USNRC Regulatory Guides, SRP Branch Technical Positions and Appendices

USNRC Regulatory Guides, SRP Branch Technical Positions

15.1.2

and Appendices

Guide 1.4, "Assumptions Used for

Regulatory

Evaluating the Potential Radiological Consequences of a Loss-of-

(The method of

Coolant Accident for Pressurized Water Reactors."

calculating X/Q values in this guide is superseded by the method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.")

1.53, "Application of the

Guide

Regulatory

Single-Failure Criterion to Nuclear Power Plant Protection Sys-

tems."

1.145, "Atmosphere Dispersion

Regulatory

Guide

Models for Potential Accident Consequence Assessments at Nuclear

Power Plants."

Branch Technical Position ASB 3-1,

SRP

3.6.1,

"Protection Against Postulated Piping Failures in Fluid Systems

Outside Containment."

Branch Technical Position MEB 3-1,

SRP

3.6.2,

"Postulated Rupture Locations in Fluid System Piping Inside and

Outside Containment."

SRP 15.1.5, Appendix A, "Radiological Consequences

of Main Steam Line Failures Outside Containment of a PWR."

Codes and Standards

15.1.3

ASME Boiler and Pressure Vessel Code, "Rules for

Construction of Nuclear Power Plant Components," Section III,

Division 1, Article NB-7000, "Protection Against Overpressure."

IEEE

379-1972, "IEEE Trial-Use Guide for the

Application of the Single-Failure Criterion to Nuclear Power Gen-

erating Station Class 1E Systems." (This standard was revised and

issued as IEEE 379-1988, "IEEE Standard Application of the

Single-Failure Criterion to Nuclear Power Generating Station

Class 1E Systems.")

15.1.4

Supplemental Information

NUREG-0800,

USNRC "Standard Review Plan," June

1987.

SRP

15.1.1,

"Decrease in Feedwater Tempera-

ture."

15-2