Safety systems of nuclear facilities should be designed to meet various design criteria considered necessary to ensure the safety of the facility over its entire service life, and it should be demonstrated that these safety requirements are fulfilled. This paper assesses the safety design of the reactor protection systems in the Jordan Research and Training Reactor. The design of the reactor protection system is evaluated in terms of reliability using qualitative and quantitative analyses. In addition, an engineering evaluation of potential software common cause failures is performed to determine whether vulnerabilities to the digital safety system software common cause failures have been adequately addressed in the design of instrumentation and control systems. The safety systems of research reactors, such as the reactor protection system, should be designed to be highly reliable to achieve the required safety functions during any design basis event. The level of safety of those systems can be evaluated using the appropriate safety assessment methods described in this paper.