Abstract
Reactor protection system (RPS) is one of the very important systems in nuclear power plant (NPP). Since the digital technology was used in RPS, for the software development,the quality control (QC) and quality assurance (QA) should be further researched. Based on the CPR1000 digital RPS software development project, this paper discusses the definitions and necessity for QC and QA, illustrates the software life cycle, proposes the practical verification and validation (V&V) activities, describes V&V process through in software development. In each stage of V&V process, the V&V activities that QC and QA works and products implemented by are detailed introduced, provides a practical and efficient reference of QC and QA method for other nuclear digital safety system software development projects.
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Liu Z, Hu L S, Bai T (2015) Requirements and Methods of Reliability Design for Safety Level Software of Nuclear Power. PROCESS AUTOMATION INSTRUMENTATION, 36(11):116–120.
Software Engineering Standards Committee of the IEEE Computer Society (2004) IEEE 1012 IEEE Standard for Software Verification and Validation. Institute of Electrical and Electronics Engineer, New York.
HAF 102 (2004) Safety of Nuclear Power Plant Design Regulations. Doctoral dissertation.
HAF 102/16 (2004) Safety of Nuclear Power Plant Design Regulations Guides. Doctoral dissertation.
HAF 003 (1991) Safety of Nuclear Power Plant Design Regulations. Doctoral dissertation.
HAD 003/06 (1986) Safety of Nuclear Power Plant Design Regulations Guides. Doctoral dissertation.
R.G.1.152 (2006) Criteria For Use Of Computers in Safety Systems of Nuclear Power Plants [S]. U.S Nuclear Regulatory Commission.
International Electro technical Commission (2006) IEC 60880 Nuclear power plants-Instrumentation and control systems important to safety-Software aspects for computer-based systems performing category a functions. International Electro technical Commission, Switzerland.
Joint Technical Committee ISO/IEC JTC 1, Information technology, Subcommittee SC 7, Software engineering (1995) IEC 12207 Software Life Cycle Processes. International Electro technical Commission, Switzerland.
Nuclear Power Engineering Committee of the IEEE Power Engineering Committee (2010) IEEE 7-4.3.2 IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations. Institute of Electrical and Electronics Engineers, New York.
R.G.1.172 (1997) Software Requirement Specification For Digital Computer Software Used in Safety Systems of Nuclear Power Plants [S]. U.S NUCLEAR REGULATORY COMMISSION.
Ding Y X, Gu P F, et al. (2015) Study on Standard about Safety Digital I&C System in NPP. Process Automation Instrumentation, 36 (11):61–64.
Acknowledgements
This project was financially supported with funds which provided by a reliability research of reactor protection system which based on digital microprocessor and electrical equipment (national science and technology major project). The award number is 2014ZX06004002-004.
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Chen, WH., Xi, W., Gu, PF., Ye, WP. (2017). A Study About Software Development QC and QA of the Digital RPS in Nuclear Power Plant. In: Xu, Y. (eds) Nuclear Power Plants: Innovative Technologies for Instrumentation and Control Systems. SICPNPP 2016. Lecture Notes in Electrical Engineering, vol 400. Springer, Singapore. https://doi.org/10.1007/978-981-10-3361-2_12
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DOI: https://doi.org/10.1007/978-981-10-3361-2_12
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