Appendix C: Others Standards-Related Documents - Continued

DOE-TSL-1-2007

APPENDIX C

OTHER STANDARDS-RELATED DOCUMENTS

DOCUMENT NO.

TITLE

NRC RG 1.145

Atmospheric Dispersion Models for Potential Accident

Consequence Assessments at Nuclear Power Plants

NRC RG 1.149

Nuclear Power Plant Simulation Facilities for Use in Operator

License Examinations

NRC RG 1.23

Onsite Meteorological Programs

NRC RG 1.26

Quality Group Classifications and Standards for Water,

Steam, and Radioactive Waste-Containing Components of

Nuclear Power Plants

NRC RG 1.28

Quality Assurance Program Requirements (Design and

Construction)

NRC RG 1.3

Assumptions Used for Evaluating the Potential Radiological

Consequences of a Loss of Coolant Accident for Boiling

Water Reactors

NRC RG 1.4

Assumptions Used for Evaluating the Potential Radiological

Consequences of a Loss of Coolant Accident for

Pressurized Water Reactors

NRC RG 1.47

Bypassed and Inoperable Status Indication for Nuclear

Power Plant Safety Systems

NRC RG 1.52

Design Testing and Maintenance Criteria for Post Accident

Engineered-Safety-Feature Atmosphere Cleanup System Air

Filtration and Adsorption Units of Light-Water-Cooled

Nuclear Power Plants

NRC RG 1.60

Design Response Spectra for Seismic Design of Nuclear

Power Plants

NRC RG 1.61

Damping Values for Seismic Design of Nuclear Power

NRC RG 1.70

Standard Format and Content of Safety Analysis Reports

for Nuclear Power Plants

NRC RG 1.75

Physical Independence of Electric Systems

NRC RG 1.8

Qualification and Training of Personnel for Nuclear Power

NRC RG 1.84

Design and Fabrication Code Case Acceptability--ASME

Section III, Division 1

NRC RG 1.85

Materials Code Case Acceptability--ASME Section III,

Division 1

NRC RG 1.86

Termination of Operating Licenses for Nuclear Reactors

NRC RG 1.87

Guidance for Construction of Class I Components in

Elevated-Temperature Reactors

NRC RG 1.97

Instrumentation for Light-Water-Cooled Nuclear Power

Plants to Assess Plants and Environs Conditions During and

Following an Accident

NRC RG 3.10

Liquid Waste Treatment System Design Guide for Plutonium

Processing and Fuel Fabrication Plants

C-15