References
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- “Standard Review Plan for the Review of a License Application for a Fuel Cycle Facility,” NUREG-1520, U.S. Nuclear Regulatory Commission (2010).
- K. Takebe et al., “The Experience of Risk Assessment and its Future Utilization at Rokkasho Reprocessing Plant,” Proc. Workshop on Fuel Cycle Safety—Past, Present, and Future, Wilmington, North Carolina, October 16-18, 2007, Organisation for Economic Co-operation and Development/Nuclear Energy Agency.
- M. T. Ryan, Memorandum to D. Klein, “Regulation of Advanced Spent Nuclear Fuel Reprocessing and Refabrication Facilities,” ACNWMR-0270 (Oct. 11, 2007); http://pbadupws.nrc.gov/docs/ML0728/ML072840119.pdf (current as of October 19, 2012).
- Code of Federal Regulations, Title 10, “Energy,” Part 70, “Domestic Licensing of Special Nuclear Material,” Sec. 70.4, “Definitions,” U.S. Nuclear Regulatory Commission (2011).
- Code of Federal Regulations, Title 10, “Energy,” Part 70, “Domestic Licensing of Special Nuclear Material,” Sec. 70.61, “Performance Requirements,” U.S. Nuclear Regulatory Commission (2012).
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- C. F. Miller et al., “Data Summaries of Licensee Event Reports of Valves at U.S. Commercial Nuclear Power Plants,” Rev. 1, NUREG/CR-1363, U.S. Nuclear Regulatory Commission (1982); see also “IEEE Guide to the Collection and Presentation of Electrical, Electronic, Sensing Component and Mechanical Equipment Reliability Data for Nuclear-Power Generating Stations,” Standard 500-1984, IEEE (1983); see also “Data Summaries of licensee Event Reports of Pumps at U.S. Commercial Nuclear Power Plants,” Rev. 1, NUREG-1205, U.S. Nuclear Regulatory Commission (Jan. 1982); see also A. D. Swain and H. E. Guttmann, “Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications—Final Report,” NUREG/CR-1278, U.S. Nuclear Regulatory Commission (1983).
- “Industry-Average Performance for Components and Initiating Events at U.S. Commercial Nuclear Power Plants,” NUREG/CR-6928, U.S. Nuclear Regulatory Commission (2007); see also http://www.nucia.jp/NRIA/RePORT/PDF/REPORT200905.pdf (current as of May 27, 2011) (in Japanese); see also A. Blanchard, “Savannah River Site Generic Data Base Development,” WSRC-TR-93-262, Rev. 1, Savannah River Site (1998).
- T. P. McLaughlin et al., “A Review of Criticality Accidents,” LA-13638, Los Alamos National Laboratory (2000).