Research on the Verification and Validation Method of Commercial Grade Software in Nuclear Power Plants

Author(s):  
Wang-Ping Ye ◽  
Ya-Nan He ◽  
Peng-Fei Gu ◽  
Wei-Hua Chen
1998 ◽  
Vol 183 (1-2) ◽  
pp. 117-132 ◽  
Author(s):  
Akira Fukumoto ◽  
Toshifumi Hayashi ◽  
Hiroshi Nishikawa ◽  
Hiroshi Sakamoto ◽  
Teruaki Tomizawa ◽  
...  

Author(s):  
Steve Yang ◽  
Jun Ding ◽  
Huifang Miao ◽  
Jianxiang Zheng

All 1000 MW nuclear power plants currently in construction or projected to-be-built in China will use the digital instrumentation and control (I&C) systems. Safety and reliability are the ultimate concern for the digital I&C systems. To obtain high confidence in the safety of digital I&C systems, rigorous software verification and validation (V&V) life-cycle methodologies are necessary. The V&V life-cycle process ensures that the requirements of the system and software are correct, complete, and traceable; that the requirements at the end of each life-cycle phase fulfill the requirements imposed by the previous phase; and the final product meets the user-specified requirements. The V&V process is best illustrated via the so-called V-model. This paper describes the V-model in detail by some examples. Through the examples demonstration, it is shown that the process detailed in the V-model is consistent with the IEEE Std 1012-1998, which is endorsed by the US Regulatory Guide 1.168-2004. The examples show that the V-model process detailed in this paper provides an effective V&V approach for digital I&C systems used in nuclear power plants. Additionally, in order to obtain a qualitative mathematical description of the V-model, we study its topological structure in graph theory. This study confirms the rationality of the V-model. Finally, the V&V approach affording protection against common-cause failure from design deficiencies, and manufacturing errors is explored. We conclude that rigorous V&V activities using the V-model are creditable in reducing the risk of common-cause failures.


Author(s):  
Yao-Tung Hsu ◽  
Ming-Huei Chen

This paper describes the general practice and lessons learned from Commercial-Grade Item dedication for nuclear safety-related system applications in Taiwan. The dedication process qualified the commercial off-the-shelf components to be applied as basic components. In past fifteen years, Institute of Nuclear Energy Research (INER) has actively performed the dedication service to help local nuclear power plants solve their procurement problems of nuclear grade items, due to reduced availability of qualified suppliers and/or obsolete issues of qualified components. The Scope of dedication includes material, electrical and mechanical components located in mild and harsh environment. Thousands of components such as piping, fitting, breaker, relay, motor, and control device etc., have already been dedicated to and successfully used in local nuclear power plants. The Commercial-Grade Item dedication process is based on EPRI documentations. Besides, the technical evaluation and equipment qualification are included during the dedication process. The requirements for equipment qualification are described in IEEE standards. Although the codes and standards for dedication in Taiwan refer to those in USA, the challenges may happen due to different regulators, utility, manufacture’s quality culture, and personal responsibility. The key to successful dedication will be dependent on the well-defined component requirements and good project planning. This paper introduces the self-reliant experiences in dedication and economic benefit to local nuclear power plants.


2021 ◽  
Vol 8 (3A) ◽  
Author(s):  
ANA ROSA BALIZA MAIA ◽  
Youssef Morghi ◽  
AMIR ZACARIAS MESQUITA

According to NRC, the commercial-grade dedication is a process by which a commercial-grade item (CGI) is designated for use as a basic component. This acceptance process is undertaken to provide reasonable assurance that a CGI to be used as a basic component will perform its intended safety function and, in this respect, is deemed equivalent to an item designed and manufactured under a quality assurance program. This assurance is achieved by identifying the critical characteristics of the item and verifying their acceptability by inspections, tests, or analyses by the purchaser or third-party dedicating entity. In Brazil there are two Nuclear Power Plants in operation, one is American design (Angra 1), other is German design (Angra 2) and one is under construction that is German design (Angra 3). The nuclear safety items are imported and many of them are obsolete and besides the process of purchasing imported items is very complicated. If the nuclear industry in Brazil adopt the Commercial-grade dedication it will improve the internal market and facilitate the process of purchasing items. The Brazilian Quality Assurance Standard (Cnen NN 1.16) shows the 18 Basic requirements of 10 CFR 50 App B, so the Brazilian Industry can be qualified according to this Brazilian standard. The critical characteristics identification and the testing process is an engineering responsibility that Brazilian engineer can perform. This work shows the challenge of commercial-grade dedication in Brazil and discuss the importance of this process to the operation of the nuclear power plants in Brazil, including the long-term operation and others Brazilian nuclear projects..


Author(s):  
Marjorie B. Bauman ◽  
Richard F. Pain ◽  
Harold P. Van Cott ◽  
Margery K. Davidson

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