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# Using SNAP/RADTRAD and HABIT to Establish the Analysis Methodology for Maanshan PWR (NUREG/IA-0506)

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## Publication Information

**Manuscript Completed:** March 2018**Date Published:** January 2019

**Prepared by:** Jong-Rong Wang, Yu Chiang, Wen-Sheng Hsu, Hsiung-Chih Chen, Jung-Hua Yang, Chun-Kuan Shih, Shao-Wen Chen, Ting-Yi Wang*, Tzu-Yao Yu*

Nuclear and New Energy Education and Research Foundation; Institute of Nuclear Engineering and Science, National Tsing Hua University 101 Section 2, Kuangfu Rd., Hsinchu, Taiwan

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

S. Bush-Goddard, NRC RAMP Project Manager C. Sun, NRC HABIT Project Manager J. Tomon, NRC SNAP/RADTRAD 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 Radiation Protection Computer Code Analysis and Maintenance Program (RAMP)

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

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## Abstract

The objective of this study is to evaluate the control room (CR) habitability for the pressurized-water reactor (PWR) at the Maanshan nuclear power plant (NPP) site. The study focuses on the analysis methodology for CR habitability using the Symbolic Nuclear Analysis Package/RADionuclide, Transport, Removal And Dose Estimation (SNAP/RADTRAD) and the HABITability (HABIT) computer codes and is performed in two parts. In the first part of the analysis, the SNAP/RADTRAD computer code is used to develop models to evaluate the occupational radiation doses in the CR and the cumulative radiation doses at the exclusion area boundary (EAB), and low population zone (LPZ) during a loss-of-coolant accident (LOCA) design-basis accident (DBA). In the second part of the analysis, the HABIT code is used to evaluate the CR habitability during an accidental release of liquid carbon dioxide (CO2) from a storage tank under burst conditions. Additionally during this step, the HABIT code results were compared with the results from the Areal Locations of Hazardous Atmospheres (ALOHA) computer code results. The results of the SNAP/RADTRAD code CR habitability analysis of the Maanshan NPP demonstrate that the occupational doses to the CR are below the requirements of General Design Criterion 19 (GDC-19), "Control Room," of Appendix A to Title 10, Part 50 of the Code of Federal Regulations (10 CFR Part 50) and Chapter 6.4, "Control Room Habitability System," Revision 3 of NUREG-0800, "Standard Review Plan," (SRP). Additionally, the SNAP/RADTRAD code dose results for the EAB and LPZ demonstrate that they are below the criteria 10 CFR Part 100, "Reactor Site Criteria." The results of the HABIT and ALOHA code evaluations of CR habitability of the Maanshan NPP following an accidental release of liquid CO2 demonstrate that the results are below the U.S. Nuclear Regulatory Commission (NRC) Regulatory Guide (RG) 1.78, "Evaluating the Habitability of a Nuclear Power Plant Control Room during a Postulated Hazardous Chemical Release," toxicity limits. These results indicate that Maanshan NPP habitability can be maintained under the above conditions.

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