United States Nuclear Regulatory Commission - Protecting People and the Environment

LBLOCA Uncertainty Analysis of Maanshan Nuclear Power Plant with RELAP5/SNAP and DAKOTA (NUREG/IA-0509)

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Publication Information

Manuscript Completed: June 2018
Date Published: April 2019

Prepared by:
Chunkuan Shih, Jong-Rong Wang, Jian-Ting Chen, Yuh-Ming Ferng, Shao-Wen Chen,
Ting-Yi Wang *, and Tzu-Yao Yu*

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 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

Availability Notice


The objective of this study is to assess the applicability of the RELAP5/MOD3.3 model of Maanshan NPP on LBLOCA transient. Maanshan NPP was the first three-loop PWR in Taiwan constructed by Westinghouse. The total power of the two units of the power plant is 2785 MWt, which consist of 2775 MWt for reactor power and 10 MWt for cooling pumps. For the last few years, the TRACE model of Maanshan NPP was developed and several kinds of transient event including the LOCA, AOO and the URG transient were performed and verified. Recently, the RELAP5/MOD3.3 code is another important development priority for our group. In 2015, the RELAP5/MOD3.3 model of Maanshan NPP was developed with SNAP interface.

An uncertainty analysis methodology of the postulated LBLOCA for Maanshan NPP using RELAP5/MOD3.3, DAKOTA, and SNAP codes are established in this study. The uncertainty parameters are related to ECCS property. The ranges of uncertainty analysis are based on FSAR and Training Manual of Maanshan. The maximum PCT of the uncertainty analysis is 1293 K. The PCT of FSAR is 1383.7 K. Hence, the result of the uncertainty analysis is below the FSAR data. The difference of uncertainty analysis results and FSAR data may be caused by the different calculation procedures, phenomenological modeling, and nodalization, etc. Additionally, the PCT criteria of 10 CFR 50.46 is 1477.6 K (2200°F). The prediction of the uncertainty analysis is below the criteria of 10 CFR 50.46. This implies that Maanshan NPP in LBLOCA transient is at a safety situation when ECCS is performed.

Page Last Reviewed/Updated Friday, May 17, 2019