BS IEC 61839 : 2000
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
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NUCLEAR POWER PLANTS - DESIGN OF CONTROL ROOMS - FUNCTIONAL ANALYSIS AND ASSIGNMENT
Hardcopy , PDF
30-09-2014
English
01-01-2000
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FOREWORD
1 Scope and object
2 Normative references
3 Definitions
4 Process of functional analysis and assignment
4.1 General description
4.1.1 Functional analysis
4.1.2 Assignment of functions
4.2 Basic technical team for FA and A
5 Functional analysis
5.1 General
5.2 Identification of functions
5.3 Identification of basic information and
processing requirements
5.3.1 Individual function analysis
5.3.2 Identification of time requirements
and representative events
6 Assignment of functions
6.1 General
6.2 Control function analysis
6.2.1 Identifying functional units
6.2.2 Characterising the control functions
6.2.3 Identifying control function
characteristic measurements
6.3 Development of assignment criteria
6.3.1 Characteristic measurement and man-
machine capabilit and guides
6.3.2 National law, national and
international legal rules
6.3.3 Utility and vendors' rules and policies
6.3.3 Utility and vendors' rules and policies
6.4 Assignment process
Annex A (informative) Examples of decomposition of goals and
subgoals
Annex B (informative) Beginning of PWR (pressurized water
reactor) functional analysis
Bibliography
Figure 1 - Illustrated FA and A activities given in IEC 60964
Table 1 - Humans and machines in the functional domain and in
the physical domain
Table 2 - Assignment of functions to humans and machines -
Basic structure
Specifies functional analysis and assignment procedures (FA and A, sometimes calles allocation of functions) for the design of the control-room system for nuclear power plants and gives rules for developing criteria for the assignment of functions. Supplementary to IEC 60964, which applies to the design of the control-room for nuclear power plants. Provides specific requirements to carry out functional analysis and assignment required in 3.1 and 3.2 of IEC 60964, and therefore supersedes the guidance given in A.3.1 and A.3.2 of IEC 60964. Applies to the design of new control-rooms or backfits to existing control-rooms.
| Committee |
NCE/8
|
| DevelopmentNote |
Supersedes 97/708136 DC. (05/2005) Reviewed and confirmed by BSI, September 2013. (08/2013) Renumbered and superseded by BS EN 61839. (09/2014)
|
| DocumentType |
Standard
|
| Pages |
24
|
| PublisherName |
British Standards Institution
|
| Status |
Superseded
|
| SupersededBy | |
| Supersedes |
| Standards | Relationship |
| IEC 61839:2000 | Identical |
| IEC 61226:2009 | Nuclear power plants - Instrumentation and control important to safety - Classification of instrumentation and control functions |
| ANS 58.8-1994(R2017) | TIME RESPONSE DESIGN CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS |
| IEC 61772:2009 | Nuclear power plants - Control rooms - Application of visual display units (VDUs) |
| IEC 61227:2008 | Nuclear power plants - Control rooms - Operator controls |
| IEC 60965:2016 | Nuclear power plants - Control rooms - Supplementary control room for reactor shutdown without access to the main control room |
| IEC 61771:1995 | Nuclear power plants - Main control-room - Verification and validation of design |
| IEC 60960:1988 | Functional design criteria for a safety parameter display system for nuclear power stations |
| IEC 61225:2005 | Nuclear power plants - Instrumentation and control systems important to safety - Requirements for electrical supplies |
| IEC 60964:2009 | Nuclear power plants - Control rooms - Design |
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