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.

Graphs showing power calibration and preconditioning data for the second of six planned tests in the Reactivity Initiated Accident (RIA) Test Series 1, Test RIA 1-2. Results are presented for the time after the start of power calibration in hours for each variable (see pages ix - xi of report).

Computer-generated graphical and tabular presentations of transient test and posttest deformation data for Multirod Burst Test (MRBT) Bundle B-6 (see pages 131-141 of report). "The primary objective of this 8 x 8 multirod burst test was to investigate cladding de-formation in the alpha-plus-beta-Zircaloy temperature range under simulated light-water-reactor (LWR) loss-of-coolant accident (LOCA) conditions. B-6 test conditions simulated the adiabatic heatup (reheat) phase of an LOCA and produced very uniform temperature distributions." - from Abstract

Graphical presentations of data from the 1/5-scale Mark I BWR Pressure Suppression Experiment (PSE) air transient tests, including HVLF Characterization Data, Impulse Characterization, Computed Load Cell Response Histories and Frequency Analyses, and Enthalpy Flux Evaluation (see Table E-1. Summary of microfiche descriptions)