Abstract: This report documents the Federal/State regulatory permitting actions in 12 case histories of nuclear power station licensing in nine different states. General observations regarding Federal/State siting roles in the siting process include: new regulations, with the exceptions of those imposed by NEPA, were not found to be the source of significant delay; interventions were the sources of significant delay in only two cases; in only two cases was a local agency a source of delay; no one factor was found to be a source of delay, rather several factors often combined to cause delay; it is still too early to assess the influence of State power plant siting laws on the licensing process; clarification of the word "delay" is needed; water related issues predominate in State permitting requirements associated with delay; generalizations on the sources and nature of delay in the licensing process are difficult to make because of site specific characteristics; and frequently problems outside the Federal/State realm have had, or can have, a delaying effect on the process. Eleven of the case histories are illustrated with a logic network that gives the actions of the utilities in addition to the Federal/State permits.

This report presents the analysis of the fuel rod materials behavior based on the postirradiation examination of the Test PCM-1 fuel rod from the Power-Cooling-Mismatch Test Series.

Appendix to report presenting detailed data from the postirradiation examination and pretest characterization for Test PCM-1, including the U0₂ oxidation calculation.

Appendix to report presenting detailed data from the postirradiation examination and pretest characterization for Test PCM-1, including changes in cladding thermal conductivity with oxidation to ZrO₂.

Appendix to report presenting detailed data from the postirradiation examination and pretest characterization for Test PCM-1, including additional metallography illustrating the physical and chemical changes in the cladding and fuel.

Appendix to report presenting detailed data from the postirradiation examination and pretest characterization for Test PCM-1, including tabulated data from the particle size analysis of the broke fuel rod pieces.

Appendix to report presenting detailed data from the postirradiation examination and pretest characterization for Test PCM-1, including a description of the axial power profile.

Report presenting the pretest physical characteristics and instrumentation of the Test PCM-1 (Power-Cooling Mismatch Test Series) fuel rod and shroud components.

Appendix to report presenting detailed data from the postirradiation examination and pretest characterization for Test PCM-1, including details of the microprobe examination.