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GB/T 13624-2008: Functional design criteria for safety parameter display system for nuclear power plants
Status: Valid GB/T 13624: Evolution and historical versions
| Standard ID | Contents [version] | USD | STEP2 | [PDF] delivered in | Standard Title (Description) | Status | PDF |
| GB/T 13624-2008 | English | 209 |
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Functional design criteria for safety parameter display system for nuclear power plants
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GB/T 13624-2008
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| GB/T 13624-1992 | English | 319 |
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Functional design criteria for safety parameter display system for nuclear power plants
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GB/T 13624-1992
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PDF similar to GB/T 13624-2008
Basic data | Standard ID | GB/T 13624-2008 (GB/T13624-2008) | | Description (Translated English) | Functional design criteria for safety parameter display system for nuclear power plants | | Sector / Industry | National Standard (Recommended) | | Classification of Chinese Standard | F83 | | Classification of International Standard | 27.120.20 | | Word Count Estimation | 9,918 | | Date of Issue | 2008-07-02 | | Date of Implementation | 2009-04-01 | | Older Standard (superseded by this standard) | GB/T 13624-1992 | | Quoted Standard | GB/T 13628 | | Regulation (derived from) | Announcement of Newly Approved National Standards No. 11 of 2008 (No. 124 overall) | | Issuing agency(ies) | General Administration of Quality Supervision, Inspection and Quarantine of the People's Republic of China, Standardization Administration of the People's Republic of China | | Summary | This standard specifies the nuclear power plant safety parameter display system function design criteria. This standard applies to nuclear power plant safety parameter display system design. | GB/T 13624-2008: Functional design criteria for safety parameter display system for nuclear power plants
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Functional design criteria for safety parameter display system for nuclear power plants
ICS 27.120.20
F83
National Standards of People's Republic of China
Replacing GB/T 13624-1992
Nuclear Power Plant Safety Parameter Display System
Functional design criteria
Posted 2008-07-02
2009-04-01 implementation
Administration of Quality Supervision, Inspection and Quarantine of People's Republic of China
Standardization Administration of China released
Foreword
The reference to the standard IEC 60960 (1988) "Nuclear Power Plant Safety Parameter Display System Functional design criteria."
This standard replaces GB/T 13624-1992 "Nuclear Power Plant Functional design criteria for safety parameter display system."
This standard compared with GB/T 13624-1992 main changes are as follows.
a) Delete Chapter 2 reference standard GB 12172's;
b) In Chapter 3, Section 5 and Chapter 6 added content digitization.
Appendix A of this standard is an informative annex.
The standard proposed by China National Nuclear Corporation.
This standard by the National Standardization Technical Committee on nuclear instrumentation.
This standard was drafted. China Nuclear Power Institute.
The main drafters of this standard. Ling Zhou Xiong Yan.
This standard replaces the standards previously issued as follows.
--- GB/T 13624-1992.
Nuclear Power Plant Safety Parameter Display System
Functional design criteria
1 Scope
This standard specifies the nuclear power plant safety parameter display system (SPDS) functional design criteria.
This standard applies to the design of nuclear power plant safety parameter display system.
2 Normative references
The following documents contain provisions which, through reference in this standard and become the standard terms. For dated references, subsequent
Amendments (not including errata content) or revisions do not apply to this standard, however, encourage the parties to the agreement are based on research
Whether the latest versions of these documents. For undated reference documents, the latest versions apply to this standard.
GB/T 13628 nuclear reactor protection system for the purpose of non-safety guidelines
3 Total performance requirements
3.1 The basic equipment for the control room operator to provide the reactor in normal, transient and accident conditions necessary for the safe operation of the information.
SPDS used to enhance and complement the information.
3.2 SPDS by the meter, a display device and a computer to form a stand-alone system. In the digital design of nuclear power plants in the SPDS functions
It can be integrated in the nuclear power plant and computer control systems, as part of the operator support systems, equipment and operator station shared.
3.3 SPDS in a concise manner to provide normal conditions to the control room staff, especially the abnormal condition information is used to help control room staff
Quickly and reliably determine the security status of the plant. For example. the integrity of the reactivity control, reactor coolant system, reactor core cooling
Cooling and a heat loop system export, radiological monitoring, containment integrity and so on.
Although SPDS in normal conditions and abnormal conditions are working, but the main purpose and function is to assist SPDS control room staff in different
And accident conditions often determine the security status of the plant and the estimated need for the operator to take corrective action to avoid the loss of core fuel elements
Bad and radioactive releases. This occurs when a transient initial accident and the whole process of the accident is particularly important.
3.4 SPDS position control room staff should be easy to observe. The system should be able to provide data in order to quickly and reliably evaluate the safety of the plant status even
Continued display information.
3.5 SPDS should be designed to be flexible enough so that it may be further advanced diagnostic concepts, advanced technologies and such assessment
Expert systems as advanced systems combined.
3.6 Supplementary information is displayed (for example, consult the rules, trend information, and unconfirmed information, etc.) should be used as an actual branch SPDS
Who show consideration.
4 Functional design criteria
Basic requirements 4.1 functional design
4.1.1 SPDS functional design guidelines apply to the control room and emergency response facilities.
4.1.2 SPDS should be designed to select a minimum set of parameters to assess the state of safety of the plant. Parameter selection and display should be able to raise
High operator without the need for a comprehensive view of the control room, in a timely manner to assess the ability of the plant to the state. However, according to the commentary SPDS
Assessment results, a control room to confirm additional information.
4.1.3 Upon detecting abnormal conditions of nuclear power plants, SPDS should immediately provide information and analysis to help diagnose this abnormal state and beyond
Fruit, helping the operator to select the most effective corrective action. Suitable procedures may also be displayed on the display.
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