Occurring in the most challenging nuclear power plant accidents, transient critical heat flux (CHF) is the primary phenomenon that drives peak cladding temperature and ultimately fuel failure. It is unclear whether the use of steady-state CHF correlations can accurately predict the gross thermal-hydraulic perturbations of a blowdown in a large break loss of coolant accident. Complex multi-physics and limited engineered experiments at prototypic conditions have made it difficult to mechanistically quantify any hysteresis in predicting transient CHF. Eleven model parameters were randomly perturbed by their uncertainties in a 738-test matrix. RELAP5-3D code was used to model the Loss-of-Fluid Test facility’s L2-5 blowdown. Nine applicable correlations were tested; they predicted CHF earlier than the measured time to CHF. This supports the current assumption that steady-state CHF correlations will produce conservative predictions in highly transient scenarios. Limited by experimental data records, this study did not estimate the threshold rate of transients by which steady-state CHF correlations begin to fail to capture transient effects.