Abstract: A Final Environmental Statement for the Power Authority of the State of New York for the construction of the Greene County Nuclear Power Plant (Docket No. 50-549) located in Greene County, New York, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission (NRC). This statement provides (1) a summary of environmental impact and adverse effects of the proposed facility, and (2) a consideration of principal alternatives. Also included are comments of governmental agencies and other organizations on the Draft Environmental Statement for the project and staff responses to these comments. The NRC staff has concluded, based on a weighing of environmental, economic, technical, and other benefit against environmental costs and available alternatives, that a construction permit should be denied because the alternative sites available to the applicant are environmentally preferable. If the permit is granted, the applicant will be required to take the necessary mitigating actions to decrease the aesthetic impact by using alternative closed cycle cooling systems and to undertake monitoring programs to identify, evaluate and mitigate construction related community and public services impacts in the immediate three-county impact area.

This report examines the adequacy of existing fire-hazards analysis methodology in the context of nuclear power plant safety

A report presenting the results from Power-Cooling-Mismatch Test CM-3

Appendix to Test PCM-3 report presenting a description of the "instrumentation and the calibration equations that were used to convert the transducer output to engineering units during the data reduction process." (p. 61)

Report presenting the results of thermal heat balance power calibration and neutron flux axial distribution measurements for the Power-Cooling-Mismatch Test PCM-3.

Report presenting data plots for selected parameters measured during Test PCM-3 of the Power-Cooling-Mismatch Test Series.

Report presenting pretest characterization measurements for two of the four Power-Cooling Mismatch Test PCM-3 fuel rods, Rods UTA-0011 and UTA-0013.

Report to appendix presenting a comparison of the calculated and measured fuel rod behavior determined during steady state power calibration, the onset of departure from nucleate boiling (DNB), and post-DNB test for Power-Cooling Mismatch Test PCM-3. (p. 155)

Report presenting estimates of the methods used to establish fuel rod cladding temperatures for Test PCM-3 using three techniques: metallographic examination of the cladding microstructures, isothermal reaction rate correlations, and BUILD5 computer code calculations.

This report presents and discusses the results from Test PCM-4 of the Power-Cooling-Mismatch Test Series.

"A summary of the methods used to establish fuel rod cladding temperatures associated with the axial region of film boiling for Test PCM-4 and the results of the calculations are presented in this appendix." (p. 219)

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.

"A comparison of the calculated and measured fuel rod behavior (cladding elongation, fuel centerline temperature, and fuel rod internal pressure) determined during the steady state power calibration, onset of departure from nucleate boiling (DNB), and post-DNB testing is presented in this appendix" (p. 184).

Report providing tabulated data for pretest measurements preformed to characterize three of the four Power-Cooling-Mismatch (PCM-4) fuel rods, Rods UTA-0014, UTA-0015, and UTA-0016.

Description of the test assembly and instrumentation used for Power-Cooling-Mismatch (PCM) Test Series, Test PCM-1 that includes a table and figures illustrating elements of the facility and test train assembly.

Description of the analytical methods and results for the Power-Cooling-Mismatch (PCM) Test Series, Test PCM-1.

Report providing a description of the FRAP-T4 (Fuel Rod Analysis Program - Transient) computer code used for Power-Cooling-Mismatch (PCM) Test Series, Test PCM-1.