High chromium nickel-base Alloy 690 materials exhibit an increased resistance to stress corrosion cracking (SCC) in pressurized water reactor (PWR) primary water environments over lower chromium alloy 600. As a result alloy 690 has been used to replace alloy 600 for steam generator tubing and reactor pressure vessel nozzles. However recent laboratory testing has revealed that highly cold-worked alloy 690 materials can become susceptible to SCC. In an effort to evaluate reasons for this SCC susceptibility detailed characterizations have been performed using Vickers hardness measurements scanning electron microscopy and electron backscatter diffraction (EBSD). Testing was performed on cross sections of alloy 690 compact tension crack growth test specimens that were run in simulated primary water at a variety of cold-work reductions ranging from 0% to 32%. Hardness and the EBSD integrated misorientation density could both be related to the overall cold work in the sample for materials of similar grain size. However a strong microstructural dependence was observed in the as tested samples. Correlations will also be discussed between the current measurements and the measured SCC growth rates.