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Page Title:
USNRC Regulatory Guides, SRP Branch Technical Positions and Appendices |
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|  15.
GDC 52,
"Capability for Containment Leakage
Rate Testing."
"Provisions for Containment Testing
16.
GDC 53,
and Inspection."
17.
GDC 54,
"Piping Systems Penetrating Contain-
ment."
18. GDC 55,
"Reactor Coolant Pressure Boundary
Penetrating Containment."
19.
GDC 56,
"Primary Containment Isolation."
"Closed Systems Isolation Valves."
20.
GDC 57,
"Monitoring Radioactivity Releases."
21.
GDC 64,
F.
10 CFR 50,
Appendix J, "Primary Reactor Contain-
ment Leakage Testing for Water-Cooled Power Reactors."
G.
10 CFR 50,
Appendix K, "ECCS Evaluation Models."
H.
10 CFR 100.11, "Determination of Exclusion Area,
Low Population Zone, and Population Center Distance."
6.2.2
USNRC Regulatory Guides, SRP Branch Technical Positions
and Appendices
The method of calculating X/Q values in Regulatory
Guides 1.3 and 1.4 is superseded by the method presented in
Regulatory Guide 1.145, "Atmospheric Dispersion Models for Poten-
tial Accident Consequence Assessments at Nuclear Power Plants."
A.
Regulatory Guide 1.1, "Net Positive Suction Head
for Emergency Core Cooling and Containment Heat Removal System
Pumps."
B.
Regulatory
Guide 1.3, "Assumptions Used for
Evaluating the Potential Radiological Consequences of a Loss-of-
Coolant Accident for Boiling Water Reactors."
C.
Regulatory
Guide 1.4, "Assumptions Used for
Evaluating the Potential Radiological Consequences of a Loss-of-
Coolant Accident for Pressurized Water Reactors."
D.
Regulatory Guide 1.7, "Control of Combustible Gas
Concentrations in Containment Following a Loss-of-Coolant Acci-
dent."
6-5
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