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|  DOE-STD-101-92
The criteria in this chapter are for initiating events
that result in a criticality accident.
Technical
10 CFR 50.34, "Contents of Applications:
A.
Information."
10 CFR 60.21, "Content of Application."
B.
10 CFR 61.13, "Technical Analyses."
C.
10 CFR 70.22, "Content of Applications."
D.
"Requirements for the Approval of
E.
10 CFR 70.23,
Applications."
Technical
10 CFR 72.24, "Contents of Application:
F.
Information."
G.
10 CFR 100.11, "Determination of Exclusion Area,
Low Population Zone, and Population Center Distance."
A.
Regulatory Guide 1.25, "Assumptions Used for
Evaluating the Potential Radiological Consequences of a Fuel-
Handling Accident in the Fuel-Handling and Storage Facility for
(The method of cal-
Boiling and Pressurized Water Reactors."
culating X/Q values in this guide is superseded by the method
presented in Regulatory Guide 1.145, "Atmosphere Dispersion
Models for Potential Accident Consequence Assessments at Nuclear
Power Plants.")
Regulatory Guide 1.91, "Evaluations of Explosions
B.
Postulated to Occur on Transportation Routes Near Nuclear Power
Plants."
Regulatory Guide 1.113, "Estimated Aquatic Disper-
C.
sion of Effluents from Accidental and Routine Releases for the
Purpose of Implementing Appendix I."
10-1
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