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Page Title:
Decrease in Forced Reactor Coolant Flow Rate |
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|  This section identifies criteria for initiating events
that involve loss of forced reactor coolant flow, trip of pump
motor and flow controller malfunctions, and reactor coolant pump
rotor seizure and pump shaft break.
Code of Federal Regulations
15.3.1
10 CFR 50.34, "Contents of Applications; Technical
A.
Information."
10 CFR 50, Appendix A, "General Design Criteria for
B.
Nuclear Power Plants."
10, "Reactor Design."
GDC
1.
15, "Reactor Coolant System Design."
2.
GDC
26, "Reactivity Control System Redundancy
GDC
3.
and Capability."
4.
GDC
27, "Combined Reactivity Control Systems
Capability."
28, "Reactivity Limits."
5.
GDC
6.
GDC
31,
Prevention
of
Reactor
Coolant Pressure Boundary."
C.
10 CFR 100.11, "Determination of Exclusion Area,
Low Population Zone, and Population Center Distance."
15.3.2
USNRC Regulatory Guides, SRP Branch Technical Positions
and Appendices
Regulatory Guide
1.145, "Atmospheric Dispersion
A.
Models for Potential Accident Consequence Assessments at Nuclear
Power Plants."
15.3.3
Codes and Standards
A.
ASME Boiler and Pressure Vessel Code, "Rules for
Construction of Nuclear Power Plant Components," Section III,
Division 1, Article NB-7000, "Protection Against Overpressure."
15-6
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