Radioactive Release From a Subsystem or Component

15.7

RADIOACTIVE RELEASE FROM A SUBSYSTEM OR COMPONENT

This section identifies criteria for initiating events

that involve postulated radioactive releases due to liquid-

containing tank failures, radiological consequences of fuel-

handling accidents, and spent fuel cask drop accidents.

15.7.1

Code of Federal Regulations

10 CFR 20, Appendix B, "Concentrations in Air and

Water Above Background."

"Control of Applications; Technical

10 CFR 50.34,

Information."

10 CFR 50.36a, "Technical

Specifications

Effluents from Nuclear Power Reactors."

10 CFR 50, Appendix A, "General Design Criteria for

Nuclear Power Plants."

GDC 60, "Control of Releases of Radioactive

Materials to the Environment."

Handling and

GDC

61,

"Fuel

Storage

and

Radioactivity Control."

10 CFR 100.11, "Determination of Exclusion Area,

Low Population Zone, and Population Center Distance."

15.7.2

USNRC Regulatory Guides, SRP Branch Technical Positions

and Appendices

Regulatory

Guide

1.25, "Assumptions Used for

Evaluating the Potential Radiological Consequences of a Fuel-

Handling Accident in the Fuel Handling and Storage Facility for

Boiling and Pressurized Water Reactors."

(The method of cal-

culating X/Q values in this guide is superseded by the method

presented in Regulatory Guide 1.145, "Atmospheric Dispersion

Models for Potential Accident Consequence Assessments at Nuclear

Power Plants.")

1.145, "Atmospheric Dispersion

Regulatory Guide

Models for Potential Accident Consequence Assessments at Nuclear

Power Plants."

15.7.3

Codes and Standards

None.

15-15