Part 6 Special Applications - doe-std-1098-99cn1a0077

DOE-STD-1098-99

Radiological Control

Conduct of Radiological Work

March 2005

PART 6 Special Applications

This Part provides supplemental information to augment the basic requirements of the Standard. Articles 361 through

365 provide information to be used in developing the site-specific radiological control manual. Written guidance and

requirements contained within DOE documents, consensus standards, or Federal regulations that delineate specifics for

each application are referenced.

Articles 361 through 363 of this Part are applicable to those facilities where the majority of the work or operations

involve the subject radionuclide as the significant source term. This Part is not intended to apply to facilities that use the

subject radionuclides in limited or tracer amounts, such as analytical laboratories.

361 Plutonium Operations

There is the perception that exposure to small quantities of plutonium presents greater risk than exposure to other

radionuclides. Low levels of plutonium in the body are difficult to measure and biological removal processes for

plutonium are slow. For these reasons:

Primary emphasis shall be placed on engineered features to contain plutonium and to prevent airborne and surface

contamination [see 835.1001(a)].

In addition to the provisions of this Standard, guidance contained in the document, DOE-STD-1128-98, Guide to

Good Practices For Occupational Radiation Protection in Plutonium Facilities, Reaffirmation with Errata (May

2003) should be considered in preparing the site-specific radiological control manual for plutonium operations.

This standard provides specific guidance related to dosimetry, radiological monitoring, instrumentation,

contamination control, and applicable radiological control procedures.

362 Uranium Operations

Natural, depleted, and low-enriched uranium are unusual in that their chemical toxicity is more limiting in the human

body than their radioactivity. Also, processed uranium sometimes contains transuranic and other radionuclides from

recycled materials.

For these reasons, in addition to the provisions of this Standard, the guidance contained in DOE-STD-1136-2000,

Guide of Good Practice for Occupational Radiological Protection in Uranium Facilities, Change Notice No. 3,

(December, 2001) should be considered in preparing the site-specific radiological control manual for uranium operations.

This manual provides specific guidance related to management controls, radiological monitoring, contamination control,

and internal and external exposure controls.

363 Tritium Operations

The following characteristics of tritium require consideration in the implementation of the radiological control program at

tritium facilities:

Tritium emits low energy beta particles which cannot be monitored using external dosimeters, consequently

requiring the use of bioassay measurements to evaluate worker dose.

Worker exposure to tritium as water vapor causes a much greater dose than exposure to elemental tritium gas.

Normal personnel frisking techniques are ineffective for tritium. Consequently, a high reliance is placed on worker

bioassay and routine contamination and air monitoring programs.

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