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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


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