[en] The structural integrity of reactor pressure vessel internals has been analyzed in detail in a life time extension project for a BWR. During the manufacturing inspection of a new core shroud cover (CSC) an unexpected microstructure was revealed in 316L steel plates, which needed to be taken into account in the development of an inspection programme for safe operation. A methodology is described for assessment of acceptable flaw sizes and inspection intervals to ensure that the integrity and safety functions of the analyzed CSC are not compromised. Fundamental steps in the approach are a structured review of damage mechanisms and identification of governing loads and residual stresses. Background information that has large influence on the results is presented. Even though the methodology is illustrated for a specific case, all essential steps are generic. (author)