Single Point Vulnerabilities Management Strategy of Qinshan Nuclear Power Plant

2020 ◽  
Author(s):  
Wang Hanlin
Keyword(s):  
Risk Management ◽  
Power Plant ◽  
Management Strategy ◽  
Nuclear Power ◽  
Single Point ◽  
Load Reduction ◽  
Good Practices ◽  
Equipment Reliability ◽  
Criticality Analysis ◽  
Plant Shutdown

Abstract A SPV (Single Point Vulnerability) analysis consists of a list of trains, components or tag IDs, any which could result in a plant shutdown or significant load reduction were the affected equipment be unable to perform its function in supporting generation. Usually, a SPV related components or tag IDs that are identified as a part of an AP-913 based component criticality analysis. But how can we build a solid SPV component management strategy is a key issue for a heathy equipment reliability process. This paper developed a good practices to integrated SPV which related to the generation risk management into the equipment reliability process.

Criticality analysis for safety-critical software in nuclear power plant distributed control system

Kerntechnik ◽  
2021 ◽  
Vol 86 (5) ◽  
pp. 343-352
Author(s):  
J. Cui ◽  
Y. Cai ◽  
Y. Wu
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Application Process ◽  
Software Module ◽  
Critical System ◽  
Safety Critical ◽  
Plant Safety ◽  
Safety Integrity Level ◽  
Criticality Analysis

Abstract Software criticality analysis examines the degree of contribution that each individual failure mode of a software component has on the reliability of software. Higher safety integrity levels are assigned to software modules whose failures cause an unacceptable impact on the operation of the system, and these levels require the implementation of more rigorous software quality assurance measures as defined in IEEE Std 1012 and in the customer’s system requirements specification. In this paper, a novel software criticality analysis method is proposed, the results of which can be used to guide the development of newly developed software and the procurement of Commercial-Off-The-Shelf (COTS) software. The software structure is first analyzed and the software is divided into modules according to their functions. Then the criticality levels of software components are preliminarily classified by means of a safety criticality preliminary analysis tree, followed by their verification through the software hazard and operability analysis (HAZOP). Finally, the target Safety Integrity Level (SIL) of each software module is determined based on its criticality level and the overall safety objective (i. e., SIL) of the system it resides in. As an example, this proposed method is applied to a nuclear power plant safety-critical system to demonstrate the detail application process and to verify the feasibility of the method. Compared with the existing software criticality analysis methods, this method has better operability and verifiability, and can be utilized as a technical guidance for the software criticality analysis of nuclear power plant digital control systems.

Analysis of Severe Accident Management Strategy for a BWR-4 Nuclear Power Plant

2005 ◽  
Vol 152 (3) ◽  
pp. 253-265 ◽  
Author(s):  
Te-Chuan Wang ◽  
Shih-Jen Wang ◽  
Jyh-Tong Teng
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Management Strategy ◽  
Nuclear Power ◽  
Severe Accident ◽  
Accident Management

Electricity-market price and nuclear power plant shutdown: Evidence from California

Energy Policy ◽  
2014 ◽  
Vol 73 ◽  
pp. 234-244 ◽  
Author(s):  
C.K. Woo ◽  
T. Ho ◽  
J. Zarnikau ◽  
A. Olson ◽  
R. Jones ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Electricity Market ◽  
Nuclear Power ◽  
Market Price ◽  
Plant Shutdown

The Comparison Research About Two Reliability Management Methods in AP1000 Design

2017 ◽  
Author(s):  
Zhixin Xu ◽  
Chengzhang Wang ◽  
Jingjing Liu
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Implementation Process ◽  
Power Production ◽  
Classification Method ◽  
Reliability Management ◽  
Equipment Reliability ◽  
Comparison Research ◽  
R Classification

As a kind of Generation-III passive nuclear power plant, AP1000 has applied two kinds of equipment reliability management methods: the equipment Power Production Reliability Classification (R-Classification) method and Design-Reliability Assurance Program (D-RAP). To invest these two methods, the comparison is implemented between the classification principles, judgment basis and implementation process. According to the RCS and CVS systems, the R-Classification and D-RAP results are compared and some suggestions to enhance the NPP reliability managements are proposed.

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