Abstract
As part of the participation of the Universidad Politecnica de Madrid research group in CAMP project, an analysis of Medium Break Loss of Coolant Accident (MBLOCA) sequences in a PWR Westinghouse has been performed with TRACE thermal-hydraulic code. The objective of the analysis has been to apply the Integrated Safety Assessment (ISA) methodology, developed by the Spanish Nuclear Safety Council (CSN), to a thermo-hydraulic analysis of sequences with a cold leg MBLOCA. In order to understand the impact of the availability of the accumulators in this kind of sequences, simulations have been performed both, with available and unavailable accumulators. The ISA methodology, by means of dynamic event trees and path analysis, allows obtaining the damage domain for each sequence of the MBLOCA event tree as a function of the break area and the operator actuation time needed to cool down and depressurize the reactor coolant system by means of steam generators. The results show the capability of the ISA methodology to obtain accurate results that take into account time delays and parameter uncertainties.
