Appendix C: Other Government Documents - Continued

DOE-TSL-1- 2002

APPENDIX C

OTHER STANDARDS-RELATED DOCUMENTS

DOCUMENT NO.

TITLE

NRC RG 3.22

Periodic Testing of Fuel Reprocessing Plant-Protection System

Actuation Functions

NRC RG 3.26

Standard Format and Content of Safety Analysis Reports for

Fuel Reprocessing Plants

NRC RG 3.27

Nondestructive Examination of Welds in the Liners of Concrete

Barriers in Fuel Reprocessing Plants

NRC RG 3.32

General Design Guide for Ventilation Systems for Fuel

Processing Plants

NRC RG 3.33

Assumptions Used for Evaluating the Potential Radiological

Consequences of Accidental Nuclear Criticality in a Fuel

Reprocessing Plant

NRC RG 3.34

Assumptions Used for Evaluating the Potential Radiological

Consequences of Accidental Nuclear Criticality in a Uranium

Fuel Fabrication Plant

NRC RG 3.35

Assumptions Used for Evaluating the Potential Radiological

Consequences of Accidental Nuclear Criticality in a Plutonium

Processing and Fuel Fabrication Plant

NRC RG 3.43

Nuclear Criticality Safety in the Storage of Fissile Materials

NRC RG 3.49

Design of an Independent (Water Basin Type) Spent Fuel

Storage Installation

NRC RG 3.54

Spent Fuel Heat Generation in an Independent Spent Fuel

Storage Installation

NRC RG 4.15

Quality Assurance for Radiological Monitoring Programs (Normal

Operations)--Effluent Streams and the Environment

NRC RG 7.6

Design Criteria for the Structural Analysis of Shipping Cask

Containment Vessels, Rev. 1

NRC RG 7.8

Load Combinations for the Structural Analysis of Shipping Casks

for Radioactive Material, Rev. 1

NRC RG 7.9

Standard Format and Content of Part 71 Application for Approval

of Packaging of Type B, Large Quantity, and Fissile Radioactive

Material

NRC RG 7.10

Establishing Quality Assurance Programs for Packaging

NRC RG 7.11

Fracture Toughness Criteria of Base Material for Ferritic Steel

Shipping Cask Containment Vessels with a Maximum Wall

Thickness of 4 Inches

NRC RG 7.12

Fracture Toughness Criteria of Base Material for Ferritic Steel

Shipping Cask Containment Vessels with a Wall Thickness

Greater Than 4 Inches But Not Exceeding 12 Inches

NRC RG 8.8

Information Relevant to Ensuring that Occupational Radiation

Exposures at Nuclear Power Stations Will Be As Low As

Reasonably Achievable

NRC RG 8.13

Instruction Concerning Prenatal Radiation Exposure

C-14