As has been observed during refueling in pressurized water reactors (PWRs), some assemblies may experience quite significant bowing. Bowed assemblies affect the core power distribution and consequently some safety criteria. This paper is devoted to the thermal hydraulic modeling of assembly bowing in a PWR core and analysis of one of the primary safety limit criteria, the departure from nucleate boiling ratio (DNBR), using subchannel code COBRA-TF. Bowing of a PWR assembly in the center of a mini-core model of 3x3 assemblies with diagonal and side displacements is considered. In the case where both power changes and flow geometry changes are taken into account, the power and TH effects compensate each other and overall minimum DNBR change for the considered cases is not more than 7%. Individually, the power and TH effect on DNBR are around 30 % for the selected cases. This result has revealed the importance of thermal-hydraulic feedback consideration in DNBR analysis and the need for further comprehensive verification and validation analyses with detailed computational fluid dynamics (CFD) modelling as well as experimental data.