Chapter 4 Reactor

This chapter identifies criteria for establishing the

capability of the reactor to perform its safety functions

throughout its design lifetime under all normal operational

modes, including both transient and steady state, and accident

conditions.

4.1

This section in an SAR contains a summary description of

the mechanical, nuclear, and thermal and hydraulic designs of the

various reactor components, including the fuel, reactor vessel

internals, and reactivity control systems.

No specific NRC

criteria are specified for this summary description.

4.2

4.2.1

Code of Federal Regulations

10 CFR 50.46, "Acceptance Criteria for Emergency

Core Cooling Systems for Light Water Nuclear Power Reactors."

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

Nuclear Power Plants."

GDC 10,

"Reactor Design."

GDC 27,

"Combined Reactivity Control Systems

Capability."

GDC 35,

"Emergency Core Cooling."

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

10 CFR 100.11, "Determination of Exclusion Area,

Low Population Zone, and Population Center Distance."

4.2.2

USNRC Regulatory Guides, SRP Branch Technical Positions

and Appendices

The method of calculating X/Q values in Regulatory

Guides 1.3, 1.4, 1.25, and 1.77 is superseded by the method pre-

sented in Regulatory Guide 1.145, "Atmospheric Dispersion Models

for Potential Accident Consequence Assessments at Nuclear Power

Plants."

4-1