Appendix B: Definitions

DOE-HDBK-1129-99

APPENDIX B: DEFINITIONS

Airborne radioactivity area Any area where the measured concentration of airborne

radioactivity, above natural background, exceeds or is likely to exceed 10 percent of the derived

air concentration (DAC) values listed in Appendix A or Appendix C of this part (10 CFR 835).

(DOE 10 CFR 835)

As low as reasonably achievable (ALARA) A phrase (acronym) used to describe an

approach to radiation protection to control or manage exposures (both individual and collective

to the work force and the general public) and releases of radioactive material to the environment

as low as social, technical, economic, practical, and public policy considerations permit. (DOE

5400.5)

Below regulatory concern A definable amount of low-level waste that can be deregulated

with minimal risk to the public. (DOE 5820.2A)

Best available technology for radioactive effluent control (BATREC) The preferred

effluent treatment technology, selected after taking into account factors related to technology,

economics, public policy, and other parameters. As used in this part, the BATREC is not a

specific level of treatment, but is the conclusion of a selection process in which several

alternative effluent treatment technologies are evaluated. It has evolved from the BAT concept

described in DOE 5400.5. This process, however, is not applied to tritium. (Draft DOE 834)

Buffer zone The smallest region beyond the disposal unit that is required as controlled space

for monitoring and for taking mitigative measures, as may be required. (DOE 5820.2A)

Byproduct material (1) any radioactive material (except special nuclear material) yielded in

or made radioactive by exposure to the radiation incident to the process of producing or utilizing

special nuclear material, and (2) the tailings or wastes produced by the extraction or

concentration of uranium or thorium from any ore processed primarily for its source material

content. (Atomic Energy Act of 1954, 42 USC 2011)

Certified waste Waste that has been confirmed to comply with disposal site waste

acceptance criteria (e.g., the Waste Isolation Pilot Plant-Waste Acceptance Criteria for

transuranic waste, the DOE/NVO-325 criteria) under an approved certification program. (DOE

5820.2A)

Confinement system

1. Any equipment, structure, or system, which limits the release and/or dispersion of a

hazardous/radioactive material within a facility. Examples are fume hoods, air locks,

ventilation systems, and may include containment and recovery systems. Confinement

systems may consist of multiple techniques and barriers depending upon the quantity of

tritium involved and the consequences of an uncontrolled release. (U.S. DOE Tritium Focus

Group)

2. A collection of barriers that can satisfy a specified leak criterion contingent upon operation of

its ancillary (active) system. An example of a confinement system is a glovebox and its

associated cleanup system. (DOE-HDBK-1129-99)

The assembly of components of the packaging intended to retain the radioactive material

during transport. (10 CFR Part 71)

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