Code of Federal Regulations

steam generator tube failure, main steam line failure outside

containment, and loss of coolant accidents resulting from a spec-

trum of postulated piping breaks within the reactor coolant pres-

sure boundary.

15.6.1

Code of Federal Regulations

10 CFR 50.34, "Contents of Applications; Technical

Information."

10 CFR 50.44, "Standards for Combustible Gas Con-

trol System in Light-Water-Cooled Power Reactors."

10 CFR 50.46, "Acceptance Criteria for Emergency

Core Cooling Systems for Light-Water Nuclear Power Reactors."

10 CFR 50.61, "Fracture Toughness Requirements for

Protection Against Pressurized Thermal Shock Events."

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

Nuclear Power Plants."

GDC 10, "Reactor Design."

GDC 15, "Reactor Coolant System Design."

GDC 26, "Reactivity Control System Redundancy

and Capability."

GDC 35, "Emergency Core Cooling."

GDC 41, "Containment Atmosphere Cleanup."

GDC 55, "Reactor Coolant Pressure Boundary

Penetrating Containment."

10 CFR 50, Appendix K, "ECCS Evaluation Models."

10 CFR 100.11, "Determination of Exclusion Area,

Low Population Zone, and Population Center Distance."

15.6.2

USNRC Regulatory Guides, BRP Branch Technical Positions

and Appendices

The method of calculating X/Q values in Regulatory

Guides 1.3, 1.4, and 1.5 is superseded by the method presented in

Regulatory Guide 1.145, "Atmospheric Dispersion Models for Poten-

tial Accident Consequence Assessments at Nuclear Power Plants."

Regulatory

Guide 1.3, "Assumptions Used for

Evaluating the Potential Radiological Consequences of a Loss-of-

Coolant Accident for Boiling Water Reactors."

15-12