Codes and Standards - std0100t0048

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."

1.25, "Assumptions Used for

Regulatory

Guide

Evaluating the Potential Radiological Consequences of a Fuel Han-

dling Accident in the Fuel Handling and Storage Facility for

Boiling and Pressurized Water Reactors."

Regulatory Guide 1.60, "Design Response Spectra

for Seismic Design of Nuclear Power Plants."

1.77, "Assumptions Used for

Regulatory

Guide

Evaluating a Control Rod Ejection Accident for Pressurized Water

Reactors."

Regulatory Guide 1.126, "An Acceptable Model and

Related Statistical Methods for the Analysis of Fuel Densifica-

tion."

Regulatory Guide 1.145, "Atmospheric Dispersion

Models for Potential Accident Consequence Assessments at Nuclear

Power Plants."

Regulatory Guide 2.3, "Quality Verification for

Plate-Type Uranium-Aluminum Fuel Elements for Use in Research

Reactors."

SRP 4.2, Appendix A, "Evaluation of Fuel Assembly

Structural Responses to Externally Applied Forces."

4.2.3

Codes and Standards

ANSI N398-1974, "Quality Verification for Plate-

Type Uranium-Aluminum Fuel Elements." (This standard was revised

and issued as ANSI/ANS 15.2-1974(R1982), "Quality Control for

Plate-Type Uranium-Aluminum Fuel Elements.")

ASME Boiler and Pressure Vessel Code, Section III,

"Rules for Construction of Nuclear Power Plant Components," Divi-

sion 1.

Specification for

ASTM C776-1983, "Standard

Sintered Uranium Dioxide Pellets."

(This standard was revised

and issued as ASTM C776-1986, "Specification for Sintered Uranium

Dioxide Pellets.")

4-2