RELAP5/MOD2 assessment calculation of Semiscale Test S-UT-8

In support of the US Nuclear Regulatory Commission's independent assessment of RELAP5, the Idaho National Engineering Laboratory (INEL) has performed analysis of Semiscale Test S-UT-8 using RELAP5/MOD2. Test S-UT-8, representing a 5% cold leg break, is of interest because an extended core liquid level depression that was related to liquid holdup in the steam generator U-tubes occurred prior to loop seal clearing. Initial subsequent renodalization calculations were performed. Calculation results were compared with experimental data. Assessment of the code's performance relative to the observed test phenomena, including loop seal clearing, steam generator liquid holdup, and core liquid level depression, was performed.