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|  DOE-STD-101-92
Regulatory Guide 1.145, "Atmospheric Dispersion
D.
Models for Potential Accident Consequence Assessments at Nuclear
Power Plants."
Regulatory Guide 3.33, "Assumptions Used for
E.
Evaluating the Potential Radiological Consequences of Accidental
Nuclear Criticality in a Fuel Reprocessing Plant."
Regulatory Guide 3.34, "Assumptions Used for
F.
Evaluating the Potential Radiological Consequences of Accidental
Nuclear Criticality in a Uranium Fuel Fabrication Plant."
Regulatory Guide 3.35, "Assumptions Used for
G.
Evaluating the Potential Radiological Consequences of accidental
Nuclear Criticality in a Plutonium Processing and Fuel Fabrica-
tion Plant."
ANSI/ANS 2.17-1980, "Evaluation of Radionuclide
A.
Transport in Ground Water for Nuclear Power Sites."
A.
NUREG-1320, "Nuclear Fuel Cycle Facility Accident
Analysis Handbook," USNRC, May 1988.
NUREG-1179, "Rupture of Model 48Y UF6 Cylinder and
B.
Release of Uranium Hexafluoride," USNRC, February 1986.
C.
NUREG-0772, "The Effects of Natural Phenomena on
the Exxon Nuclear Company Mixed-Oxide Fabrication Plant at
Richland Washington," USNRC, September 1980.
NUREG/CR-4303, "High-Level Waste Preclosure Systems
D.
Safety Analysis, " GA Technologies, Inc., September 1985.
NUREG/CR-3682, "Nuclear Fuel Cycle Risk Assessment-
E.
Review and Evaluation of Existing Methods," Pelto, P.J. et al.,
Battelle Pacific Northwest Laboratories, May 1984.
NUREG/CR-3210, "Low-Level Waste Risk Methodology
F.
Development," Cox, N.D. et al., EG&G Inc., May 1983.
G.
NUREG/CR-3139, "Scenarios and Analytical Methods
for UF6 Releases at NRC-Licensed Fuel Cycle Facilities," Siman-
Tov, M. et al., Oak Ridge National Laboratory, July 1984.
10-2
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