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http://dx.doi.org/10.7731/KIFSE.2016.30.4.020

Study of Post-Fire Safe-Shutdown Analysis of a CANDU Main Control Room based on NEI 00-01 Methodology  

Kim, In-Hwan (Fire Safety Group, KHNP Central Research Institute)
Lim, Heok-Soon (Fire Safety Group, KHNP Central Research Institute)
Bae, Yeon-Kyoung (Fire Safety Group, KHNP Central Research Institute)
Publication Information
Fire Science and Engineering / v.30, no.4, 2016 , pp. 20-26 More about this Journal
Abstract
When the fire takes place in Nuclear Powr Plants(NPPs), the reactor should achieve and maintain safe shut-down conditions and minimize the radioactive material released to the environment. The U.S. Nuclear Regulatory Commission (NRC) has issued numerous generic communications related to fire protection over the past 20 years, after it issued its requirements in the Fire Protection Rule set forth in Title 10, Section 50.48 of the Code of Federal Regulations (10 CFR 50.48) and Appendix R to the 10 CFR 50. The and Nuclear Energy Institute (NEI) has developed a Methodology for Risk Informed Fire Safe-Shutdown Analysis, which is related to the Deterministic Method for Multiple Spurious Operations solutions. The aim of this study was to identify, achieve, and maintain Post-Fire Safe-Shutdown of the Main Control Room (MCR) of the CANDU reactor, even though one train of the multiple Safety Structures, Systems, and Components (SCCs) fail by the technical specification and analysis method.
Keywords
Nuclear power plant; Post-fire safe-shutdown; Safe-shutdown analysis;
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  • Reference
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5 Nuclear Energy Institute, Guidance for Post Fire Safe Shutdown Circuit Analysis, NEI 00-01, B.1-1-36, Rev3, October (2011).