Browse > Article
http://dx.doi.org/10.5516/NET.2009.41.1.091

"3+3 PROCESS" FOR SAFETY CRITICAL SOFTWARE FOR I&C SYSTEM IN NUCLEAR POWER PLANTS  

Jung, Jae-Cheon (NSSS Engineering and Development Division, Korea Power Engineering Company)
Chang, Hoon-Sun (NSSS Engineering and Development Division, Korea Power Engineering Company)
Kim, Hang-Bae (NSSS Engineering and Development Division, Korea Power Engineering Company)
Publication Information
Nuclear Engineering and Technology / v.41, no.1, 2009 , pp. 91-98 More about this Journal
Abstract
The "3+3 Process" for safety critical software for nuclear power plants' I&C (Instrumentation and Control system) has been developed in this work. The main idea of the "3+3 Process" is both to simplify the software development and safety analysis in three steps to fulfill the requirements of a software safety plan [1]. The "3-Step" software development process consists of formal modeling and simulation, automated code generation and coverage analysis between the model and the generated source codes. The "3-Step" safety analysis consists of HAZOP (hazard and operability analysis), FTA (fault tree analysis), and DV (design validation). Put together, these steps are called the "3+3 Process". This scheme of development and safety analysis minimizes the V&V work while increasing the safety and reliability of the software product. For assessment of this process, validation has been done through prototyping of the SDS (safety shut-down system) #1 for PHWR (Pressurized Heavy Water Reactor).
Keywords
Safety Critical Software; Validation and Verification; Safety Analysis; Model Driven Architecture;
Citations & Related Records

Times Cited By Web Of Science : 0  (Related Records In Web of Science)
Times Cited By SCOPUS : 0
연도 인용수 순위
  • Reference
1 IEEE Std. 1228-1994, “IEEE Standards for Software Safety Plans”, IEEE, Aug. 1994
2 Debra S. Herrmann, “Software Safety and Reliability”, IEEE Computer Society, 1999, pp. 28-32, 48-54
3 Standish Group International, Inc., “Extreme Chaos”, 2001
4 Jean-Louis Camus, Bernard Dion, “Efficient Development of Airborne Software with Scade SuiteTM”, Esterel Technologies white-paper, 2003
5 NUREG/CR-6430, “Software Safety Hazard Analysis”, U.S. Nuclear Regulatory Commission, Feb. 1996
6 IEEE Std. 1012-2004, “IEEE Standard for Software Verification and Validation”, IEEE, June 2005
7 Regulatory guide 1.173, “Developing Software Life Cycle Processes for Digital Computer Software used in Safety System of NPPs”, U.S. Nuclear Regulatory Commission, Sep. 1997
8 Elizabeth Hull, Ken Jackson and Jeremy Dick, “Requirements Engineering”, Springer, 2005
9 Neil Storey, “Safety-Critical Computer Systems”, Addison- Wesley Publishing Company, 1996
10 Korea Institute of Nuclear Science, “Development of Safety Requirements and Guides for Digital Based I&C System Important to Safety in NPPs”, KINS/RR-106, Mar. 2002
11 Felix Redmill, Morris Chudleigh, and James Catmur, “System Safety: HAZOP and Software HAZOP,” John Wiley & Sons, 1999, pp. 25–26
12 IEC Std. 61508-5, “Functional Safety of Electrical/Electronics/ Programmable/Electronics Safety-related Systems - Part 5: Examples of Methods for the Determination of Safety Integrity Levels”, IEC, 1998
13 IEEE Std. 1074-1995, “IEEE Standards for Software Life Cycle Processes”, IEEE, Sep. 1995
14 Francois Pilarski, “Cost Effectiveness of Formal Methods in the Development of Avionics System at Aerospace”, $17^{th}$ Digital Avionics Conference, WA, Nov. 1998   DOI
15 Wolfram Hohmann “Supporting Model based Development with Unambiguous Specifications, Formal Verification and Correct-by-construction Embedded Software”, Society of Automotive Engineers, SAE international, 2004