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Page Title:
Mechanical System and Components |
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|  This section identifies criteria for ASME Code and non-
Code items, control rod drive systems, and reactor pressure ves-
sel internals.
Code of Federal Regulations
3.9.1
10 CFR 50.55a, "Codes and Standards."
A.
10 CFR 50, Appendix A, "General Design Criteria for
B.
Nuclear Power Plants."
1, "Quality Standards and Records."
GDC
1.
2, "Design Bases fox Protection Against
GDC
2.
Natural Phenomena."
4,
"Environmental
and
Missle
Design
GDC
3.
Bases."
10, "Reactor Design."
GDC
4.
14, "Reactor Coolant Pressure Boundary."
GDC
5.
15, "Reactor Coolant System Design."
GDC
6.
26, "Reactivity Control System Redundancy
GDC
7.
and Capability."
27, "Combined Reactivity Control Systems
GDC
8.
Capability."
29, "Protection Against Anticipated Oper-
GDC
9.
ational Occurrences."
37, "Testing of Emergency Core Cooling
GDC
10.
System."
40, "Testing of Containment Heat Removal
GDC
11.
System."
43, "Testing of Containment Atmosphere
GDC
12.
Cleanup Systems."
46, "Testing of Cooling Water Systems."
GDC
13.
54, "Piping Systems Penetrating Contain-
GDC
14.
ment."
10 CFR 100, Appendix A, "Seismic and Geologic
C.
Siting Criteria for Nuclear Power Plants."
3-13
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