[en] Recorded test data are presented for Tests S-07-5 and S-07-5A of the Semiscale Mod-3 baseline test series. These tests are among several Semiscale Mod-3 experiments conducted to investigate the thermal-hydraulic phenomena accompanying a hypothesized loss-of-coolant accident in a pressurized water reactor (PWR) system. Tests S-07-5 and S-07-5A were conducted from initial conditions of 0.127 MPa and 0.137 MPa, respectively, and average heater rod temperatures of 970 K to investigate the response of the Semiscale Mod-3 system to a reflood transient following a simulated double-ended offset shear of the broken loop cold leg piping. The specific objective of these tests was to define the thermal-hydraulic behavior under reflood conditions representative of an integral 200% cold leg break in the Mod-3 system. During these tests, cooling water was injected into the vessel lower plenum to simulate emergency core coolant in a PWR. The purpose of this report is to make available the uninterpreted data from Tests S-07-5 and S-07-5A for future data analysis. The data, presented in the form of graphs in engineering units, have been analyzed only to the extent necessary to ensure that they are reasonable and consistent