The R5 defect assessment procedures are widely used to assess componen
ts in Nuclear Electric's Advanced Gas-Cooled Reactor plant. In this pa
per, the use of R5 is illustrated by calculating the creep-fatigue cra
ck growth in a specific component. The resulting crack size is compare
d with the limiting crack size calculated using R6. The implications o
f considering ductile tearing in the latter calculation, the possible
interaction of tearing with creep crack growth, and the use of leak be
fore break arguments are discussed.