[en] Fuel cladding temperature predictions were performed for loss-of-fluid test (LOFT) loss-of-coolant experiment (LOCE) L1-5 using the RELAP4 computer code. Two versions of this code were used, RELAP4/MOD5 and RELAP4/MOD6. Measured thermocouple data have been compared to these predictions to determine the relative accuracy of the two RELAP4 computer code versions and their respective blowdown heat transfer correlations selected to describe the fuel cladding surface temperature response during the subcooled and saturated blowdown phase of the LOCE. LOFT LOCE L1-5 simulated a 200% double-ended offset shear break in the cold leg of a four-loop large pressurized water reactor (LPWR). The initial conditions for the LOCE were: zero power with a nuclear core installed, primary coolant (PC) temperature of 541 K, PC pressure of 15.6 MPa, and PC flow of 176 Kg/sec. The PC pumps were running until the end of the blowdown phase of the LOCE, and cold leg emergency core coolant (ECC) injection initiated at 19 seconds