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This chapter identifies criteria for the engineered
safety features addressed in Regulatory Guide 1.70 that are com-
monly used to limit the consequences of postulated accidents in
light-water-cooled power reactors.
6.1.1
Code of Federal Regulations
10 CFR 50.55a, "Codes and Standards."
A.
10 CFR 50, Appendix A, "General Design Criteria for
B.
Nuclear Power Plants."
"Quality Standards and Records."
GDC 1,
1.
"Environmental and Missile Design
GDC
4,
2.
Bases."
"Reactor Coolant Pressure Boundary."
3.
GDC 14,
"Fracture Prevention of Reactor
4.
GDC  31,
Coolant Pressure Boundary."
"Emergency Core Cooling."
5.
GDC 35,
"Containment Atmosphere Cleanup."
6.
GDC 41,
"Fracture Prevention of Containment
7.
GDC 51,
Pressure Boundary."
10 CFR 50, Appendix B, "Quality Assurance Criteria
C.
for Nuclear Power Plants and Fuel Reprocessing Plants."
USNRC Regulatory Guides, SRP Branch Technical Positions
6.1.2
and Appendices
Regulatory  Guide 1.7, "Control of Combustible Gas
A.
Concentrations in Containment Following a Loss-of-Coolant Acci-
dent."
Guide  1.31,
"Control of Ferrite Con-
B.
Regulatory
tent in Stainless Steel Weld Metal."
1.36,  "Nonmetallic Thermal
Guide
C.
Regulatory
Insulation for Austenitic Stainless Steel."
6-1


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