A parametric analysis has been performed analysing the hypothetical st
eam generator tube rupture (SGTR) accident combined with the total los
s of secondary heat sink. The analyses have been performed by RELAP5/M
OD2/36.05 an MOD3 5M5 computer code versions using universal Krsko NPP
input deck, developed at IJS. Two break sizes have been chosen for th
e SGTR event: two and five double-ended broken tubes have been assumed
. Total loss of secondary heat sink has been assumed from the beginnin
g of the calculation with no possibility of initiating secondary-side
feed and bleed. The ways of cooling down the plant after the postulate
d accidents have been investigated. A scenario has been analysed, when
the operator applies rediagnosis procedure, during the period of loss
of secondary heat sink threat, and manages SGTR consequences first. T
he Krsko nuclear power plant emergency operating procedures have been
verified for this case.