availability principles.16
5.5 Human factors engineering principles.17
5.6 Utility operating principles .17
5.7 Relationship with other control and management centres .17
5.8 Operational experience .18
6 Functional design of the main control room .18
6.1 General .18
6.2 Functional analysis.18
6.2.1 General .18
6.2.2 Identification of functions.18
6.2.3 Information flow and processing requirements .18
6.3 Assignment of functions .19
6.3.1 General .19
6.3.2 Operator capabilities .19
6.3.3 I&C system processing capabilities.20
6.4 Verification of function assignment .20
6.4.1 General .20
6.4.2 Process .20
6.5 Validation of function assignment .21
6.5.1 General .21
6.5.2 Process .21
6.5.3 General evaluation criteria for validation.21
6.6 Job analysis .21
7 Functional design specification.22
7.1 General .22
7.2 Provision of data base on human capabilities and characteristics .22
7.3 Location, environment and protection .22
7.3.1 Location .22
7.3.2 Environment .22
7.3.3 Protection.23
7.4 Space and configuration.24
7.4.1 Space.24
7.4.2 Configuration.24
7.5 Panel layout .25
7.5.1 Priority.25
7.5.2 Positioning on control desks and panels .25
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60964 © IEC:2009 – 3 –
7.5.3 Mirror image layout.25
7.6 Location aids.25
7.6.1 Grouping of display information and controls .25
7.6.2 Nomenclature .26
7.6.3 Coding.26
7.6.4 Labelling.27
7.7 Information and control systems .27
7.7.1 General .27
7.7.2 Information functions .28
7.7.3 Control functions .31
7.8 Control-display integration.32
7.9 Communication systems.32
7.9.1 General .32
7.9.2 Verbal communication systems.33
7.9.3 Non-verbal communication systems.34
7.10 Other requirements .34
7.10.1 Power supplies .34
7.10.2 Qualification .34
7.10.3 Maintainability .34
7.10.4 Repairs.35
7.10.5 Testability.35
8 Verification and validation of the integrated control room system.35
8.1 General .35
8.2 Control room system verification .35
8.2.1 General .35
8.2.2 Process .35
8.2.3 General evaluation criteria for integrated system verification .35
8.3 Control room system validation .35
8.3.1 General .35
8.3.2 Process .35
8.3.3 General evaluation criteria for integrated system validation .36
Annex A (informative) Explanation of concepts .37
Figure 1 – Overview of control room system .14
Figure 2 – Overall design process and the relationship to clauses and subclauses of
this standard.15
Table A.1 – Human and machine in functional domain and physical domain .38
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INTERNATIONAL ELECTROTECHNICAL COMMISSION
____________
NUCLEAR POWER PLANTS –
CONTROL ROOMS –
DESIGN
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
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consensus of opinion on the relevant subjects since each technical committee has representation from all
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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 60964 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 1989.
The revision of the standard is intended to accomplish the following:
– to take into account the fact that software engineering techniques advanced significantly in
the intervening years;
– to align the Standard with the new revisions of IAEA documents NS-R-1 and NS-G-1.3,
which includes as far as possible adaptation of the definitions;
– to replace, where relevant, the previous requirements in the standard, where these are
now given by references to Standards published since the first edition, especially
IEC 60709, IEC 60780, IEC 60980, IEC 61225, IEC 61226, IEC 61227, IEC 61513,
IEC 61771, IEC 61772, IEC 61839, IEC 62241 and ISO 11064;
– to review the existing requirements and to update the terminology and definitions.
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60964 © IEC:2009 – 5 –
The text of this standard is based on the following documents:
FDIS Report on voting
45A/724/FDIS 45A/731/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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INTRODUCTION
a) Technical background, main issues and organization of the standard
IEC 60964:1989 was developed to supply requirements relevant to the design of the main
control room of NPPs. The first edition of IEC 60964 has been used extensively within the
nuclear industry. It was however recognized that recent technical developments especially
those which are based on software technology should be incorporated. It was also recognized
that the relationships with derivative standards (i.e. IEC 61227, IEC 61771, IEC 61772,
IEC 61839, and IEC 62241) should be clarified and conditioned.
This IEC standard specifically focuses on the functional designing of the main control room of
NPPs. It is intended that the Standard be used by NPP vendors, utilities, and by licensors.
b) Situation of the current standard in the structure of the IEC SC 45A standard series
IEC 60964 is the second level IEC SC 45A document tackling the generic issue of control
room design.
IEC 60964 is to be read in association with the derivative standards mentioned above which
are the appropriate IEC SC 45A documents which provide guidance on operator controls,
verification and validations of design, application of visual display units, functional analysis
and assignment, and alarm functions and presentation.
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 the Standard
This standard is intended for application to new control rooms whose conceptual design is
initiated after the publication of this standard. The recommendations of the standard may be
used for refits, upgrades and modifications.
The primary purpose of this standard is to provide functional design requirements to be used
in the design of the main control room of a nuclear power plant to meet operational and safety
requirements.
This standard also provides functional interface requirements which relate to control room
staffing, operating procedures and the training programme which are, together with the
human-machine interface, constituents of the control room system.
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.
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60964 © IEC:2009 – 7 –
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
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 –
DESIGN
1 Scope and object
This International Standard establishes requirements for the human-machine interface in the
main control rooms of nuclear power plants. The standard also establishes requirements for
the selection of functions, design consideration and organization of the human-machine
interface and procedures which shall be used systematically to verify and validate the
functional design. These requirements reflect the application of human factors engineering
principles as they apply to the human-machine interface during normal and abnormal plant
conditions. This standard does not cover special purpose or normally unattended control
points, such as those provided for shutdown operations from outside the main control room or
for radioactive waste handling, or emergency response facilities. Detailed equipment design is
outside the scope of this standard.
The primary purpose of this standard is to provide functional design requirements to be used
in the design of the main control room of a nuclear power plant to meet operational and safety
requirements. This standard also provides functional interface requirements which relate to
control room staffing, operating procedures, and the training programmes which, together with
the human-machine interface, constitute the control room system.
This standard is intended for application to new control rooms whose conceptual design is
initiated after the publication of this standard. If it is desired to apply it to an existing control
room, special caution must be exercised so that the design basis is kept consistent.
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 60709, Nuclear power plants – Instrumentation and control systems important to safety –
Separation
IEC 60780, Nuclear power plants – Electrical equipment of the safety system – Qualification
IEC 60960, Functional design criteria for a safety parameter display system for nuclear power
stations
IEC 60965, Supplementary control points for reactor shutdown without access to the main
control room
IEC 60980, Recommended practices for seismic qualification of electrical equipment of the
safety system for nuclear generating stations
IEC 61225, Nuclear power plants – Instrumentation and control systems important for safety –
Requirements for electrical supplies
IEC 61226, Nuclear power plants – Instrumentation and control important to safety –
Classification of instrumentation and control functions
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60964 © IEC:2009 – 9 –
IEC 61227, 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 61772, Nuclear power plants – Main control room – Application of visual display units
(VDU)
IEC 61839, Nuclear power plants – Design of control rooms – Functional analysis and
assignments
IEC 62241, Nuclear power plants – Main control room – Alarm functions and presentation
ISO 11064 (all parts), Ergonomic design of control centres
IAEA NS-G-1.3, Instrumentation and control systems important to safety in Nuclear Power
Plants, 2002
IAEA NS-G-1.9, Design of the reactor coolant system and associated systems in nuclear
power plants
IAEA, NS-G-1.11, Protection against internal hazards other than fires and explosions in the
design of nuclear power plants
3 Terms and definitions
For the purposes of this document, the following terms and definitions apply. For other terms,
refer to the general terminology defined in IEC 61513 and in the IAEA NUSS programme,
such as Safety Guide NS-G-1.3.
3.1
alarms
an item of diagnostic, prognostic, or guidance information, which is used to alert the operator
and to draw his or her attention to a process or system deviation.
NOTE Specific information provided by alarms includes the existence of an anomaly for which corrective action
might be needed, the cause and potential consequences of the anomaly, the overall plant status, corrective action
to the anomaly, and feedback of corrective actions.
Two types of
...
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