Risk assessment of safety-critical data communication in digital safety feature control system - 205

Conference · Thu Jun 15 04:00:00 EDT 2017

OSTI ID:23035330

Lee, Sang Hun; Kang, Hyun Gook ^[1]; Jung, Won Dae; Son, Kwang Seop ^[2]

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1. Department of Mechanical, Aerospace, and Nuclear Engineering, Rensselaer Polytechnic Institute, 110 8th St, Troy, NY (United States)
2. Korea Atomic Energy Research Institute, 111, Daedeok-daero, Daejeon (Korea, Republic of)

As one of the safety-critical systems in Advanced Power Reactor-1400 (APR-1400) nuclear power plant (NPP), the Engineered Safety Feature-Component Control System (ESF-CCS) employs safety data link and network communication for transmitting safety component actuation to effectively facilitate various safety-critical field controllers. However, data communication failure risk in the ESF-CCS has yet to be fully quantified, the probability that a safety-critical system in digitalized NPP becomes unsafe due to a network failure must be evaluated to quantify the risk of digital I and C system. In this study, a fault tree model was developed to assess the data link and data network failure-induced unavailability of a safety-critical system function used to generate an automated control signal for actuating design basis accident mitigation equipment. Especially, the risk of data communication failure in a digital safety feature control system was analyzed in consideration of interconnection between safety-critical controllers and the fault-tolerant algorithm implemented in the network configuration. Based on the developed fault tree model, case studies were performed to quantitatively assess the unavailability of ESF-CCS signal generation due to safety data link and network failure and their risk effect on safety signal generation unavailability. This study is expected to provide risk information on the safety-critical data communication in a digitalized NPP instrumentation and control system. (authors)

• Research Organization: American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 23035330
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY
ALGORITHMS
COMMUNICATIONS
CRITICAL FIELD
DESIGN-BASIS ACCIDENTS
FAULT TREE ANALYSIS
MITIGATION
NUCLEAR POWER PLANTS
PROBABILISTIC ESTIMATION
PWR TYPE REACTORS
REACTOR CONTROL SYSTEMS
REACTOR SAFETY
RISK ASSESSMENT
SIGNALS