Department of Energy (DOE) Radiological Control Manual
Chapter 3 - Conduct of Radiological Work
Part 6 - Special Applications
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Table of Contents (Articles 36x)
This Part provides supplemental information to augment the basic
requirements of the Manual. 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.
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Article 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.
- In addition to the provisions of this Manual, guidance contained in
the document, "Health Physics Manual of Good Practices for Plutonium
Facilities," PNL-6534, should be considered for plutonium operations
in preparing the Site- Specific Radiological Control Manual. This manual
provides specific guidance related to dosimetry, radiological
monitoring, instrumentation, contamination control, and applicable
radiological control procedures.
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Article 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 Manual, the guidance
contained in the document, "Health Physics Manual of Good Practices for
Uranium Facilities," EG&G-2530, should be considered for uranium
operations in preparing the Site-Specific Radiological Control Manual. This
manual provides specific guidance related to management controls, radiological
monitoring, contamination control, and internal and external exposure controls.
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Article 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.
- Due to its high permeability, tritium is difficult to contain.
Special attention should be directed to the selection of Personal
Protective Equipment and Clothing.
For the above reasons, guidance contained in the document, "Health
Physics Manual of Good Practices at Tritium Facilities," MLM-3719, should
be considered for tritium operations in preparing the Site-Specific Radiological
Control Manual. This manual provides specific guidance related to internal
dosimetry, contamination and air monitoring, tritium containment practices and
techniques and Personal Protective Equipment and Clothing selection.
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Article 364 - Accelerator Operations
Special considerations associated with accelerator facilities include the
presence of extremely high dose rates, high energy and heavy particles, the
generation of activation products and detection and monitoring difficulties
associated with pulsed or high energy radiation. For these reasons:
- In addition to the provisions of this Manual, guidance contained in
the document, "Health Physics Manual of Good Practices for Accelerator
Facilities," SLAC-327, should be considered for accelerator operations
in preparing the Site- Specific Radiological Control Manual. This manual
provides specific guidance related to radiological monitoring,
dosimetry, shielding design, use of interlocks, and procedures and
administrative controls.
- Consideration should be given to the information provided in DOE Order
5480.25, "Safety of Accelerator Facilities," in preparing the
Site-Specific Radiological Control Manual.
- Safety devices and interlocks shall be operational prior to and during
operation of a beam. Operational status shall be verified by testing.
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Article 365 - Radiation Generating Devices
Special considerations associated with the use of radiation generating
devices include the presence of extremely high dose rates and the potential for
uncontrolled exposures. Operation of these devices requires stringent physical
and administrative controls to prevent overexposure to operating and support
personnel and those in adjacent work areas. The Site-Specific Radiological
Control Manual shall contain the following provisions for applicable types of
radiation generating devices.
- DOE 5480.4 mandates the use of ANSI N43.3 entitled, "American
National Standard for General Radiation Safety- Installations Using
Non-Medical X-Ray and Sealed Gamma-Ray Sources, Energies up to 10 MeV,"
for operations involving the irradiation of materials.
- DOE 5480.4 mandates the use of ANSI N43.2 entitled, "Radiation
Safety for X-Ray Diffraction and Fluorescence Analysis Equipment," for
operations involving the following devices:
- Analytical diffraction and fluorescence
- Flash x-ray
- Sealed source irradiators used for diffraction studies.
- Line management in conjunction with the Radiological Control
Organization shall establish the radiological control requirements for
incidental x-ray devices such as electron microscopes and electron beam
welders.
- Devices for medical use shall be registered with the appropriate
regulatory agency.
- Control requirements for radiographic devices are:
- On-site operations with devices containing sealed sources should
be conducted in accordance with the requirements contained in Title 10
CFR Part 34 entitled, "Licenses for Radiography and Radiation
Safety Requirements for Radiographic Operations."
- DOE 5480.4 mandates the use of ANSI N43.3 entitled, "American
National Standard for General Radiation Safety-Installations Using
Non-Medical X-Ray and Sealed Gamma-Ray Sources, Energies up to 10 MeV,"
for on-site operations with devices other than sealed sources.
- On-site operations conducted by off-site contractors shall be
approved by line management in coordination with the site Radiological
Control Organization. This process shall ensure the contractor has a
valid Nuclear Regulatory Commission or Agreement State license and
that the operational and emergency procedures are current and
available.
- Safety devices and interlocks at fixed installations shall be
operational prior to and during generation of a radiation field.
Operational status shall be verified by testing.
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Last modified: Thursday September 10 1998
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