|
| This section identifies criteria for the design of ESF
systems for fission product removal from post accident atmo-
spheres by filtration, adsorption, and spray systems, and
-
includes structures to contain these atmospheres.
6.5.1
Code of Federal Regulations
10 CFR 50, Appendix A, "General Design Criteria for
A.
Nuclear Power Plants."
"Control Room."
1.
GDC 19,
2.
GDC 41,
"Containment Atmosphere Cleanup."
"Inspection of Containment Atmo-
3.
GDC 42,
sphere Cleanup Systems."
4.
"Testing of Containment Atmosphere
GDC 43,
Cleanup Systems."
5.
GDC
61,
"Fuel Storage and Handling and
Radioactivity Control."
6.
GDC 64,
"Monitoring Radioactivity Releases."
B.
10 CFR 100.11, "Determination of Exclusion Area,
Low Population Zone, and Population Center Distance."
6.5.2
USNRC Regulatory Guides, SRP Branch Technical Positions
and Appendices
The method of calculating X/Q values in regulatory
guides 1.3, 1.4, and 1.25 is superseded by the method presented
in Regulatory Guide 1.145, "Atmospheric Dispersion Models for
Potential Accident Consequence Assessments at Nuclear Power
Plants."
A.
Regulatory
Guide 1.3, "Assumptions Used for
Evaluating the Potential Radiological Consequences of a Loss-of-
Coolant Accident for Boiling Water Reactors."
B.
Regulatory
Guide 1.4, "Assumptions Used for
Evaluating the Potential Radiological Consequences of a Loss-of-
Coolant Accident for Pressurized Water Reactors."
C.
Regulatory Guide 1.7, "Control of Combustible Gas
Concentrations in Containment Following a Loss-of-Coolant Acci-
dent."
6-13
|
Privacy Statement - Press Release - Copyright Information. - Contact Us |