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|  and drop accidents.
Code of Federal Regulations
15.4.1
"Control of Applications; Technical
10 CFR 50.34,
A.
Information."
10 CFR 50, Appendix A, "General Design Criteria for
B.
Nuclear Power Plants."
GDC 10, "Reactor Design."
1.
GDC 13, "Instrumentation and Control."
2.
3.
GDC 15, "Reactor Coolant System Design."
4.
GDC 20, "Protection System Functions."
GDC 25, "Protection System Requirements for
5.
Reactivity Control Malfunctions."
6.
GDC 26, "Reactivity Control System Redundancy
and Capability."
7.
GDC 28, "Reactivity Limits."
C.
10 CFR 100.11, "Determination of Exclusion Area,
Low Population Zone, and Population Center Distance."
15.4.2
USNRC Regulatory Guides, SRP Branch Technical Positions
and Appendices
A.
Regulatory
Guide
1.53, "Application of the
Single-Failure Criterion to Nuclear Power Plant Protection Sys-
tems."
B.
Regulatory
Guide
1.77, "Assumptions Used for
Evaluating a Control Rod Ejection Accident for Pressurized Water
Reactors."
(The method of calculating X/Q values in this guide
is superseded by the method presented in Regulatory Guide 1.145,
"Atmospheric Dispersion Models for Potential Accident Con-
sequences Assessments at Nuclear Power Plants.")
C.
Regulatory
Guide
1.105, "Instrument Setpoints for
Safety-Related Systems."
D.
Regulatory Guide
1.145, "Atmospheric Dispersion
Models for Potential Accident Consequence Assessments at Nuclear
Power Plants."
SRP
15.4.8,
E.
Appendix A, "Radiological
Con-
sequences of a Control Rod Ejection Accident (PWR)."
15-8
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