GB/T 7163-2021 in English
VALIDRequirements of reliability analysis for nuclear power plant safety systems
- Issued on:2021-08-20
- Implemented on:2022-03-01
- File Format:PDF
- Delivery:Via email within 1~3 business days
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《GB/T 7163-2021核电厂安全系统可靠性分析要求》由TC30（全国核仪器仪表标准化技术委员会）归口，TC30SC2（全国核仪器仪表标准化技术委员会反应堆仪表分会）执行，主管部门为国家标准化管理委员会。
Introduction
Core changes in the standard revision
| Technical elements | 2008 edition | 2021 edition |
|---|---|---|
| Definition of terms | Safety related system | Safety system |
| Fault analysis | Single fault | Cascading fault description |
| Analysis objectives | Conservative/non-conservative separation | Objective integration |
Analysis of key technical requirements
4.1.5 Design Change Management
The standard emphasizes that hardware modifications and software changes should be treated differently, and especially points out that software modifications are more likely to cause unknown interactive effects. It is recommended to establish a change impact matrix and conduct a full-link failure analysis for version upgrades of safety-level DCS systems.
4.2.3 Complex Fault Handling
New requirements for cascading fault analysis, typical application scenarios include:
- Failure of the cooling chain caused by the failure to start the emergency diesel engine
- Pressure boundary chain reaction caused by the malfunction of the containment isolation valve
Implementation Suggestions
Fault Data Analysis
It is recommended to establish a power plant-specific database, and implement operating environment corrections for key components such as safety-level relays:
| Data source type | Correction coefficient range |
|---|---|
| Laboratory data | 1.2-1.8 |
| Data of similar power plants | 0.9-1.3 |
Test interval optimization
According to clause 4.4, it is recommended to use the Bayesian update method to dynamically adjust the test cycle and establish a performance degradation model for key equipment such as pressure regulator safety valve.
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