TRAC-PF1: pressurized-thermal shock calculations for several small-break loss-of-coolant accident transients in the Oconee-1 nuclear power plant

This paper presents the thermal-hydraulic response of the Oconee-1 plant to several small-break loss-of-coolant accidents and a description of the TRAC-PF1 plant model of Oconee-1 used in support of the Nuclear Regulatory Commission directed pressurized thermal shock study. The small-break transients investigated included a stuck-open power-operated-relief-valve, a 2-in.-diam surge line break, and a 4-in.-diam surge line break. The results of the TRAC-PF1 calculations indicated that none of the small-break accidents investigated were found to be serious pressurized thermal shock transients