[en] Compliance with the damage criteria specified in Section 3.13 of the LOFT Technical Specifications is demonstrated for reactor operating Modes 1-7. Documented analysis and existing Technical Specification constraints are used to show that maximum allowable consequence levels will not be exceeded for planned operations and postulated accident conditions. A potential problem has been identified involving radiation damage to the containment vessel pressure boundary. Specifically, potential gamma doses from steady state operation combined with multiple LOCEs, a limiting fault LOCA, or a LOCA-MHA exceed the damage threshold for the teflon seal rings in the H and V system 9 containment isolation valves