Appendix C. NGS Activity - Continued

DOE-TSL-4- 99

APPENDIX C

NGS Activity

Use of Fixed Neutron Absorbers in the Design of Nuclear

ANS-8.21

Facilities Outside Reactors

Nuclear Criticality Safety Based on Limited and Controlled

ANS-8.22

Moderation

Criticality Accident Emergency Planning & Response

ANS-8.23

Posting Standard

ANS-8.25

Mathematics and Computation

ANS-10

Guidelines for the Verification and Validation of Scientific and

ANS-10.4

Engineering Computer Programs for the Nuclear Industry

Technical Specifications

ANS-15.1

Selection/Training of Personnel

ANS-15.4

Quality Assurance Program Requirements for Research

ANS-15.8

Reactors

Decommissioning

ANS-15.10

Radiological Control at Research Reactor Facilities

ANS-15.11

Emergency Planning for Research Reactors

ANS-15.16

Shipment and Receipt of Special Nuclear Material (SNM) by

ANS-15.19

Research Reactors

Measurement of the Leachability of Solidified Low-Level

ANS-16.1

Radioactive Wastes by a Short-Term Test Procedure

Physics of Reactor Design

ANS-19

Nuclear Data Sets for Reactor Design Calculations

ANS-19.1

Environmental Remediation of Radioactively Contaminated

ANS-41

Sites

Criteria for Remote Sensing Techniques for Site

ANS-41.2

Characterization in Environmental Remediation

Analytical Methods for In Situ Gamma Ray Emitter in Soil

ANS-41.4

Criteria for Protection Against the Effects of Compartment

ANS-56.11

Flooding in Light Water Reactors

Time Response Design Criteria for Nuclear Safety Related

ANS-58.8

Operator Actions

Nuclear Criticality Safety

ANS-N16

Research Reactors, Reactor Physics, Radiation Shielding and

ANS-N17

Computational Methods

Radioactive Waste Management

ANS-N48

Nuclear Power Plant Standards Committee

ANS-NUPPSCO

C- 3