In order to prevent the brittle fracture,during nuclear power plant(NPP) heatup and cooldown processes,pressure and temperature in the reactor pressure vessel should be kept under the pressure-temperature(P-T) limit curve.In this paper,the P-T limit curve methodologies of ASME code,RCCM code and Chinese Nuclear Industry Standard EJ/T 918 are studied.Calculation and comparison of the P-T curves obtained using methods from different codes are performed.It shows that using static fracture toughness KIC instead of reference fracture toughness KIR to calculate the P-T curves increases acceptable operating region during NPP heatup and cooldown processes significantly.Comparing to the latest versions of ASME and RCCM codes,the Chinese standard is more conservative.