Department of Energy (DOE) Radiological Control Manual

Chapter 3 - Conduct of Radiological Work

Part 6 - Special Applications


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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:

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

  2. 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:

  1. Tritium emits low energy beta particles which cannot be monitored using external dosimeters, consequently requiring the use of bioassay measurements to evaluate worker dose.

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

  3. Normal personnel frisking techniques are ineffective for tritium. Consequently, a high reliance is placed on worker bioassay and routine contamination and air monitoring programs.

  4. 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:

  1. 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.

  2. 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.

  3. 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.

  1. 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.

  2. 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:

  3. Analytical diffraction and fluorescence
  4. Flash x-ray
  5. 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:

    1. 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."
    2. 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.
    3. 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.

    4. 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. Return to Chapter 3, Part 6 Table of Contents

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