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|  This section identifies criteria for the materials,
pressure-temperature limits, and integrity of the reactor vessel.
Code of Federal Regulations
5.3.1
10 CFR 50.55a, "Codes and Standards."
A.
10 CFR 50.60, "Acceptance Criteria for Fracture
B.
Prevention Measurements for Light-Water Nuclear Power Reactors
for Normal Operation."
10 CFR 50.61, "Fracture Toughness Requirements for
C.
Protection Against Pressurized Thermal Shock Events."
10 CFR 50, Appendix A, "General Design Criteria for
D.
Nuclear Power Plants."
1, "Quality Standards and Records."
GDC
1.
"Environmental and Missile Design
GDC
4,
2.
Bases."
GDC
14, "Reactor Coolant Pressure Boundary."
3.
30, "Quality of Reactor Coolant Pressure
4.
GDC
Boundary."
GDC 31, "Fracture Prevention of the Reactor
5.
Coolant Pressure Boundary."
GDC 32, "Inspection of Reactor Coolant Pres-
6.
sure Boundary."
10 CFR 50, Appendix B, "Quality Assurance Criteria
E.
for Nuclear Power Plants and Fuel Reprocessing Plants."
10 CFR 50, Appendix G, "Fracture Toughness Require-
F.
ments."
"Reactor Vessel Material
G.
10 CFR 50, Appendix H,
Surveillance Program Requirements."
USNRC Regulatory Guides, SRP Branch Technical Postions
5.3.2
and Appendices
Guide 1.2, "Thermal Shock to Reactor
A.
Regulatory
Pressure Vessels."
Regulatory Guide 1.31,
"Control of Ferrite Con-
B.
tent in Stainless Steel Weld Metal."
5-5
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