1、raising standards worldwideNO COPYING WITHOUT BSI PERMISSION EXCEPT AS PERMITTED BY COPYRIGHT LAWBSI Standards PublicationNuclear power plants Control rooms Application of visual display units (VDUs)BS EN 61772:2013National forewordThis British Standard is the UK implementation of EN 61772:2013. It
2、is identical to IEC 61772:2009. It supersedes BS IEC 61772:2009 which is withdrawn.The UK participation in its preparation was entrusted to Technical CommitteeNCE/8, Reactor instrumentation.A list of organizations represented on this committee can be obtained onrequest to its secretary.This publicat
3、ion does not purport to include all the necessary provisions of acontract. Users are responsible for its correct application. The British Standards Institution 2013 Published by BSI Standards Limited 2013 ISBN 978 0 580 75551 4 ICS 27.120.20Compliance with a British Standard cannot confer immunity f
4、rom legal obligations.This British Standard was published under the authority of the Standards Policy and Strategy Committee on 31 March 2013.Amendments issued since publicationDate Text affectedBRITISH STANDARDBS EN 61772:2013EUROPEAN STANDARD EN 61772 NORME EUROPENNE EUROPISCHE NORM February 2013
5、CENELEC European Committee for Electrotechnical Standardization Comit Europen de Normalisation Electrotechnique Europisches Komitee fr Elektrotechnische Normung Management Centre: Avenue Marnix 17, B - 1000 Brussels 2013 CENELEC - All rights of exploitation in any form and by any means reserved worl
6、dwide for CENELEC members. Ref. No. EN 61772:2013 E ICS 27.120.20 English version Nuclear power plants - Control rooms - Application of visual display units (VDUs) (IEC 61772:2009) Centrales nuclaires de puissance - Salles de commande - Utilisation des units de visualisation (CEI 61772:2009) Kernkra
7、ftwerke - Warten - Anwendung von Sichtgerten (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
8、 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 a
9、ny 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
10、, 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
11、and the United Kingdom. BS EN 61772:2013EN 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: latest date by which
12、 this document has to be implemented at national level by publication of an identical national standard or by endorsement (dop) 2014-01-14 latest date by which the national standards conflicting with this document have to be withdrawn (dow) 2016-01-14 Attention is drawn to the possibility that some
13、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 m
14、ore 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 no
15、tice The text of the International Standard IEC 61772:2009 was approved by CENELEC as a European Standard without any modification. BS EN 61772:2013- 3 - EN 61772:2013 Annex ZA (normative) Normative references to international publications with their corresponding European publications The following
16、 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 interna
17、tional 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 - Design EN 60964 2010 IEC 61226 2005 1)Nuclear power plants - Instrumentation and control systems impor
18、tant 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 important to safety - General requirement for systems EN 61513 - IEC 61771 - Nuclear
19、 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 Ergonom
20、ic design of control centres EN ISO 11064 Series IAEA Safety Guide NS-G-1.3 2002 Instrumentation and control systems important to safety in nuclear power plants - - 1) IEC 61226 is superseded by IEC 61226:2009, which is harmonised as EN 61226:2010. BS EN 61772:2013 2 61772 IEC:2009 CONTENTS INTRODUC
21、TION.6 1 Scope and object8 2 Normative references .9 3 Terms, efinitions and abbreviations 9 4 Design requirements 10 4.1 Intended purpose and application10 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.
22、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 formats17 5.1 Design.17 5.2 General requirements18 5.2.1 Presentation 18 5.2.2 Availab
23、ility.18 5.2.3 Legibility18 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 formats19 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 disp
24、lays .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-conte
25、nt of LSD formats .25 6.4.1 General .25 6.4.2 Screen and display performance26 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 BS EN 61772:201361772 IEC:2009 3 Annex A (inf
26、ormative) 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 an
27、d 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 verification38 BS EN 61772:2013 6 61772 IEC:2009 INTRODUCTION a) Technical background, main issues and organisation of this Stand
28、ard 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 sta
29、ndard 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 ta
30、ckling 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
31、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 additio
32、nal 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 o
33、ther 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 giving examples of good practice and guiding the designer to avoid deficiencies of design. This standard contains: a) requirements f
34、or 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 g
35、ood 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 orient
36、ed 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: b
37、y 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 presen
38、tation (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. BS EN 61772:201361772 IEC:2009 9 This standard is intended for application to the design of new main control rooms in
39、 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 th
40、is 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
41、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 powe
42、r 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
43、 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 Pow
44、er 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 o
45、r 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.
46、2 Large Screen Display (LSD) any form of larger display intended for group viewing, shared tasks, monitoring at a distance, etc. BS EN 61772:2013 10 61772 IEC:2009 3.3 navigation targets areas on the display screens that provide access to other displays, when a cursor or pointer is placed on the are
47、a 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 operators main monitoring and control tasks. Primary displays need to be located more restrictively so that the operator is able to use them effectively from
48、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 p
49、osition detector to detect the operators 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: la
