MAAP4-CANDU Application to The PSA Level 2 for The Point Lepreau Nuclear Generating Station Refurbishment Project

Abstract

A Level 2 Probabilistic Safety Assessment was performed for the Point Lepreau Generating Station. It focused on determining: i) the frequency and timing of containment failure, and ii) the quantities and species of radioactive fission products that might be released to the environment, during a severe core damage accident. The MAAP4 CANDU code was used to calculate the progression of postulated severe core damage accidents and fission product releases. Five representative severe core damage accidents were selected: Station Blackout, Small Loss-of-Coolant Accident, Stagnation Feeder Break, Steam Generator Tube Rupture, and Shutdown State Accident. Analysis results for these scenarios (including some sensitivity cases) are discussed in this overview paper.