Appendix C: Other Government Documents - Continued

DOE-TSL-1- 2002

APPENDIX C

OTHER STANDARDS-RELATED DOCUMENTS

DOCUMENT NO.

TITLE

NIOSH

Criteria Documents (National Institute for Occupational Safety

and Health, Department of Health and Human Services)

NIOSH 77-157A

Manual of Analytical Methods

NIOSH 77-157B

Manual of Analytical Methods

NIOSH 77-157C

Manual of Analytical Methods

NIOSH 78-175

Manual of Analytical Methods

NIOSH 79-141

Manual of Analytical Methods

NIOSH 80-106

Criteria for a Recommended Standard--Working in Confined

Spaces

NIOSH 85-115

Occupational Safety and Health Guidance Manual for Hazardous

Waste Site Activities

NIOSH Pub. No. 77-173

Occupational Exporsure Sampling Strategy Manual

NIRMA TG17-1993

Nuclear Information Records Management Association

Guidelines for Management of Nuclear-Related Training Records

NIST

Federal Information Processing Standards (National Institute of

Standards and Technology)

NIST 64

Guidelines for Documentation of Computer Programs and

Automated Data Systems for the Initiation Phase

NIST SP 800-14

Generally Accepted Practices for Securing Information Systems

NOAA 40

Rainfall Frequency Atlas of the United States for Durations from

30 Minutes to 24 Hours and Return Periods from One to 100

years (National Oceanic and Atmospheric Administration)

NOAA NGS 247

Manual of Geodetic Triangulation

NOAA NOS NGS 1

Geodetic Bench Marks

NOAA NOS NGS 3

Geodetic Leveling

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 1.8

Qualification and Training of Personnel for Nuclear Power Plants

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 1.47

Bypassed and Inoperable Status Indication for Nuclear Power

Plant Safety Systems

C-12