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Page Title:
Anticipated Transients Without Scram |
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|  Supplemental Information
15.7.4
USNRC "Standard Review Plan," June
NUREG-0800,
A.
1987.
1.
SRP 15.7.3, "Postulated Radioactive Releases
Due to Liquid-Containing Tank Failures."
2.
SRP
"Radiological Consequences of
15.7.4,
Fuel Handling Accidents."
SRP 15.7.5, "Spent Fuel Cask Drop Accidents."
3.
NUREG-0133,
"Preparation of Radiological Effluent
B.
Technical Specifications for Nuclear Power Plants," USNRC, Octo-
ber 1978.
15.8.1
Code of Federal Regulations
A.
10 CFR 50.62, "Requirements for Reduction of Risk
from Anticipated Transients Without Scram (ATWS) Events for
Light-Water-Cooled Nuclear Power Plants."
B.
10 CFR 50, Appendix A, "General Design Criteria for
Nuclear Power Plants."
1.
GDC 10, "Reactor Design."
2.
GDC 15, "Reactor Coolant System Design."
3.
GDC 26, "Reactivity Control System Redundancy
and Capability."
4.
GDC 27, "Combined Reactivity Control Systems
Capability."
5.
GDC 29, "Protection Against Anticipated Oper-
ational Occurrences."
15.8.2
USNRC Regulatory Guides, SRP Branch Technical Positions
and Appendices
None.
15.8.3
Codes and Standards
None.
15-16
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