Samples taken from irradiated zircaloy-2 pressure tubes of Pressurised Heavy Water Reactors (PHWRs) of Rajasthan Atomic Power Station (RAPS) Unit # 1 and Madras Atomic Power Station (MAPS) Unit # 1 were examined using scanning electron and optical microscopy. The morphology of oxide formed on the inside surface of the pressure tube and morphological orientation distribution of zirconium hydride precipitates in the samples were studied. Crystallographic texture of one unirradiated sample was also determined using X-ray diffraction technique. Results show maximum oxide thickness of 15 mm in pressure tube operated for 7 effective full power years (EFPYs) and 40 mm for operation period of 9.5 EFPYs. Micro-cracks and micropores were found in the oxide layer of 25 mm thickness. Small fine cracks parallel to metal – oxide interface were also observed in the oxide layer. The fraction of radial hydrides (FN number) in irradiated tube was found to be 0.52 and texture parameters fR, fT and fL which represent the effective fractions of the grains with their basal poles oriented in radial, transverse and longitudinal directions respectively, of the tube were found to be 0.44, 0.49 and 0.11.