RELAP5/MOD3.3 Model Assessment and Hypothetical Accident Analysis of Kuosheng Nuclear Power Plant with SNAP Interface (NUREG/IA-0464)

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Publication Information

Manuscript Completed: August 2015
Date Published: March 2016

Prepared by:
Chunkuan Shih*, Hao-Chun Chang*, Jong-Rong Wang*, Shao-Wen Chen*, Hao-Tzu Lin, Show-Chyuan Chiang**, Tzu-Yao Yu**

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; Nuclear and New Energy Education and Research Foundation
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 technical exchange and cooperation between the U.S. Nuclear Regulatory Commission and the Task Force for
Safety Critical Software in the Field of Nuclear Safety Resear

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

Availability Notice

Abstract

After the measurement uncertainty recapture power uprates, Kuosheng nuclear power plant (NPP) has been uprated the power from 2894 MWt to 2943 MWt. For these power upgrade, several analysis codes were applied to assess the safety of Kuosheng Nuclear Power Plant. In our group, there were a lot of effort on thermal hydraulic code, TRACE, had been done before. However, to enhance the reliability and confidence of these transient analyses, thermal hydraulic code, RELAP5/MOD3.3 will be applied in the future. The main work of this research is to establish a RELAP5/MOD3.3 model of Kuosheng NPP with SNAP interface. Model establishment of RELAP5 code is referred to the Final Safety Analysis Report (FSAR), training documents, and TRACE model which has been developed and verified before. After completing the model establishment, three startup test scenarios would be applied to the RELAP5 model. With comparing the startup test data and TRACE model analysis results, the applicability of RELAP5 model would be assessed.

Recently, Taiwan Power Company is concerned in stretch power uprated plan and uprates the power to 3030 MWt. Before the stretch power uprates, several transient analysis should be done for ensuring that the power plant could maintain stability in higher power operating conditions. In this research, three overpressurization transient scenario including main steam isolation valves closure, turbine trip with bypass failure and load rejection with bypass failure would be performed. These analysis results would be compared with the TRACE model results which had been performed before.