TYPE OF RADIATION | Quality Factor (Q) | Absorbed Dose Equal to A Unit Dose Equivalenta |
X, gamma, or beta radiation and high-speed electrons | 1 | 1 |
Alpha particles, multiple- charged particles, fission fragments and heavy particles of unknown charge | 20 | 0.05 |
Neutrons of unknown energy | 10 | 0.1 |
High-energy protons | 10 | 0.1 |
a | Absorbed dose in rad equal to 1 rem or the absorbed dose in gray equal to 1 Sv. |
If it is more convenient to measure the neutron fluence rate rather than to determine the neutron dose equivalent rate in sievert per hour or rem per hour as required for Table I, then 0.01 Sv (1 rem) of neutron radiation of unknown energies may, for purposes of these rules, be assumed to result from a total fluence of 25 million neutrons per square centimeter incident upon the body. If sufficient information exists to estimate the approximate energy distribution of the neutrons, the licensee or registrant may use the fluence rate per unit dose equivalent or the appropriate Q value from Table II to convert a measured tissue dose in gray or rad to dose equivalent in sievert or rem.
TABLE II
MEAN QUALITY FACTORS, Q, AND FLUENCE PER UNIT DOSE EQUIVALENT FOR MONOENERGETIC NEUTRONS
Neutron Energy (MeV) | Quality Factora (Q) | Fluence per Unit Dose Equivalentb (neutrons cm-2 rem-1) | Fluence per Unit Dose Equivalentb (neutrons cm-2 Sv-1) |
(thermal) 2.5 x 10-8 | 2 | 980 x 106 | 980 x 108 |
1 x 10-7 | 2 | 980 x 106 | 980 x 108 |
1 x 10-6 | 2 | 810 x 106 | 810 x 108 |
1 x 10-5 | 2 | 810 x 106 | 810 x 108 |
1 x 10-4 | 2 | 840 x 106 | 840 x 108 |
1 x 10-3 | 2 | 980 x 106 | 980 x 108 |
1 x 10-2 | 2.5 | 1010 x 106 | 1010 x 108 |
1 x 10-1 | 7.5 | 170 x 106 | 170 x 108 |
5 x 10-1 | 11 | 39 x 106 | 39 x 108 |
1 | 11 | 27 x 106 | 27 x 108 |
2.5 | 9 | 29 x 106 | 29 x 108 |
5 | 8 | 23 x 106 | 23 x 108 |
7 | 7 | 24 x 106 | 24 x 108 |
10 | 6.5 | 24 x 106 | 24 x 108 |
14 | 7.5 | 17 x 106 | 17 x 108 |
20 | 8 | 16 x 106 | 16 x 108 |
40 | 7 | 14 x 106 | 14 x 108 |
60 | 5.5 | 16 x 106 | 16 x 108 |
1 x 102 | 4 | 20 x 106 | 20 x 108 |
2 x 102 | 3.5 | 19 x 106 | 19 x 108 |
3 x 102 | 3.5 | 16 x 106 | 16 x 108 |
4 x 102 | 3.5 | 14 x 106 | 14 x 108 |
a | Value of quality factor (Q) at the point where the dose equivalent is maximum in a 30-cm diameter cylinder tissue-equivalent phantom. |
b | Monoenergetic neutrons incident normally on a 30-cm diameter cylinder tissue-equivalent phantom. |
(109) "QNFT (quantitative fit test)" means an assessment of the adequacy of respirator fit by numerically measuring the amount of leakage into the respirator.
(110) "Quarter" means a period of time equal to one-fourth of the year observed by the licensee, approximately 13 consecutive weeks, providing that the beginning of the first quarter in a year coincides with the starting date of the year and that no day is omitted or duplicated in consecutive quarters.
(111) "Rad" means the special unit of absorbed dose. One rad equals one-hundredth of a joule per kilogram of material; for example, if tissue is the material of interest, then 1 rad equals 100 ergs per gram of tissue. One rad is equal to an absorbed dose of 100 erg/gram or 0.01 joule/kilogram (0.01 gray).
(112) "Radiation" means alpha particles, beta particles, gamma rays, X-rays, neutrons, high-speed electrons, high-speed protons, and other particles capable of producing ions. For purposes of these rules: Radiation does not include magnetic fields or nonionizing radiation, such as radiowaves or microwaves, visible, infrared, or ultraviolet light; and ionizing radiation is an equivalent term.
(113) "Radiation area" means any area, accessible to individuals, in which radiation levels could result in an individual receiving a dose equivalent in excess of 0.05 mSv (0.005 rem) in one hour at 30 centimeters from the source of radiation or from any surface that the radiation penetrates.
(114) "Radiation machine" means any device capable of producing ionizing radiation except those devices with radioactive material as the only source of radiation.
(115) "Radiation safety officer" means an individual who has the knowledge and responsibility to apply appropriate radiation protection rules and has been assigned that responsibility by the licensee or registrant.
(116) "Radiation source." See "Source of radiation."
(117) "Radioactive material" means any material (solid, liquid, or gas) which emits radiation spontaneously.
(118) "Radioactive waste" means any radioactive material which is no longer of use and intended for disposal or treatment for the purposes of disposal.
(119) "Radioactivity" means the transformation of unstable atomic nuclei by the emission of radiation.
(120) "Reference man" means a hypothetical aggregation of human physical and physiological characteristics determined by international consensus. These characteristics may be used by researchers and public health workers to standardize results of experiments and to relate biological insult to a common base.
(121)
"Registrable item" means any radiation-producing machine except those exempted by RCW
70A.388.200 or exempted by the department under the authority of RCW
70A.388.050.
(122) "Registrant" means any person who is registered by the department or is legally obligated to register with the department in accordance with these rules and the act.
(123) "Registration" means registration with the department in accordance with the rules adopted by the department.
(124) "Regulations of the United States Department of Transportation" means the regulations in 49 C.F.R. Parts 170-189, 14 C.F.R. Part 103, and 46 C.F.R. Part 146.
(125) "Rem" means the special unit of any of the quantities expressed as dose equivalent. The dose equivalent in rem is equal to the absorbed dose in rad multiplied by the quality factor (1 rem = 0.01 Sv).
(126) "Research and development" means: (a) Theoretical analysis, exploration, or experimentation; or (b) the extension of investigative findings and theories of a scientific or technical nature into practical application for experimental and demonstration purposes, including the experimental production and testing of models, devices, equipment, materials, and processes. Research and development does not include the internal or external administration of radiation or radioactive material to human beings.
(127) "Respiratory protective equipment" means an apparatus, such as a respirator, used to reduce an individual's intake of airborne radioactive materials.
(128) "Restricted area" means any area to which access is limited by the licensee or registrant for purposes of protecting individuals against undue risks from exposure to radiation and radioactive material. "Restricted area" does not include any areas used for residential quarters, although a separate room or rooms in a residential building may be set apart as a restricted area.
(129) "Roentgen" (R) means the special unit of exposure. One roentgen equals 2.58 x 10-4 coulombs/kilogram of air.
(130) "Sanitary sewerage" means a system of public sewers for carrying off waste water and refuse, but excluding sewage treatment facilities, septic tanks, and leach fields owned or operated by the licensee or registrant.
(131) "Sealed source" means any radioactive material that is encased in a capsule designed to prevent leakage or the escape of the radioactive material.
(132)
"SEPA" means the State Environmental Policy Act under chapter
43.21C RCW.
(133) "SCBA (self-contained breathing apparatus)" means an atmosphere-supplying respirator for which the breathing air source is designed to be carried by the user.
(134) "Shallow dose equivalent" (Hs), which applies to the external exposure of the skin of the whole body or the skin of an extremity, means the dose equivalent at a tissue depth of 0.007 centimeter (7 mg/cm2).
(135) "SI" means an abbreviation of the International System of Units.
(136) "Sievert" means the SI unit of any of the quantities expressed as dose equivalent. The dose equivalent in sievert is equal to the absorbed dose in gray multiplied by the quality factor (1 Sv = 100 rem).
(137) "Site area emergency" means events which may occur, are in progress, or have occurred that could lead to a significant release of radioactive material and that could require a response by off-site response organizations to protect persons off-site.
(138) "Site boundary" means that line beyond which the land or property is not owned, leased, or otherwise controlled by the licensee or registrant.
(139) "Source container" means a device in which radioactive material is transported or stored.
(140) "Source material" means: (a) Uranium or thorium, or any combination thereof, in any physical or chemical form, or (b) ores which contain by weight one-twentieth of one percent (0.05 percent) or more of uranium, thorium, or any combination thereof. Source material does not include special nuclear material.
(141) "Source material milling" means the extraction or concentration of uranium or thorium from any ore processing primarily for its source material content.
(142) "Source of radiation" means any radioactive material, or any device or equipment emitting or capable of producing ionizing radiation.
(143) "Special nuclear material" means:
(a) Plutonium, uranium-233, uranium enriched in the isotope 233 or in the isotope 235, and any other material that the NRC, under the provisions of section 51 of the Atomic Energy Act of 1954, as amended, determines to be special nuclear material, but does not include source material; or
(b) Any material artificially enriched in any of the foregoing, but does not include source material.
(144) "Special nuclear material in quantities not sufficient to form a critical mass" means uranium enriched in the isotope U-235 in quantities not exceeding 350 grams of contained U-235; uranium-233 in quantities not exceeding 200 grams; plutonium in quantities not exceeding 200 grams; or any combination of them in accordance with the following formula: For each kind of special nuclear material, determine the ratio between the quantity of that special nuclear material and the quantity specified above for the same kind of special nuclear material. The sum of the ratios for all of the kinds of special nuclear material in combination shall not exceed "1" (i.e., unity). For example, the following quantities in combination would not exceed the limitation and are within the formula:
175 (grams contained U-235) | + | |
350 | |
50 (grams U-233) | + | |
200 | |
50 (grams Pu) | < 1 | |
200 | |
(145) "Stochastic effect" means a health effect that occurs randomly and for which the probability of the effect occurring, rather than its severity, is assumed to be a linear function of dose without threshold. Hereditary effects and cancer incidence are examples of stochastic effects. For purposes of these rules, probabilistic effect is an equivalent term.
(146) "SAR (supplied-air respirator)" or "airline respirator" means an atmosphere-supplying respirator for which the source of breathing air is not designed to be carried by the user.
(147) "Survey" means an evaluation of the radiological conditions and potential hazards incident to the production, use, release, disposal, or presence of sources of radiation. When appropriate, the evaluation includes, but is not limited to, tests, physical examinations, calculations and measurements of levels of radiation or concentration of radioactive material present.
(148) "Test" means (a) the process of verifying compliance with an applicable rule, or (b) a method for determining the characteristics or condition of sources of radiation or components thereof.
(149) "These rules" mean all parts of the rules for radiation protection of the state of Washington.
(150) "Tight-fitting facepiece" means a respiratory inlet covering that forms a complete seal with the face.
(151) "TEDE (total effective dose equivalent)" means the sum of the effective dose equivalent for external exposures and the committed effective dose equivalent for internal exposures.
(152) "TODE (total organ dose equivalent)" means the sum of the deep dose equivalent and the committed dose equivalent to the organ or tissue receiving the highest dose.
(153) "United States Department of Energy" means the Department of Energy established by Public Law 95-91, August 4, 1977, 91 Stat. 565, 42 U.S.C. 7101 et seq., to the extent that the department exercises functions formerly vested in the United States Atomic Energy Commission, its chairman, members, officers and components and transferred to the United States Energy Research and Development Administration and to the administrator thereof under sections 104 (b), (c) and (d) of the Energy Reorganization Act of 1974 (Public Law 93-438, October 11, 1974, 88 Stat. 1233 at 1237, 42 U.S.C. 5814 effective January 19, 1975) and retransferred to the Secretary of Energy under section 301(a) of the Department of Energy Organization Act (Public Law 95-91, August 4, 1977, 91 Stat. 565 at 577-578, 42 U.S.C. 7151, effective October 1, 1977).
(154) "Unrefined and unprocessed ore" means ore in its natural form prior to any processing, such as grinding, roasting or beneficiating, or refining. Processing does not include sieving or encapsulation of ore, or preparation of samples for laboratory analysis.
(155) "Unrestricted area" (uncontrolled area) means any area which is not a restricted area. Areas where the external dose exceeds 2 mrem in any one hour or where the public dose, taking into account occupancy factors, will exceed 100 mrem total effective dose equivalent in any one year must be restricted.
(156) "User seal check" (fit check) means an action conducted by the respirator user to determine if the respirator is properly seated to the face. Examples include negative pressure check, positive pressure check, irritant smoke check, or isoamyl acetate check.
(157) "Very high radiation area" means an area, accessible to individuals, in which radiation levels from radiation sources external to the body could result in an individual receiving an absorbed dose in excess of 5 Gy (500 rad) in one hour at one meter from a source of radiation or one meter from any surface that the radiation penetrates.
(158) "Waste" means those low-level radioactive wastes containing source, special nuclear or by-product material that are acceptable for disposal in a land disposal facility. For purposes of this definition, low-level radioactive waste means radioactive waste not classified as high-level radioactive waste, transuranic waste, spent nuclear fuel, or by-product material as defined in subsection (17)(b), (c), and (d) of the definition of by-product material in this section.
(159) "Waste handling licensees" mean persons licensed to receive and store radioactive wastes prior to disposal or persons licensed to dispose of radioactive waste.
(160) "Week" means seven consecutive days starting on Sunday.
(161) "Weighting factor" wT for an organ or tissue (T) means the proportion of the risk of stochastic effects resulting from irradiation of that organ or tissue to the total risk of stochastic effects when the whole body is irradiated uniformly. For calculating the effective dose equivalent, the values of wT are:
ORGAN DOSE WEIGHTING FACTORS
| Organ or Tissue | wT | |
| Gonads | 0.25 | |
| Breast | 0.15 | |
| Red bone marrow | 0.12 | |
| Lung | 0.12 | |
| Thyroid | 0.03 | |
| Bone surfaces | 0.03 | |
| Remainder | 0.30a | |
| Whole Body | 1.00b | |
a | 0.30 results form 0.06 for each of 5 "remainder" organs, excluding the skin and the lens of the eye, that receive the highest doses. |
b | For the purpose of weighting the external whole body dose, for adding it to the internal dose, a single weighting factor, wT =1.0, has been specified. The use of other weighting factors for external exposure will be approved on a case-by-case basis until such time as specific guidance is issued. |
(162) "Whole body" means, for purposes of external exposure, head, trunk including male gonads, arms above the elbow, or legs above the knee.
(163)
"Worker" means an individual engaged in activities under a license or registration issued by the department and controlled by a licensee or registrant but does not include the licensee or registrant. Where the licensee or registrant is an individual rather than one of the other legal entities defined under "person," the radiation exposure limits for the worker also apply to the individual who is the licensee or registrant. If students of age 18 years or older are subjected routinely to work involving radiation, then the students are considered to be workers. Individuals of less than 18 years of age shall meet the requirements of WAC
246-221-050.
(164) "WL (working level)" means any combination of short-lived radon daughters in 1 liter of air that will result in the ultimate emission of 1.3 x 105 MeV of potential alpha particle energy. The short-lived radon daughters are - For radon-222: Polonium-218, lead-214, bismuth-214, and polonium-214; and for radon-220: Polonium-216, lead-212, bismuth-212, and polonium-212.
(165) "WLM (working level month)" means an exposure to one working level for 170 hours - 2,000 working hours per year divided by 12 months per year is approximately equal to 170 hours per month.
(166) "Year" means the period of time beginning in January used to determine compliance with the provisions of these rules. The licensee or registrant may change the starting date of the year used to determine compliance by the licensee or registrant provided that the change is made at the beginning of the year and that no day is omitted or duplicated in consecutive years.
[Statutory Authority: RCW
43.70.040 and 2020 c 20. WSR 22-07-025, § 246-220-010, filed 3/9/22, effective 4/9/22. Statutory Authority: RCW
70.98.050 and
70.98.110. WSR 16-13-054, § 246-220-010, filed 6/10/16, effective 7/11/16. Statutory Authority: RCW
70.98.050. WSR 15-06-015, § 246-220-010, filed 2/23/15, effective 3/26/15; WSR 14-01-077, § 246-220-010, filed 12/16/13, effective 1/16/14. Statutory Authority: RCW
70.98.050 and
70.98.080. WSR 11-03-020, § 246-220-010, filed 1/7/11, effective 2/7/11; WSR 09-06-003, § 246-220-010, filed 2/18/09, effective 3/21/09. Statutory Authority: RCW
70.98.050. WSR 06-05-019, § 246-220-010, filed 2/6/06, effective 3/9/06; WSR 04-23-093, § 246-220-010, filed 11/17/04, effective 12/18/04; WSR 01-05-110, § 246-220-010, filed 2/21/01, effective 3/24/01; WSR 00-08-013, § 246-220-010, filed 3/24/00, effective 4/24/00; WSR 99-15-105, § 246-220-010, filed 7/21/99, effective 8/21/99; WSR 98-13-037, § 246-220-010, filed 6/8/98, effective 7/9/98; WSR 95-01-108, § 246-220-010, filed 12/21/94, effective 1/21/95; WSR 94-01-073, § 246-220-010, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW
70.98.050 and
70.98.080. WSR 91-15-112 (Order 184), § 246-220-010, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW
43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-220-010, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW
70.98.080. WSR 87-01-031 (Order 2450), § 402-12-050, filed 12/11/86; WSR 83-19-050 (Order 2026), § 402-12-050, filed 9/16/83. Statutory Authority: Chapter
70.121 RCW. WSR 81-16-031 (Order 1683), § 402-12-050, filed 7/28/81. Statutory Authority: RCW
70.98.050. WSR 81-01-011 (Order 1570), § 402-12-050, filed 12/8/80; Order 1095, § 402-12-050, filed 2/6/76; Order 708, § 402-12-050, filed 8/24/72; Order 1, § 402-12-050, filed 7/2/71; Order 1, § 402-12-050, filed 1/8/69; Rules (part), filed 10/26/66.]