Thermal and Hydraulic Design

NUREG-0085, "The Analysis of Fuel Densification,"

USNRC, July 1976.

BNL-50274 (ENDF-102), "Data Formats and Procedures

for the ENDF Neutron Cross Section Library," M.K. Drake, ed.,

National Neutron Cross Section Center, Brookhaven National

Laboratory, 1970.

4.4

4.4.1

Code of Federal Regulations

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

Nuclear Power Plants."

GDC 10, "Reactor Design."

USNRC Regulatory Guides, SRP Branch Technical Positions

4.4.2

and Appendices

Regulatory Guide 1.68, "Initial Test Programs for

Water-Cooled Nuclear Power Plants."

1.133, "Loose Parts Detection

Regulatory Guide

Program for the Primary Systems of Light-Water-Cooled Reactors."

4.4.3

Codes and Standards

None.

4.4.4

Supplemental Information

NUREG-0800,

USNRC "Standard Review Plan," June

1987.

SRP 4.4, "Thermal and Hydraulic Design."

NUREG-0718,

"Licensing Requirements for Pending

Applications for Construction Permits and Manufacturing License,"

Item II.F.2, USNRC, March 1981.

NUREG-0737 ,

"Clarification of TMI Action Plan

Requirements," Item II.F.2, USNRC, November 1980.

4.5

This section identifies criteria for control rod drive

system structural materials and reactor internal materials.

4-5