Environmental Health and Safety’sehs.colorado.edu/wp-content/uploads/2014/10/Radiation... · Web viewNon-Ionizing Radiation not having enough energy to ionize atomic or molecular

EH&S Health Physics(303) 492-6523

GlossaryAbsorbed Dose The energy imparted to matter by ionizing radiation per unit mass

of irradiated material at the place of interest. The SI unit is the gray (Gy); 1 Gy = 1 Joule/Kg, or 100 rads. The conventional unit of absorbed dose is the rad; 1 rad = 100 ergs/g. See also Dose, Absorbed.

Activated Metal A metal that has been made radioactive through the process of activation. For the purpose of the University of Colorado, an activated metal is considered a sealed source and is usually a small metal disc. See also Activation.

Activation The process of making a radionuclide by bombarding a stable element with neutrons, protons, or other nuclear radiation.

Activity Time rate of nuclear transformations. The conventional unit of activity is the curie, Ci and the SI unit of activity is the Becquerel, Bq. See also Radioactivity and Decay, Radioactive.

ALARA Acronym for “As Low As Reasonably Achievable.” An approach to radiation protection which has the objective of attaining individual and collective doses as far below regulatory limits as is reasonably achievable. ALARA considers the state of technology, the economics of improvements in relation to the state of technology and benefits to the public health and safety, and other societal and socioeconomic considerations, and in relation to utilization of nuclear energy and radioactive materials in the public interest.

Alpha Particle A positively charged particle ejected spontaneously from the nuclei of some radioactive elements. Identical to a helium nucleus having a mass number of 4 and an electrostatic charge of +2, it has low penetrating power and a short range. The most energetic alpha particle generally fails to penetrate the dead layers of cells covering the skin. Alphas are hazardous when an alpha-emitting radionuclide is inside the body.

Analytical X-ray An x-ray producing device used to determine elemental composition,

or to examine the microstructure of materials using diffraction or fluorescence analysis. See also Medical X-ray and X-ray.

Annual Limit on The derived limit for the amount of radioactive material taken into Intake (ALI) the body of an adult worker by inhalation or ingestion in a year.

An ALI is the smaller value of intake of a given radionuclide in a year by the reference man that would result in a committed effective dose equivalent of 0.05 Sv (5 rem) or a committed dose equivalent of 0.5 Sv (50 rem) to any individual organ or tissue.

Area Survey A survey using a portable radiation survey meter to determine the dose rate in a given area. Most radiation survey meters have scales of mR/hr or counts per minute (cpm). See also Contamination Survey.

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Atom The smallest particle of an element that cannot be divided or broken up by chemical means. It consists of a central core of protons and neutrons, called the nucleus. Electrons revolve in orbits in the region surrounding the nucleus.

Atomic Number The number of positively charged protons in the nucleus of an atom.

Attenuation The process by which the number of particles or photons entering a body of matter is reduced by absorption and scatter.

Audit, Laboratory See Laboratory Audit.

Authorized User An individual who uses radioactive materials and/or radiation unsupervised, or supervises their use and is issued a University ofColorado Radioactive Materials License. See also Principal Investigator and Licensee.

Background Radiation from cosmic sources; naturally occurring radioactive Radiation materials, including radon and global fallout as it exists in the

environment from the testing of nuclear explosive devices. It doesnot include radiation from source material, byproduct material, orspecial nuclear materials. The typically quoted average individualexposure from background radiation is 360 millirem per year.

Becquerel (Bq) The unit of radioactive decay equal to 1 disintegration per second.3.7 x 1010 Bq = 1 Curie.

Beta Particle A charged particle emitted from a nucleus during radioactive decay, with a mass equal to 1/1837 that of a proton. A negatively charged beta particle is identical to an electron. A positively charged beta particle is called a positron. Large amounts of beta radiation may cause skin burns, and beta emitters are harmful if they enter the body. Beta particles may be stopped by thin sheets of plastic, wood, or metal.

BIER VII The National Research Council’s committee on the BiologicalEffects of Ionizing Radiations (BIER). Committee VII published areport in 2006 titled Health Risks From Radiation which suggested levels of risk associated with radiation exposure.

Bioassay The determination of kinds, quantities or concentrations, and in some cases, the locations of radioactive material in the human body, whether by direct measurement (in vivo) or by analysis and evaluation of materials excreted or removed from the human body (in vitro).

Biohazardous Waste For the purposes of this handbook, biologically active waste material that has not been rendered non-infectious using bleach or other disinfectant. Reminder - Autoclaves are NOT PERMITTED for use with radioactive materials.

Biological Half-life The time required for a biological system, such as that of a human, to eliminate, by natural processes, half of the amount of a substance (such as a radioactive material) that has entered it.

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Calibration The act or process of tuning an instrument by determining the deviation from a standard to ascertain the proper correction factors. Refers to radiation survey meters for the purposes of this handbook. Radiation survey meters are calibrated at least annually by Health Physics.

CDPHE Acronym for the “Colorado Department of Public Health andEnvironment” which establishes and enforces the regulations relating to radiation and radioactive materials in the State of Colorado.

Container Contents A sheet of paper near or attached to a waste container whichSheet describes the waste material inside the container. Each sheet must

be completed properly for the container to be collected for disposal.

Contamination The deposition of unwanted radioactive material on the surfaces of structures, areas, objects, or personnel. It may also be airborne or internal (inside components or personnel).

Contamination A survey using a wipe smear and liquid scintillation counter (LSC)Survey or gamma counter to determine the radioactive contamination in a

given area. Most LSCs and gamma counters provide results in counts per minute (cpm) which are converted to decays per minute (dpm) using the efficiency of the instrument. See also Area Survey.

Cosmic Radiation Penetrating ionizing radiation, both particulate and electromagnetic, originating in outer space. Secondary cosmic rays, formed by interactions in the earth’s atmosphere, account for approximately 0.45 to 0.5 mSv (45 to 50 mrem) of the 3.6 mSv (360 mrem) background radiation that an average individual receives in a year.

Curie (Ci) The conventional unit used to describe the intensity of radioactivity in a sample of material. The curie is equal to 37 billion disintegrations per second, which is approximately the rate of decay of 1 gram of radium. A curie is also a quantity of any radionuclide that decays at a rate of 37 billion disintegrations per second or 37 billion Becquerels. Named for Marie and Pierre Curie, who discovered radium in 1898.

Decay, Radioactive The decrease in the amount of any radioactive material with the passage of time, due to the spontaneous emission from the atomic nuclei of either alpha or beta particles, often accompanied by gamma radiation. See also Activity and Radioactivity.

Declared Pregnant A woman who has voluntarily informed her employer, in writing, Woman of her pregnancy and the estimated date of conception. For the

purposes of this handbook, informing the employer meansinforming Health Physics.

Decontamination The reduction or removal of contaminating radioactive materialfrom a structure, area, object, or person.

Dose The absorbed dose, given in grays (Gy) or rads, that represents the energy absorbed from the radiation in a gram of any material.

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Furthermore, the biological dose or dose equivalent, given in sieverts (Sv) or rem, is a measure of the biological damage to living tissue from the radiation exposure.

Dose, Absorbed The amount of energy deposited in any substance by ionizing radiation per unit mass of the substance. It is expressed numerically in grays (Gy) or rads. See also Absorbed Dose.

Dose Equivalent A term used to express the amount of biologically effective radiation dose when modifying factors have been considered. The product of absorbed dose multiplied by a quality factor multiplied by a distribution factor. It is expressed numerically in sieverts (Sv) or rems. If the dose is in Gray (Gy), the dose equivalent is in sieverts (Sv). If the dose is in rads, the dose equivalent is in rems.

Dose Limit A limitation on the legal amount of dose allowed during a given period, usually one year. The values are established in regulations and enforced by CDPHE. Dose limits vary depending upon the classification of the individual of concern; for example, a radiation worker, a member of the public, a minor, or an embryo/fetus.

Dosimeter A portable instrument for measuring and registering the total accumulated dose to ionizing radiation.

Dosimetry The theory and application of the principles and techniques involved in the measurement and recording of radiation doses.

Dose Rate The radiation dose delivered per unit time, e.g. rem per hour or mrem per hour. In practice, it may also be expressed as mR/hr. New meters also reflect SI units of Sieverts per hour (Sv/hr) or millisieverts per hour (mSv/hr).

Effective Dose The sum over the tissues of the product of the dose equivalent in a Equivalent tissue, the weighting factor representing its proportion of the risk

resulting from irradiation of tissue to the total risk when the whole body is irradiated uniformly.

Effective Half-life The time required for the amount of a radioactive element deposited in a living organism to be diminished 50% as a result of the combined action of radioactive decay and biological elimination.

Electron An elementary particle with a negative charge and a mass equal to 1/1837 of the proton. Electrons surround the positively charged nucleus and determine the chemical properties of the atom.

Element One of the 103+ known chemical substances that cannot be broken down further without changing its chemical properties. Some examples include: Hydrogen, Nitrogen, Gold, Lead, and Uranium.

Emergency For the purposes of this handbook, anyone responding to an Responder emergency involving radioactive materials. These individuals may

include EH&S, Police, and Fire personnel.

Environmental Monitoring conducted to evaluate radioactive material and/or Monitoring radiation released to the environment to ensure compliance with

applicable regulations. Monitoring may include area dosimetry,

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air samples, and water samples.

Equipment Survey A contamination survey conducted to ensure that an instrument or piece of equipment is not contaminated prior to transfer and/or disposal.

Exposure Being exposed to radiation or to radioactive material. Also that amount of or x-radiation that produces one electrostatic unit of charge in air at standard temperature and pressure. This concept applies only to electromagnetic radiation in air.

External Radiation Exposure to ionizing radiation when the radiation source is located outside the body.

Extremity Dosimeter An instrument used to measure and register the accumulated dose received by an extremity. Generally associated with radionuclides emitting high energy beta particles or gamma rays. See also Dosimeter, Fetal Dosimeter, Ring Badge, and Whole Body Dosimeter.

Extremity (-ies) The hands, forearms, elbows, feet, knee, leg below the knee, and ankles. Permissible radiation exposures in these regions are generally greater than the whole body because they contain less blood forming organs and have smaller volumes for energy absorption.

Fetal Dosimeter An instrument used to measure and register the accumulated dose received by an embryo/fetus. See also Declared Pregnant Woman, Dosimeter and Whole Body Dosimeter.

Freezer Frost The frost created in a freezer that can be potentially contaminated with radioactive materials, especially tritium (H-3).

Gamma Ray High-energy, short wavelength, electromagnetic radiation emitted from the nucleus. Gamma radiation frequently accompanies alpha and beta emissions and always accompanies fission. Gamma rays are very penetrating and are best stopped or shielded by dense materials, such as lead or uranium. Gamma rays are similar to X-rays.

Geiger-Mueller A radiation detection and measuring instrument. It consists of a Counter gas-filled tube containing electrodes, between which there is an

electrical voltage, but no current flowing. When incoming radiation ionizes the gas in the tube, a short, intense pulse of current passes from the negative electrode (cathode) to the positive electrode (anode) causing an electrical pulse which is measured or counted by the meter. The number of pulses per second measures the intensity of the radiation field. It was named for Hans Geiger and W. Mueller, who invented it in the 1920’s. It is sometimes simply called a Geiger counter or a GM Counter.

Generator For the purposes of this handbook, anyone who handles or produces hazardous waste.

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Generator Cabinet A protective cabinet surrounding each x-ray generator which limits leakage radiation measured at a distance of 5 centimeters from its surface such that it is not capable of producing a dose in excess of 0.25 mrem (2.5 Sv) in one hour.

Genetic Effects Those effects of radiation that may be transmitted to the progeny of exposed individuals.

Gray (Gy) The System International (SI) unit of absorbed radiation dose equal to 1 Joule per Kilogram. 1 Gy = 100 rad.

Half-life The time in which one half of the atoms of a particular radioactive substance disintegrates into another nuclear form. Measured half-lives vary from millionths of a second to billions of years. Also called physical or radiological half-life.

Half-life, Biological The time required for the body to eliminate one half of the material taken in by natural biological means.

Half-life, Effective The time required for a radionuclide contained in a biological system, such as a human or an animal, to reduce its activity by one half as a combined result of radioactive decay and biological elimination.

Half-life Categories The categories used by Health Physics to separate wastes for decay-in-storage prior to disposal. There are three categories, identified by the colors yellow, orange and green, representing the half-lives less than 60 days, between 60 and 90 days, and greater than 90 days.

Health Physics The science concerned with recognition, evaluation, and control of health hazards from ionizing radiation. The group in Environmental Health and Safety that is responsible for Radiation Safety.

High Radiation Area Any area with dose rates greater than 1 mSv (100 mrem) in one hour at 30 cm from the source or from any surface through which the radiation penetrates. These areas must be posted as “high radiation area” and access into these areas is maintained under strict control.

Hot A colloquial term meaning highly radioactive.

Hot Spot The region in a radiation / contamination area in which the level of radiation / contamination is noticeably greater than in neighboring regions in the area.

Interlock For the purposes of this Handbook, a safety device used to prevent an operator from inadvertently placing any portion of their body in the direct beam of an x-ray device.

Internal Radiation Nuclear radiation resulting from radioactive substances in the body. Some examples are Iodine-131 (found in the thyroid gland) and Strontium-90 and Plutonium-239 (found in bone).

Inventory See Radioactive Materials Inventory.

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Inverse Square Law A result of geometry, this law shows that the radiation intensity is inversely proportional to the square of the distance from the source. Therefore, if the distance is increased from 1 meter to 2 meters, the intensity will be only one fourth of the original intensity, 1/22.

Ionization The process of adding one or more electrons to, or removing one or more electrons from, atoms or molecules, thereby creating ions. High temperatures, electrical discharges, or nuclear radiations can cause ionization.

Ionizing Radiation Any radiation capable of displacing electrons from atoms or molecules, thereby producing ions. Some examples are alpha, beta, gamma, X-ray, neutrons, and ultraviolet light. High doses of ionizing radiation may produce severe skin or tissue damage.

Isotope One of two or more atoms with the same number of protons, but different numbers of neutrons in their nuclei. Thus Carbon-12, Carbon-13, and Carbon- 14 are isotopes of the element carbon, the numbers denoting the approximate atomic weights. Isotopes have very nearly the same chemical properties, but often different physical properties. For example, Carbon-12 and Carbon-13 are stable, but Carbon-14 is radioactive.

Label A sticker, sign, tape, or posting which provides identification ordescription.

Laboratory Audit An audit of a laboratory’s procedures and use of radioactivematerials under the University of Colorado Radioactive Materials License issued to a Principal Investigator. Usually conducted at least annually and usually unannounced.

Laboratory Contact An individual designated on the University of ColoradoRadioactive Materials License who is the liaison between the laboratory and the Health Physics staff. This person usually receives mailings, exchanges dosimeters, and handles waste pick-up requests.

Leak Test A wipe smear test similar to a contamination survey which verifiesthe integrity of a sealed source. If the results of the survey indicate more than 185 Bq (0.005 Ci) of contamination, the sealed source is considered leaking, taken out of use, and either repaired or disposed of promptly.

License A document authorizing a Principal Investigator to use radioactive materials and/or radiation for specific purposes in specific locations. Officially referred to as the University of Colorado Radioactive Materials License. See also Authorized User, Licensee, and Principal Investigator.

Licensee An individual who uses radioactive materials and/or radiation unsupervised, or supervises their use and is issued a University ofColorado Radioactive Materials License. See also Authorized User and Principal Investigator.

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Licensing The review process and paperwork necessary to obtain a University of Colorado Radioactive Materials License.

Liquid Scintillation Instrument used to measure radiation and/or contamination levelsCounter (LSC) by utilizing a liquid solution which fluoresces, or emits light, when

interacting with radioactive material. LSCs are primarily used in association with beta emitters; however, they can also detect some alpha particles and most gamma emitting radiation.

Medical X-ray A device used to irradiate human beings for the purpose of Device diagnosis or treatment. See also Analytical X-ray and X-ray.

Microcurie One millionth of a Curie. Abbreviated Ci.

Milli- Prefix indicating one thousandth of a unit. sievert One thousandth of a Sievert. Abbreviated mSv.gray One thousandth of a Gray. Abbreviated mGy.curie One thousandth of a Curie. Abbreviated mCi.rad One thousandth of a rad. Abbreviated mrad.rem One thousandth of a rem. Abbreviated mrem.roentgen One thousandth of a Roentgen. Abbreviated mR.

Mixed Waste Waste that has both radioactive and chemical constituents. This waste must comply with regulations governing both hazards.

Natural Uranium Uranium as found in nature. It contains 0.7% Uranium-235, 99.3 % of Uranium-238, and a trace of Uranium-234.

Neutron An uncharged elementary particle with a mass slightly greater than a proton, and found in the nucleus of every atom heavier than hydrogen.

Non-Ionizing Radiation not having enough energy to ionize atomic or molecularRadiation systems with a single event. Characterized by frequencies below

the far ultraviolet region of the electromagnetic spectrum and includes ultraviolet (UV), visible light, infrared (IR), microwave, and other radio-frequency (RF) radiation. It is also found in the acoustic spectrum and includes sonic and ultrasonic radiation.

Nucleus The small, central, positively charged region of an atom that carries essentially all of the mass. Except for the nucleus of ordinary hydrogen, which has a single proton, all atomic nuclei contain both protons and neutrons. The number of protons determines the total positive charge, or atomic number. This is the same for all the atomic nuclei of a given chemical element. The total number of neutrons and protons is called the mass number.

Nuclide A general term referring to all known isotopes, both stable (279) and unstable (about 5,000), of the chemical elements.

Over Exposure An exposure to radiation which leads to a dose in excess of the regulatory limits.

Pancake Probe A thin paddle-like probe used to detect high energy alpha, beta and

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gamma radiation. See also Geiger-Mueller Counter.

Personnel Monitoring The use of survey meters to determine the amount of radioactive contamination on an individual, or the use of dosimetry to determine an individual’s radiation dose.

Photon A quantum (or packet) of energy emitted in the form of electromagnetic radiation. Gamma rays and X-rays are examples of photons.

Pick-up Request See Radioactive Waste Pick-up Request Form.

Pig A container (usually lead or plastic) used to ship or store radioactive materials. The thick walls protect the person handling the container from radiation. Large containers are commonly called casks. (The word may have originated from the use of “pig iron” in the early days of handling radioactive materials.)

Plated Source Generally considered a sealed source for the purposes of this handbook. A source which has radioactive material bound to its surface by electroplating. The material cannot be removed from the surface under normal conditions.

Port An opening on an x-ray device which allows the primary beam to pass out of the device to irradiate an object of interest. Sometimes used to mount a camera or other analytical device.

Positron Particle equal in mass, but opposite in charge, to the electron (a positive electron).

Principal Investigator An individual who uses radioactive materials and/or radiation unsupervised, or supervises their use and is issued a University ofColorado Radioactive Materials License. See also Authorized User and Licensee.

Procurement Card The University’s Master Card obtained through the Procurement Services Center. Reminder – the Procurement Card CANNOT be used for purchasing radioactive materials.

Proton An elementary nuclear particle with a positive electric charge located in the nucleus of an atom.

Purchase Request A form used to request a purchase and designate a shipping address. Normally available in each department, these forms are approved by Health Physics for purchasing radioactive materials and radiation producing machines. If used without a Standing Purchase Order, they must be signed by Health Physics.

Quality Factor The factor by which the absorbed dose (e.g., ergs/g or rad) is to be multiplied to obtain a quantity that expresses, on a common scale for all ionizing radiation, the biological damage (e.g., Sievert or rem) to exposed persons. It is used because some types of radiation, such as alpha particles, are more biologically damaging than other types.

Rad Acronym for Radiation Absorbed Dose, the basic unit of absorbed dose of radiation. A dose of one rad means the absorption of 100

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ergs (a small but measurable amount of energy) per gram of absorbing tissue. 100 rad = 1 Gray.

Radiation, Nuclear Particles (alpha, beta, neutrons) or photons (gamma) emitted from the nucleus of an unstable radioactive atom as a result of radioactive decay.

Radiation Area Any area with radiation levels greater than 0.05 mSv (5 mrem) in one hour at 30 cm from the source or from any surface through which the radiation penetrates.

Radiation Producing Machines designed to produce radiation, usually x-rays, when Machines operating.

Radiation Safety The on-site regulatory Committee for the University’s Radioactive Committee (RSC) Materials License. This committee has the authority to establish

policies and procedures, provide enforcement sanctions, and restrict the use of radioactive materials and/or radiation. The RSC issues, amends, and terminates laboratory licenses, which authorize the specific activities associated with radioactive materials and/or radiation. It is composed of faculty and staff members representing various departments and levels of experience with radioactive materials and radiation, as well as a representative from Administration.

Radiation Safety A user’s guide for the University of Colorado’s laboratory licensees that

Handbook includes topics such as the safe use of radioactive materials and radiation, licensing, and waste disposal. This document becomes regulation through the Radiation Safety Committee (RSC) and the State of Colorado. Amendments are reviewed and approved by the RSC.

Radiation Safety An individual approved by the State of Colorado who has theOfficer knowledge, responsibility, and authority to apply appropriate

radiation protection regulations. The University of Colorado must have a Radiation Safety Officer (RSO) in order to have its Radioactive Materials License.

Radiation Safety A logbook of contamination survey results for each laboratory.Survey Log This log may also contain room diagrams and results of area

surveys. It should be kept in a central location for review during laboratory audits and inspections by Federal, State, or local agencies.

Radiation Safety The basic radiation safety courses offered by Health Physics toTraining fulfill the training requirements of the University’s License for

users of unsealed isotope, sealed sources, and radiation-producing machines.

Radiation Shielding Reduction of radiation by interposing a shield of absorbing material between any radioactive source and a person, work area, or radiation-sensitive device.

Radiation Source Usually a manmade sealed source of radiation used in various

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types of instruments and industrial gauges. Machines such as accelerators and natural radionuclides may be considered sources.

Radiation Source The material surrounding the x-ray tube that restricts physicalHousing proximity and radiation released from the radiation producing

machine.

Radiation Standards Exposure standards, permissible concentrations, rules for safe handling, regulations for transportation, regulations for industrial control of radiation, and control of radioactive material by legislative means.

Radiation Warning An officially prescribed symbol (a magenta or black trefoil) on a Symbol yellow background that must be displayed where certain quantities

of radioactive materials are present or where certain doses of radiation could be received.

Radioactive Exhibiting radioactivity or pertaining to radioactivity.

Radioactive Any solid, liquid, or gas which emits radiation spontaneously.Materials Sometimes abbreviated as RAM.

Radioactive Materials A list of radionuclides in a laboratory. The inventory includes theInventory date of receipt, an unique identification number, the radionuclide,

and the activity. Reminder – laboratories should keep this list updated at all times. Health Physics updates each laboratory’s inventory on a quarterly basis.

Radioactive Waste A form used to request a radioactive waste pick-up. It summarizes Pick-Up Request for each container, the container type(s), volume, radionuclide(s),

total activity, constituents, pH, and location. This form is used to properly manifest the waste for transportation and to ensure appropriate replacement containers are issued.

Radioactive Waste Unwanted radioactive material or items that are contaminated with radioactive material.

Radioactivity The spontaneous emission of radiation, generally alpha or beta particles, often accompanied by gamma rays, from the nucleus of an unstable atom. See also Activity and Decay, Radioactive.

Radioisotope An unstable form of an element that decays or disintegrates spontaneously, emitting radiation. Approximately 5000 natural and artificial radioisotopes have been identified. See also radionuclide.

Radionuclide An unstable form of an element that decays or disintegrates spontaneously, emitting radiation. Approximately 5000 natural and artificial radioisotopes have been identified. See also radioisotope.

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Radiosensitivity The relative susceptibility of cells, tissues, organs, organisms, or other substances to the injurious action of radiation.

Relative Risk The ratio of risk from radiation in an irradiated population to the risk in a comparable non-irradiated population.

Rem The special unit of dose equivalent. The dose equivalent equals the absorbed dose multiplied by the quality factor. 100 Rem = 1 Sievert (Sv).

Restricted Materials Items that should be segregated from each other and include(Waste) sharps, lead pigs, liquids, solids, and scintillation vials.

Ring Badge See Extremity Dosimeter.

Roentgen An unit of exposure to ionizing radiation. It is the amount of gamma or X-rays required to produce ions resulting in a charge of 0.00258 coulombs/kilogram of air under standard conditions. Named after Wilhelm Roentgen, German scientist who discovered X-rays in 1895.

Safety Devices When used in conjunction with radioactive material or x-ray devices, these may be interlocks, physical barriers, or other engineering controls.

Scattered Radiation Radiation that, during its passage through a substance, has been changed in direction. It may also have been modified by a decrease in energy. It is one form of secondary radiation.

Sealed Source Radioactive material that is permanently bonded or fixed in a capsule or matrix designed to prevent release and dispersal of the radioactive material under the most severe conditions which are likely to be encountered in normal use and handling.

Sealed Source A list of sealed sources in a laboratory. The inventory includes theInventory date of receipt, an unique identification number, the radionuclide,

and the activity.

Sealed Source A record of source use including the date when it is removed from Sign-out Log storage, the date it is returned to storage, and the location in which

it is being used. Generally found on or near the storage location. Secondary Radiation Radiation originating as the result of absorption of other radiation

in matter. It may be either electromagnetic or particulate in nature.

Shielding Any material or obstruction that absorbs radiation and thus tends to protect personnel or materials from the effects of ionizing radiation.

Shutter An automatic closure device on x-ray machines that cannot be opened unless a collimator or coupling has been connected to the port.

Sievert (Sv) The System International (SI) unit of dose equivalent equal to 1 Joule per Kilogram. 1 Sv = 100 rem.

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Spill An unintentional release or spread of radioactive materials.

Standing Purchase A form/system used to request multiple purchases from the sameOrder supplier. Normally available in each department, these forms are

approved by Health Physics for purchasing radioactive materials and radiation producing machines for a period of one year. They are established through the Procurement Service Center (PSC).

Storage Cabinet A cabinet used to hold radioactive materials not in use in a laboratory. Generally used for sealed sources of radioactive material.

Storage Freezer A freezer used to hold radioactive materials not in use in a laboratory. Generally used for unsealed radioactive sources.

Storage Refrigerator A refrigerator used to hold radioactive materials not in use in a laboratory. Generally used for unsealed radioactive sources.

Support Staff University of Colorado staff members and others involved in service functions in relation to administration of laboratories using radioactive materials. Custodians and facilities management trades people are examples of support staff.

Survey A study to find the radiation or contamination level of specific objects or locations within an area of interest, or to locate regions of higher-than-average intensity, i.e., hot spots.

Survey Meter Any portable radiation detection instrument adapted for inspecting an area to establish the existence and amount of radioactive material.

Terrestrial Radiation The portion of natural radiation (background) that is emitted by naturally occurring radioactive materials in the earth.

Thermoluminescent A device used to measure radiation by evaluating the amount of visible Dosimeter (TLD) light emitted from a crystal in the detector after being exposed to

radiation. See also Extremity Dosimeter.

Thin-end Window A small cylinder-like probe used to detect high energy beta and Probe gamma radiation. See also Geiger-Mueller Counter.

Tritium A radioactive isotope of hydrogen (3H, one proton, two neutrons). Because it is chemically identical to natural hydrogen, tritium can be taken into the body by any ingestion path. It decays by beta emission. It has a radioactive half-life of about 12.5 years.

Unstable Isotope A radioisotope.

Unsealed Radioactive materials which do not meet the definition of sealedRadionuclide sources. Generally, these are in liquid form in laboratories.

Uranium (U) A radioactive element with the atomic number 92 and as found in natural ores, an atomic weight of approximately 238. The two principle natural isotopes are U-235 (0.7% of natural Uranium) and U-238 (99.3% of natural Uranium). See also Natural

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Uranium.

Urinalysis An analysis and evaluation of urine used to determine kinds, quantities or concentrations, and in some cases, the locations of radioactive material in the human body. A form of bioassay used for individuals working with large amounts of tritium.

Very High An area in which radiation levels exceed 5 Gy (500 rads) in one hour at Radiation Area 1 meter from the source or from any surface that the radiation

penetrates.

Warning Device(s) Lights, sounds, signs, or barriers which indicate an existing hazard.

Waste, Radioactive Materials from radioactive materials operations that are radioactive or become radioactive and for which there is no further use. Wastes are generally classified as high, low, or intermediate levels based on activity per gallon or per cubic foot. The University generates low level radioactive waste.

Waste Container For the purposes of this handbook, containers used to hold waste items. These are color coded for half-life categories and are specific to the type of waste generated. See also Container Contents Sheet and Radioactive Waste Pick-up Request Form.

Whole-Body For the purposes of external dose; head, trunk including male gonads, arms above the elbow, or legs above the knee.

Whole-Body An instrument used to measure and register the accumulated dose Dosimeter received by the whole body. See also Dosimeter and Extremity

Dosimeter.

Whole-Body An exposure of the body to radiation, in which the entire body, rather Exposure than an isolated part, is irradiated. Where a radioisotope is uniformly

distributed throughout the body tissues, rather than being concentrated in certain parts, the result can be considered as whole-body exposure.

Wipe Sample A sample made to determine the presence of removable radioactive

(a.k.a. Wipe Smear, contamination on a surface. It is done by wiping, with slight pressure,

Swipe, etc.) a piece of soft filter paper over a representative type of surface area, usually 100 cm2.

X-ray Penetrating electromagnetic radiation (photon) having a wavelength that is much shorter than that of visible light. These rays are usually produced by excitation of the electron field around certain nuclei. In nuclear reactions, it is customary to refer to photons originating in the nucleus as gamma rays, and to those originating in the electron field of the atom as X-rays. See also Analytical X-ray and Medical X-ray.

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Appendices

Appendix A University of Colorado’s ALARA Program

Appendix B Sample License Form for Unsealed Sources of Radioactive Material

Appendix C Safe Use of Radioactive Materials

Appendix D Sample Radioactive Materials Inventory Form

Appendix E Sample Radiation Safety Survey Webpage Form

Appendix F Decontamination Procedures

Appendix G Defrosting a Contaminated Freezer

Appendix H Container Contents Sheet

Appendix I Radiation Waste Pick-Up Request Form

Appendix J Sealed Sources Sign Out Log

Appendix K Whole Body Dosimetry Application

Appendix L Fetal Dosimeter Application

Appendix M Solid Spill Decontamination Procedures

Appendix N Liquid Spill Decontamination Procedures

Appendix O Personnel Decontamination Procedures

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Appendix A

The University of Colorado ALARA Program

The University of Colorado maintains a Radioactive Materials license through the Colorado Department of Public Health and Environment (CDPHE). The ALARA philosophy, or As Low As Reasonably Achievable, is a regulatory requirement for all radiation protection programs. The University actively works to reduce dose and exposure due to radiation in our radiation safety program. This reduction in dose and exposure should be accomplished in accordance with ALARA with an emphasis on protecting individuals at the University, including members of the general public.

ALARA LevelsDosimetry - External MonitoringThe ALARA levels used for monthly and/or quarterly monitoring are as follows:

Level I Level II Level III Whole Body Dose: 0.5 mSv (50 mrem) 3 mSv (300 mrem) 5 mSv (500 mrem)Skin Dose: 0.5 mSv (50 mrem) 5 mSv (500 mrem) 50 mSv (5000 mrem)Lens of the Eye Dose: 0.5 mSv (50 mrem) 5 mSv (500 mrem) 15 mSv (1500 mrem)Extremity Dose: 0.5 mSv (50 mrem) 5 mSv (500 mrem) 50 mSv (5000 mrem)Individual Organ Dose: 0.5 mSv (50 mrem) 5 mSv (500 mrem) 50 mSv (5000 mrem)

Actions taken:1. Dose/Exposure less than Level I – No action unless deemed necessary by RSO. 2. Dose/Exposure equal to or greater than Level I - Notification of employee and the RSC.

A copy of this notification is maintained in the individual’s dosimetry file.

3. Dose/Exposure equal to or greater than Level II - Notification of employee and the RSC.A copy of this notification is maintained in the individual’s dosimetry file. The employee is encouraged to investigate and evaluate techniques for reducing future exposure in their work. Assistance may be provided by Health Physics.

4. Dose/Exposure equal to or greater than Level III (10% of Annual Limit) - Notification of employee and the RSC. A copy of this notification is maintained in the individual’s dosimetry file. An investigation will be performed by the employee and Health Physics. A written report explaining the exposure will be provided for their dosimetry file and the RSC.

Bioassay - Internal MonitoringThe ALARA levels (modified in 1999 to match the University’s Radioactive Materials License Conditions) used to monitor internal contamination are as follows:

Level I Level II Level IIIThyroid (Iodine-125): 2.22 kBq (60 nCi) 4.44 kBq (120 nCi) 18.5 kBq (500 nCi)Thyroid (Iodine-131): 0.74 kBq (20 nCi) 1.48 kBq (40 nCi) 5.18 kBq (140 nCi)Urinalysis (Tritium): 370 kBq (10 Ci)/Liter 1.04 MBq (28 Ci)/L 1.85 MBq (50 Ci)/L

16 (2010)


Actions taken:

1. Exposure less than Level I – No action unless deemed necessary by RSO. A copy of the test report is given to the employee and placed in his/her dosimetry file.

2. Exposure equal to or greater than Level I - Notification of employee and the RSC. A copy of this notification is maintained in the individual’s dosimetry file. The employee is encouraged to discuss experimental protocols with Health Physics to seek ways of reducing future exposures.

3. Exposure equal to or greater than Level II - Notification of employee and the RSC. A copy of this notification is maintained in the individual’s dosimetry file. In addition,

For Radioiodines –a. An investigation by Health Physics personnel will examine operations involved,

potentially including ventilation surveys, to determine the causes of exposures and to evaluate the potential for further exposures.

b. If this investigation indicates that further work in the area might result in exposure of the employee to concentrations that are excessive, the employee will be restricted from further exposure until the source of exposure is discovered and corrected.

c. Following the investigation, corrective actions that will eliminate or lower the potential for further exposures will be implemented and documented.

d. A repeat bioassay will be performed within one week of the previous measurement to confirm the effectiveness of the corrective action and/or to verify internal radioiodines present.

For Tritium – If this level is exceeded in the course of a calendar quarter, a written report shall be sent to the Director of CDPHE within 30 days of the end of the quarter. This report will contain the results of all urinalyses for the individual during the calendar quarter, the cause of the excessive concentrations, and the corrective steps taken or planned to prevent recurrence.

4. Exposure equal to or greater than Level III - Notification of employee and the RSC. A copy of this notification is maintained in the individual’s dosimetry file. In addition,

For Radioiodines –a. The employee will be prevented from any further handling of radioiodine until the

thyroid burden is below this limit.b. All investigative steps listed in item 3 above, will be carried out.c. The employee will be sent to an appropriate medical facility for evaluation of therapeutic

methods to accelerate removal of the radioiodine from the body.d. Repeat bioassays shall be conducted at one-week intervals until the thyroid burden is

below 0.12 Ci of I-125 or 0.04 Ci of I-131.

For Tritium – If this level is exceeded in a single bioassay, a written report shall be sent to the Director of CDPHE within 7 days of the receipt of the bioassay results.

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5. If any bioassay shows dose levels exceeding the limits listed in RH 4.52 of the Colorado Rules and Regulations Pertaining to Radiation Control, all notifications will occur as required, with follow-up written reports to CDPHE within 30 days.

Total Effective Dose Equivalent –IMMEDIATE NOTIFICATION OF CDPHE: 2.5 Sv (25 rem)24-HOUR NOTIFICATION OF CDPHE: 0.5 Sv (5 rem)

Total Organ Dose Equivalent –IMMEDIATE NOTIFICATION OF CDPHE: 2.5 Gy (250 rad)24-HOUR NOTIFICATION OF CDPHE: 0.5 Sv (50 rem)

Sealed SourcesThe ALARA levels used with leaking sealed sources are as follows:

Level I Level IITier I source/wipe: 37 Bq (0.001 Ci) 185 Bq (0.005 Ci)

Actions taken:1. Contamination less than Level I – No action taken unless deemed necessary by RSO. 2. Contamination equal to or greater than Level I - Notification of user and the RSC. It is

recommended that the source be monitored more frequently and possibly removed from circulation, repaired, or disposed of as radioactive waste.

3. Contamination equal to or greater than Level II - Notification of user, the RSC, and CDPHE (RH 4.58). The source is removed from use for repair or disposal by Health Physics personnel.

Radiation SurveysThe ALARA levels currently used for Contamination Surveys are as follows:

Level I Level IIdpm/100 cm2 100 1,000

Actions taken:1. Contamination less than Level I – No action taken unless deemed necessary by RSO.2. Contamination equal to or greater than Level I - Notification of the licensee/lab and RSC.

Immediate clean-up of the area is recommended. Documentation is maintained by the laboratory involved.

3. Contamination equal to or greater than Level II - Notification of the licensee/lab and RSC. Immediate clean-up is required and the area is re-surveyed by Health Physics staff. Documentation is maintained by the laboratory involved and Health Physics.

The ALARA levels currently used for Freezer Frost Contamination are as follows:

Level I Level II Level IIIdpm/100 cm2 or per ml 100 1,000 10,000

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Actions taken:1. Contamination less than Level I – No action taken unless deemed necessary by RSO.2. Contamination equal to or greater than Level I - Notification of the licensee/lab and RSO.3. Contamination equal to or greater than Level II - Notification of the licensee/lab and RSO.

Defrosting or clean-up of the freezer is recommended.4. Contamination equal to or greater than Level III - Notification of the licensee/lab and RSC.

Defrosting or clean-up of the freezer is required and the freezer is re-surveyed by Health Physics personnel.

Radioactive Material Receipt and InventoryThe following ALARA levels are in effect for packages received:

Level I Level IIdpm/100 cm2 on outside of vial 1,000 10,000dpm/100 cm2 on outside of box 100 --mR/hr on outside of box -- 200

Actions taken:1. Contamination/Exposure rate less than Level I on vial or box – No action taken unless

deemed necessary by RSO. Package is delivered to laboratory.2. Contamination equal to or greater than Level I on vial - Notification of laboratory and the

RSC. The laboratory is reminded of safe handling practices and has the right to refuse the package. Contamination equal to or greater than Level I on box - An alternate box with appropriate certification and labeling may be used to transport the package, provided the vial is not contaminated. The contaminated box is disposed of as radioactive waste.

3. Contamination equal to or greater than Level II on vial - Notification of laboratory and the RSC. The package is not delivered to the laboratory but is instead disposed of at Health Physics as radioactive waste. Arrangements for replacement are the responsibility of the laboratory involved. Exposure rate equal to or greater than Level II on box - CDPHE is contacted for further instruction before the box is opened by Health Physics staff.

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Appendix B

UNIVERSITY OF COLORADORADIOACTIVE MATERIALS LICENSEUNSEALED SOURCES APPLICATION

Check one: NEW APPLICATION AMENDMENT #

1. PERSONNELName and Title Department Building Office Phone FaxPrincipalInvestigator:

Campus Box: Home Phone: E-mail:

Radiation SafetyLab Contact:


DosimetryContact:


Note: The Dosimetry Contact receives and exchanges dosimeters. This person may be the Principal Investigator, the Radiation Safety Contact, or another individual. However, if the Principal Investigator assumes these duties, an alternate contact must be listed for emergencies.

2. RADIOACTIVE MATERIALS

Possession Limit Physical ChemicalRadionuclide Limit per Exp. Form Form

(LSC Sources) Acquire Date ID Number

3. PROPOSED OPERATION

Provide a summary of the investigation(s) and the principal procedures involved in the use of each radioactive isotope. Include the procedures important to contamination control (evaporation, assay methods, etc.). Attach additional sheets as needed. Be sure to clearly indicate whether or not these experiments will include biohazardous materials. If so, also clearly indicate the procedures used to render the materials non-infectious.

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Principal Investigator:

4. LOCATION OF USE

Building: Room(s) where used and/or stored: Telephone:

5. FACILITIES AND EQUIPMENT

Absorbent Paper Lab Coat Respirator Dosimeter(s) Mechanical Pipette Shielded Storage Fume Hood Protective Gloves Shielding Glove Box Radiation Signs Shoe Covers Handling Tongs Radiation Labels/Tape Trays

*LSC or Gamma Counter, etc. Indicate any internal and liquid calibration check sources for these devices in Section 2, includethe radionuclide, initial activity, physical and chemical forms, and date of initial activity.

*Survey Meter *Storage Freezer, etc. * Please describe Location, Make, Model, Serial Number, and Type.

6. RADIOACTIVE WASTEPercent of material that will become waste %

Estimate proportions % Solids % Liquid % Scint. VialsEstimated Monthly Volume Solids (gallons) Liquids (liters) Vials

Describe the expected chemical constituents (compounds and % of total volume) of the liquid waste for each protocol: (Please use full chemical names, no abbreviation. Total % should equal 100%. Attach additional sheet if necessary) Scintillation Cocktail Used: Biodegradable: Yes No

7. TRAINING Dates of the Training

Type of Training Where Trained On the Job Formal CoursePrinciples and Practices ofRadiation Protection

Radiation measurement, monitoringtechniques, and instruments

Calculations basic to use andmeasurement of radioactivity

Biological effects of radiation

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Principal Investigator:

8. EDUCATION

Degree Major School City State YearB.A./B.S.M.S.Ph.D.

9. EXPERIENCE WITH RADIATION

Radionuclide Activity Where Gained Dates Type of Use

10. STATEMENT OF COMPLIANCE

Upon receipt of the radioactive materials to be used as described in this application, I (we) will be responsible for the safe use of these materials in compliance with US Nuclear Regulatory Commission (NRC), Colorado Department of Public Health and Environment (CDPHE), and University of Colorado Radiation Safety Committee regulations.

SIGNATURE DATE , Principal Investigator

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Appendix C

RECOMMENDATIONS FOR THE SAFE USE OF RADIOACTIVE MATERIALS

1. Wear laboratory coats or other protective clothing at all times when working with radioactive materials. Long pants and closed-toed shoes are strongly recommended while short pants and sandals are discouraged.

2. Wear at least one pair of disposable gloves at all times while handling radioactive materials.

3. After each procedure, monitor your hands and feet for contamination using an appropriate portable radiation survey meter in a low-background area.

4. Do NOT eat, drink, smoke, or apply cosmetics in any area where radioactive or materials or chemicals are used or stored. Each laboratory should designate an area(s) for eating and drinking.

5. Do NOT store food, drink, or personal effects in areas where radioactive materials or chemicals are used or stored.

6. Wear appropriate dosimeter(s) at all times while working with or near radioactive materials. When not being worn to monitor personnel exposures, dosimeters should be stored in a low-background area.

7. Dispose of radioactive waste only in designated, labeled, and properly shielded containers. Waste containers should be closed when not in use. Appropriate containers may be obtained from Health Physics. Liquid containers should be in secondary containment tubs which are also available from Health Physics. An entry should be made on the Container Contents Sheet each time waste is placed in the container.

8. Never pipette by mouth.

9. Survey the work area, floor, handles, equipment, etc. for contamination using wipe smears. These surveys should be conducted weekly when radioactive materials are used.

10. Perform an area survey periodically before, during, and after an experiment using an appropriate portable radiation survey meter to monitor for levels of increased radiation.

11. Record all survey results and keep the printouts from the Liquid Scintillation Counter in the Radiation Safety Survey Log.

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Appendix D

University of ColoradoRadioactive Materials Inventory

Principal Investigator: Dr. M. Strangelove License Limits (mCi):Department: Chemistry P-32 = 5Lab Location: Cristol 0045 S-35 = 2Inventory Date: 10/23/08Page Number: 1

ID # Isotope Compound Receipt Date Initial Activity Current Activity Disposal Date Initials12345 P-32 ATP 9/9/08 0.2500 mCi 0.0296 mCi _______ ______12399 P-32 dCTP 10/1/08 0.500 mCi 0.1720 mCi _______ ______12455 P-32 ATP 10/9/08 0.2500 mCi 0.1268 mCi _______ ______

Amount on Hand: 0.3284 mCi License Limit: 5.0000 mCi

12400 S-35 dATP 10/1/08 0.2500 mCi 0.2091 mCi _______ ______ Amount on Hand: 0.2091 mCi License Limit: 2.0000 mCi

Please update this inventory as radioactive materials are consumed by putting a line through the ID # and recording the disposal date.

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Appendix E

SAMPLE RADIATION SAFETY SURVEY WEBPAGE FORMhttp://ehsonline.colorado.edu/radsurveys

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Appendix F

DECONTAMINATION PROCEDURES

1. Use a decontamination solution (such as RadiacWash or IsoClean) or a strong detergent to clean up the area with paper towels. For some radionuclides, a portable survey instrument may be helpful in narrowing down areas of contamination.

2. When wiping the area with the paper towels, be sure to wipe from the outside to inside in order to prevent spreading the contamination.

3. Dispose of all clean-up materials in an appropriate radioactive waste container.

4. Take a wipe smear survey of the area to be sure it is clean. If it is twice background, repeat cleaning process.

5. Record all wipe smear results in the laboratory’s Radiation Safety Survey Log.

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Appendix G

DEFROSTING A CONTAMINATED FREEZER

1. Check to see if appropriate tritium (3H) waste containers (liquid and solid) are available for the waste generated from the freezer. If appropriate waste containers are not available, contact Health Physics at (303) 492-6523. See Waste Chapter.

2. Open the door and follow manufacturer’s directions for switching to DEFROST mode.

3. Be sure to place pans and absorbent bench paper around the freezer to catch any water leakage.

4. Prepare the fume hood by placing absorbent paper with a plastic backing in the bottom of the hood. The fume hood will be used to allow ice to melt in containers and dry out paper towels.

5. When chunks of ice begin to loosen, put on two pairs of disposable gloves and a lab coat and remove the larger pieces of ice. Change gloves frequently, as tritium (3H) can infiltrate the plastic of the gloves.

6. Place the ice in large beakers or other containers and let thaw in an adequately ventilated fume hood.

7. Blot up frost melt with disposable paper towels and place the towels in the hood to dry.

8. Place liquid frost melt in a tritium (3H) liquid radioactive waste container, noting activity on container contents sheet. Place the dry paper towels and used gloves in a tritium (3H) solid radioactive waste container, noting the approximate activity on container contents sheet.

9. After all the ice and residual liquid is removed, wash down the interior surfaces with a decontamination solution and disposable paper towels. Rinse and dry. Dispose of paper towels, rinse, and used gloves as in 5 and 6 above.

10. Check freezer handles, exterior, and area around freezer for contamination

11. Wash hands.

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Appendix H

This Container Is For: Liquid WasteIsotopes Allowed: P-32, P-33, Rb-86 and others with half life < 60 days

Please enter the following information EACH time waste is added to container.Amount Added Isotope

ActivitymCi Chemical Constituents & % Date

GeneratorInitials

(see other side for additional entries)

Totals:Volume Isotope

ActivitymCi Chemical Constituents & %

Chemical Constituents & % Continued

Generator Certification:To the best of my knowledge, the information submitted on this form is accurate and complete, all constituent chemicals have been listed, all ethers and other peroxide forming chemicals are properly inhibited, and any biological, bio-medical, and biohazardous materials have been rendered inactive and non-infectious. The provision of false information on this form may subject the generator to criminal penalties under both state and federal laws. I also certify that I have completed radiation safety training at the University of Colorado.

Form Completed By (Print) Signature Date

For Disposal, complete a RADIOACTIVE WASTE PICK-UP REQUEST form online at: www.colorado.edu/radsafety, Fax to(303) 492-1322, or mail to Health Physics at 413 UCB. Questions? Call Health Physics at (303) 492-6523.

Radioactive Waste Container Contents

Generator Information:Principal Investigator Department Building/Room #

Before pick-up, each container must be tested for contamination using LSC analysis (filter paper wipe smear). LSC results for this container:

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http://www.colorado.edu/radsafety


Appendix I

RADIOACTIVE WASTE PICK-UP REQUESTPrincipal Investigator: Person completing form: Department: Phone: Building: Room: Date of Request: Page of

Type of

Waste Volume Isotope

Total Activity (mCi)

Constituents (ex: solid- paper, gloves; liquid- individual

chemicals, NO ABBREVIATIONS)

% by Volume

(sum must = 100%) pH

(For Health Physics Use)

DOT Shipping Name

For Waste Pick-up:1. Complete and sign the tag on the full container in your lab.2. Complete pick-up request form (above) with information from all containers to be picked up.3. Complete online Pick-up Request at www.colorado.edu/radsafety, Fax (303-492-1322), or Mail (413

UCB) the pick-up request to Health Physics.4. Waste containers will not be picked up if the tag on the container is not completed and signed or if a

request has not been submitted to Health Physics.

Waste Run Schedule: Wednesday (subject to change)

Health Physics must receive your request before noon on the day preceding the scheduled pick-up

If you have any questions about your waste pick-up please callHealth Physics at (303) 492-6523.

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http://www.colorado.edu/radsafety

SEALED SOURCE

SIGN-OUT LOG

SIGN OUT SOURCES PRIOR TO

USE!

Questions? Call Health Physics at (303) 492-

6523Sign-out list (Please print):


Appendix J

Initi

als

Act

ual R

etur

n D

ate

Exp

ecte

d R

etur

n D

ate

Plac

e of

Use

Use

r’s N

ame

and

Tel

epho

ne #

Sour

ce ID

#D

ate

30 (2010)


Appendix KTO BE ISSUED A DOSIMETER, PLEASE COMPLETE THIS FORM AND RETURN IT TO:

Radiation Safety Office1000 Regent Drive, 413 UCB

(303) 492-6523 FAX: (303) 492-1322

------------------------------------------------------------------------------------------------------------------------------------------------------------------------------DB: FOR Rad Safety USE ONLY RP: Spare Dosimeter No.: Permanent Dosimeter No.: Spare Extremity No.: Start Date: Rad Safety Training Date Quiz Score: ______ Term Date: ------------------------------------------------------------------------------------------------------------------------------------------------------------------------------

Please complete all of the following items as completely as possible. Please print clearly!

Name:____________________________________________________________________________ (last) (first) (middle) (any previous last names)

Identification No.:_________________ Identification type (choose one): Social Security No. ( ).; Passport No. ( ); Canadian Social Insurance No. ( ); Work Permit No. ( ); Other ______________ ( ) please specify _____________Birth Date:________________________ Sex: Male ( ); Female ( )

Campus Box:______________________ Licensee (Professor):_______________

Lab Room #:_______________________ Lab Telephone #:___________________

Radioactive isotopes you expect to work with:_________________________________(a dosimeter is not required if you are only working 3H (tritium) or 14C)

Maximum activity per experiment (mCi):___________ Check here if you need an extremity monitor: _____Location and type of Radiation Producing (If working with >1 mCi of a strong beta/gamma Machine you expect to work with:________________________ emitter or x-ray machine)

RADIATION EXPOSURE HISTORYIn accordance with state and federal regulations, we are required to request past exposure histories from any and all places where you might have been employed or assigned. Please list only those places where you have been issued a personal monitoring device (film badge, TLD ring, etc.)

Name(s) and Complete Mailing Address(es) Dates (Month/Year) Device Type_________________________________ ______________________ _____________________________________________ ______________________ _____________________________________________ ______________________ _____________________________________________ ______________________ _____________________________________________ ______________________ ____________Please indicate the radioisotopes and/or radiation machines (x-ray, accelerator, etc.), if any, that you have ever worked with in the past. ______________________________________________________________________________If you have been occupationally exposed to radiation within the past calendar year, please indicate your estimated dose here: _______________

RELEASE OF INFORMATIONThe University of Colorado is required by regulation to attempt to determine your total occupational exposure history from all institutions where you have been monitored for radiation dose (see section above). In order to obtain the records necessary to complete this requirement, your signature is needed below. Also, by signing below, you acknowledge that it is your responsibility to notify the Radiation Safety office of any occupational dose received while working at another institution concurrently with your employment at CU.

You are authorized to furnish the University of Colorado Radiation Safety Office with any information concerning my radiation exposure history.

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_________________________________ ___________________________ (signature) (date)

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Appendix L

FETAL DOSIMETER APPLICATION

To receive a Fetal Dosimeter, please COMPLETE this form and RETURN to:

EH&S Health Physics1000 Regent Drive, 413 UCB

(303) 492-6523 FAX: (303) 492-1322

Employee Name: (last) (first) (M.I.)

Local Address:

Campus Address: (Licensee) (Room)

ID NO.:

Identification Type U.S. Social Security Number ( ), Passport ( ), Canadian Social Insurance ( ),

Work Permit ( ), Other (please specify) ( )

Conception Date (Approx.) Due Date:

Some women prefer to wear only one badge for privacy or convenience reasons. If you do not want a second badge to be worn on the belly, please initial here ____________________(Remember the mother’s badge may be worn anywhere on the torso between the neck and waist.)

Please list any radioactive isotopes or radiation-producing machines you plan to be working with or around during pregnancy:

Isotope/Machine Activity

I hereby declare myself a pregnant radiation worker at the University of Colorado and request the protection of Title 10, Part 20 of the Code of Federal Regulations (see below).

_____________________________________________ ________________________(Employee Signature) (Date)

Every effort will be made to preserve the privacy of the Declared Pregnant Worker and her condition.

Definition of DECLARED PREGNANT WORKER: "A woman who has voluntarily informed her employer, in writing, of her pregnancy and the estimated date of conception." (10 CFR 20.1003)

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DOSE LIMIT to embryo/fetus: 10 CFR 20.1208 details the dose to the fetus over the full term of pregnancy as 0.5 rem (500 mrem or 5 mSv). This dose is determined by the sum of the deep dose to the pregnant worker and the dose to the embryo/fetus from the radionuclides in the declared pregnant worker.

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Appendix M

SOLID SPILL PROCEDURES

1. Use appropriate personal protective clothing and equipment, including gloves, lab coat, etc. For some radionuclides, a survey instrument may be helpful in narrowing down areas of contamination.

1. Pick up the solid item(s)

1. Place in an appropriate radioactive waste container

1. Use a decontamination solution (such as RadiacWash or IsoClean) or a strong detergent to clean up the spill with paper towels.


1. Dispose of all clean-up materials in an appropriate radioactive waste container


1. Record all wipe smear results in the laboratory’s Radiation Survey Logbook. Please refer to the Radiation Survey chapter for further information.

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Appendix N

LIQUID SPILL PROCEDURES

1. Use appropriate personal protective clothing and equipment, including gloves, lab coat, etc. For some radionuclides, a survey instrument may be helpful in narrowing down areas of contamination.

2. Dike around the spill with absorbent material such as paper towels to prevent the spread of the contaminated area. Try to block access to any drains or hazardous materials.

3. Use a decontamination solution (such as RadiacWash or IsoClean) or a strong detergent to clean up the spill with paper towels.


5. Dispose of all diking and clean-up materials in an appropriate radioactive waste container.


7. Record all wipe smear results in the laboratory’s Radiation Survey Logbook. Refer to the Radiation Survey Chapter for further information.

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Appendix O

PERSONNEL DECONTAMINATION PROCEDURES

1. Contaminated skin should be washed thoroughly with soap and warm water. Do not scrub the area, as that could break the skin, increasing the chances of internal contamination. If necessary, emergency showers may be used.

2. If the contamination involves a wound, flush the area to remove contamination and seek medical attention appropriate to the scope of the wound.

3. Call 911 if the wound is life-threatening. If the bleeding is not severe, allow the wound to bleed as an aid in removing contamination.

4. Contaminated clothing should be carefully removed and set aside in a plastic bag or on absorbent paper.

5. Take a wipe smear survey of the skin to be sure it is clean. If it is twice background, repeat cleaning process.

6. Record all wipe smear results in the laboratory’s Radiation Survey Logbook. Refer to the Radiation Survey Chapter for further information.

7. Notify Health Physics as soon as possible at (303) 492-6523.

37 (2010)

Documents

Environmental Health and Safety’sehs.colorado.edu/wp-content/uploads/2014/10/Radiation... · Web viewNon-Ionizing Radiation not having enough energy to ionize atomic or molecular