NUREG-1801, Rev. 1, Section XI.M.13, states that an ASME Code Section XI VT-3 examination is required to be performed of reactor internal components. In addition, the NUREG report specifies that for the license renewal period, these inspections shall be augmented by an aging management program to assess the synergistic effects of thermal aging and neutron embittlement of cast austenitic stainless steel (CASS) components. This aging management program consists of (a) identifying susceptible components; and (b) either performing additional inspections of these components, or performing a component-specific evaluation to confirm that the stresses in the components are sufficiently low such that augmented inspections are not warranted. This paper presents the results of evaluations conducted to assess the potential synergistic effects of thermal aging and neutron embrittlement of CASS components in BWR internals and recommend augmented inspections if needed. The evaluation shows that all the BWR CASS components have ferrite levels below the level for which aging embrittlement is a concern. Furthermore, for the Control Rod Guide Tube Base and Core Spray Sparger Nozzle Elbows, the end of life fluence is less than the threshold value for toughness loss. The end-of-life fluence levels for the orificed fuel support, the jet pump assembly castings and the Low Pressure Core Injecion (LPCI) Couplings exceed the threshold, but the toughness data for irradiated austenitic stainless steel show that these components will have sufficient fracture toughness at end of the license renewal period so that augmented inspection is not required. It is concluded that augmented inspections are not required for the BWR CASS internals.