Mitigation of multiple tube ruptures in both steam generators

To address the issue of successful mitigation of the consequences of multiple steam generator tube ruptures, this paper provides an evaluation of the thermal-hydraulic response of a pressurized water reactor using the Combustion Engineering (C-E) Plant Analysis Code, CEPAC. Specifically, the purpose of the paper is to demonstrate that the power plant can be aggressively cooled to hot shutdown conditions without either excessive steam releases/doses to the environment or exhausting safety injection water supplies, and without the need to use pressurizer relief valves. The evaluations considered one tube rupture in each steam generator of a typical C-E PWR as well as three tube ruptures in each steam generator and assumed loss-of-offsite power subsequent to plant trip