The Development and Application of Kuosheng (BWR/6) Nuclear Power Plant TRACE/SNAP Model (NUREG/IA-0450)

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Publication Information

Manuscript Completed:August 2014
Date Published:December 2014

Prepared by:
Chunkuan Shih*, Hao-Tzu Lin, Jong-Rong Wang*, Hsiung-Chih Chen*, Show-Chyuan Chiang**,
Chia-Chuan Liu**

Institute of Nuclear Energy Research, Atomic Energy Council, R.O.C.
1000, Wenhua Rd., Chiaan Village, Lungtan, Taoyuan, 325, Taiwan

*Institute of Nuclear Engineering and Science, National Tsing Hua University
101 Section 2, Kuang Fu Rd., HsinChu, Taiwan

**Department of Nuclear Safety, Taiwan Power Company
242, Section 3, Roosevelt Rd., Zhongzheng District, Taipei, Taiwan

K. Tien, NRC Project Manager

Division of Systems Analysis
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

Prepared as part of:
The Agreement on Research Participation and Technical Exchange
Under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)

Published by:
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

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Abstract

Kuosheng Nuclear Power Plant (NPP) is the second NPP in Taiwan which is the BWR/6 plant. This research focuses on the development of the Kuosheng NPP TRACE/SNAP model. In order to check the system response of the Kuosheng NPP TRACE/SNAP model, this study uses the analysis results of Final Safety Analysis Report (FSAR) and startup tests data to assess the Kuosheng NPP TRACE/SNAP model. The load rejection and a feedwater pump trip transients were selected to validate the Kuosheng NPP TRACE/SNAP model. The trends of TRACE analysis results were consistent with the FSAR and startup tests data. It indicates that there is a respectable accuracy in the Kuosheng NPP TRACE/SNAP model. Besides, this research also focuses on the application of the Kuosheng NPP TRACE/SNAP model in the core shroud leakage. The core shroud leakage is one of issues of concern by the U.S. NRC and NPPs. This research is using the Kuosheng NPP TRACE/SNAP model to perform the core shroud leakage transients for Kuosheng NPP safety analysis. The TRACE analysis results show that the pure core shroud leakage transient wasn't influence the Kuosheng NPP safety. However, the core shroud leakage + station blackout (SBO) / steamline break (loss of coolant accident, LOCA) transient caused the cladding temperature larger than 1088 K and affected the Kuosheng NPP safety.