This paper presents a brief summary of the methodology used for the as
sessment of risk arising from fuel handling and dismantling operations
in advanced gas-cooled reactor power stations. The difficulties with
and problems arising from such risk assessments are discussed. In part
icular, difficulties arise from (i) the onerous risk criteria that nuc
lear plants are expected to satisfy, (ii) the necessary complexity of
the plant, (iii) the conflicting requirements for the fault consequenc
e assessments to be bounding but not grossly pessimistic, and (iv) are
as of fault frequency assessment which contain possibly subjective con
siderations such as software and common mode failure.