[en] The structural integrity assessment of a nuclear power plant steam generator establishes the allowable dimensions for each crack at the end of the next cycle of operation in terms of its burst accumulated probability of failure. If the limit is met there are enough margins to avoid tube failure. The leakage assessment establishes the maximum leaking rate due to those defects not detected in the inspection, those ones that will appear and grow during the cycle and those ones eventually left in service, considering the defects growing during the next plant cycle when some of them can become thru-wall. The maximum allowable defect dimensions, su ch as length or depth, should tak e into account all uncertainties. Usually, a Monte Carlo analysis should be performed to establish the allowable values and it can be a simplified analysis or a multi-cycle one. The latter takes into account the data collected in all previous outages to allow a better data extrapolation for the end of the next cycle adjusting of the data to a given statistical distribution associated with the involved parameters. This work describes some tube structural integrity and leaking assessment performed for the most common degradation, in its 2008 outage, along with a discussion of the obtained results using industry available correlations. Despite the great amount of repaired tubes , all analyses have shown the Angra 1 SG worked within the structural and leaking parameters of safety defined by the regulatory board. (author)