Theoretical predictions and experimental data have been extensively used to establish the range of variation of the ITER plasma scenario parameters since they have a direct impact on the dimensioning of the PF (Poloidal Field) system and on the design of the first wall components. Compared to today's experiments, the working margins adopted for the ITER design are reduced. Resistive flux consumption, li and bp ranges play an important role for the capability of the tokamak to guarantee the required plasma shape, plasma current, and flattop duration. Actually the nominal ITER plasma scenario #2 has an Ohmic slow aperture expansion ramp-up where li at flattop is ~0.85, and Cejima mean values during ramp up are ~0.45 (see ITER design documentation, and related documents).