The National Research and Development Institute for Cryogenics and Isotopic Technologies (ICSI Rm. Valcea) was established in 1970 as a research entity with the main goal of developing a heavy water production technology. One of the departments of the institute, entitled ICSI Nuclear, is oriented toward the development of a heavy water detritiation technology with the main beneficiary being the Cernavoda nuclear power plant. Thus, ICSI Nuclear has completed the technical project of the Cernavoda Tritium Removal Facility (CTRF). This paper focuses on the CTRF front end (water detritiation system) and will analyze achievement of the nominal regime at start-up and analysis of the transient regimes that may occur during normal operation and their impact on the water detritiation factor. Analysis results can become input for improvement of the CTRF control and instrumentation system, for subsequent operating facility procedures, and for verification of the isotopic exchange software models corresponding to these modes of operation.