USNRC Regulatory Guides and SRP Branch Technical Positions and Appendices

10 CFR 20.207, "Storage and Control of Licensed

Materials in Unrestricted Areas."

10 CFR 50.34, "Contents of Applications; Technical

Information."

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

Nuclear Power Plants."

Storage and

Handling

and

"Fuel

GDC 61,

USNRC Regulatory Guides and SRP Branch Technical Posi-

12.2.2

tions 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Guides 1 .3 and 1.4 is superseded by the method presented in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."

Guide 1.3, "Assumptions Used for

Regulatory

Evaluating the Potential Radiological Consequences of a Loss-of-

Coolant Accident for Boiling Water Reactors."

Guide 1.4, "Assumptions Used for

Regulatory

Evaluating the Potential Radiological Consequences of a Loss-of-

Coolant Accident for Pressurized Water Reactors."

Regulatory Guide 1.7, "Control of Combustible Gas

Concentrations in Containment Following a Loss-of-Coolant Acci-

dent."

Regulatory Guide 1.112, "Calculation of Releases

of Radioactive Materials in Gaseous and Liquid Effluents from

Light-Water-Cooled Power Reactors."

Regulatory Guide 1.145, "Atmospheric Dispersion

Models for Potential Accident Consequence Assessments at Nuclear

Power Plants."

12.2.3

Codes and Standards

ANSI N237-1976, "Source Term Specification." (This

standard was revised and issued as ANSI/ANS 18.1-1984, "Radioac-

tive Source Term for Normal Operation of Light Water Reactors.")

ANSI/ANS 18.1-1984, "Radioactive Source Term for

Normal Operation of Light-Water Reactors."

12-3