[en] As visual examinations carried out in autumn 1994 detected cracks in a German BWR plant due to intergranular stress corrosion cracking in several core shroud components manufactured from 1.4550 steel, precautionary examinations and assessments were performed for all other plants. In accordance with these analyses, it can be stated for Isar, Unit 1 that the heat treatment to which the components in question were subjected in the course of manufacture cannot have caused sensitization of the material, and that crack formation due to the damage mechanism primarily identified in the reactor pressure vessel internals at Wuergassen Nuclear Power Station need not be feared. Although the material and corrosion-chemical assessments performed to date did not give any indications for the other crack formation mechanisms that are theoretically relevant for reactor pressure vessel internals (IGSCC due to weld sensitization, IASCC), visual examinations with a limited scope will be carried out with the independent expert's agreement during the scheduled inservice inspections. The fluid-dynamic and structure-mechanical analyses showed that the individual components are subjected only to low loadings, even in the event of accidents, and that the safety objectives shutdown and residual heat removal can be fulfilled even in the case of large postulated cracks. The fracture-mechanics analyses indicated critical through-wall crack lengths which, however, can be promptly and reliably detected during random inservice inspections even when assuming stress corrosion cracking and irradiation-induced low-toughness material conditions. In addition, both the VGB and the Isar, Unit 1 licensee are pursuing further prophylactic measures such as alternative water chemistry modes and an appropriate repair and replacement concept. (author)