Super Critical Water (SCW) has advantages like high thermal efficiency and can operate at high temperature and pressure. At the same time however, these properties bring up related issues, such as material compatibility and corrosion resistance. In an effort to fully investigate the operating conditions, and solutions to these issues, test facilities are being built by many research organizations. One such organization, the Research Centre Rež (CVR) located in the Czech Republic has developed an experimental Super Critical Water Loop (SCWL). The purpose of this loop is to provide experimental data from material testing in various conditions, including operating under the neutron field. This will be achieved by inserting a test channel into the existing experimental reactor LVR-15, which will require a license from the state nuclear regulator (SUJB). Part of the licensing documentation is the safety analysis, which combines results from developed models using the thermohydraulic code ATHLET 3.1A patch 1, as well as the experimental out of pile data. Among the postulated scenarios, an abnormal sequence (labelled A2 - Loss of power in the loop) was analysed in order to provide a preliminary benchmark. This scenario is similar to the postulated in-pile A2 and it was used for the benchmark activity. The aim of this paper is to present this activity including the adopted assumptions in the model. In particular, the paper presents, how these assumptions influenced the results indicating the discrepancies obtained in the first part of the transient.