Comparison of APR1400 safety between brake site and shin-Kori site Due to the difference in the climate conditions

Brake Nuclear Power Plant (BNPP) is now under the construction based on APR1400 designed by Korean Electric Power Corporation (KEPCO). APR1400 is a two loop pressurized water reactor, the nuclear steam supply system (NSSS) US designed for about put of 4,000 MWt, with a corresponding electrical output of approximately 1,390 MWe. The first APR1400 (SKN 3 and 4) constructed in Shin-Kori, Korea has been modified according to the surrounding environment of the United Arab Emirates. In this paper, authors would like to compare safety issues between B NPP and Skin due to the changes of surroundings, since the site characteristics are very different. For instance, the mean annual air temperature in the UAE is 28 .deg. C and the peak air temperature was recorded as 48.8 .deg. C. Sea temperatures are varying from 17. deg. C in January to 35. deg. C in August, while that of Korea is in 9-16. deg. C range. Hot climate of UAE and the malfunction of HVAC system can lead the increasing of the water temperature in safety injection system (SIS). The heated water in SIS may affect the safety margin of the peak cladding temperature (PCT). The change of PCT and response time according to design basis accident scenarios such as large break LOCA are analyzed in detail. To evaluate such effect, Mars code was utilized to evaluate assumed condition by KAIST and the analyses of the results were carried out by Khalifa Univ.