Verification of Safety in Safety Critical Computer-Based Systems: A Case Study of Nuclear Power Plant System

2016 ◽  
Vol 195 (3) ◽  
pp. 301-309 ◽  
Author(s):  
Lalit Singh ◽  
Hitesh Rajput
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Safety Critical ◽  
Plant System ◽  
Computer Based

Early Prediction of Software Reliability: A Case Study with a Nuclear Power Plant System

Computer ◽  
2016 ◽  
Vol 49 (1) ◽  
pp. 52-58 ◽  
Author(s):  
Lalit Kumar Singh ◽  
Gopika Vinod ◽  
A.K. Tripathi
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Software Reliability ◽  
Nuclear Power ◽  
Early Prediction ◽  
Plant System

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.

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