WSR 09-06-003

PERMANENT RULES

DEPARTMENT OF HEALTH


[ Filed February 18, 2009, 3:50 p.m. , effective March 21, 2009 ]


     Effective Date of Rule: Thirty-one days after filing.

     Purpose: The purpose of these rules is to better regulate sources of ionizing radiation, address two new federal rules, and correct minor grammatical errors in previously adopted rules. The rules incorporate the Nuclear Regulatory Commission's (NRC) expanded definition of by-product material and national source tracking system requirements. The rules affect radium 226, accelerator-produced materials, and discrete sources of naturally occurring radioactive material.

     Citation of Existing Rules Affected by this Order: Amending 32.

     Statutory Authority for Adoption: RCW 70.98.050 and 70.98.080.

      Adopted under notice filed as WSR 08-21-099 on October 16, 2008.

     Changes Other than Editing from Proposed to Adopted Version: Made clarifying corrections recommended by the U.S. NRC. In WAC 246-221-236, corrections made to the table for consistency with WAC 246-235-125. In WAC 246-233-020 added more detail to an existing requirement and corrected a reference number. In WAC 246-235-100 added a C.F.R. reference and included details.

     Number of Sections Adopted in Order to Comply with Federal Statute: New 0, Amended 0, Repealed 0; Federal Rules or Standards: New 6, Amended 32, Repealed 0; or Recently Enacted State Statutes: New 0, Amended 0, Repealed 0.

     Number of Sections Adopted at Request of a Nongovernmental Entity: New 0, Amended 0, Repealed 0.

     Number of Sections Adopted on the Agency's Own Initiative: New 0, Amended 0, Repealed 0.

     Number of Sections Adopted in Order to Clarify, Streamline, or Reform Agency Procedures: New 0, Amended 0, Repealed 0.

     Number of Sections Adopted Using Negotiated Rule Making: New 0, Amended 0, Repealed 0;      Pilot Rule Making: New 0, Amended 0, Repealed 0; or Other Alternative Rule Making: New 6, Amended 32, Repealed 0.

     Date Adopted: February 18, 2009.

Mary C. Selecky

Secretary

OTS-1820.2


AMENDATORY SECTION(Amending WSR 06-05-019, filed 2/6/06, effective 3/9/06)

WAC 246-220-010   Definitions.   As used in ((these regulations)) chapters 246-220 through 246-254 WAC, these terms have the definitions set forth below. Additional definitions used only in a certain ((part)) chapter will be found in that ((part)) chapter.

     (((1))) "Absorbed dose" means the energy imparted by ionizing radiation per unit mass of irradiated material. The units of absorbed dose are the gray (Gy) and the rad.

     (((2))) "Accelerator produced material" means any material made radioactive by exposing it in a particle accelerator.

     (((3))) "Act" means Nuclear energy and radiation, chapter 70.98 RCW.

     (((4))) "Activity" means the rate of disintegration or transformation or decay of radioactive material. The units of activity are the becquerel (Bq) and the curie (Ci).

     (((5))) "Adult" means an individual eighteen or more years of age.

     (((6))) "Agreement state" means any state with which the United States Nuclear Regulatory Commission has entered into an effective agreement under section 274 b. of the Atomic Energy Act of 1954, as amended (73 Stat. 689).

     (((7))) "Airborne radioactive material" means any radioactive material dispersed in the air in the form of particulates, dusts, fumes, mists, vapors, or gases.

     (((8))) "Airborne radioactivity area" means a room, enclosure, or operating area in which airborne radioactive material exists in concentrations (a) in excess of the derived air concentration (DAC) specified in WAC 246-221-290, Appendix A, or (b) to the degree that an individual present in the area without respiratory protective equipment could exceed, during the hours an individual is present in a week, an intake of 0.6 percent of the annual limit on intake (ALI) or twelve DAC-hours.

     (((9))) "Air purifying respirator" means a respirator with an air-purifying filter, cartridge, or canister that removes specific air contaminants by passing ambient air through the air-purifying element.

     (((10))) "Alert" means events may occur, are in progress, or have occurred that could lead to a release of radioactive material but that the release is not expected to require a response by offsite response organizations to protect persons offsite.

     (((11))) "Annual limit on intake" (ALI) means the derived limit for the amount of radioactive material taken into the body of an adult worker by inhalation or ingestion in a year. 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. ALI values for intake by ingestion and by inhalation of selected radionuclides are given in WAC 246-221-290.

     (((12))) "Assigned protection factor" (APF) means the expected workplace level of respiratory protection that would be provided by a properly functioning respirator or a class of respirators to properly fitted and trained users. Operationally, the inhaled concentration can be estimated by dividing the ambient airborne concentration by the APF.

     (((13))) "Atmosphere-supplying respirator" means a respirator that supplies the respirator user with breathing air from a source independent of the ambient atmosphere, and includes supplied-air respirators (SARs) and self-contained breathing apparatus (SCBA) units.

     (((14))) "Background radiation" means radiation from cosmic sources; naturally occurring radioactive materials, including radon, except as a decay product of source or special nuclear material, and including global fallout as it exists in the environment from the testing of nuclear explosive devices or from past nuclear accidents such as Chernobyl that contribute to background radiation and are not under the control of the licensee. "Background radiation" does not include sources of radiation from radioactive materials regulated by the department.

     (((15))) "Becquerel" (Bq) means the SI unit of activity. One becquerel is equal to 1 disintegration or transformation per second (s-1).

     (((16))) "Bioassay" means 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 counting, or by analysis and evaluation of materials excreted or removed from the human body. For purposes of these regulations, "radiobioassay" is an equivalent term.

     (((17))) "Byproduct material" means: (a) Any radioactive material (except special nuclear material) yielded in or made radioactive by exposure to the radiation incident to the process of producing or utilizing special nuclear material((, and)); (b) the tailings or wastes produced by the extraction or concentration of uranium or thorium from any ore processed primarily for its source material content, including discrete surface wastes resulting from uranium or thorium solution extraction processes. Underground ore bodies depleted by these solution extraction operations do not constitute "byproduct material" within this definition; (c) any material that has been made radioactive by use of a particle accelerator; (d) any discrete source of radium 226 that is produced, extracted, or converted after extraction for commercial, medical or research use; and (e) any discrete source of naturally occurring radioactive materials which pose a threat similar to the threat posed by a discrete source of radium 226 to the health and safety or the common defense and security, that is produced, extracted, or converted after extraction for use for commercial, medical or research activities.

     (((18))) "Calendar quarter" means at least twelve but no more than fourteen consecutive weeks. The first calendar quarter of each year begins in January and subsequent calendar quarters shall be arranged so that no day is included in more than one calendar quarter and no day in any one year is omitted from inclusion within a calendar quarter. A licensee or registrant may not change the method of determining calendar quarters for purposes of these regulations.

     (((19))) "Calibration" means the determination of (a) the response or reading of an instrument relative to a series of known radiation values over the range of the instrument, or (b) the strength of a source of radiation relative to a standard.

     (((20))) "CFR" means Code of Federal Regulations.

     (((21))) "Class" means a classification scheme for inhaled material according to its rate of clearance from the pulmonary region of the lung. Materials are classified as D, W, or Y, which applies to a range of clearance half-times: For Class D, Days, of less than ten days, for Class W, Weeks, from ten to one hundred days, and for Class Y, Years, of greater than one hundred days. For purposes of these regulations, "lung class" and "inhalation class" are equivalent terms. For "class of waste" see WAC 246-249-040.

     (((22))) "Collective dose" means the sum of the individual doses received in a given period of time by a specified population from exposure to a specified source of radiation.

     (((23))) "Committed dose equivalent" (HT,50) means the dose equivalent to organs or tissues of reference (T) that will be received from an intake of radioactive material by an individual during the fifty-year period following the intake.

     (((24))) "Committed effective dose equivalent" (HE,50) is the sum of the products of the weighting factors applicable to each of the body organs or tissues that are irradiated and the committed dose equivalent to each of these organs or tissues (HE,50 = Sgr; wT,HT,50).

     "Consortium" means an association of medical use licensees and a PET radionuclide production facility in the same geographical area that jointly own or share in the operation and maintenance cost of the PET radionuclide production facility that produces PET radionuclides for use in producing radioactive drugs within the consortium for noncommercial distributions among its associated members for medical use. The PET radionuclide production facility within the consortium must be located at an educational institution or a federal facility or a medical facility.

     (((25))) "Constraint" or dose constraint means a value above which specified licensee actions are required.

     (((26))) "Controlled area." See "Restricted area."

     (((27))) "Curie" means a unit of quantity of radioactivity. One curie (Ci) is that quantity of radioactive material which decays at the rate of 3.7 x 1010 transformations per second (tps).

     (((28))) "Declared pregnant woman" means a woman who has voluntarily informed the licensee or registrant, in writing, of her pregnancy, and the estimated date of conception. The declaration remains in effect until the declared pregnant woman withdraws the declaration in writing or is no longer pregnant.

     (((29))) "Deep dose equivalent" (Hd), which applies to external whole body exposure, means the dose equivalent at a tissue depth of 1 centimeter (1000 mg/cm2).

     (((30))) "Demand respirator" means an atmosphere-supplying respirator that admits breathing air to the facepiece only when a negative pressure is created inside the facepiece by inhalation.

     (((31))) "Department" means the Washington state department of health, ((office of radiation protection,)) which has been designated as the state radiation control agency under chapter 70.98 RCW.

     (((32))) "Depleted uranium" means the source material uranium in which the isotope Uranium-235 is less than 0.711 percent by weight of the total uranium present. Depleted uranium does not include special nuclear material.

     (((33))) "Derived air concentration" (DAC) means the concentration of a given radionuclide in air which, if breathed by the reference man for a working year of two thousand hours under conditions of light work, results in an intake of one ALI. For purposes of these regulations, the condition of light work is an inhalation rate of 1.2 cubic meters of air per hour for two thousand hours in a year. DAC values are given in WAC 246-221-290.

     (((34))) "Derived air concentration-hour" (DAC-hour) means the product of the concentration of radioactive material in air, expressed as a fraction or multiple of the derived air concentration for each radionuclide, and the time of exposure to that radionuclide, in hours. A licensee or registrant may take two thousand DAC-hours to represent one ALI, equivalent to a committed effective dose equivalent of 0.05 Sv (5 rem).

     (((35))) "Discrete source" means a radionuclide that has been processed so that its concentration within a material has been purposely increased for use for commercial, medical or research activities.

     "Disposable respirator" means a respirator for which maintenance is not intended and that is designed to be discarded after excessive breathing resistance, sorbent exhaustion, physical damage, or end-of-service-life renders it unsuitable for use. Examples of this type of respirator are a disposable half-mask respirator or a disposable escape-only self-contained breathing apparatus (SCBA).

     (((36))) "Dose" is a generic term that means absorbed dose, dose equivalent, effective dose equivalent, committed dose equivalent, committed effective dose equivalent, total organ dose equivalent, or total effective dose equivalent. For purposes of these rules, "radiation dose" is an equivalent term.

     (((37))) "Dose commitment" means the total radiation dose to a part of the body that will result from retention in the body of radioactive material. For purposes of estimating the dose commitment, it is assumed that from the time of intake the period of exposure to retained material will not exceed fifty years.

     (((38))) "Dose equivalent" (HT) means the product of the absorbed dose in tissue, quality factor, and all other necessary modifying factors at the location of interest. The units of dose equivalent are the sievert (Sv) and rem.

     (((39))) "Dose limits" means the permissible upper bounds of radiation doses established in accordance with these regulations. For purposes of these regulations, "limits" is an equivalent term.

     (((40))) "Dosimetry processor" means a person that processes and evaluates individual monitoring devices in order to determine the radiation dose delivered to the monitoring devices.

     (((41))) "dpm" means disintegrations per minute. See also "curie."

     (((42))) "Effective dose equivalent" (HE) means the sum of the products of the dose equivalent to each organ or tissue (HT) and the weighting factor (wT) applicable to each of the body organs or tissues that are irradiated (HE = Sgr; wTHT).

     (((43))) "Embryo/fetus" means the developing human organism from conception until the time of birth.

     (((44))) "Entrance or access point" means any opening through which an individual or extremity of an individual could gain access to radiation areas or to licensed radioactive materials. This includes entry or exit portals of sufficient size to permit human entry, without respect to their intended use.

     (((45))) "Exposure" means (a) being exposed to ionizing radiation or to radioactive material, or (b) the quotient of &Dgr;Q by &Dgr;m where "&Dgr;Q" is the absolute value of the total charge of the ions of one sign produced in air when all the electrons (negatrons and positrons) liberated by photons in a volume element of air having mass "&Dgr;m" are completely stopped in air. The special unit of exposure is the roentgen (R) and the SI equivalent is the coulomb per kilogram. One roentgen is equal to 2.58 x 10-4 coulomb per kilogram of air.

     (((46))) "Exposure rate" means the exposure per unit of time, such as roentgen per minute and milliroentgen per hour.

     (((47))) "External dose" means that portion of the dose equivalent received from any source of radiation outside the body.

     (((48))) "Extremity" means hand, elbow, arm below the elbow, foot, knee, and leg below the knee.

     (((49))) "Filtering facepiece" (dust mask) means a negative pressure particulate respirator with a filter as an integral part of the facepiece or with the entire facepiece composed of the filtering medium, not equipped with elastomeric sealing surfaces and adjustable straps.

     (((50))) "Fit factor" means a quantitative estimate of the fit of a particular respirator to a specific individual, and typically estimates the ratio of the concentration of a substance in ambient air to its concentration inside the respirator when worn.

     (((51))) "Fit test" means the use of a protocol to qualitatively or quantitatively evaluate the fit of a respirator on an individual.

     (((52))) "Former United States Atomic Energy Commission (AEC) or United States Nuclear Regulatory Commission (NRC) licensed facilities" means nuclear reactors, nuclear fuel reprocessing plants, uranium enrichment plants, or critical mass experimental facilities where AEC or NRC licenses have been terminated.

     (((53))) "Generally applicable environmental radiation standards" means standards issued by the United States Environmental Protection Agency (EPA) under the authority of the Atomic Energy Act of 1954, as amended, that impose limits on radiation exposures or levels, or concentrations or quantities of radioactive material, in the general environment outside the boundaries of locations under the control of persons possessing or using radioactive material.

     (((54))) "Gray" (Gy) means the SI unit of absorbed dose. One gray is equal to an absorbed dose of 1 joule/kilogram (100 rad).

     (((55))) "Healing arts" means the disciplines of medicine, dentistry, osteopathy, chiropractic, podiatry, and veterinary medicine.

     (((56))) "Helmet" means a rigid respiratory inlet covering that also provides head protection against impact and penetration.

     (((57))) "High radiation area" means any area, accessible to individuals, in which radiation levels from radiation sources external to the body could result in an individual receiving a dose equivalent in excess of 1 mSv (0.1 rem) in one hour at 30 centimeters from any source of radiation or 30 centimeters from any surface that the radiation penetrates. For purposes of these regulations, rooms or areas in which diagnostic X-ray systems are used for healing arts purposes are not considered high radiation areas.

     (((58))) "Hood" means a respiratory inlet covering that completely covers the head and neck and may also cover portions of the shoulders and torso.

     (((59))) "Human use" means the intentional internal or external administration of radiation or radioactive material to human beings.

     (((60))) "Immediate" or "immediately" means as soon as possible but no later than four hours after the initiating condition.

     (((61))) "IND" means investigatory new drug for which an exemption has been claimed under the United States Food, Drug and Cosmetic Act (Title 21 CFR).

     (((62))) "Individual" means any human being.

     (((63))) "Individual monitoring" means the assessment of:

     (a) Dose equivalent (i) by the use of individual monitoring devices or (ii) by the use of survey data; or

     (b) Committed effective dose equivalent (i) by bioassay or (ii) by determination of the time-weighted air concentrations to which an individual has been exposed, that is, DAC-hours.

     (((64))) "Individual monitoring devices" (individual monitoring equipment) means devices designed to be worn by a single individual for the assessment of dose equivalent e.g., as film badges, thermoluminescent dosimeters (TLDs), pocket ionization chambers, and personal ("lapel") air sampling devices.

     (((65))) "Inspection" means an official examination or observation by the department including but not limited to, tests, surveys, and monitoring to determine compliance with rules, orders, requirements and conditions of the department.

     (((66))) "Interlock" means a device arranged or connected so that the occurrence of an event or condition is required before a second event or condition can occur or continue to occur.

     (((67))) "Internal dose" means that portion of the dose equivalent received from radioactive material taken into the body.

     (((68))) "Irretrievable source" means any sealed source containing licensed material which is pulled off or not connected to the wireline downhole and for which all reasonable effort at recovery, as determined by the department, has been expended.

     (((69))) "Lens dose equivalent" (LDE) applies to the external exposure of the lens of the eye and is taken as the dose equivalent at a tissue depth of 0.3 centimeters (300 mg/cm2).

     (((70))) "License" means a license issued by the department.

     (((71))) "Licensed material" means radioactive material received, possessed, used, transferred, or disposed under a general or specific license issued by the department.

     (((72))) "Licensee" means any person who is licensed by the department under these rules and the act.

     (((73))) "Licensing state" means any state with regulations equivalent to the suggested state regulations for control of radiation relating to, and an effective program for, the regulatory control of NARM and which has been granted final designation by the Conference of Radiation Control Program Directors, Inc.

     (((74))) "Loose-fitting facepiece" means a respiratory inlet covering that is designed to form a partial seal with the face.

     (((75))) "Lost or missing licensed material" means licensed material whose location is unknown. This definition includes licensed material that has been shipped but has not reached its planned destination and whose location cannot be readily traced in the transportation system.

     (((76))) "Member of the public" means an individual except when the individual is receiving an occupational dose.

     (((77))) "Minor" means an individual less than eighteen years of age.

     (((78))) "Monitoring" means the measurement of radiation, radioactive material concentrations, surface area activities or quantities of radioactive material and the use of the results of these measurements to evaluate potential exposures and doses. For purposes of these regulations, radiation monitoring and radiation protection monitoring are equivalent terms.

     (((79))) "NARM" means any naturally occurring or accelerator-produced radioactive material. It does not include by-product, source, or special nuclear material. For the purpose of meeting the definition of a licensing state by the Conference of Radiation Control Program Directors, Inc. (CRCPD), NARM refers only to discrete sources of NARM. Diffuse sources of NARM are excluded from consideration by the CRCPD for Licensing State designation purposes.

     (((80))) "Nationally tracked source" means a sealed source containing a quantity equal to or greater than Category 1 or Category 2 levels of any radioactive material listed in WAC 246-221-236. In this context a sealed source is defined as radioactive material that is sealed in a capsule or closely bonded, in a solid form and which is not exempt from regulatory control. It does not mean material encapsulated solely for disposal, or nuclear material contained in any fuel assembly, subassembly, fuel rod, or fuel pellet. Category 1 nationally tracked sources are those containing radioactive material at a quantity equal to or greater than the Category 1 threshold. Category 2 nationally tracked sources are those containing radioactive material at a quantity equal to or greater than the Category 2 threshold but less than the Category 1 threshold.

     "Natural radioactivity" means radioactivity of naturally occurring nuclides.

     (((81))) "NDA" means a new drug application which has been submitted to the United States Food and Drug Administration.

     (((82))) "Negative pressure respirator" (tight-fitting) means a respirator in which the air pressure inside the facepiece is negative during inhalation with respect to the ambient air pressure outside the respirator.

     (((83))) "Nonstochastic effect" means a health effect, the severity of which varies with the dose and for which a threshold is believed to exist. Radiation-induced cataract formation is an example of a nonstochastic effect. For purposes of these rules, a "deterministic effect" is an equivalent term.

     (((84))) "Nuclear Regulatory Commission" (NRC) means the United States Nuclear Regulatory Commission or its duly authorized representatives.

     (((85))) "Occupational dose" means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee, registrant, or other person. Occupational dose does not include dose received: From background radiation, from any medical administration the individual has received, from exposure to individuals administered radioactive material and released under chapter 246-240 WAC, from voluntary participation in medical research programs, or as a member of the public.

     (((86))) "Ore refineries" means all processors of a radioactive material ore.

     (((87))) "Particle accelerator" means any machine capable of accelerating electrons, protons, deuterons, or other charged particles in a vacuum and of discharging the resultant particulate or other radiation into a medium at energies usually in excess of 1 MeV. For purposes of this definition, "accelerator" is an equivalent term.

     (((88))) "Permittee" means a person who has applied for, and received, a valid site use permit for use of the low-level waste disposal facility at Hanford, Washington.

     (((89))) "Person" means any individual, corporation, partnership, firm, association, trust, estate, public or private institution, group, agency, political subdivision of this state, any other state or political subdivision or agency thereof, and any legal successor, representative, agent or agency of the foregoing, but shall not include federal government agencies.

     (((90))) "Personal supervision" means supervision where the supervisor is physically present at the facility and in sufficient proximity that contact can be maintained and immediate assistance given as required.

     (((91))) "Personnel monitoring equipment." See individual monitoring devices.

     "PET" means positron emission tomography.

     (((92))) "Pharmacist" means an individual licensed by this state to compound and dispense drugs, and poisons.

     (((93))) "Physician" means a medical doctor or doctor of osteopathy licensed by this state to prescribe and dispense drugs in the practice of medicine.

     (((94))) "Planned special exposure" means an infrequent exposure to radiation, separate from and in addition to the annual occupational dose limits.

     (((95))) "Positive pressure respirator" means a respirator in which the pressure inside the respiratory inlet covering exceeds the ambient air pressure outside the respirator.

     (((96))) "Powered air-purifying respirator" (PAPR) means an air-purifying respirator that uses a blower to force the ambient air through air-purifying elements to the inlet covering.

     (((97))) "Practitioner" means an individual licensed by the state in the practice of a healing art (i.e., physician, dentist, podiatrist, chiropractor, etc.).

     (((98))) "Pressure demand respirator" means a positive pressure atmosphere-supplying respirator that admits breathing air to the facepiece when the positive pressure is reduced inside the facepiece by inhalation.

     (((99))) "Public dose" means the dose received by a member of the public from exposure to sources of radiation under the licensee's or registrant's control or to radiation or radioactive material released by the licensee. Public dose does not include occupational dose or doses received from background radiation, from any medical administration the individual has received, from exposure to individuals administered radioactive material and released under chapter 246-240 WAC, or from voluntary participation in medical research programs.

     (((100))) "Qualified expert" means an individual who has demonstrated to the satisfaction of the department he/she has the knowledge, training, and experience to measure ionizing radiation, to evaluate safety techniques, and to advise regarding radiation protection needs. The department reserves the right to recognize the qualifications of an individual in specific areas of radiation protection.

     (((101))) "Qualitative fit test" (QLFT) means a pass/fail fit test to assess the adequacy of respirator fit that relies on the individual's response to the test agent.

     (((102))) "Quality factor" (Q) means the modifying factor, listed in Tables I and II, that is used to derive dose equivalent from absorbed dose.


TABLE I
QUALITY FACTORS AND ABSORBED DOSE EQUIVALENCIES

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 regulations, 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.

     (((103))) "Quantitative fit test" (QNFT) means an assessment of the adequacy of respirator fit by numerically measuring the amount of leakage into the respirator.

     (((104))) "Quarter" means a period of time equal to one-fourth of the year observed by the licensee, approximately thirteen 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.

     (((105))) "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).

     (((106))) "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 regulations, ionizing radiation is an equivalent term. Radiation, as used in these regulations, does not include magnetic fields or nonionizing radiation, like radiowaves or microwaves, visible, infrared, or ultraviolet light.

     (((107))) "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 thirty centimeters from the source of radiation or from any surface that the radiation penetrates.

     (((108))) "Radiation machine" means any device capable of producing ionizing radiation except those devices with radioactive materials as the only source of radiation.

     (((109))) "Radiation safety officer" means an individual who has the knowledge and responsibility to apply appropriate radiation protection regulations and has been assigned that responsibility by the licensee or registrant.

     (((110))) "Radiation source." See "Source of radiation."

     (((111))) "Radioactive material" means any material (solid, liquid, or gas) which emits radiation spontaneously.

     (((112))) "Radioactive waste" means any radioactive material which is no longer of use and intended for disposal or treatment for the purposes of disposal.

     (((113))) "Radioactivity" means the transformation of unstable atomic nuclei by the emission of radiation.

     (((114))) "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.

     (((115))) "Registrable item" means any radiation machine except those exempted by RCW 70.98.180 or exempted by the department under the authority of RCW 70.98.080.

     (((116))) "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.

     (((117))) "Registration" means registration with the department in accordance with the regulations adopted by the department.

     (((118))) "Regulations of the United States Department of Transportation" means the regulations in 49 CFR Parts 170-189, 14 CFR Part 103, and 46 CFR Part 146.

     (((119))) "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).

     (((120))) "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.

     (((121))) "Respiratory protective equipment" means an apparatus, such as a respirator, used to reduce an individual's intake of airborne radioactive materials.

     (((122))) "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.

     (((123))) "Roentgen" (R) means the special unit of exposure. One roentgen equals 2.58 x 10-4 coulombs/kilogram of air.

     (((124))) "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.

     (((125))) "Sealed source" means any radioactive material that is encased in a capsule designed to prevent leakage or the escape of the radioactive material.

     (((126))) "Self-contained breathing apparatus" (SCBA) means an atmosphere-supplying respirator for which the breathing air source is designed to be carried by the user.

     (((127))) "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).

     (((128))) "SI" means an abbreviation of the International System of Units.

     (((129))) "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).

     (((130))) "Site area emergency" means events 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 offsite response organizations to protect persons offsite.

     (((131))) "Site boundary" means that line beyond which the land or property is not owned, leased, or otherwise controlled by the licensee or registrant.

     (((132))) "Source container" means a device in which radioactive material is transported or stored.

     (((133))) "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 (i) uranium, (ii) thorium, or (iii) any combination thereof. Source material does not include special nuclear material.

     (((134))) "Source material milling" means the extraction or concentration of uranium or thorium from any ore processing primarily for its source material content.

     (((135))) "Source of radiation" means any radioactive material, or any device or equipment emitting or capable of producing ionizing radiation.

     (((136))) "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 United States Nuclear Regulatory Commission, 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.

     (((137))) "Special nuclear material in quantities not sufficient to form a critical mass" means uranium enriched in the isotope U-235 in quantities not exceeding three hundred fifty grams of contained U-235; uranium-233 in quantities not exceeding two hundred grams; plutonium in quantities not exceeding two hundred 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)

200

 < 1

     (((138))) "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 regulations, probabilistic effect is an equivalent term.

     (((139))) "Supplied-air respirator" (SAR) or "airline respirator" means an atmosphere-supplying respirator for which the source of breathing air is not designed to be carried by the user.

     (((140))) "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.

     (((141))) "Test" means (a) the process of verifying compliance with an applicable regulation, or (b) a method for determining the characteristics or condition of sources of radiation or components thereof.

     (((142))) "These rules" mean all parts of the rules for radiation protection of the state of Washington.

     (((143))) "Tight-fitting facepiece" means a respiratory inlet covering that forms a complete seal with the face.

     (((144))) "Total effective dose equivalent" (TEDE) means the sum of the deep dose equivalent for external exposures and the committed effective dose equivalent for internal exposures.

     (((145))) "Total organ dose equivalent" (TODE) means the sum of the deep dose equivalent and the committed dose equivalent to the organ or tissue receiving the highest dose.

     (((146))) "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).

     (((147))) "Unrefined and unprocessed ore" means ore in its natural form prior to any processing, such as grinding, roasting, beneficiating, or refining.

     (((148))) "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.

     (((149))) "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.

     (((150))) "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.

     (((151))) "Waste" means those low-level radioactive wastes containing source, special nuclear or byproduct 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 byproduct material as defined in this section.

     "Waste handling licensees" mean persons licensed to receive and store radioactive wastes prior to disposal and/or persons licensed to dispose of radioactive waste.

     (((152))) "Week" means seven consecutive days starting on Sunday.

     (((153))) "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.

     (((154))) "Whole body" means, for purposes of external exposure, head, trunk including male gonads, arms above the elbow, or legs above the knee.

     (((155))) "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 eighteen years or older are subjected routinely to work involving radiation, then the students are considered to be workers. Individuals of less than eighteen years of age shall meet the requirements of WAC 246-221-050.

     (((156))) "Working level" (WL) 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.

     (((157))) "Working level month" (WLM) means an exposure to one working level for one hundred seventy hours -- two thousand working hours per year divided by twelve months per year is approximately equal to one hundred seventy hours per month.

     (((158))) "Year" means the period of time beginning in January used to determine compliance with the provisions of these regulations. 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 70.98.050. 06-05-019, § 246-220-010, filed 2/6/06, effective 3/9/06; 04-23-093, § 246-220-010, filed 11/17/04, effective 12/18/04; 01-05-110, § 246-220-010, filed 2/21/01, effective 3/24/01; 00-08-013, § 246-220-010, filed 3/24/00, effective 4/24/00; 99-15-105, § 246-220-010, filed 7/21/99, effective 8/21/99; 98-13-037, § 246-220-010, filed 6/8/98, effective 7/9/98; 95-01-108, § 246-220-010, filed 12/21/94, effective 1/21/95; 94-01-073, § 246-220-010, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. 91-15-112 (Order 184), § 246-220-010, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-220-010, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 87-01-031 (Order 2450), § 402-12-050, filed 12/11/86; 83-19-050 (Order 2026), § 402-12-050, filed 9/16/83. Statutory Authority: Chapter 70.121 RCW. 81-16-031 (Order 1683), § 402-12-050, filed 7/28/81. Statutory Authority: RCW 70.98.050. 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.]

OTS-1821.4


NEW SECTION
WAC 246-221-235   Reports of transactions involving nationally tracked sources.   Each licensee who manufactures, transfers, receives, disassembles, or disposes of a nationally tracked source shall complete and submit a National Source Tracking Transaction Report as specified in subsections (1) through (5) of this section for each type of transaction.

     (1) Each licensee who manufactures a nationally tracked source shall complete and submit a National Source Tracking Transaction Report. The report must include the following information:

     (a) The name, address, and license number of the reporting licensee;

     (b) The name of the individual preparing the report;

     (c) The manufacturer, model, and serial number of the source;

     (d) The radioactive material in the source;

     (e) The initial source strength in becquerels (curies) at the time of manufacture; and

     (f) The manufacture date of the source.

     (2) Each licensee that transfers a nationally tracked source to another person shall complete and submit a National Source Tracking Transaction Report. The report must include the following information:

     (a) The name, address, and license number of the reporting licensee;

     (b) The name of the individual preparing the report;

     (c) The name and license number of the recipient facility and the shipping address;

     (d) The manufacturer, model, and serial number of the source or, if not available, other information to uniquely identify the source;

     (e) The radioactive material in the source;

     (f) The initial or current source strength in becquerels (curies);

     (g) The date for which the source strength is reported;

     (h) The shipping date;

     (i) The estimated arrival date; and

     (j) For nationally tracked sources transferred as waste under a Uniform Low-Level Radioactive Waste Manifest, the waste manifest number and the container identification of the container with the nationally tracked source.

     (3) Each licensee that receives a nationally tracked source shall complete and submit a National Source Tracking Transaction Report. The report must include the following information:

     (a) The name, address, and license number of the reporting licensee;

     (b) The name of the individual preparing the report;

     (c) The name, address, and license number of the person that provided the source;

     (d) The manufacturer, model, and serial number of the source or, if not available, other information to uniquely identify the source;

     (e) The radioactive material in the source;

     (f) The initial or current source strength in becquerels (curies);

     (g) The date for which the source strength is reported;

     (h) The date of receipt; and

     (i) For material received under a Uniform Low-Level Radioactive Waste Manifest, the waste manifest number and the container identification with the nationally tracked source.

     (4) Each licensee that disassembles a nationally tracked source shall complete and submit a National Source Tracking Transaction Report. The report must include the following information:

     (a) The name, address, and license number of the reporting licensee;

     (b) The name of the individual preparing the report;

     (c) The manufacturer, model, and serial number of the source or, if not available, other information to uniquely identify the source;

     (d) The radioactive material in the source;

     (e) The initial or current source strength in becquerels (curies);

     (f) The date for which the source strength is reported;

     (g) The disassemble date of the source.

     (5) Each licensee who disposes of a nationally tracked source shall complete and submit a National Source Tracking Transaction Report. The report must include the following information:

     (a) The name, address, and license number of the reporting licensee;

     (b) The name of the individual preparing the report;

     (c) The waste manifest number;

     (d) The container identification with the nationally tracked source;

     (e) The date of disposal; and

     (f) The method of disposal.

     (6) The reports discussed in subsections (1) through (5) of this section must be submitted by the close of the next business day after the transaction. A single report may be submitted for multiple sources and transactions. The reports must be submitted to the National Source Tracking System by using:

     (a) The on-line National Source Tracking System;

     (b) Electronically using a computer-readable format;

     (c) By facsimile;

     (d) By mail to the address on the National Source Tracking Transaction Report Form (NRC Form 748); or

     (e) By telephone with follow-up by facsimile or mail.

     (7) Each licensee shall correct any error in previously filed reports or file a new report for any missed transaction within five business days of the discovery of the error or missed transaction. Such errors may be detected by a variety of methods such as administrative reviews or by physical inventories required by regulation. In addition, each licensee shall reconcile the inventory of nationally tracked sources possessed by the licensee against that licensee's data in the National Source Tracking System. The reconciliation must be conducted during the month of January in each year. The reconciliation process must include resolving any discrepancies between the National Source Tracking System and the actual inventory by filing the reports identified by subsections (1) through (5) of this section. By January 31, of each year, each licensee must submit to the National Source Tracking System confirmation that the data in the National Source Tracking System is correct.

     (8) Each licensee that possesses Category 1 or 2 nationally tracked sources shall report its initial inventory of Category 1 or 2 nationally tracked sources to the National Source Tracking System by January 31, 2009. The information may be submitted by using any of the methods identified in subsection (6)(a) through (d) of this section. The initial inventory report shall include the following information:

     (a) The name, address, and license number of the reporting licensee;

     (b) The name of the individual preparing the report;

     (c) The manufacturer, model, and serial number of each nationally tracked source or, if not available, other information to uniquely identify the source;

     (d) The radioactive material in the sealed source;

     (e) The initial or current source strength in becquerels (curies); and

     (f) The date for which the source strength is reported.

[]


NEW SECTION
WAC 246-221-236   Nationally tracked source thresholds.   The Terabecquerel (TBq) values are the regulatory standard. The curie (Ci) values specified are obtained by converting from the TBq value. The curie values are provided for practical usefulness only and are rounded after conversion.


Radioactive Material Category 1

(TBq)

 Category 1

(Ci)

 Category 2

(TBq)

 Category 2

(Ci)
Actinium-227 20 540 0.2 5.4
Americium-241 60 1,600 0.6 16
Americium-241/Be 60 1,600 0.6 16
Californium-252 20 540 0.2 5.4
Cobalt-60 30 810 0.3 8.1
Cesium-137 100 2,700 1 27
Curium-244 50 1,400 0.5 14
Gadolinium-153 1,000 27,000 10 270
Iridium-192 80 2,200 0.8 22
Plutonium-238 60 1,600 0.6 16
Plutonium-239/Be 60 1,600 0.6 16
Polonium-210 60 1,600 0.6 16
Promethium-147 40,000 1,100,000 400 11,000
Radium-226 40 1,100 0.4 11
Selenium-75 200 5,400 2 54
Strontium-90 1,000 27,000 10 270
Thorium-228 20 540 0.2 5.4
Thorium-229 20 540 0.2 5.4
Thulium-170 20,000 540,000 200 5,400
Ytterbium-169 300 8,100 3 81

[]


AMENDATORY SECTION(Amending WSR 94-01-073, filed 12/9/93, effective 1/9/94)

WAC 246-221-290   Appendix A -- Annual limits on intake (ALI) and derived air concentrations (DAC) of radionuclides for occupational exposure; effluent concentrations; concentrations for release to sanitary sewerage.   For each radionuclide, Table I indicates the chemical form which is to be used for selecting the appropriate ALI or DAC value. The ALIs and DACs for inhalation are given for an aerosol with an activity median aerodynamic diameter (AMAD) of 1 µm (micron) and for three classes (D,W,Y) of radioactive material, which refer to their retention (approximately days, weeks or years) in the pulmonary region of the lung. This classification applies to a range of clearance half-times for D if less than ten days, for W from ten to one hundred days, and for Y greater than one hundred days. Table II provides concentration limits for airborne and liquid effluents released to the general environment. Table III provides concentration limits for discharges to sanitary sewerage.


Note: The values in Tables I, II, and III are presented in the computer "E" notation. In this notation a value of 6E-02 represents a value of 6 x 10-2 or 0.06, 6E+2 represents 6 x ((1O)) 102 or 600, and 6E+0 represents 6 x 100 or 6.

     Table I "Occupational Values"


     Note that the columns in Table I of this appendix captioned "Oral Ingestion ALI," "Inhalation ALI," and "DAC," are applicable to occupational exposure to radioactive material.


     The ALIs in this appendix are the annual intakes of given radionuclide by "Reference Man" which would result in either: A committed effective dose equivalent of 0.05 Sv (5 rem), stochastic ALI; or a committed dose equivalent of 0.5 Sv (50 rem) to an organ or tissue, nonstochastic ALI. The stochastic ALIs were derived to result in a risk, due to irradiation of organs and tissues, comparable to the risk associated with deep dose equivalent to the whole body of 0.05 Sv (5 rem). The derivation includes multiplying the committed dose equivalent to an organ or tissue by a weighting factor, wT. This weighting factor is the proportion of the risk of stochastic effects resulting from irradiation of the organ or tissue, T, to the total risk of stochastic effects when the whole body is irradiated uniformly. The values of wT are listed under the definition of weighting factor in WAC 246-221-005. The nonstochastic ALIs were derived to avoid nonstochastic effects, such as prompt damage to tissue or reduction in organ function.


     A value of wT = 0.06 is applicable to each of the five organs or tissues in the "remainder" category receiving the highest dose equivalents, and the dose equivalents of all other remaining tissues may be disregarded. The following portions of the GI tract -- stomach, small intestine, upper large intestine, and lower large intestine -- are to be treated as four separate organs.


     Note that the dose equivalents for an extremity, elbows, arms below the elbows, feet and lower legs, knees, and legs below the knees, skin, and lens of the eye are not considered in computing the committed effective dose equivalent, but are subject to limits that must be met separately.


     When an ALI is defined by the stochastic dose limit, this value alone is given. When an ALI is determined by the non-stochastic dose limit to an organ, the organ or tissue to which the limit applies is shown, and the ALI for the stochastic limit is shown in parentheses. Abbreviated organ or tissue designations are used:


LLI wall = lower large intestine wall;
St. wall = stomach wall;
Blad wall = bladder wall; and
Bone surf = bone surface.

     The use of the ALIs listed first, the more limiting of the stochastic and nonstochastic ALIs, will ensure that nonstochastic effects are avoided and that the risk of stochastic effects is limited to an acceptably low value. If, in a particular situation involving a radionuclide for which the nonstochastic ALI is limiting, use of that nonstochastic ALI is considered unduly conservative, the licensee may use the stochastic ALI to determine the committed effective dose equivalent. However, the licensee shall also ensure that the 0.5 Sv (50 rem) dose equivalent limit for any organ or tissue is not exceeded by the sum of the external deep dose equivalent plus the internal committed dose equivalent to that organ, not the effective dose. For the case where there is no external dose contribution, this would be demonstrated if the sum of the fractions of the nonstochastic ALIs (ALIns) that contribute to the committed dose equivalent to the organ receiving the highest dose does not exceed unity, that is, ∑ (intake (in µCi) of each radionuclide/ALIns) ≤ 1.0. If there is an external deep dose equivalent contribution of Hd, then this sum must be less than 1 - (Hd/50), instead of ≤ 1.0.


     The derived air concentration (DAC) values are derived limits intended to control chronic occupational exposures. The relationship between the DAC and the ALI is given by:


DAC = ALI (in µCi)/(2000 hours per working year x 60 minutes/hour x 2 x 104 ml per minute) = [ALI/2.4 x 109] µCi/ml,
where 2 x 104 ml per minute is the volume of air breathed per minute at work by Reference Man under working conditions of light work.


     The DAC values relate to one of two modes of exposure: Either external submersion or the internal committed dose equivalents resulting from inhalation of radioactive materials. DACs based upon submersion are for immersion in a semi-infinite cloud of uniform concentration and apply to each radionuclide separately.


     The ALI and DAC values include contributions to exposure by the single radionuclide named and any in-growth of daughter radionuclides produced in the body by decay of the parent. However, intakes that include both the parent and daughter radionuclides should be treated by the general method appropriate for mixtures.


     The values of ALI and DAC do not apply directly when the individual both ingests and inhales a radionuclide, when the individual is exposed to a mixture of radionuclides by either inhalation or ingestion or both, or when the individual is exposed to both internal and external irradiation. See WAC 246-221-015. When an individual is exposed to radioactive materials which fall under several of the translocation classifications of the same radionuclide, such as, Class D, Class W, or Class Y, the exposure may be evaluated as if it were a mixture of different radionuclides.


     It should be noted that the classification of a compound as Class D, W, or Y is based on the chemical form of the compound and does not take into account the radiological half-life of different radionuclides. For this reason, values are given for Class D, W, and Y compounds, even for very short-lived radionuclides.


     Table II "Effluent Concentrations"


     The columns in Table II of this appendix captioned "Effluents," "Air" and "Water" are applicable to the assessment and control of dose to the public, particularly in the implementation of the provisions of WAC 246-221-070. The concentration values given in Columns 1 and 2 of Table II are equivalent to the radionuclide concentrations which, if inhaled or ingested continuously over the course of a year, would produce a total effective dose equivalent of 0.50 mSv (0.05 rem).


     Consideration of nonstochastic limits has not been included in deriving the air and water effluent concentration limits because nonstochastic effects are presumed not to occur at or below the dose levels established for individual members of the public. For radionuclides, where the nonstochastic limit was governing in deriving the occupational DAC, the stochastic ALI was used in deriving the corresponding airborne effluent limit in Table II. For this reason, the DAC and airborne effluent limits are not always proportional as was the case in the previous Appendix A of this chapter.


     The air concentration values listed in Table II, Column 1 were derived by one of two methods. For those radionuclides for which the stochastic limit is governing, the occupational stochastic inhalation ALI was divided by 2.4 x 109, relating the inhalation ALI to the DAC, as explained above, and then divided by a factor of three hundred. The factor of three hundred includes the following components: A factor of fifty to relate the 0.05 Sv (5 rem) annual occupational dose limit to the 1 mSv (0.1 rem) limit for members of the public, a factor of three to adjust for the difference in exposure time and the inhalation rate for a worker and that for members of the public; and a factor of two to adjust the occupational values, derived for adults, so that they are applicable to other age groups.


     For those radionuclides for which submersion, that is external dose, is limiting, the occupational DAC in Table I, Column 3 was divided by two hundred nineteen. The factor of two hundred nineteen is composed of a factor of fifty, as described above, and a factor of 4.38 relating occupational exposure for two thousand hours per year to full-time exposure (eight thousand seven hundred sixty hours per year). Note that an additional factor of two for age considerations is not warranted in the submersion case.


     The water concentrations were derived by taking the most restrictive occupational stochastic oral ingestion ALI and dividing by 7.3 x 107. The factor of 7.3 x 107 (ml) includes the following components: The factors of fifty and two described above and a factor of 7.3 x 105 (ml) which is the annual water intake of Reference Man.


     Note 2 of this appendix provides groupings of radionuclides which are applicable to unknown mixtures of radionuclides. These groupings, including occupational inhalation ALIs and DACs, air and water effluent concentrations and releases to sewer, require demonstrating that the most limiting radionuclides in successive classes are absent. The limit for the unknown mixture is defined when the presence of one of the listed radionuclides cannot be definitely excluded as being present either from knowledge of the radionuclide composition of the source or from actual measurements.


     Table III "Releases to Sewers"


     The monthly average concentrations for release to sanitary sewerage are applicable to the provisions in WAC 246-221-190. The concentration values were derived by taking the most restrictive occupational stochastic oral ingestion ALI and dividing by 7.3 x ((1O)) 106 (ml). The factor of 7.3 x ((1O)) 106 (ml) is composed of a factor of 7.3 x ((1O)) 105 (ml), the annual water intake by Reference Man, and a factor of ten, such that the concentrations, if the sewage released by the licensee were the only source of water ingested by a Reference Man during a year, would result in a committed effective dose equivalent of 5 mSv (0.5 rem).

LIST OF ELEMENTS
Name Symbol Atomic

Number

 Name Symbol Atomic

Number
Actinium Ac 89 ((Mercury)) Molybdenum ((Hg)) Mo ((80)) 42
Aluminum Al 13 ((Molybdenum)) Neodymium ((Mo)) Nd ((42)) 60
Americium Am 95 ((Neodymium)) Neptunium ((Nd)) Np ((60)) 93
Antimony Sb 51 ((Neptunium)) Nickel ((Np)) Ni ((93)) 28
Argon Ar 18 ((Nickel)) Nitrogen ((Ni)) N ((28)) 7
Arsenic As 33 Niobium Nb 41
Astatine At 85 Osmium Os 76
Barium Ba 56 ((Palladium)) Oxygen ((Pd)) O ((46)) 8
Berkelium Bk 97 ((Phosphorus)) Palladium ((P)) Pd ((15)) 46
Beryllium Be 4 ((Platinum)) Phosphorus ((Pt)) P ((78)) 15
Bismuth Bi 83 ((Plutonium)) Platinum ((Pu)) Pt ((94)) 78
Bromine Br 35 ((Polonium)) Plutonium ((Po)) Pu ((84)) 94
Cadmium Cd 48 ((Potassium)) Polonium ((K)) Po ((19)) 84
Calcium Ca 20 ((Praseodymium)) Potassium ((Pr)) K ((59)) 19
Californium Cf 98 ((Promethium)) Praseodymium ((Pm)) Pr ((61)) 59
Carbon C 6 ((Protactinium)) Promethium ((Pa)) Pm ((91)) 61
Cerium Ce 58 ((Radium)) Protactinium ((Ra)) Pa ((88)) 91
Cesium Cs 55 ((Radon)) Radium ((Rn)) Ra ((86)) 88
Chlorine Cl 17 ((Rhenium)) Radon ((Re)) Rn ((75)) 86
Chromium Cr 24 ((Rhodium)) Rhenium ((Rh)) Re ((45)) 75
Cobalt Co 27 ((Rubidium)) Rhodium ((Rb)) Rh ((37)) 45
Copper Cu 29 ((Ruthenium)) Rubidium ((Ru)) Rb ((44)) 37
Curium Cm 96 ((Samarium)) Ruthenium ((Sm)) Ru ((62)) 44
Dysprosium Dy 66 ((Scandium)) Samarium ((Sc)) Sm ((21)) 62
Einsteinium Es 99 ((Selenium)) Scandium ((Se)) Sc ((34)) 21
Erbium Er 68 ((Silicon)) Selenium ((Si)) Se ((14)) 34
Europium Eu 63 ((Silver)) Silicon ((Ag)) Si ((47)) 14
Fermium Fm 100 ((Sodium)) Silver ((Na)) Ag ((11)) 47
Fluorine F 9 ((Strontium)) Sodium ((Sr)) Na ((38)) 11
Francium Fr 87 ((Sulfur)) Strontium ((S)) Sr ((16)) 38
Gadolinium Gd 64 ((Tantalum)) Sulfur ((Ta)) S ((73)) 16
Gallium Ga 31 ((Technetium)) Tantalum ((Tc)) Ta ((43)) 73
Germanium Ge 32 ((Tellurium)) Technetium ((Te)) Tc ((52)) 43
Gold Au 79 ((Terbium)) Tellurium ((Tb)) Te ((65)) 52
Hafnium Hf 72 ((Thallium)) Terbium ((Tl)) Tb ((81)) 65
Holmium Ho 67 ((Thorium)) Thallium ((Th)) Tl ((90)) 81
Hydrogen H 1 ((Thulium)) Thorium ((Tm)) Th ((69)) 90
Indium In 49 ((Tin)) Thulium ((Sn)) Tm ((50)) 69
Iodine I 53 ((Titanium)) Tin ((Ti)) Sn ((22)) 50
Iridium Ir 77 ((Tungsten)) Titanium ((W)) Ti ((74)) 22
Iron Fe 26 ((Uranium)) Tungsten ((U)) W ((92)) 74
Krypton Kr 36 ((Vanadium)) Uranium ((V)) U ((23)) 92
Lanthanum La 57 ((Xenon)) Vanadium ((Xe)) V ((54)) 23
Lead Pb 82 ((Ytterbium)) Xenon ((Yb)) Xe ((70)) 54
Lutetium Lu 71 ((Yttrium)) Ytterbium ((Y)) Yb ((39)) 70
Magnesium Mg 12 ((Zinc)) Yttrium ((Zn)) Y ((30)) 39
Manganese Mn 25 ((Zirconium)) Zinc ((Zr)) Zn ((40)) 30
Mendelevium Md 101 Zirconium Zr 40
Mercury Hg 80


Table 1

Occupational Values
Table II

Effluent

Concentration

 Table III

Releases to

Sewers
Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Monthly

Average

Concen-

tration
Oral

Ingestion

 Inhalation
Atomic No. Radionuclide Class ALI

µCi

 ALI

µCi

 DAC

µCi/ml

 Air

µCi/ml

 Water

µCi/ml

µCi/ml
1 Hydrogen-3 Water, DAC includes

skin absorption

8E+4

8E+4

2E-5

1E-7

1E-3

1E-2
Gas (HT or T2) Submersion1: Use above values as HT and T2 oxidize in air and in the body to HTO.
4 Beryllium-7 W, all compounds except

those given for Y

 4E+4 2E+4 9E-6 3E-8 6E-4 6E-3
Y, oxides, halides, and nitrates - 2E+4 8E-6 3E-8 - -
4 Beryllium-10 W, see 7Be 1E+3 2E+2 6E-8 2E-10 - -
LLI wall (1E+3) - - - 2E-5 2E-4
Y, see 7Be - 1E+1 6E-9 2E-11 - -
6 Carbon-112 Monoxide - 1E+6 5E-4 2E-6 - -
Dioxide - 6E+5 3E-4 9E-7 - -
Compounds 4E+5 4E+5 2E-4 6E-7 6E-3 6E-2
6 Carbon-14 Monoxide - 2E+6 7E-4 2E-6 - -
Dioxide - 2E+5 9E-5 3E-7 - -
Compounds 2E+3 2E+3 1E-6 3E-9 3E-5 3E-4
7 Nitrogen-132 Submersion1 - - 4E-6 2E-8 - -
8 Oxygen-152 Submersion1 - - 4E-6 2E-8 - -
9 Fluorine-182 D, fluorides of H, Li,

Na, K, Rb, Cs, and Fr

 5E+4 7E+4 3E-5 1E-7 - -
St wall

(5E+4)

 - - - 7E-4 7E-3
W, fluorides of Be, Mg,

Ca, Sr, Ba, Ra, Al, Ga,

In, Tl, As, Sb, Bi, Fe,

Ru, Os, Co, Ni, Pd, Pt,

Cu, Ag, Au, Zn, Cd, Hg,

Sc, Y, Ti, Zr, V, Nb,

Ta, Mn, Tc, and Re

Y, lanthanum fluoride

 -

-

 9E+4

8E+4

 4E-5

3E-5

 1E-7

1E-7

 -

-

-

-
11 Sodium-22 D, all compounds 4E+2 6E+2 3E-7 9E-10 6E-6 6E-5
11 Sodium-24 D, all compounds 4E+3 5E+3 2E-6 7E-9 5E-5 5E-4
12 Magnesium-28 D, all compounds except

those given for W

 7E+2 2E+3 7E-7 2E-9 9E-6 9E-5
W, oxides, hydroxides,

carbides, halides, and nitrates

 - 1E+3 5E-7 2E-9 - -
13 Aluminum-26 D, all compounds except

those given for W

 4E+2 6E+1 3E-8 9E-11 6E-6 6E-5
W, oxides, hydroxides,

carbides, halides, and nitrates

 - 9E+1 4E-8 1E-10 - -
14 Silicon-31 D, all compounds except

those given for W and Y

 9E+3 3E+4 1E-5 4E-8 1E-4 1E-3
W, oxides, hydroxides,

carbides, and nitrates

Y, aluminosilicate glass

 -

-

 3E+4

3E+4

 1E-5

1E-5

 5E-8

4E-8

 -

-

 -

-
14 Silicon-32 D, see 31Si 2E+3 2E+2 1E-7 3E-10 - -
LLI wall (3E+3) - - - 4E-5 4E-4
W, see 31Si - 1E+2 5E-8 2E-10 - -
Y, see 31Si - 5E+0 2E-9 7E-12 - -
15 Phosphorus-32 D, all compounds except

phosphates given for W

 6E+2 9E+2 4E-7 1E-9 9E-6 9E-5
W, phosphates of Zn2+,

S3+, Mg2+, Fe3+, Bi3+,

and lanthanides

 - 4E+2 2E-7 5E-10 - -
15 Phosphorus-33 D, see 32P 6E+3 8E+3 4E-6 1E-8 8E-5 8E-4
W, see 32P - 3E+3 1E-6 4E-9 - -
16 Sulfur-35 Vapor - 1E+4 6E-6 2E-8 - -
D, sulfides and sulfates

except those given for W

 1E+4 2E+4 7E-6 2E-8 - -
LLI wall (8E+3) - - - 1E-4 1E-3
W, elemental sulfur,

sulfides of Sr, Ba, Ge,

Sn, Pb, As, Sb, Bi, Cu,

Ag, Au, Zn, Cd, Hg, W, and

Mo. Sulfates of Ca, Sr,

Ba, Ra, As, Sb, and Bi

 6E+3

-

2E+3

9E-7

3E-9

-

-
17 Chlorine-36 D, chlorides of H, Li,

Na, K, Rb, Cs, and Fr

 2E+3 2E+3 1E-6 3E-9 2E-5 2E-4
W, chlorides of lantha-

nides, Be, Mg, Ca, Sr,

Ba, Ra, Al, Ga, In, Tl,

Ge, Sn, Pb, As, Sb, Bi,

Fe, Ru, Os, Co, Rh, Ir,

Ni, Pd, Pt, Cu, Ag, Au,

Zn, Cd, Hg, Sc, Y, Ti,

Zr, Hf, V, Nb, Ta, Cr,

Mo, W, Mn, Tc, and Re

 - 2E+2 1E-7 3E-10 - -
17 Chlorine-382 D, see 36Cl 2E+4 4E+4 2E-5 6E-8 - -
St wall

(3E+4)

 - - - 3E-4 3E-3
W, see 36Cl - 5E+4 2E-5 6E-8 - -
17 Chlorine-392 D, see 36Cl 2E+4 5E+4 2E-5 7E-8 - -
St wall

(4E+4)

 - - - 5E-4 5E-3
W, see 36Cl - 6E+4 2E-5 8E-8 - -
18 Argon-37 Submersion1 - - 1E+0 6E-3 - -
18 Argon-39 Submersion1 - - 2E-4 8E-7 - -
18 Argon-41 Submersion1 - - 3E-6 1E-8 - -
19 Potassium-40 D, all compounds 3E+2 4E+2 2E-7 6E-10 4E-6 4E-5
19 Potassium-42 D, all compounds 5E+3 5E+3 2E-6 7E-9 6E-5 6E-4
19 Potassium-43 D, all compounds 6E+3 9E+3 4E-6 1E-8 9E-5 9E-4
19 Potassium-442 D, all compounds 2E+4 7E+4 3E-5 9E-8 - -
St wall

(4E+4)

 - - - 5E-4 5E-3
19 Potassium-452 D, all compounds 3E+4 1E+5 5E-5 2E-7 - -
St wall

(5E+4)

 - - - 7E-4 7E-3
20 Calcium-41 W, all compounds 3E+3 4E+3 2E-6 - - -
Bone surf (4E+3) Bone surf (4E+3) - 5E-9 6E-5 6E-4
20 Calcium-45 W, all compounds 2E+3 8E+2 4E-7 1E-9 2E-5 2E-4
20 Calcium-47 W, all compounds 8E+2 9E+2 4E-7 1E-9 1E-5 1E-4
21 Scandium-43 Y, all compounds 7E+3 2E+4 9E-6 3E-8 1E-4 1E-3
21 Scandium-44m Y, all compounds 5E+2 7E+2 3E-7 1E-9 7E-6 7E-5
21 Scandium-44 Y, all compounds 4E+3 1E+4 5E-6 2E-8 5E-5 5E-4
21 Scandium-46 Y, all compounds 9E+2 2E+2 1E-7 3E-10 1E-5 1E-4
21 Scandium-47 Y, all compounds 2E+3 3E+3 1E-6 4E-9 - -
LLI wall (3E+3) - - - 4E-5 4E-4
21 Scandium-48 Y, all compounds 8E+2 1E+3 6E-7 2E-9 1E-5 1E-4
21 Scandium-492 Y, all compounds 2E+4 5E+4 2E-5 8E-8 3E-4 3E-3
22 Titanium-44 D, all compounds except

those given for W and Y

 3E+2 1E+1 5E-9 2E-11 4E-6 4E-5
W, oxides, hydroxides,

carbides, halides, and nitrates

 - 3E+1 1E-8 4E-11 - -
Y, SrTi0 - 6E+0 2E-9 8E-12 - -
22 Titanium-45 D, see 44Ti 9E+3 3E+4 1E-5 3E-8 1E-4 1E-3
W, see 44Ti - 4E+4 1E-5 5E-8 - -
Y, see 44Ti - 3E+4 1E-5 4E-8 - -
23 Vanadium-472 D, all compounds except

those given for W

 3E+4 8E+4 3E-5 1E-7 - -
St wall

(3E+4)

 - - - 4E-4 4E-3
W, oxides, hydroxides,

carbides, and halides

 - 1E+5 4E-5 1E-7 - -
23 Vanadium-48 D, see 47V 6E+2 1E+3 5E-7 2E-9 9E-6 9E-5
W, see 47V - 6E+2 3E-7 9E-10 - -
23 Vanadium-49 D, see 47V 7E+4 3E+4 1E-5 - - -
LLI wall (9E+4) Bone surf (3E+4) - 5E-8 1E-3 1E-2
W, see 47V - 2E+4 8E-6 2E-8 - -
24 Chromium-48 D, all compounds except

those given for W and Y

 6E+3 1E+4 5E-6 2E-8 8E-5 8E-4
W, halides and nitrates - 7E+3 3E-6 1E-8 - -
Y, oxides and hydroxides - 7E+3 3E-6 1E-8 - -
24 Chromium-492 D, see 48Cr 3E+4 8E+4 4E-5 1E-7 4E-4 4E-3
W, see 48Cr - 1E+5 4E-5 1E-7 - -
Y, see 48Cr - 9E+4 4E-5 1E-7 - -
24 Chromium-51 D, see 48Cr 4E+4 5E+4 2E-5 6E-8 5E-4 5E-3
W, see 48Cr - 2E+4 1E-5 3E-8 - -
Y, see 48Cr - 2E+4 8E-6 3E-8 - -
25 Manganese-512 D, all compounds except

those given for W

 2E+4 5E+4 2E-5 7E-8 3E-4 3E-3
W, oxides, hydroxides,

halides, and nitrates

 - 6E+4 3E-5 8E-8 - -
25 Manganese-52m2 D, see 51Mn 3E+4 9E+4 4E-5 1E-7 - -
St wall

(4E+4)

 - - - 5E-4 5E-3
W, see 51Mn - 1E+5 4E-5 1E-7 - -
25 Manganese-52 D, see 51Mn 7E+2 1E+3 5E-7 2E-9 1E-5 1E-4
W, see 51Mn - 9E+2 4E-7 1E-9 - -
25 Manganese-53 D, see 51Mn 5E+4 1E+4 5E-6 - 7E-4 7E-3
- Bone surf (2E+4) - 3E-8 - -
W, see 51Mn - 1E+4 5E-6 2E-8 - -
25 Manganese-54 D, see 51Mn 2E+3 9E+2 4E-7 1E-9 3E-5 3E-4
W, see 51Mn - 8E+2 3E-7 1E-9 - -
25 Manganese-56 D, see 51Mn 5E+3 2E+4 6E-6 2E-8 7E-5 7E-4
W, see 51Mn - 2E+4 9E-6 3E-8 - -
26 Iron-52 D, all compounds except

those given for W

 9E+2 3E+3 1E-6 4E-9 1E-5 1E-4
W, oxides, hydroxides,

and halides

 - 2E+3 1E-6 3E-9 - -
26 Iron-55 D, see 52Fe 9E+3 2E+3 8E-7 3E-9 1E-4 1E-3
W, see 52Fe - 4E+3 2E-6 6E-9 - -
26 Iron-59 D, see 52Fe 8E+2 3E+2 1E-7 5E-10 1E-5 1E-4
W, see 52Fe - 5E+2 2E-7 7E-10 - -
26 Iron-60 D, see 52Fe 3E+1 6E+0 3E-9 9E-12 4E-7 4E-6
W, see 52Fe - 2E+1 8E-9 3E-11 - -
27 Cobalt-55 W, all compounds except

those given for Y

 1E+3 3E+3 1E-6 4E-9 2E-5 2E-4
Y, oxides, hydroxides,

halides, and nitrates

 - 3E+3 1E-6 4E-9 - -
27 Cobalt-56 W, see 55Co 5E+2 3E+2 1E-7 4E-10 6E-6 6E-5
Y, see 55Co 4E+2 2E+2 8E-8 3E-10 - -
27 Cobalt-57 W, see 55Co 8E+3 3E+3 1E-6 4E-9 6E-5 6E-4
Y, see 55Co 4E+3 7E+2 3E-7 9E-10 - -
27 Cobalt-58m W, see 55Co 6E+4 9E+4 4E-5 1E-7 8E-4 8E-3
Y, see 55Co - 6E+4 3E-5 9E-8 - -
27 Cobalt-58 W, see 55Co 2E+3 1E+3 5E-7 2E-9 2E-5 2E-4
Y, see 55Co 1E+3 7E+2 3E-7 1E-9 - -
27 Cobalt-60m2 W, see 55Co 1E+6 4E+6 2E-3 6E-6 - -
St wall

(1E+6)

 - - - 2E-2 2E-1
Y, see 55Co - 3E+6 1E-3 4E-6 - -
27 Cobalt-60 W, see 55Co 5E+2 2E+2 7E-8 2E-10 3E-6 3E-5
Y, see 55Co 2E+2 3E+1 1E-8 5E-11 - -
27 Cobalt-612 W, see 55Co 2E+4 6E+4 3E-5 9E-8 3E-4 3E-3
Y, see 55Co 2E+4 6E+4 2E-5 8E-8 - -
27 Cobalt-62m2 W, see 55Co 4E+4 2E+5 7E-5 2E-7 - -
St wall

(5E+4)

 - - - 7E-4 7E-3
Y, see 55Co - 2E+5 6E-5 2E-7 - -
28 Nickel-56 D, all compounds except

those given for W

 1E+3 2E+3 8E-7 3E-9 2E-5 2E-4
W, oxides, hydroxides,

and carbides

 - 1E+3 5E-7 2E-9 - -
Vapor - 1E+3 5E-7 2E-9 - -
28 Nickel-57 D, see 56Ni 2E+3 5E+3 2E-6 7E-9 2E-5 2E-4
W, see 56Ni - 3E+3 1E-6 4E-9 - -
Vapor - 6E+3 3E-6 9E-9 - -
28 Nickel-59 D, see 56Ni 2E+4 4E+3 2E-6 5E-9 3E-4 3E-3
W, see 56Ni - 7E+3 3E-6 1E-8 - -
Vapor - 2E+3 8E-7 3E-9 - -
28 Nickel-63 D, see 56Ni 9E+3 2E+3 7E-7 2E-9 1E-4 1E-3
W, see 56Ni - 3E+3 1E-6 4E-9 - -
Vapor - 8E+2 3E-7 1E-9 - -
28 Nickel-65 D, see 56Ni 8E+3 2E+4 1E-5 3E-8 1E-4 1E-3
W, see 56Ni - 3E+4 1E-5 4E-8 - -
Vapor - 2E+4 7E-6 2E-8 - -
28 Nickel-66 D, see 56Ni 4E+2 2E+3 7E-7 2E-9 - -
LLI wall (5E+2) - - - 6E-6 6E-5
W, see 56Ni - 6E+2 3E-7 9E-10 - -
Vapor - 3E+3 1E-6 4E-9 - -
29 Copper-602 D, all compounds except

those given for W and Y

 3E+4 9E+4 4E-5 1E-7 - -
St wall

(3E+4)

 - - - 4E-4 4E-3
W, sulfides, halides,

and nitrates

-

1E+5

5E-5

2E-7

-

-
Y, oxides and hydroxides - 1E+5 4E-5 1E-7 - -
29 Copper-61 D, see 60Cu 1E+4 3E+4 1E-5 4E-8 2E-4 2E-3
W, see 60Cu - 4E+4 2E-5 6E-8 - -
Y, see 60Cu - 4E+4 1E-5 5E-8 - -
29 Copper-64 D, see 60Cu 1E+4 3E+4 1E-5 4E-8 2E-4 2E-3
W, see 60Cu - 2E+4 1E-5 3E-8 - -
Y, see 60Cu - 2E+4 9E-6 3E-8 - -
29 Copper-67 D, see 60Cu 5E+3 8E+3 3E-6 1E-8 6E-5 6E-4
W, see 60Cu - 5E+3 2E-6 7E-9 - -
Y, see 60Cu - 5E+3 2E-6 6E-9 - -
30 Zinc-62 Y, all compounds 1E+3 3E+3 1E-6 4E-9 2E-5 2E-4
30 Zinc-632 Y, all compounds 2E+4 7E+4 3E-5 9E-8 - -
St wall

(3E+4)

 - - - 3E-4 3E-3
30 Zinc-65 Y, all compounds 4E+2 3E+2 1E-7 4E-10 5E-6 5E-5
30 Zinc-69m Y, all compounds 4E+3 7E+3 3E-6 1E-8 6E-5 6E-4
30 Zinc-692 Y, all compounds 6E+4 1E+5 6E-5 2E-7 8E-4 8E-3
30 Zinc-71m Y, all compounds 6E+3 2E+4 7E-6 2E-8 8E-5 8E-4
30 Zinc-72 Y, all compounds 1E+3 1E+3 5E-7 2E-9 1E-5 1E-4
31 Gallium-652 D, all compounds except

those given for W

 5E+4 2E+5 7E-5 2E-7 - -
St wall

(6E+4)

 - - - 9E-4 9E-3
W, oxides, hydroxides,

carbides, halides, and nitrates

 - 2E+5 8E-5 3E-7 - -
31 Gallium-66 D, see 65Ga 1E+3 4E+3 1E-6 5E-9 1E-5 1E-4
W, see 65Ga - 3E+3 1E-6 4E-9 - -
31 Gallium-67 D, see 65Ga 7E+3 1E+4 6E-6 2E-8 1E-4 1E-3
W, see 65Ga - 1E+4 4E-6 1E-8 - -
31 Gallium-682 D, see 65Ga 2E+4 4E+4 2E-5 6E-8 2E-4 2E-3
W, see 65Ga - 5E+4 2E-5 7E-8 - -
31 Gallium-702 D, see 65Ga 5E+4 2E+5 7E-5 2E-7 - -
St wall

(7E+4)

 - - - 1E-3 1E-2
W, see 65Ga - 2E+5 8E-5 3E-7 - -
31 Gallium-72 D, see 65Ga 1E+3 4E+3 1E-6 5E-9 2E-5 2E-4
W, see 65Ga - 3E+3 1E-6 4E-9 - -
31 Gallium-73 D, see 65Ga 5E+3 2E+4 6E-6 2E-8 7E-5 7E-4
W, see 65Ga - 2E+4 6E-6 2E-8 - -
32 Germanium-66 D, all compounds except

those given for W

 2E+4 3E+4 1E-5 4E-8 3E-4 3E-3
W, oxides, sulfides, and halides - 2E+4 8E-6 3E-8 - -
32 Germanium-672 D, see 66Ge 3E+4 9E+4 4E-5 1E-7 - -
St wall

(4E+4)

 - - - 6E-4 6E-3
W, see 66Ge - 1E+5 4E-5 1E-7 - -
32 Germanium-68 D, see 66Ge 5E+3 4E+3 2E-6 5E-9 6E-5 6E-4
W, see 66Ge - 1E+2 4E-8 1E-10 - -
32 Germanium-69 D, see 66Ge 1E+4 2E+4 6E-6 2E-8 2E-4 2E-3
W, see 66Ge - 8E+3 3E-6 1E-8 - -
32 Germanium-71 D, see 66Ge 5E+5 4E+5 2E-4 6E-7 7E-3 7E-2
W, see 66Ge - 4E+4 2E-5 6E-8 - -
32 Germanium-752 D, see 66Ge 4E+4 8E+4 3E-5 1E-7 - -
St wall

(7E+4)

 - - - 9E-4 9E-3
W, see 66Ge - 8E+4 4E-5 1E-7 - -
32 Germanium-77 D, see 66Ge 9E+3 1E+4 4E-6 1E-8 1E-4 1E-3
W, see 66Ge - 6E+3 2E-6 8E-9 - -
32 Germanium-782 D, see 66Ge 2E+4 2E+4 9E-6 3E-8 - -
St wall

(2E+4)

 - - - 3E-4 3E-3
W, see 66Ge - 2E+4 9E-6 3E-8 - -
33 Arsenic-692 W, all compounds 3E+4 1E+5 5E-5 2E-7 - -
St wall

(4E+4)

 - - - 6E-4 6E-3
33 Arsenic-702 W, all compounds 1E+4 5E+4 2E-5 7E-8 2E-4 2E-3
33 Arsenic-71 W, all compounds 4E+3 5E+3 2E-6 6E-9 5E-5 5E-4
33 Arsenic-72 W, all compounds 9E+2 1E+3 6E-7 2E-9 1E-5 1E-4
33 Arsenic-73 W, all compounds 8E+3 2E+3 7E-7 2E-9 1E-4 1E-3
33 Arsenic-74 W, all compounds 1E+3 8E+2 3E-7 1E-9 2E-5 2E-4
33 Arsenic-76 W, all compounds 1E+3 1E+3 6E-7 2E-9 1E-5 1E-4
33 Arsenic-77 W, all compounds 4E+3 5E+3 2E-6 7E-9 - -
LLI wall (5E+3) - - - 6E-5 6E-4
33 Arsenic-782 W, all compounds 8E+3 2E+4 9E-6 3E-8 1E-4 1E-3
34 Selenium-702 D, all compounds except

those given for W

 2E+4 4E+4 2E-5 5E-8 1E-4 1E-3
W, oxides, hydroxides,

carbides, and elemental Se

 1E+4 4E+4 2E-5 6E-8 - -
34 Selenium-73m2 D, see 70Se 6E+4 2E+5 6E-5 2E-7 4E-4 4E-3
W, see 70Se 3E+4 1E+5 6E-5 2E-7 - -
34 Selenium-73 D, see 70Se 3E+3 1E+4 5E-6 2E-8 4E-5 4E-4
W, see 70Se - 2E+4 7E-6 2E-8 - -
34 Selenium-75 D, see 70Se 5E+2 7E+2 3E-7 1E-9 7E-6 7E-5
W, see 70Se - 6E+2 3E-7 8E-10 - -
34 Selenium-79 D, see 70Se 6E+2 8E+2 3E-7 1E-9 8E-6 8E-5
W, see 70Se - 6E+2 2E-7 8E-10 - -
34 Selenium-81m2 D, see 70Se 4E+4 7E+4 3E-5 9E-8 3E-4 3E-3
W, see 70Se 2E+4 7E+4 3E-5 1E-7 - -
34 Selenium-812 D, see 70Se 6E+4 2E+5 9E-5 3E-7 - -
St wall

(8E+4)

 - - - 1E-3 1E-2
W, see 70Se - 2E+5 1E-4 3E-7 - -
34 Selenium-832 D, see 70Se 4E+4 1E+5 5E-5 2E-7 4E-4 4E-3
W, see 70Se 3E+4 1E+5 5E-5 2E-7 - -
35 Bromine-74m2 D, bromides of H, Li,

Na, K, Rb, Cs, and Fr

 1E+4 4E+4 2E-5 5E-8 - -
St wall

(2E+4)

 - - - 3E-4 3E-3
W, bromides of lantha-

nides, Be, Mg, Ca, Sr,

Ba, Ra, Al, Ga, In, Tl,

Ge, Sn, Pb, As, Sb, Bi,

Fe, Ru, Os, Co, Rh, Ir,

Ni, Pd, Pt, Cu, Ag, Au,

Zn, Cd, Hg, Sc, Y, Ti,

Zr, Hf, V, Nb, Ta, Mn,

Tc, and Re

 - 4E+4 2E-5 6E-8 - -
35 Bromine-742 D, see 74mBr 2E+4 7E+4 3E-5 1E-7 - -
St wall

(4E+4)

 - - - 5E-45E-3 -
W, see 74mBr - 8E+4 4E-5 1E-7 - -
35 Bromine-752 D, see 74mBr 3E+4 5E+4 2E-5 7E-8 - -
St wall

(4E+4)

 - - - 5E-4 5E-3
W, see 74mBr - 5E+4 2E-5 7E-8 - -
35 Bromine-76 D, see 74mBr 4E+3 5E+3 2E-6 7E-9 5E-5 5E-4
W, see 74mBr - 4E+3 2E-6 6E-9 - -
35 Bromine-77 D, see 74mBr 2E+4 2E+4 1E-5 3E-8 2E-4 2E-3
W, see 74mBr - 2E+4 8E-6 3E-8 - -
35 Bromine-80m D, see 74mBr 2E+4 2E+4 7E-6 2E-8 3E-4 3E-3
W, see 74mBr - 1E+4 6E-6 2E-8 - -
35 Bromine-802 D, see 74mBr 5E+4 2E+5 8E-5 3E-7 - -
St wall

(9E+4)

 - - - 1E-3 1E-2
W, see 74mBr - 2E+5 9E-5 3E-7 - -
35 Bromine-82 D, see 74mBr 3E+3 4E+3 2E-6 6E-9 4E-5 4E-4
W, see 74mBr - 4E+3 2E-6 5E-9 - -
35 Bromine-83 D, see 74mBr 5E+4 6E+4 3E-5 9E-8 - -
St wall

(7E+4)

 - - - 9E-4 9E-3
W, see 74mBr - 6E+4 3E-5 9E-8 - -
35 Bromine-842 D, see 74mBr 2E+4 6E+4 2E-5 8E-8 - -
St wall

(3E+4)

 - - - 4E-4 4E-3
W, see 74mBr - 6E+4 3E-5 9E-8 - -
36 Krypton-742 Submersion1 - - 3E-6 1E-8 - -
36 Krypton-76 Submersion1 - - 9E-6 4E-8 - -
36 Krypton-772 Submersion1 - - 4E-6 2E-8 - -
36 Krypton-79 Submersion1 - - 2E-5 7E-8 - -
36 Krypton-81 Submersion1 - - 7E-4 3E-6 - -
36 Krypton-83m2 Submersion1 - - 1E-2 5E-5 - -
36 Krypton-85m Submersion1 - - 2E-5 1E-7 - -
36 Krypton-85 Submersion1 - - 1E-4 7E-7 - -
36 Krypton-872 Submersion1 - - 5E-6 2E-8 - -
36 Krypton-88 Submersion1 - - 2E-6 9E-9 - -
37 Rubidium-792 D, all compounds 4E+4 1E+5 5E-5 2E-7 - -
St wall

(6E+4)

 - - - 8E-4 8E-3
37 Rubidium-81m2 D, all compounds 2E+5 3E+5 1E-4 5E-7 - -
St wall

(3E+5)

 - - - 4E-3 4E-2
37 Rubidium-81 D, all compounds 4E+4 5E+4 2E-5 7E-8 5E-4 5E-3
37 Rubidium-82m D, all compounds 1E+4 2E+4 7E-6 2E-8 2E-4 2E-3
37 Rubidium-83 D, all compounds 6E+2 1E+3 4E-7 1E-9 9E-6 9E-5
37 Rubidium-84 D, all compounds 5E+2 8E+2 3E-7 1E-9 7E-6 7E-5
37 Rubidium-86 D, all compounds 5E+2 8E+2 3E-7 1E-9 7E-6 7E-5
37 Rubidium-87 D, all compounds 1E+3 2E+3 6E-7 2E-9 1E-5 1E-4
37 Rubidium-882 D, all compounds 2E+4 6E+4 3E-5 9E-8 - -
St wall

(3E+4)

 - - - 4E-4 4E-3
37 Rubidium-892 D, all compounds 4E+4 1E+5 6E-5 2E-7 - -
St wall

(6E+4)

 - - - 9E-4 9E-3
38 Strontium-802 D, all soluble compounds

except SrTiO

 4E+3 1E+4 5E-6 2E-8 6E-5 6E-4
Y, all insoluble com-

pounds and SrTi0

 - 1E+4 5E-6 2E-8 - -
38 Strontium-812 D, see 80Sr 3E+4 8E+4 3E-5 1E-7 3E-4 3E-3
Y, see 80Sr 2E+4 8E+4 3E-5 1E-7 - -
38 Strontium-82 D, see 80Sr 3E+2 4E+2 2E-7 6E-10 - -
LLI wall (2E+2) - - - 3E-6 3E-5
Y, see 80Sr 2E+2 9E+1 4E-8 1E-10 - -
38 Strontium-83 D, see 80Sr 3E+3 7E+3 3E-6 1E-8 3E-5 3E-4
Y, see 80Sr 2E+3 4E+3 1E-6 5E-9 - -
38 Strontium-85m2 D, see 80Sr 2E+5 6E+5 3E-4 9E-7 3E-3 3E-2
Y, see 80Sr - 8E+5 4E-4 1E-6 - -
38 Strontium-85 D, see 80Sr 3E+3 3E+3 1E-6 4E-9 4E-5 4E-4
Y, see 80Sr - 2E+3 6E-7 2E-9 - -
38 Strontium-87m D, see 80Sr 5E+4 1E+5 5E-5 2E-7 6E-4 6E-3
Y, see 80Sr 4E+4 2E+5 6E-5 2E-7 - -
38 Strontium-89 D, see 80Sr 6E+2 8E+2 4E-7 1E-9 - -
LLI wall (6E+2) - - - 8E-6 8E-5
Y, see 80Sr 5E+2 1E+2 6E-8 2E-10 - -
38 Strontium-90 D, see 80Sr 3E+1 2E+1 8E-9 - - -
Bone surf (4E+1) Bone surf (2E+1) - 3E-11 5E-7 5E-6
Y, see 80Sr - 4E+0 2E-9 6E-12 - -
38 Strontium-91 D, see 80Sr 2E+3 6E+3 2E-6 8E-9 2E-5 2E-4
Y, see 80Sr - 4E+3 1E-6 5E-9 - -
38 Strontium-92 D, see 80Sr 3E+3 9E+3 4E-6 1E-8 4E-5 4E-4
Y, see 80Sr - 7E+3 3E-6 9E-9 - -
39 Yttrium-86m2 W, all compounds except

those given for Y

 2E+4 6E+4 2E-5 8E-8 3E-4 3E-3
Y, oxides and hydroxides - 5E+4 2E-5 8E-8 - -
39 Yttrium-86 W, see 86mY 1E+3 3E+3 1E-6 5E-9 2E-5 2E-4
Y, see 86mY - 3E+3 1E-6 5E-9 - -
39 Yttrium-87 W, see 86mY 2E+3 3E+3 1E-6 5E-9 3E-5 3E-4
Y, see 86mY - 3E+3 1E-6 5E-9 - -
39 Yttrium-88 W, see 86mY 1E+3 3E+2 1E-7 3E-10 1E-5 1E-4
Y, see 86mY - 2E+2 1E-7 3E-10 - -
39 Yttrium-90m W, see 86mY 8E+3 1E+4 5E-6 2E-8 1E-4 1E-3
Y, see 86mY - 1E+4 5E-6 2E-8 - -
39 Yttrium-90 W, see 86mY 4E+2 7E+2 3E-7 9E-10 - -
LLI wall (5E+2) - - - 7E-6 7E-5
Y, see 86mY - 6E+2 3E-7 9E-10 - -
39 Yttrium-91m2 W, see 86mY 1E+5 2E+5 1E-4 3E-7 2E-3 2E-2
Y, see 86mY - 2E+5 7E-5 2E-7 - -
39 Yttrium-91 W, see 86mY 5E+2 2E+2 7E-8 2E-10 - -
LLI wall (6E+2) - - - 8E-6 8E-5
Y, see 86mY - 1E+2 5E-8 2E-10 - -
39 Yttrium-92 W, see 86mY 3E+3 9E+3 4E-6 1E-8 4E-5 4E-4
Y, see 86mY - 8E+3 3E-6 1E-8 - -
39 Yttrium-93 W, see 86mY 1E+3 3E+3 1E-6 4E-9 2E-5 2E-4
Y, see 86mY - 2E+3 1E-6 3E-9 - -
39 Yttrium-942 W, see 86mY 2E+4 8E+4 3E-5 1E-7 - -
St wall

(3E+4)

 - - - 4E-4 4E-3
Y, see 86mY - 8E+4 3E-5 1E-7 - -
39 Yttrium-952 W, see 86mY 4E+4 2E+5 6E-5 2E-7 - -
St wall

(5E+4)

 - - - 7E-4 7E-3
Y, see 86mY - 1E+5 6E-5 2E-7 - -
40 Zirconium-86 D, all compounds except

those given for W and Y

 1E+3 4E+3 2E-6 6E-9 2E-5 2E-4
W, oxides, hydroxides,

halides, and nitrates

 - 3E+3 1E-6 4E-9 - -
Y, carbide - 2E+3 1E-6 3E-9 - -
40 Zirconium-88 D, see 86Zr 4E+3 2E+2 9E-8 3E-10 5E-5 5E-4
W, see 86Zr - 5E+2 2E-7 7E-10 - -
Y, see 86Zr - 3E+2 1E-7 4E-10 - -
40 Zirconium-89 D, see 86Zr 2E+3 4E+3 1E-6 5E-9 2E-5 2E-4
W, see 86Zr - 2E+3 1E-6 3E-9 - -
Y, see 86Zr - 2E+3 1E-6 3E-9 - -
40 Zirconium-93 D, see 86Zr 1E+3 6E+0 3E-9 - - -
Bone surf (3E+3) Bone surf (2E+1) - 2E-11 4E-5 4E-4
W, see 86Zr - 2E+1 1E-8 - - -
- Bone surf (6E+1) - 9E-11 - -
Y, see 86Zr - 6E+1 2E-8 - - -
- Bone surf (7E+1) - 9E-11 - -
40 Zirconium-95 D, see 86Zr 1E+3 1E+2 5E-8 - 2E-5 2E-4
- Bone surf (3E+2) - 4E-10 - -
W, see 86Zr - 4E+2 2E-7 5E-10 - -
Y, see 86Zr - 3E+2 1E-7 4E-10 - -
40 Zirconium-97 D, see 86Zr 6E+2 2E+3 8E-7 3E-9 9E-6 9E-5
W, see 86Zr - 1E+3 6E-7 2E-9 - -
Y, see 86Zr - 1E+3 5E-7 2E-9 - -
41 Niobium-882 W, all compounds except

those given for Y

 5E+4 2E+5 9E-5 3E-7 - -
St wall

(7E+4)

 - - - 1E-3 1E-2
Y, oxides and hydroxides - 2E+5 9E-5 3E-7 - -
41 Niobium-892

(66 min)

 W, see 88Nb 1E+4 4E+4 2E-5 6E-8 1E-4 1E-3
Y, see 88Nb - 4E+4 2E-5 5E-8 - -
41 Niobium-89

(122 min)

 W, see 88Nb 5E+3 2E+4 8E-6 3E-8 7E-5 7E-4
Y, see 88Nb - 2E+4 6E-6 2E-8 - -
41 Niobium-90 W, see 88Nb 1E+3 3E+3 1E-6 4E-9 1E-5 1E-4
Y, see 88Nb - 2E+3 1E-6 3E-9 - -
41 Niobium-93m W, see 88Nb 9E+3 2E+3 8E-7 3E-9 - -
LLI wall (1E+4) - - - 2E-4 2E-3
Y, see 88Nb - 2E+2 7E-8 2E-10 - -
41 Niobium-94 W, see 88Nb 9E+2 2E+2 8E-8 3E-10 1E-5 1E-4
Y, see 88Nb - 2E+1 6E-9 2E-11 - -
41 Niobium-95m W, see 88Nb 2E+3 3E+3 1E-6 4E-9 - -
LLI wall (2E+3) - - - 3E-5 3E-4
Y, see 88Nb - 2E+3 9E-7 3E-9 - -
41 Niobium-95 W, see 88Nb 2E+3 1E+3 5E-7 2E-9 3E-5 3E-4
Y, see 88Nb - 1E+3 5E-7 2E-9 - -
41 Niobium-96 W, see 88Nb 1E+3 3E+3 1E-6 4E-9 2E-5 2E-4
Y, see 88Nb - 2E+3 1E-6 3E-9 - -
41 Niobium-972 W, see 88Nb 2E+4 8E+4 3E-5 1E-7 3E-4 3E-3
Y, see 88Nb - 7E+4 3E-5 1E-7 - -
41 Niobium-982 W, see 88Nb 1E+4 5E+4 2E-5 8E-8 2E-4 2E-3
Y, see 88Nb - 5E+4 2E-5 7E-8 - -
42 Molybdenum-90 D, all compounds except

those given for Y

 4E+3 7E+3 3E-6 1E-8 3E-5 3E-4
Y, oxides, hydroxides,

and MoS

2E+3

5E+3

2E-6

6E-9

-

-
42 Molybdenum-93m D, see 90Mo 9E+3 2E+4 7E-6 2E-8 6E-5 6E-4
Y, see 90Mo 4E+3 1E+4 6E-6 2E-8 - -
42 Molybdenum-93 D, see 90Mo 4E+3 5E+3 2E-6 8E-9 5E-5 5E-4
Y, see 90Mo 2E+4 2E+2 8E-8 2E-10 - -
42 Molybdenum-99 D, see 90Mo 2E+3 3E+3 1E-6 4E-9 - -
LLI wall (1E+3) - - - 2E-5 2E-4
Y, see 90Mo 1E+3 1E+3 6E-7 2E-9 - -
42 Molybdenum-1012 D, see 90Mo 4E+4 1E+5 6E-5 2E-7 - -
St wall

(5E+4)

 - - - 7E-4 7E-3
Y, see 90Mo - 1E+5 6E-5 2E-7 - -
43 Technetium-93m2 D, all compounds except

those given for W

 7E+4 2E+5 6E-5 2E-7 1E-3 1E-2
W, oxides, hydroxides,

halides, and nitrates

 - 3E+5 1E-4 4E-7 - -
43 Technetium-93 D, see 93mTc 3E+4 7E+4 3E-5 1E-7 4E-4 4E-3
W, see 93mTc - 1E+5 4E-5 1E-7 - -
43 Technetium-94m2 D, see 93mTc 2E+4 4E+4 2E-5 6E-8 3E-4 3E-3
W, see 93mTc - 6E+4 2E-5 8E-8 - -
43 Technetium-94 D, see 93mTc 9E+3 2E+4 8E-6 3E-8 1E-4 1E-3
W, see 93mTc - 2E+4 1E-5 3E-8 - -
43 Technetium-95m D, see 93mTc 4E+3 5E+3 2E-6 8E-9 5E-5 5E-4
W, see 93mTc - 2E+3 8E-7 3E-9 - -
43 Technetium-95 D, see 93mTc 1E+4 2E+4 9E-6 3E-8 1E-4 1E-3
W, see 93mTc - 2E+4 8E-6 3E-8 - -
43 Technetium-96m2 D, see 93mTc 2E+5 3E+5 1E-4 4E-7 2E-3 2E-2
W, see 93mTc - 2E+5 1E-4 3E-7 - -
43 Technetium-96 D, see 93mTc 2E+3 3E+3 1E-6 5E-9 3E-5 3E-4
W, see 93mTc - 2E+3 9E-7 3E-9 - -
43 Technetium-97m D, see 93mTc 5E+3 7E+3 3E-6 - 6E-5 6E-4
- St wall

(7E+3)

 - 1E-8 - -
W, see 93mTc - 1E+3 5E-7 2E-9 - -
43 Technetium-97 D, see 93mTc 4E+4 5E+4 2E-5 7E-8 5E-4 5E-3
W, see 93mTc - 6E+3 2E-6 8E-9 - -
43 Technetium-98 D, see 93mTc 1E+3 2E+3 7E-7 2E-9 1E-5 1E-4
W, see 93mTc - 3E+2 1E-7 4E-10 - -
43 Technetium-99m D, see 93mTc 8E+4 2E+5 6E-5 2E-7 1E-3 1E-2
W, see 93mTc - 2E+5 1E-4 3E-7 - -
43 Technetium-99 D, see 93mTc 4E+3 5E+3 2E-6 - 6E-5 6E-4
- St wall

(6E+3)

 - 8E-9 - -
W, see 93mTc - 7E+2 3E-7 9E-10 - -
43 Technetium-1012 D, see 93mTc 9E+4 3E+5 1E-4 5E-7 - -
St wall

(1E+5)

 - - - 2E-3 2E-2
W, see 93mTc - 4E+5 2E-4 5E-7 - -
43 Technetium-1042 D, see 93mTc 2E+4 7E+4 3E-5 1E-7 - -
St wall

(3E+4)

 - - - 4E-4 4E-3
W, see 93mTc - 9E+4 4E-5 1E-7 - -
44 Ruthenium-942 D, all compounds except

those given for W and Y

 2E+4 4E+4 2E-5 6E-8 2E-4 2E-3
W, halides - 6E+4 3E-5 9E-8 - -
Y, oxides and hydroxides - 6E+4 2E-5 8E-8 - -
44 Ruthenium-97 D, see 94Ru 8E+3 2E+4 8E-6 3E-8 1E-4 1E-3
W, see 94Ru - 1E+4 5E-6 2E-8 - -
Y, see 94Ru - 1E+4 5E-6 2E-8 - -
44 Ruthenium-103 D, see 94Ru 2E+3 2E+3 7E-7 2E-9 3E-5 3E-4
W, see 94Ru - 1E+3 4E-7 1E-9 - -
Y, see 94Ru - 6E+2 3E-7 9E-10 - -
44 Ruthenium-105 D, see 94Ru 5E+3 1E+4 6E-6 2E-8 7E-5 7E-4
W, see 94Ru - 1E+4 6E-6 2E-8 - -
Y, see 94Ru - 1E+4 5E-6 2E-8 - -
44 Ruthenium-106 D, see 94Ru 2E+2 9E+1 4E-8 1E-10 - -
LLI wall (2E+2) - - - 3E-6 3E-5
W, see 94Ru - 5E+1 2E-8 8E-11 - -
Y, see 94Ru - 1E+1 5E-9 2E-11 - -
45 Rhodium-99m D, all compounds except

those given for W and Y

2E+4

6E+4

2E-5

8E-8

2E-4

2E-3
W, halides - 8E+4 3E-5 1E-7 - -
Y, oxides and hydroxides - 7E+4 3E-5 9E-8 - -
45 Rhodium-99 D, see 99mRh 2E+3 3E+3 1E-6 4E-9 3E-5 3E-4
W, see 99mRh - 2E+3 9E-7 3E-9 - -
Y, see 99mRh - 2E+3 8E-7 3E-9 - -
45 Rhodium-100 D, see 99mRh 2E+3 5E+3 2E-6 7E-9 2E-5 2E-4
W, see 99mRh - 4E+3 2E-6 6E-9 - -
Y, see 99mRh - 4E+3 2E-6 5E-9 - -
45 Rhodium-101m D, see 99mRh 6E+3 1E+4 5E-6 2E-8 8E-5 8E-4
W, see 99mRh - 8E+3 4E-6 1E-8 - -
Y, see 99mRh - 8E+3 3E-6 1E-8 - -
45 Rhodium-101 D, see 99mRh 2E+3 5E+2 2E-7 7E-10 3E-5 3E-4
W, see 99mRh - 8E+2 3E-7 1E-9 - -
Y, see 99mRh - 2E+2 6E-8 2E-10 - -
45 Rhodium-102m D, see 99mRh 1E+3 5E+2 2E-7 7E-10 - -
LLI wall (1E+3) - - - 2E-5 2E-4
W, see 99mRh - 4E+2 2E-7 5E-10 - -
Y, see 99mRh - 1E+2 5E-8 2E-10 - -
45 Rhodium-102 D, see 99mRh 6E+2 9E+1 4E-8 1E-10 8E-6 8E-5
W, see 99mRh - 2E+2 7E-8 2E-10 - -
Y, see 99mRh - 6E+1 2E-8 8E-11 - -
45 Rhodium-103m2 D, see 99mRh 4E+5 1E+6 5E-4 2E-6 6E-3 6E-2
W, see 99mRh - 1E+6 5E-4 2E-6 - -
Y, see 99mRh - 1E+6 5E-4 2E-6 - -
45 Rhodium-105 D, see 99mRh 4E+3 1E+4 5E-6 2E-8 - -
LLI wall (4E+3) - - - 5E-5 5E-4
W, see 99mRh - 6E+3 3E-6 9E-9 - -
Y, see 99mRh - 6E+3 2E-6 8E-9 - -
45 Rhodium-106m D, see 99mRh 8E+3 3E+4 1E-5 4E-8 1E-4 1E-3
W, see 99mRh - 4E+4 2E-5 5E-8 - -
Y, see 99mRh - 4E+4 1E-5 5E-8 - -
45 Rhodium-1072 D, see 99mRh 7E+4 2E+5 1E-4 3E-7 - -
St wall

(9E+4)

 - - - 1E-3 1E-2
W, see 99mRh - 3E+5 1E-4 4E-7 - -
Y, see 99mRh - 3E+5 1E-4 3E-7 - -
46 Palladium-100 D, all compounds except

those given for W and Y

 1E+3 1E+3 6E-7 2E-9 2E-5 2E-4
W, nitrates - 1E+3 5E-7 2E-9 - -
Y, oxides and hydroxides - 1E+3 6E-7 2E-9 - -
46 Palladium-101 D, see 100Pd 1E+4 3E+4 1E-5 5E-8 2E-4 2E-3
W, see 100Pd - 3E+4 1E-5 5E-8 - -
Y, see 100Pd - 3E+4 1E-5 4E-8 - -
46 Palladium-103 D, see 100Pd 6E+3 6E+3 3E-6 9E-9 - -
LLI wall (7E+3) - - - 1E-4 1E-3
W, see 100Pd - 4E+3 2E-6 6E-9 - -
Y, see 100Pd - 4E+3 1E-6 5E-9 - -
46 Palladium-107 D, see 100Pd 3E+4 2E+4 9E-6 - - -
LLI wall (4E+4) Kidneys (2E+4) - 3E-8 5E-4 5E-3
W, see 100Pd - 7E+3 3E-6 1E-8 - -
Y, see 100Pd - 4E+2 2E-7 6E-10 - -
46 Palladium-109 D, see 100Pd 2E+3 6E+3 3E-6 9E-9 3E-5 3E-4
W, see 100Pd - 5E+3 2E-6 8E-9 - -
Y, see 100Pd - 5E+3 2E-6 6E-9 - -
47 Silver-1022 D, all compounds except

those given for W and Y

 5E+4 2E+5 8E-5 2E-7 - -
St wall

(6E+4)

 - - - 9E-4 9E-3
W, nitrates and sulfides - 2E+5 9E-5 3E-7 - -
Y, oxides and hydroxides - 2E+5 8E-5 3E-7 - -
47 Silver-1032 D, see 102Ag 4E+4 1E+5 4E-5 1E-7 5E-4 5E-3
W, see 102Ag - 1E+5 5E-5 2E-7 - -
Y, see 102Ag - 1E+5 5E-5 2E-7 - -
47 Silver-104m2 D, see 102Ag 3E+4 9E+4 4E-5 1E-7 4E-4 4E-3
W, see 102Ag - 1E+5 5E-5 2E-7 - -
Y, see 102Ag - 1E+5 5E-5 2E-7 - -
47 Silver-1042 D, see 102Ag 2E+4 7E+4 3E-5 1E-7 3E-4 3E-3
W, see 102Ag - 1E+5 6E-5 2E-7 - -
Y, see 102Ag - 1E+5 6E-5 2E-7 - -
47 Silver-105 D, see 102Ag 3E+3 1E+3 4E-7 1E-9 4E-5 4E-4
W, see 102Ag - 2E+3 7E-7 2E-9 - -
Y, see 102Ag - 2E+3 7E-7 2E-9 - -
47 Silver-106m D, see 102Ag 8E+2 7E+2 3E-7 1E-9 1E-5 1E-4
W, see 102Ag - 9E+2 4E-7 1E-9 - -
Y, see 102Ag - 9E+2 4E-7 1E-9 - -
47 Silver-1062 D, see 102Ag 6E+4 2E+5 8E-5 3E-7 - -
St. wall

(6E+4)

 - - - 9E-4 9E-3
W, see 102Ag - 2E+5 9E-5 3E-7 - -
Y, see 102Ag - 2E+5 8E-5 3E-7 - -
47 Silver-108m D, see 102Ag 6E+2 2E+2 8E-8 3E-10 9E-6 9E-5
W, see 102Ag - 3E+2 1E-7 4E-10 - -
Y, see 102Ag - 2E+1 1E-8 3E-11 - -
47 Silver-110m D, see 102Ag 5E+2 1E+2 5E-8 2E-10 6E-6 6E-5
W, see 102Ag - 2E+2 8E-8 3E-10 - -
Y, see 102Ag - 9E+1 4E-8 1E-10 - -
47 Silver-111 D, see 102Ag 9E+2 2E+3 6E-7 - - -
LLI wall (1E+3) Liver

(2E+3)

 - 2E-9 2E-5 2E-4
W, see 102Ag - 9E+2 4E-7 1E-9 - -
Y, see 102Ag - 9E+2 4E-7 1E-9 - -
47 Silver-112 D, see 102Ag 3E+3 8E+3 3E-6 1E-8 4E-5 4E-4
W, see 102Ag - 1E+4 4E-6 1E-8 - -
Y, see 102Ag - 9E+3 4E-6 1E-8 - -
47 Silver-1152 D, see 102Ag 3E+4 9E+4 4E-5 1E-7 - -
St wall

(3E+4)

 - - - 4E-4 4E-3
W, see 102Ag - 9E+4 4E-5 1E-7 - -
Y, see 102Ag - 8E+4 3E-5 1E-7 - -
48 Cadmium-1042 D, all compounds except

those given for W and Y

 2E+4 7E+4 3E-5 9E-8 3E-4 3E-3
W, sulfides, halides,

and nitrates

-

1E+5

5E-5

2E-7

-

-
Y, oxides and hydroxides - 1E+5 5E-5 2E-7 - -
48 Cadmium-107 D, see 104Cd 2E+4 5E+4 2E-5 8E-8 3E-4 3E-3
W, see 104Cd - 6E+4 2E-5 8E-8 - -
Y, see 104Cd - 5E+4 2E-5 7E-8 - -
48 Cadmium-109 D, see 104Cd 3E+2 4E+1 1E-8 - - -
Kidneys (4E+2) Kidneys (5E+1) - 7E-11 6E-6 6E-5
W, see 104Cd - 1E+2 5E-8 - - -
- Kidneys (1E+2) - 2E-10 - -
Y, see 104Cd - 1E+2 5E-8 2E-10 - -
48 Cadmium-113m D, see 104Cd 2E+1 2E+0 1E-9 - - -
Kidneys (4E+1) Kidneys (4E+0) - 5E-12 5E-7 5E-6
W, see 104Cd - 8E+0 4E-9 - - -
- Kidneys (1E+1) - 2E-11 - -
Y, see 104Cd - 1E+1 5E-9 2E-11 - -
48 Cadmium-113 D, see 104Cd 2E+1 2E+0 9E-10 - - -
Kidneys (3E+1) Kidneys (3E+0) - 5E-12 4E-7 4E-6
W, see 104Cd - 8E+0 3E-9 - - -
- Kidneys (1E+1) - 2E-11 - -
Y, see 104Cd - 1E+1 6E-9 2E-11 - -
48 Cadmium-115m D, see 104Cd 3E+2 5E+1 2E-8 - 4E-6 4E-5

-

 Kidneys (8E+1)

-

1E-10

-

-
W, see 104Cd - 1E+2 5E-8 2E-10 - -
Y, see 104Cd - 1E+2 6E-8 2E-10 - -
48 Cadmium-115 D, see 104Cd 9E+2 1E+3 6E-7 2E-9 - -
LLI wall (1E+3) - - - 1E-5 1E-4
W, see 104Cd - 1E+3 5E-7 2E-9 - -
Y, see 104Cd - 1E+3 6E-7 2E-9 - -
48 Cadmium-117m D, see 104Cd 5E+3 1E+4 5E-6 2E-8 6E-5 6E-4
W, see 104Cd - 2E+4 7E-6 2E-8 - -
Y, see 104Cd - 1E+4 6E-6 2E-8 - -
48 Cadmium-117 D, see 104Cd 5E+3 1E+4 5E-6 2E-8 6E-5 6E-4
W, see 104Cd - 2E+4 7E-6 2E-8 - -
Y, see 104Cd - 1E+4 6E-6 2E-8 - -
49 Indium-109 D, all compounds except

those given for W

 2E+4 4E+4 2E-5 6E-8 3E-4 3E-3
W, oxides, hydroxides,

halides, and nitrates

 - 6E+4 3E-5 9E-8 - -
49 Indium-1102 D, see 109In 2E+4 4E+4 2E-5 6E-8 2E-4 2E-3
(69.1 min) W, see 109In - 6E+4 2E-5 8E-8 - -
49 Indium-110 D, see 109In 5E+3 2E+4 7E-6 2E-8 7E-5 7E-4
(4.9 h) W, see 109In - 2E+4 8E-6 3E-8 - -
49 Indium-111 D, see 109In 4E+3 6E+3 3E-6 9E-9 6E-5 6E-4
W, see 109In - 6E+3 3E-6 9E-9 - -
49 Indium-1122 D, see 109In 2E+5 6E+5 3E-4 9E-7 2E-3 2E-2
W, see 109In - 7E+5 3E-4 1E-6 - -
49 Indium-113m2 D, see 109In 5E+4 1E+5 6E-5 2E-7 7E-4 7E-3
W, see 109In - 2E+5 8E-5 3E-7 - -
49 Indium-114m D, see 109In 3E+2 6E+1 3E-8 9E-11 - -
LLI wall (4E+2) - - - 5E-6 5E-5
W, see 109In - 1E+2 4E-8 1E-10 - -
49 Indium-115m D, see 109In 1E+4 4E+4 2E-5 6E-8 2E-4 2E-3
W, see 109In - 5E+4 2E-5 7E-8 - -
49 Indium-115 D, see 109In 4E+1 1E+0 6E-10 2E-12 5E-7 5E-6
W, see 109In - 5E+0 2E-9 8E-12 - -
49 Indium-116m2 D, see 109In 2E+4 8E+4 3E-5 1E-7 3E-4 3E-3
W, see 109In - 1E+5 5E-5 2E-7 - -
49 Indium-117m2 D, see 109In 1E+4 3E+4 1E-5 5E-8 2E-4 2E-3
W, see 109In - 4E+4 2E-5 6E-8 - -
49 Indium-1172 D, see 109In 6E+4 2E+5 7E-5 2E-7 8E-4 8E-3
W, see 109In - 2E+5 9E-5 3E-7 - -
49 Indium-119m2 D, see 109In 4E+4 1E+5 5E-5 2E-7 - -
St wall

(5E+4)

 - - - 7E-4 7E-3
W, see 109In - 1E+5 6E-5 2E-7 - -
50 Tin-110 D, all compounds except

those given for W

 4E+3 1E+4 5E-6 2E-8 5E-5 5E-4
W, sulfides, oxides,

hydroxides, halides,

nitrates, and stannic

phosphate

 - 1E+4 5E-6 2E-8 - -
50 Tin-1112 D, see 110Sn 7E+4 2E+5 9E-5 3E-7 1E-3 1E-2
W, see 110Sn - 3E+5 1E-4 4E-7 - -
50 Tin-113 D, see 110Sn 2E+3 1E+3 5E-7 2E-9 - -
LLI wall (2E+3) - - - 3E-5 3E-4
W, see 110Sn - 5E+2 2E-7 8E-10 - -
50 Tin-117m D, see 110Sn 2E+3 1E+3 5E-7 - - -
LLI wall (2E+3) Bone surf (2E+3) - 3E-9 3E-5 3E-4
W, see 110Sn - 1E+3 6E-7 2E-9 - -
50 Tin-119m D, see 110Sn 3E+3 2E+3 1E-6 3E-9 - -
LLI wall (4E+3) - - - 6E-5 6E-4
W, see 110Sn - 1E+3 4E-7 1E-9 - -
50 Tin-121m D, see 110Sn 3E+3 9E+2 4E-7 1E-9 - -
LLI wall (4E+3) - - - 5E-5 5E-4
W, see 110Sn - 5E+2 2E-7 8E-10 - -
50 Tin-121 D, see 110Sn 6E+3 2E+4 6E-6 2E-8 - -
LLI wall (6E+3) - - - 8E-5 8E-4
W, see 110Sn - 1E+4 5E-6 2E-8 - -
50 Tin-123m2 D, see 110Sn 5E+4 1E+5 5E-5 2E-7 7E-4 7E-3
W, see 110Sn - 1E+5 6E-5 2E-7 - -
50 Tin-123 D, see 110Sn 5E+2 6E+2 3E-7 9E-10 - -
LLI wall (6E+2) - - - 9E-6 9E-5
W, see 110Sn - 2E+2 7E-8 2E-10 - -
50 Tin-125 D, see 110Sn 4E+2 9E+2 4E-7 1E-9 - -
LLI wall (5E+2) - - - 6E-6 6E-5
W, see 110Sn - 4E+2 1E-7 5E-10 - -
50 Tin-126 D, see 110Sn 3E+2 6E+1 2E-8 8E-11 4E-6 4E-5
W, see 110Sn - 7E+1 3E-8 9E-11 - -
50 Tin-127 D, see 110Sn 7E+3 2E+4 8E-6 3E-8 9E-5 9E-4
W, see 110Sn - 2E+4 8E-6 3E-8 - -
50 Tin-1282 D, see 110Sn 9E+3 3E+4 1E-5 4E-8 1E-4 1E-3
W, see 110Sn - 4E+4 1E-5 5E-8 - -
51 Antimony-1152 D, all compounds except

those given for W

8E+4

2E+5

1E-4

3E-7

1E-3

1E-2
W, oxides, hydroxides,

halides, sulfides,

sulfates, and nitrates

-

3E+5

1E-4

4E-7

-

-
51 Antimony-116m2 D, see 115Sb 2E+4 7E+4 3E-5 1E-7 3E-4 3E-3
W, see 115Sb - 1E+5 6E-5 2E-7 - -
51 Antimony-1162 D, see 115Sb 7E+4 3E+5 1E-4 4E-7 - -
St wall

(9E+4)

 - - - 1E-3 1E-2
W, see 115Sb - 3E+5 1E-4 5E-7 - -
51 Antimony-117 D, see 115Sb 7E+4 2E+5 9E-5 3E-7 9E-4 9E-3
W, see 115Sb - 3E+5 1E-4 4E-7 - -
51 Antimony-118m D, see 115Sb 6E+3 2E+4 8E-6 3E-8 7E-5 7E-4
W, see 115Sb 5E+3 2E+4 9E-6 3E-8 - -
51 Antimony-119 D, see 115Sb 2E+4 5E+4 2E-5 6E-8 2E-4 2E-3
W, see 115Sb 2E+4 3E+4 1E-5 4E-8 - -
51 Antimony-1202 D, see 115Sb 1E+5 4E+5 2E-4 6E-7 - -
(16 min) St wall (2E+5) - - - 2E-3 2E-2
W, see 115Sb - 5E+5 2E-4 7E-7 - -
51 Antimony-120

(5.76 d)

 D, see 115Sb 1E+3 2E+3 9E-7 3E-9 1E-5 1E-4
W, see 115Sb 9E+2 1E+3 5E-7 2E-9 - -
51 Antimony-122 D, see 115Sb 8E+2 2E+3 1E-6 3E-9 - -
LLI wall (8E+2) - - - 1E-5 1E-4
W, see 115Sb 7E+2 1E+3 4E-7 2E-9 - -
51 Antimony-124m2 D, see 115Sb 3E+5 8E+5 4E-4 1E-6 3E-3 3E-2
W, see 115Sb 2E+5 6E+5 2E-4 8E-7 - -
51 Antimony-124 D, see 115Sb 6E+2 9E+2 4E-7 1E-9 7E-6 7E-5
W, see 115Sb 5E+2 2E+2 1E-7 3E-10 - -
51 Antimony-125 D, see 115Sb 2E+3 2E+3 1E-6 3E-9 3E-5 3E-4
W, see 115Sb - 5E+2 2E-7 7E-10 - -
51 Antimony-126m2 D, see 115Sb 5E+4 2E+5 8E-5 3E-7 - -
St wall

(7E+4)

 - - - 9E-4 9E-3
W, see 115Sb - 2E+5 8E-5 3E-7 - -
51 Antimony-126 D, see 115Sb 6E+2 1E+3 5E-7 2E-9 7E-6 7E-5
W, see 115Sb 5E+2 5E+2 2E-7 7E-10 - -
51 Antimony-127 D, see 115Sb 8E+2 2E+3 9E-7 3E-9 - -
LLI wall (8E+2) - - - 1E-5 1E-4
W, see 115Sb 7E+2 9E+2 4E-7 1E-9 - -
51 Antimony-1282 D, see 115Sb 8E+4 4E+5 2E-4 5E-7 - -
(10.4 min) St wall

(1E+5)

-

-

-

1E-3

1E-2
W, see 115Sb - 4E+5 2E-4 6E-7 - -
51 Antimony-128 D, see 115Sb 1E+3 4E+3 2E-6 6E-9 2E-5 2E-4
(9.01 h) W, see 115Sb - 3E+3 1E-6 5E-9 - -
51 Antimony-129 D, see 115Sb 3E+3 9E+3 4E-6 1E-8 4E-5 4E-4
W, see 115Sb - 9E+3 4E-6 1E-8 - -
51 Antimony-1302 D, see 115Sb 2E+4 6E+4 3E-5 9E-8 3E-4 3E-3
W, see 115Sb - 8E+4 3E-5 1E-7 - -
51 Antimony-1312 D, see 115Sb 1E+4 2E+4 1E-5 - - -
Thyroid (2E+4) Thyroid (4E+4) - 6E-8 2E-4 2E-3
W, see 115Sb - 2E+4 1E-5 - -
- Thyroid (4E+4) - 6E-8 - -
52 Tellurium-116 D, all compounds except

those given for W

 8E+3 2E+4 9E-6 3E-8 1E-4 1E-3
W, oxides, hydroxides,

and nitrates

 - 3E+4 1E-5 4E-8 - -
52 Tellurium-121m D, see 116Te 5E+2 2E+2 8E-8 - - -
Bone surf (7E+2) Bone surf (4E+2) - 5E-10 1E-5 1E-4
W, see 116Te - 4E+2 2E-7 6E-10 - -
52 Tellurium-121 D, see 116Te 3E+3 4E+3 2E-6 6E-9 4E-5 4E-4
W, see 116Te - 3E+3 1E-6 4E-9 - -
52 Tellurium-123m D, see 116Te 6E+2 2E+2 9E-8 - - -
Bone surf (1E+3) Bone surf (5E+2) - 8E-10 1E-5 1E-4
W, see 116Te - 5E+2 2E-7 8E-10 - -
52 Tellurium-123 D, see 116Te 5E+2 2E+2 8E-8 - - -
Bone surf (1E+3) Bone surf (5E+2) - 7E-10 2E-5 2E-4
W, see 116Te - 4E+2 2E-7 - - -
- Bone surf (1E+3) - 2E-9 - -
52 Tellurium-125m D, see 116Te 1E+3 4E+2 2E-7 - - -
Bone surf (1E+3) Bone surf (1E+3) - 1E-9 2E-5 2E-4
W, see 116Te - 7E+2 3E-7 1E-9 - -
52 Tellurium-127m D, see 116Te 6E+2 3E+2 1E-7 - 9E-6 9E-5
- Bone surf (4E+2) - 6E-10 - -
W, see 116Te - 3E+2 1E-7 4E-10 - -
52 Tellurium-127 D, see 116Te 7E+3 2E+4 9E-6 3E-8 1E-4 1E-3
W, see 116Te - 2E+4 7E-6 2E-8 - -
52 Tellurium-129m D, see 116Te 5E+2 6E+2 3E-7 9E-10 7E-6 7E-5
W, see 116Te - 2E+2 1E-7 3E-10 - -
52 Tellurium-1292 D, see 116Te 3E+4 6E+4 3E-5 9E-8 4E-4 4E-3
W, see 116Te - 7E+4 3E-5 1E-7 - -
52 Tellurium-131m D, see 116Te 3E+2 4E+2 2E-7 - - -
Thyroid (6E+2) Thyroid (1E+3) - 2E-9 8E-6 8E-5
W, see 116Te - 4E+2 2E-7 - - -
- Thyroid (9E+2) - 1E-9 - -
52 Tellurium-1312 D, see 116Te 3E+3 5E+3 2E-6 - - -
Thyroid (6E+3) Thyroid (1E+4) - 2E-8 8E-5 8E-4
W, see 116Te - 5E+3 2E-6 - - -
- Thyroid (1E+4) - 2E-8 - -
52 Tellurium-132 D, see 116Te 2E+2 2E+2 9E-8 - - -
Thyroid (7E+2) Thyroid (8E+2) - 1E-9 9E-6 9E-5
W, see 116Te - 2E+2 9E-8 - - -
- Thyroid (6E+2) - 9E-10 - -
52 Tellurium-133m2 D, see 116Te 3E+3 5E+3 2E-6 - - -
Thyroid (6E+3) Thyroid (1E+4) - 2E-8 9E-5 9E-4
W, see 116Te - 5E+3 2E-6 - - -
- Thyroid (1E+4) - 2E-8 - -
52 Tellurium-1332 D, see 116Te 1E+4 2E+4 9E-6 - - -
Thyroid (3E+4) Thyroid (6E+4) - 8E-8 4E-4 4E-3
W, see 116Te - 2E+4 9E-6 - - -
- Thyroid (6E+4) - 8E-8 - -
52 Tellurium-1342 D, see 116Te 2E+4 2E+4 1E-5 - - -
Thyroid (2E+4) Thyroid (5E+4) - 7E-8 3E-4 3E-3
W, see 116Te - 2E+4 1E-5 - - -
Thyroid
- (5E+4) - 7E-8 - -
53 Iodine-120m2 D, all compounds 1E+4 2E+4 9E-6 3E-8 - -
Thyroid (1E+4) - - - 2E-4 2E-3
53 Iodine-1202 D, all compounds 4E+3 9E+3 4E-6 - - -
Thyroid (8E+3) Thyroid (1E+4) - 2E-8 1E-4 1E-3
53 Iodine-121 D, all compounds 1E+4 2E+4 8E-6 - - -
Thyroid (3E+4) Thyroid (5E+4) - 7E-8 4E-4 4E-3
53 Iodine-123 D, all compounds 3E+3 6E+3 3E-6 - - -
Thyroid (1E+4) Thyroid (2E+4) - 2E-8 1E-4 1E-3
53 Iodine-124 D, all compounds 5E+1 8E+1 3E-8 - - -
Thyroid (2E+2) Thyroid (3E+2) - 4E-10 2E-6 2E-5
53 Iodine-125 D, all compounds 4E+1 6E+1 3E-8 - - -
Thyroid (1E+2) Thyroid

(2E+2)

 - 3E-10 2E-6 2E-5
53 Iodine-126 D, all compounds 2E+1 4E+1 1E-8 - - -
Thyroid (7E+1) Thyroid (1E+2) - 2E-10 1E-6 1E-5
53 Iodine-1282 D, all compounds 4E+4 1E+5 5E-5 2E-7 - -
St wall

(6E+4)

 - - - 8E-4 8E-3
53 Iodine-129 D, all compounds 5E+0 9E+0 4E-9 - - -
Thyroid (2E+1) Thyroid (3E+1) - 4E-11 2E-7 2E-6
53 Iodine-130 D, all compounds 4E+2 7E+2 3E-7 - - -
Thyroid (1E+3) Thyroid (2E+3) - 3E-9 2E-5 2E-4
53 Iodine-131 D, all compounds 3E+1 5E+1 2E-8 - - -
Thyroid (9E+1) Thyroid (2E+2) - 2E-10 1E-6 1E-5
53 Iodine-132m2 D, all compounds 4E+3 8E+3 4E-6 - - -
Thyroid (1E+4) Thyroid (2E+4) - 3E-8 1E-4 1E-3
53 Iodine-132 D, all compounds 4E+3 8E+3 3E-6 - - -
Thyroid (9E+3) Thyroid (1E+4) - 2E-8 1E-4 1E-3
53 Iodine-133 D, all compounds 1E+2 3E+2 1E-7 - - -
Thyroid (5E+2) Thyroid (9E+2) - 1E-9 7E-6 7E-5
53 Iodine-1342 D, all compounds 2E+4 5E+4 2E-5 6E-8 - -
Thyroid (3E+4) - - - 4E-4 4E-3
53 Iodine-135 D, all compounds 8E+2 2E+3 7E-7 - - -
Thyroid (3E+3) Thyroid (4E+3) - 6E-9 3E-5 3E-4
54 Xenon-1202 Submersion1 - - 1E-5 4E-8 - -
54 Xenon-1212 Submersion1 - - 2E-6 1E-8 - -
54 Xenon-122 Submersion1 - - 7E-5 3E-7 - -
54 Xenon-123 Submersion1 - - 6E-6 3E-8 - -
54 Xenon-125 Submersion1 - - 2E-5 7E-8 - -
54 Xenon-127 Submersion1 - - 1E-5 6E-8 - -
54 Xenon-129m Submersion1 - - 2E-4 9E-7 - -
54 Xenon-131m Submersion1 - - 4E-4 2E-6 - -
54 Xenon-133m Submersion1 - - 1E-4 6E-7 - -
54 Xenon-133 Submersion1 - - 1E-4 5E-7 - -
54 Xenon-135m2 Submersion1 - - 9E-6 4E-8 - -
54 Xenon-135 Submersion1 - - 1E-5 7E-8 - -
54 Xenon-1382 Submersion1 - - 4E-6 2E-8 - -
55 Cesium-1252 D, all compounds 5E+4 1E+5 6E-5 2E-7 - -
St wall

(9E+4)

 - - - 1E-3 1E-2
55 Cesium-127 D, all compounds 6E+4 9E+4 4E-5 1E-7 9E-4 9E-3
55 Cesium-129 D, all compounds 2E+4 3E+4 1E-5 5E-8 3E-4 3E-3
55 Cesium-1302 D, all compounds 6E+4 2E+5 8E-5 3E-7 - -
St wall

(1E+5)

 - - - 1E-3 1E-2
55 Cesium-131 D, all compounds 2E+4 3E+4 1E-5 4E-8 3E-4 3E-3
55 Cesium-132 D, all compounds 3E+3 4E+3 2E-6 6E-9 4E-5 4E-4
55 Cesium-134m D, all compounds 1E+5 1E+5 6E-5 2E-7 - -
St wall

(1E+5)

 - - - 2E-3 2E-2
55 Cesium-134 D, all compounds 7E+1 1E+2 4E-8 2E-10 9E-7 9E-6
55 Cesium-135m2 D, all compounds 1E+5 2E+5 8E-5 3E-7 1E-3 1E-2
55 Cesium-135 D, all compounds 7E+2 1E+3 5E-7 2E-9 1E-5 1E-4
55 Cesium-136 D, all compounds 4E+2 7E+2 3E-7 9E-10 6E-6 6E-5
55 Cesium-137 D, all compounds 1E+2 2E+2 6E-8 2E-10 1E-6 1E-5
55 Cesium-1382 D, all compounds 2E+4 6E+4 2E-5 8E-8 - -
St wall

(3E+4)

 - - - 4E-4 4E-3
56 Barium-1262 D, all compounds 6E+3 2E+4 6E-6 2E-8 8E-5 8E-4
56 Barium-128 D, all compounds 5E+2 2E+3 7E-7 2E-9 7E-6 7E-5
56 Barium-131m2 D, all compounds 4E+5 1E+6 6E-4 2E-6 - -
St wall

(5E+5)

 - - - 7E-3 7E-2
56 Barium-131 D, all compounds 3E+3 8E+3 3E-6 1E-8 4E-5 4E-4
56 Barium-133m D, all compounds 2E+3 9E+3 4E-6 1E-8 - -
LLI wall (3E+3) - - - 4E-5 4E-4
56 Barium-133 D, all compounds 2E+3 7E+2 3E-7 9E-10 2E-5 2E-4
56 Barium-135m D, all compounds 3E+3 1E+4 5E-6 2E-8 4E-5 4E-4
56 Barium-1392 D, all compounds 1E+4 3E+4 1E-5 4E-8 2E-4 2E-3
56 Barium-140 D, all compounds 5E+2 1E+3 6E-7 2E-9 - -
LLI wall (6E+2) - - - 8E-6 8E-5
56 Barium-1412 D, all compounds 2E+4 7E+4 3E-5 1E-7 3E-4 3E-3
56 Barium-1422 D, all compounds 5E+4 1E+5 6E-5 2E-7 7E-4 7E-3
57 Lanthanum-1312 D, all compounds except those given for W 5E+4 1E+5 5E-5 2E-7 6E-4 6E-3
W, oxides and hydroxides - 2E+5 7E-5 2E-7 - -
57 Lanthanum-132 D, see 131La 3E+3 1E+4 4E-6 1E-8 4E-5 4E-4
W, see 131La - 1E+4 5E-6 2E-8 - -
57 Lanthanum-135 D, see 131La 4E+4 1E+5 4E-5 1E-7 5E-4 5E-3
W, see 131La - 9E+4 4E-5 1E-7 - -
57 Lanthanum-137 D, see 131La 1E+4 6E+1 3E-8 - 2E-4 2E-3
- Liver

(7E+1)

 - 1E-10 - -
W, see 131La - 3E+2 1E-7 - - -
- Liver

(3E+2)

 - 4E-10 - -
57 Lanthanum-138 D, see 131La 9E+2 4E+0 1E-9 5E-12 1E-5 1E-4
W, see 131La - 1E+1 6E-9 2E-11 - -
57 Lanthanum-140 D, see 131La 6E+2 1E+3 6E-7 2E-9 9E-6 9E-5
W, see 131La - 1E+3 5E-7 2E-9 - -
57 Lanthanum-141 D, see 131La 4E+3 9E+3 4E-6 1E-8 5E-5 5E-4
W, see 131La - 1E+4 5E-6 2E-8 - -
57 Lanthanum-1422 D, see 131La 8E+3 2E+4 9E-6 3E-8 1E-4 1E-3
W, see 131La - 3E+4 1E-5 5E-8 - -
57 Lanthanum-1432 D, see 131La 4E+4 1E+5 4E-5 1E-7 - -
St wall

(4E+4)

 - - - 5E-4 5E-3
W, see 131La - 9E+4 4E-5 1E-7 - -
58 Cerium-134 W, all compounds except

those given for Y

 5E+2 7E+2 3E-7 1E-9 - -
LLI wall (6E+2) - - - 8E-6 8E-5
Y, oxides, hydroxides,

and fluorides

 - 7E+2 3E-7 9E-10 - -
58 Cerium-135 W, see 134Ce 2E+3 4E+3 2E-6 5E-9 2E-5 2E-4
Y, see 134Ce - 4E+3 1E-6 5E-9 - -
58 Cerium-137m W, see 134Ce 2E+3 4E+3 2E-6 6E-9 - -
LLI wall (2E+3) - - - 3E-5 3E-4
Y, see 134Ce - 4E+3 2E-6 5E-9 - -
58 Cerium-137 W, see 134Ce 5E+4 1E+5 6E-5 2E-7 7E-4 7E-3
Y, see 134Ce - 1E+5 5E-5 2E-7 - -
58 Cerium-139 W, see 134Ce 5E+3 8E+2 3E-7 1E-9 7E-5 7E-4
Y, see 134Ce - 7E+2 3E-7 9E-10 - -
58 Cerium-141 W, see 134Ce 2E+3 7E+2 3E-7 1E-9 - -
LLI wall (2E+3) - - - 3E-5 3E-4
Y, see 134Ce - 6E+2 2E-7 8E-10 - -
58 Cerium-143 W, see 134Ce 1E+3 2E+3 8E-7 3E-9 - -
LLI wall (1E+3) - - - 2E-5 2E-4
Y, see 134Ce - 2E+3 7E-7 2E-9 - -
58 Cerium-144 W, see 134Ce 2E+2 3E+1 1E-8 4E-11 - -
LLI wall (3E+2) - - - 3E-6 3E-5
Y, see 134Ce - 1E+1 6E-9 2E-11 - -
59 Praseodymium-1362 W, all compounds except

those given for Y

 5E+4 2E+5 1E-4 3E-7 - -
St wall
(7E+4) - - - 1E-3 1E-2
Y, oxides, hydroxides,

carbides, and fluorides

 - 2E+5 9E-5 3E-7 - -
59 Praseodymium-1372 W, see 136Pr 4E+4 2E+5 6E-5 2E-7 5E-4 5E-3
Y, see 136Pr - 1E+5 6E-5 2E-7 - -
59 Praseodymium-138m W, see 136Pr 1E+4 5E+4 2E-5 8E-8 1E-4 1E-3
Y, see 136Pr - 4E+4 2E-5 6E-8 - -
59 Praseodymium-139 W, see 136Pr 4E+4 1E+5 5E-5 2E-7 6E-4 6E-3
Y, see 136Pr - 1E+5 5E-5 2E-7 - -
59 Praseodymium-142m2 W, see 136Pr 8E+4 2E+5 7E-5 2E-7 1E-3 1E-2
Y, see 136Pr - 1E+5 6E-5 2E-7 - -
59 Praseodymium-142 W, see 136Pr 1E+3 2E+3 9E-7 3E-9 1E-5 1E-4
Y, see 136Pr - 2E+3 8E-7 3E-9 - -
59 Praseodymium-143 W, see 136Pr 9E+2 8E+2 3E-7 1E-9 - -
LLI wall (1E+3) - - - 2E-5 2E-4
Y, see 136Pr - 7E+2 3E-7 9E-10 - -
59 Praseodymium-1442 W, see 136Pr 3E+4 1E+5 5E-5 2E-7 - -
St wall

(4E+4)

 - - - 6E-4 6E-3
Y, see 136Pr - 1E+5 5E-5 2E-7 - -
59 Praseodymium-145 W, see 136Pr 3E+3 9E+3 4E-6 1E-8 4E-5 4E-4
Y, see 136Pr - 8E+3 3E-6 1E-8 - -
59 Praseodymium-1472 W, see 136Pr 5E+4 2E+5 8E-5 3E-7 - -
St wall

(8E+4)

 - - - 1E-3 1E-2
Y, see 136Pr - 2E+5 8E-5 3E-7 - -
60 Neodymium-1362 W, all compounds except

those given for Y

 1E+4 6E+4 2E-5 8E-8 2E-4 2E-3
Y, oxides, hydroxides,

carbides, and fluorides

 - 5E+4 2E-5 8E-8 - -
60 Neodymium-138 W, see 136Nd 2E+3 6E+3 3E-6 9E-9 3E-5 3E-4
Y, see 136Nd - 5E+3 2E-6 7E-9 - -
60 Neodymium-139m W, see 136Nd 5E+3 2E+4 7E-6 2E-8 7E-5 7E-4
Y, see 136Nd - 1E+4 6E-6 2E-8 - -
60 Neodymium-1392 W, see 136Nd 9E+4 3E+5 1E-4 5E-7 1E-3 1E-2
Y, see 136Nd - 3E+5 1E-4 4E-7 - -
60 Neodymium-141 W, see 136Nd 2E+5 7E+5 3E-4 1E-6 2E-3 2E-2
Y, see 136Nd - 6E+5 3E-4 9E-7 - -
60 Neodymium-147 W, see 136Nd 1E+3 9E+2 4E-7 1E-9 - -
LLI wall (1E+3) - - - 2E-5 2E-4
Y, see 136Nd - 8E+2 4E-7 1E-9 - -
60 Neodymium-1492 W, see 136Nd 1E+4 3E+4 1E-5 4E-8 1E-4 1E-3
Y, see 136Nd - 2E+4 1E-5 3E-8 - -
60 Neodymium-1512 W, see 136Nd 7E+4 2E+5 8E-5 3E-7 9E-4 9E-3
Y, see 136Nd - 2E+5 8E-5 3E-7 - -
61 Promethium-1412 W, all compounds except

those given for Y

 5E+4 2E+5 8E-5 3E-7 - -
St wall

(6E+4)

 - - - 8E-4 8E-3
Y, oxides, hydroxides,

carbides, and fluorides

 - 2E+5 7E-5 2E-7 - -
61 Promethium-143 W, see 141Pm 5E+3 6E+2 2E-7 8E-10 7E-5 7E-4
Y, see 141Pm - 7E+2 3E-7 1E-9 - -
61 Promethium-144 W, see 141Pm 1E+3 1E+2 5E-8 2E-10 2E-5 2E-4
Y, see 141Pm - 1E+2 5E-8 2E-10 - -
61 Promethium-145 W, see 141Pm 1E+4 2E+2 7E-8 - 1E-4 1E-3
- Bone surf (2E+2) - 3E-10 - -
Y, see 141Pm - 2E+2 8E-8 3E-10 - -
61 Promethium-146 W, see 141Pm 2E+3 5E+1 2E-8 7E-11 2E-5 2E-4
Y, see 141Pm - 4E+1 2E-8 6E-11 - -
61 Promethium-147 W, see 141Pm 4E+3 1E+2 5E-8 - - -
LLI wall (5E+3) Bone surf (2E+2) - 3E-10 7E-5 7E-4
Y, see 141Pm - 1E+2 6E-8 2E-10 - -
61 Promethium-148m W, see 141Pm 7E+2 3E+2 1E-7 4E-10 1E-5 1E-4
Y, see 141Pm - 3E+2 1E-7 5E-10 - -
61 Promethium-148 W, see 141Pm 4E+2 5E+2 2E-7 8E-10 - -
LLI wall (5E+2) - - - 7E-6 7E-5
Y, see 141Pm - 5E+2 2E-7 7E-10 - -
61 Promethium-149 W, see 141Pm 1E+3 2E+3 8E-7 3E-9 - -
LLI wall (1E+3) - - - 2E-5 2E-4
Y, see 141Pm - 2E+3 8E-7 2E-9 - -
61 Promethium-150 W, see 141Pm 5E+3 2E+4 8E-6 3E-8 7E-5 7E-4
Y, see 141Pm - 2E+4 7E-6 2E-8 - -
61 Promethium-151 W, see 141Pm 2E+3 4E+3 1E-6 5E-9 2E-5 2E-4
Y, see 141Pm - 3E+3 1E-6 4E-9 - -
62 Samarium-141m2 W, all compounds 3E+4 1E+5 4E-5 1E-7 4E-4 4E-3
62 Samarium-1412 W, all compounds 5E+4 2E+5 8E-5 2E-7 - -
St wall

(6E+4)

 - - - 8E-4 8E-3
62 Samarium-1422 W, all compounds 8E+3 3E+4 1E-5 4E-8 1E-4 1E-3
62 Samarium-145 W, all compounds 6E+3 5E+2 2E-7 7E-10 8E-5 8E-4
62 Samarium-146 W, all compounds 1E+1 4E-2 1E-11 - - -
Bone surf (3E+1) Bone surf (6E-2) - 9E-14 3E-7 3E-6
62 Samarium-147 W, all compounds 2E+1 4E-2 2E-11 - - -
Bone surf (3E+1) Bone surf (7E-2) - 1E-13 4E-7 4E-6
62 Samarium-151 W, all compounds 1E+4 1E+2 4E-8 - - -
LLI wall (1E+4) Bone surf (2E+2) - 2E-10 2E-4 2E-3
62 Samarium-153 W, all compounds 2E+3 3E+3 1E-6 4E-9 - -
LLI wall (2E+3) - - - 3E-5 3E-4
62 Samarium-1552 W, all compounds 6E+4 2E+5 9E-5 3E-7 - -
St wall

(8E+4)

 - - - 1E-3 1E-2
62 Samarium-156 W, all compounds 5E+3 9E+3 4E-6 1E-8 7E-5 7E-4
63 Europium-145 W, all compounds 2E+3 2E+3 8E-7 3E-9 2E-5 2E-4
63 Europium-146 W, all compounds 1E+3 1E+3 5E-7 2E-9 1E-5 1E-4
63 Europium-147 W, all compounds 3E+3 2E+3 7E-7 2E-9 4E-5 4E-4
63 Europium-148 W, all compounds 1E+3 4E+2 1E-7 5E-10 1E-5 1E-4
63 Europium-149 W, all compounds 1E+4 3E+3 1E-6 4E-9 2E-4 2E-3
63 Europium-150

(12.62h)

 W, all compounds 3E+3 8E+3 4E-6 1E-8 4E-5 4E-4
63 Europium-150

(34.2 y)

 W, all compounds 8E+2 2E+1 8E-9 3E-11 1E-5 1E-4
63 Europium-152m W, all compounds 3E+3 6E+3 3E-6 9E-9 4E-5 4E-4
63 Europium-152 W, all compounds 8E+2 2E+1 1E-8 3E-11 1E-5 1E-4
63 Europium-154 W, all compounds 5E+2 2E+1 8E-9 3E-11 7E-6 7E-5
63 Europium-155 W, all compounds 4E+3 9E+1 4E-8 - 5E-5 5E-4
- Bone surf (1E+2) - 2E-10 - -
63 Europium-156 W, all compounds 6E+2 5E+2 2E-7 6E-10 8E-6 8E-5
63 Europium-157 W, all compounds 2E+3 5E+3 2E-6 7E-9 3E-5 3E-4
63 Europium-1582 W, all compounds 2E+4 6E+4 2E-5 8E-8 3E-4 3E-3
64 Gadolinium-1452 D, all compounds except

those given for W

 5E+4 2E+5 6E-5 2E-7 - -
St wall
(5E+4) - - - 6E-4 6E-3
W, oxides, hydroxides,

and fluorides

 - 2E+5 7E-5 2E-7 - -
64 Gadolinium-146 D, see 145Gd 1E+3 1E+2 5E-8 2E-10 2E-5 2E-4
W, see 145Gd - 3E+2 1E-7 4E-10 - -
64 Gadolinium-147 D, see 145Gd 2E+3 4E+3 2E-6 6E-9 3E-5 3E-4
W, see 145Gd - 4E+3 1E-6 5E-9 - -
64 Gadolinium-148 D, see 145Gd 1E+1 8E+3 3E-12 - - -
Bone surf (2E+1) Bone surf (2E+2) - 2E-14 3E-7 3E-6
W, see 145Gd - 3E-2 1E-11 - - -
- Bone surf (6E-2) - 8E-14 - -
64 Gadolinium-149 D, see 145Gd 3E+3 2E+3 9E-7 3E-9 4E-5 4E-4
W, see 145Gd - 2E+3 1E-6 3E-9 - -
64 Gadolinium-151 D, see 145Gd 6E+3 4E+2 2E-7 - 9E-5 9E-4
- Bone surf (6E+2) - 9E-10 - -
W, see 145Gd - 1E+3 5E-7 2E-9 - -
64 Gadolinium-152 D, see 145Gd 2E+1 1E-2 4E-12 - - -
Bone surf (3E+1) Bone surf (2E-2) - 3E-14 4E-7 4E-6
W, see 145Gd - 4E-2 2E-11 - - -
- Bone surf (8E-2) - 1E-13 - -
64 Gadolinium-153 D, see 145Gd 5E+3 1E+2 6E-8 - 6E-5 6E-4
- Bone surf (2E+2) - 3E-10 - -
W, see 145Gd - 6E+2 2E-7 8E-10 - -
64 Gadolinium-159 D, see 145Gd 3E+3 8E+3 3E-6 1E-8 4E-5 4E-4
W, see 145Gd - 6E+3 2E-6 8E-9 - -
65 Terbium-1472 W, all compounds 9E+3 3E+4 1E-5 5E-8 1E-4 1E-3
65 Terbium-149 W, all compounds 5E+3 7E+2 3E-7 1E-9 7E-5 7E-4
65 Terbium-150 W, all compounds 5E+3 2E+4 9E-6 3E-8 7E-5 7E-4
65 Terbium-151 W, all compounds 4E+3 9E+3 4E-6 1E-8 5E-5 5E-4
65 Terbium-153 W, all compounds 5E+3 7E+3 3E-6 1E-8 7E-5 7E-4
65 Terbium-154 W, all compounds 2E+3 4E+3 2E-6 6E-9 2E-5 2E-4
65 Terbium-155 W, all compounds 6E+3 8E+3 3E-6 1E-8 8E-5 8E-4
65 Terbium-156m

(5.0 h)

 W, all compounds 2E+4 3E+4 1E-5 4E-8 2E-4 2E-3
65 Terbium-156m

(24.4 h)

 W, all compounds 7E+3 8E+3 3E-6 1E-8 1E-4 1E-3
65 Terbium-156 W, all compounds 1E+3 1E+3 6E-7 2E-9 1E-5 1E-4
65 Terbium-157 W, all compounds 5E+4 3E+2 1E-7 - - -
LLI wall (5E+4) Bone surf (6E+2) - 8E-10 7E-4 7E-3
65 Terbium-158 W, all compounds 1E+3 2E+1 8E-9 3E-11 2E-5 2E-4
65 Terbium-160 W, all compounds 8E+2 2E+2 9E-8 3E-10 1E-5 1E-4
65 Terbium-161 W, all compounds 2E+3 2E+3 7E-7 2E-9 - -
LLI wall (2E+3) - - - 3E-5 3E-4
66 Dysprosium-155 W, all compounds 9E+3 3E+4 1E-5 4E-8 1E-4 1E-3
66 Dysprosium-157 W, all compounds 2E+4 6E+4 3E-5 9E-8 3E-4 3E-3
66 Dysprosium-159 W, all compounds 1E+4 2E+3 1E-6 3E-9 2E-4 2E-3
66 Dysprosium-165 W, all compounds 1E+4 5E+4 2E-5 6E-8 2E-4 2E-3
66 Dysprosium-166 W, all compounds 6E+2 7E+2 3E-7 1E-9 - -
LLI wall (8E+2) - - - 1E-5 1E-4
67 Holmium-1552 W, all compounds 4E+4 2E+5 6E-5 2E-7 6E-4 6E-3
67 Holmium-1572 W, all compounds 3E+5 1E+6 6E-4 2E-6 4E-3 4E-2
67 Holmium-1592 W, all compounds 2E+5 1E+6 4E-4 1E-6 3E-3 3E-2
67 Holmium-161 W, all compounds 1E+5 4E+5 2E-4 6E-7 1E-3 1E-2
67 Holmium-162m2 W, all compounds 5E+4 3E+5 1E-4 4E-7 7E-4 7E-3
67 Holmium-1622 W, all compounds 5E+5 2E+6 1E-3 3E-6 - -
St wall

(8E+5)

 - - - 1E-2 1E-1
67 Holmium-164m2 W, all compounds 1E+5 3E+5 1E-4 4E-7 1E-3 1E-2
67 Holmium-1642 W, all compounds 2E+5 6E+5 3E-4 9E-7 - -
St wall

(2E+5)

 - - - 3E-3 3E-2
67 Holmium-166m W, all compounds 6E+2 7E+0 3E-9 9E-12 9E-6 9E-5
67 Holmium-166 W, all compounds 9E+2 2E+3 7E-7 2E-9 - -
LLI wall (9E+2) - - - 1E-5 1E-4
67 Holmium-167 W, all compounds 2E+4 6E+4 2E-5 8E-8 2E-4 2E-3
68 Erbium-161 W, all compounds 2E+4 6E+4 3E-5 9E-8 2E-4 2E-3
68 Erbium-165 W, all compounds 6E+4 2E+5 8E-5 3E-7 9E-4 9E-3
68 Erbium-169 W, all compounds 3E+3 3E+3 1E-6 4E-9 - -
LLI wall (4E+3) - - - 5E-5 5E-4
68 Erbium-171 W, all compounds 4E+3 1E+4 4E-6 1E-8 5E-5 5E-4
68 Erbium-172 W, all compounds 1E+3 1E+3 6E-7 2E-9 - -
LLI wall (E+3) - - - 2E-5 2E-4
69 Thulium-1622 W, all compounds 7E+4 3E+5 1E-4 4E-7 - -
St wall

(7E+4)

 - - - 1E-3 1E-2
69 Thulium-166 W, all compounds 4E+3 1E+4 6E-6 2E-8 6E-5 6E-4
69 Thulium-167 W, all compounds 2E+3 2E+3 8E-7 3E-9 - -
LLI wall (2E+3) - - - 3E-5 3E-4
69 Thulium-170 W, all compounds 8E+2 2E+2 9E-8 3E-10 - -
LLI wall (1E+3) - - - 1E-5 1E-4
69 Thulium-171 W, all compounds 1E+4 3E+2 1E-7 - - -
LLI wall (1E+4) Bone surf (6E+2)

-

8E-10

2E-4

2E-3
69 Thulium-172 W, all compounds 7E+2 1E+3 5E-7 2E-9 - -
LLI wall (8E+2) - - - 1E-5 1E-4
69 Thulium-173 W, all compounds 4E+3 1E+4 5E-6 2E-8 6E-5 6E-4
69 Thulium-1752 W, all compounds 7E+4 3E+5 1E-4 4E-7 - -
St wall

(9E+4)

 - - - 1E-3 1E-2
70 Ytterbium-1622 W, all compounds except

those given for Y

 7E+4 3E+5 1E-4 4E-7 1E-3 1E-2
Y, oxides, hydroxides,

and fluorides

 - 3E+5 1E-4 4E-7 - -
70 Ytterbium-166 W, see 162Yb 1E+3 2E+3 8E-7 3E-9 2E-5 2E-4
Y, see 162Yb - 2E+3 8E-7 3E-9 - -
70 Ytterbium-1672 W, see 162Yb 3E+5 8E+5 3E-4 1E-6 4E-3 4E-2
Y, see 162Yb - 7E+5 3E-4 1E-6 - -
70 Ytterbium-169 W, see 162Yb 2E+3 8E+2 4E-7 1E-9 2E-5 2E-4
Y, see 162Yb - 7E+2 3E-7 1E-9 - -
70 Ytterbium-175 W, see 162Yb 3E+3 4E+3 1E-6 5E-9 - -
LLI wall (3E+3) - - - 4E-5 4E-4
Y, see 162Yb - 3E+3 1E-6 5E-9 - -
70 Ytterbium-1772 W, see 162Yb 2E+4 5E+4 2E-5 7E-8 2E-4 2E-3
Y, see 162Yb - 5E+4 2E-5 6E-8 - -
70 Ytterbium-1782 W, see 162Yb 1E+4 4E+4 2E-5 6E-8 2E-4 2E-3
Y, see 162Yb - 4E+4 2E-5 5E-8 - -
71 Lutetium-169 W, all compounds except

those given for Y

 3E+3 4E+3 2E-6 6E-9 3E-5 3E-4
Y, oxides, hydroxides,

and fluorides

 - 4E+3 2E-6 6E-9 - -
71 Lutetium-170 W, see 169Lu 1E+3 2E+3 9E-7 3E-9 2E-5 2E-4
Y, see 169Lu - 2E+3 8E-7 3E-9 - -
71 Lutetium-171 W, see 169Lu 2E+3 2E+3 8E-7 3E-9 3E-5 3E-4
Y, see 169Lu - 2E+3 8E-7 3E-9 - -
71 Lutetium-172 W, see 169Lu 1E+3 1E+3 5E-7 2E-9 1E-5 1E-4
Y, see 169Lu - 1E+3 5E-7 2E-9 - -
71 Lutetium-173 W, see 169Lu 5E+3 3E+2 1E-7 - 7E-5 7E-4
- Bone surf (5E+2) - 6E-10 - -
Y, see 169Lu - 3E+2 1E-7 4E-10 - -
71 Lutetium-174m W, see 169Lu 2E+3 2E+2 1E-7 - - -
LLI wall (3E+3) Bone surf (3E+2) - 5E-10 4E-5 4E-4
Y, see 169Lu - 2E+2 9E-8 3E-10 - -
71 Lutetium-174 W, see 169Lu 5E+3 1E+2 5E-8 - 7E-5 7E-4
- Bone surf (2E+2) - 3E-10 - -
Y, see 169Lu - 2E+2 6E-8 2E-10 - -
71 Lutetium-176m W, see 169Lu 8E+3 3E+4 1E-5 3E-8 1E-4 1E-3
Y, see 169Lu - 2E+4 9E-6 3E-8 - -
71 Lutetium-176 W, see 169Lu 7E+2 5E+0 2E-9 - 1E-5 1E-4
- Bone surf (1E+1) - 2E-11 - -
Y, see 169Lu - 8E+0 3E-9 1E-11 - -
71 Lutetium-177m W, see 169Lu 7E+2 1E+2 5E-8 - 1E-5 1E-4
- Bone surf (1E+2) - 2E-10 - -
Y, see 169Lu - 8E+1 3E-8 1E-10 - -
71 Lutetium-177 W, see 169Lu 2E+3 2E+3 9E-7 3E-9 - -
LLI wall (3E+3) - - - 4E-5 4E-4
Y, see 169Lu - 2E+3 9E-7 3E-9 - -
71 Lutetium-178m2 W, see 169Lu 5E+4 2E+5 8E-5 3E-7 - -
St. wall

(6E+4)

 - - - 8E-4 8E-3
Y, see 169Lu - 2E+5 7E-5 2E-7 - -
71 Lutetium-1782 W, see 169Lu 4E+4 1E+5 5E-5 2E-7 - -
St wall

(4E+4)

 - - - 6E-4 6E-3
Y, see 169Lu - 1E+5 5E-5 2E-7 - -
71 Lutetium-179 W, see 169Lu 6E+3 2E+4 8E-6 3E-8 9E-5 9E-4
Y, see 169Lu - 2E+4 6E-6 3E-8 - -
72 Hafnium-170 D, all compounds except

those given for W

 3E+3 6E+3 2E-6 8E-9 4E-5 4E-4
W, oxides, hydroxides,

carbides, and nitrates

 - 5E+3 2E-6 6E-9 - -
72 Hafnium-172 D, see 170Hf 1E+3 9E+0 4E-9 - 2E-5 2E-4
- Bone surf (2E+1) - 3E-11 - -
W, see 170Hf - 4E+1 2E-8 - - -
- Bone surf (6E+1) - 8E-11 - -
72 Hafnium-173 D, see 170Hf 5E+3 1E+4 5E-6 2E-8 7E-5 7E-4
W, see 170Hf - 1E+4 5E-6 2E-8 - -
72 Hafnium-175 D, see 170Hf 3E+3 9E+2 4E-7 - 4E-5 4E-4
- Bone surf (1E+3) - 1E-9 - -
W, see 170Hf - 1E+3 5E-7 2E-9 - -
72 Hafnium-177m2 D, see 170Hf 2E+4 6E+4 2E-5 8E-8 3E-4 3E-3
W, see 170Hf - 9E+4 4E-5 1E-7 - -
72 Hafnium-178m D, see 170Hf 3E+2 1E+0 5E-10 - 3E-6 3E-5
- Bone surf (2E+0) - 3E-12 - -
W, see 170Hf - 5E+0 2E-9 - - -
- Bone surf (9E+0) - 1E-11 - -
72 Hafnium-179m D, see 170Hf 1E+3 3E+2 1E-7 - 1E-5 1E-4
- Bone surf (6E+2) - 8E-10 - -
W, see 170Hf - 6E+2 3E-7 8E-10 - -
72 Hafnium-180m D, see 170Hf 7E+3 2E+4 9E-6 3E-8 1E-4 1E-3
W, see 170Hf - 3E+4 1E-5 4E-8 - -
72 Hafnium-181 D, see 170Hf 1E+3 2E+2 7E-8 - 2E-5 2E-4
- Bone surf (4E+2) - 6E-10 - -
W, see 170Hf - 4E+2 2E-7 6E-10 - -
72 Hafnium-182m2 D, see 170Hf 4E+4 9E+4 4E-5 1E-7 5E-4 5E-3
W, see 170Hf - 1E+5 6E-5 2E-7 - -
72 Hafnium-182 D, see 170Hf 2E+2 8E-1 3E-10 - - -
Bone surf (4E+2) Bone surf (2E+0) - 2E-12 5E-6 5E-5
W, see 170Hf - 3E+0 1E-9 - - -
- Bone surf (7E+0) - 1E-11 - -
72 Hafnium-1832 D, see 170Hf 2E+4 5E+4 2E-5 6E-8 3E-4 3E-3
W, see 170Hf - 6E+4 2E-5 8E-8 - -
72 Hafnium-184 D, see 170Hf 2E+3 8E+3 3E-6 1E-8 3E-5 3E-4
W, see 170Hf - 6E+3 3E-6 9E-9 - -
73 Tantalum-1722 W, all compounds except

those given for Y

 4E+4 1E+5 5E-5 2E-7 5E-4 5E-3
Y, elemental Ta, oxides,

hydroxides, halides,

carbides, nitrates,

and nitrides

 - 1E+5 4E-5 1E-7 - -
73 Tantalum-173 W, see 172Ta 7E+3 2E+4 8E-6 3E-8 9E-5 9E-4
Y, see 172Ta - 2E+4 7E-6 2E-8 - -
73 Tantalum-1742 W, see 172Ta 3E+4 1E+5 4E-5 1E-7 4E-4 4E-3
Y, see 172Ta - 9E+4 4E-5 1E-7 - -
73 Tantalum-175 W, see 172Ta 6E+3 2E+4 7E-6 2E-8 8E-5 8E-4
Y, see 172Ta - 1E+4 6E-6 2E-8 - -
73 Tantalum-176 W, see 172Ta 4E+3 1E+4 5E-6 2E-8 5E-5 5E-4
Y, see 172Ta - 1E+4 5E-6 2E-8 - -
73 Tantalum-177 W, see 172Ta 1E+4 2E+4 8E-6 3E-8 2E-4 2E-3
Y, see 172Ta - 2E+4 7E-6 2E-8 - -
73 Tantalum-178 W, see 172Ta 2E+4 9E+4 4E-5 1E-7 2E-4 2E-3
Y, see 172Ta - 7E+4 3E-5 1E-7 - -
73 Tantalum-179 W, see 172Ta 2E+4 5E+3 2E-6 8E-9 3E-4 3E-3
Y, see 172Ta - 9E+2 4E-7 1E-9 - -
73 Tantalum-180m W, see 172Ta 2E+4 7E+4 3E-5 9E-8 3E-4 3E-3
Y, see 172Ta - 6E+4 2E-5 8E-8 - -
73 Tantalum-180 W, see 172Ta 1E+3 4E+2 2E-7 6E-10 2E-5 2E-4
Y, see 172Ta - 2E+1 1E-8 3E-11 - -
73 Tantalum-182m2 W, see 172Ta 2E+5 5E+5 2E-4 8E-7 - -
St wall

(2E+5)

 - - - 3E-3 3E-2
Y, see 172Ta - 4E+5 2E-4 6E-7 - -
73 Tantalum-182 W, see 172Ta 8E+2 3E+2 1E-7 5E-10 1E-5 1E-4
Y, see 172Ta - 1E+2 6E-8 2E-10 - -
73 Tantalum-183 W, see 172Ta 9E+2 1E+3 5E-7 2E-9 - -
LLI wall (1E+3) - - - 2E-5 2E-4
Y, see 172Ta - 1E+3 4E-7 1E-9 - -
73 Tantalum-184 W, see 172Ta 2E+3 5E+3 2E-6 8E-9 3E-5 3E-4
Y, see 172Ta - 5E+3 2E-6 7E-9 - -
73 Tantalum-1852 W, see 172Ta 3E+4 7E+4 3E-5 1E-7 4E-4 4E-3
Y, see 172Ta - 6E+4 3E-5 9E-8 - -
73 Tantalum-1862 W, see 172Ta 5E+4 2E+5 1E-4 3E-7 - -
St wall (7E+4) - - - 1E-3 1E-2
Y, see 172Ta - 2E+5 9E-5 3E-7 - -
74 Tungsten-176 D, all compounds 1E+4 5E+4 2E-5 7E-8 1E-4 1E-3
74 Tungsten-177 D, all compounds 2E+4 9E+4 4E-5 1E-7 3E-4 3E-3
74 Tungsten-178 D, all compounds 5E+3 2E+4 8E-6 3E-8 7E-5 7E-4
74 Tungsten-1792 D, all compounds 5E+5 2E+6 7E-4 2E-6 7E-3 7E-2
74 Tungsten-181 D, all compounds 2E+4 3E+4 1E-5 5E-8 2E-4 2E-3
74 Tungsten-185 D, all compounds 2E+3 7E+3 3E-6 9E-9 - -
LLI wall (3E+3) - - - 4E-5 4E-4
74 Tungsten-187 D, all compounds 2E+3 9E+3 4E-6 1E-8 3E-5 3E-4
74 Tungsten-188 D, all compounds 4E+2 1E+3 5E-7 2E-9 - -
LLI wall (5E+2) - - - 7E-6 7E-5
75 Rhenium-1772 D, all compounds except

those given for W

 9E+4 3E+5 1E-4 4E-7 - -
St wall

(1E+5)

 - - - 2E-3 2E-2
W, oxides, hydroxides,

and nitrates

 - 4E+5 1E-4 5E-7 - -
75 Rhenium-1782 D, see 177Re 7E+4 3E+5 1E-4 4E-7 - -
St wall

(1E+5)

 - - - 1E-3 1E-2
W, see 177Re - 3E+5 1E-4 4E-7 - -
75 Rhenium-181 D, see 177Re 5E+3 9E+3 4E-6 1E-8 7E-5 7E-4
W, see 177Re - 9E+3 4E-6 1E-8 - -
75 Rhenium-182 D, see 177Re 7E+3 1E+4 5E-6 2E-8 9E-5 9E-4
(12.7 h) W, see 177Re - 2E+4 6E-6 2E-8 - -
75 Rhenium-182 D, see 177Re 1E+3 2E+3 1E-6 3E-9 2E-5 2E-4
(64.0 h) W, see 177Re - 2E+3 9E-7 3E-9 - -
75 Rhenium-184m D, see 177Re 2E+3 3E+3 1E-6 4E-9 3E-5 3E-4
W, see 177Re - 4E+2 2E-7 6E-10 - -
75 Rhenium-184 D, see 177Re 2E+3 4E+3 1E-6 5E-9 3E-5 3E-4
W, see 177Re - 1E+3 6E-7 2E-9 - -
75 Rhenium-186m D, see 177Re 1E+3 2E+3 7E-7 - - -
St wall

(2E+3)

 St wall

(2E+3)

 - 3E-9 2E-5 2E-4
W, see 177Re - 2E+2 6E-8 2E-10 - -
75 Rhenium-186 D, see 177Re 2E+3 3E+3 1E-6 4E-9 3E-5 3E-4
W, see 177Re - 2E+3 7E-7 2E-9 - -
75 Rhenium-187 D, see 177Re 6E+5 8E+5 4E-4 - 8E-3 8E-2
- St wall

(9E+5)

 - 1E-6 - -
W, see 177Re - 1E+5 4E-5 1E-7 - -
75 Rhenium-188m2 D, see 177Re 8E+4 1E+5 6E-5 2E-7 1E-3 1E-2
W, see 177Re - 1E+5 6E-5 2E-7 - -
75 Rhenium-188 D, see 177Re 2E+3 3E+3 1E-6 4E-9 2E-5 2E-4
W, see 177Re - 3E+3 1E-6 4E-9 - -
75 Rhenium-189 D, see 177Re 3E+3 5E+3 2E-6 7E-9 4E-5 4E-4
W, see 177Re - 4E+3 2E-6 6E-9 - -
76 Osmium-1802 D, all compounds except

those given for W and Y

 1E+5 4E+5 2E-4 5E-7 1E-3 1E-2
W, halides and nitrates - 5E+5 2E-4 7E-7 - -
Y, oxides and hydroxides - 5E+5 2E-4 6E-7 - -
76 Osmium-1812 D, see 180Os 1E+4 4E+4 2E-5 6E-8 2E-4 2E-3
W, see 180Os - 5E+4 2E-5 6E-8 - -
Y, see 180Os - 4E+4 2E-5 6E-8 - -
76 Osmium-182 D, see 180Os 2E+3 6E+3 2E-6 8E-9 3E-5 3E-4
W, see 180Os - 4E+3 2E-6 6E-9 - -
Y, see 180Os - 4E+3 2E-6 6E-9 - -
76 Osmium-185 D, see 180Os 2E+3 5E+2 2E-7 7E-10 3E-5 3E-4
W, see 180Os - 8E+2 3E-7 1E-9 - -
Y, see 180Os - 8E+2 3E-7 1E-9 - -
76 Osmium-189m D, see 180Os 8E+4 2E+5 1E-4 3E-7 1E-3 1E-2
W, see 180Os - 2E+5 9E-5 3E-7 - -
Y, see 180Os - 2E+5 7E-5 2E-7 - -
76 Osmium-191m D, see 180Os 1E+4 3E+4 1E-5 4E-8 2E-4 2E-3
W, see 180Os - 2E+4 8E-6 3E-8 - -
Y, see 180Os - 2E+4 7E-6 2E-8 - -
76 Osmium-191 D, see 180Os 2E+3 2E+3 9E-7 3E-9 - -
LLI wall (3E+3) - - - 3E-5 3E-4
W, see 180Os - 2E+3 7E-7 2E-9 - -
Y, see 180Os - 1E+3 6E-7 2E-9 - -
76 Osmium-193 D, see 180Os 2E+3 5E+3 2E-6 6E-9 - -
LLI wall (2E+3) - - - 2E-5 2E-4
W, see 180Os - 3E+3 1E-6 4E-9 - -
Y, see 180Os - 3E+3 1E-6 4E-9 - -
76 Osmium-194 D, see 180Os 4E+2 4E+1 2E-8 6E-11 - -
LLI wall (6E+2) - - - 8E-6 8E-5
W, see 180Os - 6E+1 2E-8 8E-11 - -
Y, see 180Os - 8E+0 3E-9 1E-11 - -
77 Iridium-1822 D, all compounds except

those given for W and Y

 4E+4 1E+5 6E-5 2E-7 - -
St wall

(4E+4)

 - - - 6E-4 6E-3
W, halides, nitrates,

and metallic iridium

 - 2E+5 6E-5 2E-7 - -
Y, oxides and hydroxides - 1E+5 5E-5 2E-7 - -
77 Iridium-184 D, see 182Ir 8E+3 2E+4 1E-5 3E-8 1E-4 1E-3
W, see 182Ir - 3E+4 1E-5 5E-8 - -
Y, see 182Ir - 3E+4 1E-5 4E-8 - -
77 Iridium-185 D, see 182Ir 5E+3 1E+4 5E-6 2E-8 7E-5 7E-4
W, see 182Ir - 1E+4 5E-6 2E-8 - -
Y, see 182Ir - 1E+4 4E-6 1E-8 - -
77 Iridium-186 D, see 182Ir 2E+3 8E+3 3E-6 1E-8 3E-5 3E-4
W, see 182Ir - 6E+3 3E-6 9E-9 - -
Y, see 182Ir - 6E+3 2E-6 8E-9 - -
77 Iridium-187 D, see 182Ir 1E+4 3E+4 1E-5 5E-8 1E-4 1E-3
W, see 182Ir - 3E+4 1E-5 4E-8 - -
Y, see 182Ir - 3E+4 1E-5 4E-8 - -
77 Iridium-188 D, see 182Ir 2E+3 5E+3 2E-6 6E-9 3E-5 3E-4
W, see 182Ir - 4E+3 1E-6 5E-9 - -
Y, see 182Ir - 3E+3 1E-6 5E-9 - -
77 Iridium-189 D, see 182Ir 5E+3 5E+3 2E-6 7E-9 - -
LLI wall (5E+3) - - - 7E-5 7E-4
W, see 182Ir - 4E+3 2E-6 5E-9 - -
Y, see 182Ir - 4E+3 1E-6 5E-9 - -
77 Iridium-190m2 D, see 182Ir 2E+5 2E+5 8E-5 3E-7 2E-3 2E-2
W, see 182Ir - 2E+5 9E-5 3E-7 - -
Y, see 182Ir - 2E+5 8E-5 3E-7 - -
77 Iridium-190 D, see 182Ir 1E+3 9E+2 4E-7 1E-9 1E-5 1E-4
W, see 182Ir - 1E+3 4E-7 1E-9 - -
Y, see 182Ir - 9E+2 4E-7 1E-9 - -
77 Iridium-192m D, see 182Ir 3E+3 9E+1 4E-8 1E-10 4E-5 4E-4
W, see 182Ir - 2E+2 9E-8 3E-10 - -
Y, see 182Ir - 2E+1 6E-9 2E-11 - -
77 Iridium-192 D, see 182Ir 9E+2 3E+2 1E-7 4E-10 1E-5 1E-4
W, see 182Ir - 4E+2 2E-7 6E-10 - -
Y, see 182Ir - 2E+2 9E-8 3E-10 - -
77 Iridium-194m D, see 182Ir 6E+2 9E+1 4E-8 1E-10 9E-6 9E-5
W, see 182Ir - 2E+2 7E-8 2E-10 - -
Y, see 182Ir - 1E+2 4E-8 1E-10 - -
77 Iridium-194 D, see 182Ir 1E+3 3E+3 1E-6 4E-9 1E-5 1E-4
W, see 182Ir - 2E+3 9E-7 3E-9 - -
Y, see 182Ir - 2E+3 8E-7 3E-9 - -
77 Iridium-195m D, see 182Ir 8E+3 2E+4 1E-5 3E-8 1E-4 1E-3
W, see 182Ir - 3E+4 1E-5 4E-8 - -
Y, see 182Ir - 2E+4 9E-6 3E-8 - -
77 Iridium-195 D, see 182Ir 1E+4 4E+4 2E-5 6E-8 2E-4 2E-3
W, see 182Ir - 5E+4 2E-5 7E-8 - -
Y, see 182Ir - 4E+4 2E-5 6E-8 - -
78 Platinum-186 D, all compounds 1E+4 4E+4 2E-5 5E-8 2E-4 2E-3
78 Platinum-188 D, all compounds 2E+3 2E+3 7E-7 2E-9 2E-5 2E-4
78 Platinum-189 D, all compounds 1E+4 3E+4 1E-5 4E-8 1E-4 1E-3
78 Platinum-191 D, all compounds 4E+3 8E+3 4E-6 1E-8 5E-5 5E-4
78 Platinum-193m D, all compounds 3E+3 6E+3 3E-6 8E-9 - -
LLI wall (3E+4) - - - 4E-5 4E-4
78 Platinum-193 D, all compounds 4E+4 2E+4 1E-5 3E-8 - -
LLI wall (5E+4) - - - 6E-4 6E-3
78 Platinum-195m D, all compounds 2E+3 4E+3 2E-6 6E-9 - -
LLI wall (2E+3) - - - 3E-5 3E-4
78 Platinum-197m2 D, all compounds 2E+4 4E+4 2E-5 6E-8 2E-4 2E-3
78 Platinum-197 D, all compounds 3E+3 1E+4 4E-6 1E-8 4E-5 4E-4
78 Platinum-1992 D, all compounds 5E+4 1E+5 6E-5 2E-7 7E-4 7E-3
78 Platinum-200 D, all compounds 1E+3 3E+3 1E-6 5E-9 2E-5 2E-4
79 Gold-193 D, all compounds except

those given for W and Y

 9E+3 3E+4 1E-5 4E-8 1E-4 1E-3
W, halides and nitrates - 2E+4 9E-6 3E-8 - -
Y, oxides and hydroxides - 2E+4 8E-6 3E-8 - -
79 Gold-194 D, see 193Au 3E+3 8E+3 3E-6 1E-8 4E-5 4E-4
W, see 193Au - 5E+3 2E-6 8E-9 - -
Y, see 193Au - 5E+3 2E-6 7E-9 - -
79 Gold-195 D, see 193Au 5E+3 1E+4 5E-6 2E-8 7E-5 7E-4
W, see 193Au - 1E+3 6E-7 2E-9 - -
Y, see 193Au - 4E+2 2E-7 6E-10 - -
79 Gold-198m D, see 193Au 1E+3 3E+3 1E-6 4E-9 1E-5 1E-4
W, see 193Au - 1E+3 5E-7 2E-9 - -
Y, see 193Au - 1E+3 5E-7 2E-9 - -
79 Gold-198 D, see 193Au 1E+3 4E+3 2E-6 5E-9 2E-5 2E-4
W, see 193Au - 2E+3 8E-7 3E-9 - -
Y, see 193Au - 2E+3 7E-7 2E-9 - -
79 Gold-199 D, see 193Au 3E+3 9E+3 4E-6 1E-8 - -
LLI wall (3E+3) - - - 4E-5 4E-4
W, see 193Au - 4E+3 2E-6 6E-9 - -
Y, see 193Au - 4E+3 2E-6 5E-9 - -
79 Gold-200m D, see 193Au 1E+3 4E+3 1E-6 5E-9 2E-5 2E-4
W, see 193Au - 3E+3 1E-6 4E-9 - -
Y, see 193Au - 2E+4 1E-6 3E-9 - -
79 Gold-2002 D, see 193Au 3E+4 6E+4 3E-5 9E-8 4E-4 4E-3
W, see 193Au - 8E+4 3E-5 1E-7 - -
Y, see 193Au - 7E+4 3E-5 1E-7 - -
79 Gold-2012 D, see 193Au 7E+4 2E+5 9E-5 3E-7 - -
St wall

(9E+4)

 - - - 1E-3 1E-2
W, see 193Au - 2E+5 1E-4 3E-7 - -
Y, see 193Au - 2E+5 9E-5 3E-7 - -
80 Mercury-193m Vapor - 8E+3 4E-6 1E-8 - -
Organic D 4E+3 1E+4 5E-6 2E-8 6E-5 6E-4
D, sulfates 3E+3 9E+3 4E-6 1E-8 4E-5 4E-4
W, oxides, hydroxides,

halides, nitrates, and

sulfides

 - 8E+3 3E-6 1E-8 - -
80 Mercury-193 Vapor - 3E+4 1E-5 4E-8 - -
Organic D 2E+4 6E+4 3E-5 9E-8 3E-4 3E-3
D, see 193mHg 2E+4 4E+4 2E-5 6E-8 2E-4 2E-3
W, see 193mHg - 4E+4 2E-5 6E-8 - -
80 Mercury-194 Vapor - 3E+1 1E-8 4E-11 - -
Organic D 2E+1 3E+1 1E-8 4E-11 2E-7 2E-6
D, see 193mHg 8E+2 4E+1 2E-8 6E-11 1E-5 1E-4
W, see 193mHg - 1E+2 5E-8 2E-10 - -
80 Mercury-195m Vapor - 4E+3 2E-6 6E-9 - -
Organic D 3E+3 6E+3 3E-6 8E-9 4E-5 4E-4
D, see 193mHg 2E+3 5E+3 2E-6 7E-9 3E-5 3E-4
W, see 193mHg - 4E+3 2E-6 5E-9 - -
80 Mercury-195 Vapor - 3E+4 1E-5 4E-8 - -
Organic D 2E+4 5E+4 2E-5 6E-8 2E-4 2E-3
D, see 193mHg 1E+4 4E+4 1E-5 5E-8 2E-4 2E-3
W, see 193mHg - 3E+4 1E-5 5E-8 - -
80 Mercury-197m Vapor - 5E+3 2E-6 7E-9 - -
Organic D 4E+3 9E+3 4E-6 1E-8 5E-5 5E-4
D, see 193mHg 3E+3 7E+3 3E-6 1E-8 4E-5 4E-4
W, see 193mHg - 5E+3 2E-6 7E-9 - -
80 Mercury-197 Vapor - 8E+3 4E-6 1E-8 - -
Organic D 7E+3 1E+4 6E-6 2E-8 9E-5 9E-4
D, see 193mHg 6E+3 1E+4 5E-6 2E-8 8E-5 8E-4
W, see 193mHg - 9E+3 4E-6 1E-8 - -
80 Mercury-199m2 Vapor - 8E+4 3E-5 1E-7 - -
Organic D 6E+4 2E+5 7E-5 2E-7 - -
St wall

(1E+5)

 - - - 1E-3 1E-2
D, see 193mHg 6E+4 1E+5 6E-5 2E-7 8E-4 8E-3
W, see 193mHg - 2E+5 7E-5 2E-7 - -
80 Mercury-203 Vapor - 8E+2 4E-7 1E-9 - -
Organic D 5E+2 8E+2 3E-7 1E-9 7E-6 7E-5
D, see 193mHg 2E+3 1E+3 5E-7 2E-9 3E-5 3E-4
W, see 193mHg - 1E+3 5E-7 2E-9 - -
81 Thallium-194m2 D, all compounds 5E+4 2E+5 6E-5 2E-7 - -
St wall

(7E+4)

 - - - 1E-3 1E-2
81 Thallium-1942 D, all compounds 3E+5 6E+5 2E-4 8E-7 - -
St wall

(3E+5)

 - - - 4E-3 4E-2
81 Thallium-1952 D, all compounds 6E+4 1E+5 5E-5 2E-7 9E-4 9E-3
81 Thallium-197 D, all compounds 7E+4 1E+5 5E-5 2E-7 1E-3 1E-2
81 Thallium-198m2 D, all compounds 3E+4 5E+4 2E-5 8E-8 4E-4 4E-3
81 Thallium-198 D, all compounds 2E+4 3E+4 1E-5 5E-8 3E-4 3E-3
81 Thallium-199 D, all compounds 6E+4 8E+4 4E-5 1E-7 9E-4 9E-3
81 Thallium-200 D, all compounds 8E+3 1E+4 5E-6 2E-8 1E-4 1E-3
81 Thallium-201 D, all compounds 2E+4 2E+4 9E-6 3E-8 2E-4 2E-3
81 Thallium-202 D, all compounds 4E+3 5E+3 2E-6 7E-9 5E-5 5E-4
81 Thallium-204 D, all compounds 2E+3 2E+3 9E-7 3E-9 2E-5 2E-4
82 Lead-195m2 D, all compounds 6E+4 2E+5 8E-5 3E-7 8E-4 8E-3
82 Lead-198 D, all compounds 3E+4 6E+4 3E-5 9E-8 4E-4 4E-3
82 Lead-1992 D, all compounds 2E+4 7E+4 3E-5 1E-7 3E-4 3E-3
82 Lead-200 D, all compounds 3E+3 6E+3 3E-6 9E-9 4E-5 4E-4
82 Lead-201 D, all compounds 7E+3 2E+4 8E-6 3E-8 1E-4 1E-3
82 Lead-202m D, all compounds 9E+3 3E+4 1E-5 4E-8 1E-4 1E-3
82 Lead-202 D, all compounds 1E+2 5E+1 2E-8 7E-11 2E-6 2E-5
82 Lead-203 D, all compounds 5E+3 9E+3 4E-6 1E-8 7E-5 7E-4
82 Lead-205 D, all compounds 4E+3 1E+3 6E-7 2E-9 5E-5 5E-4
82 Lead-209 D, all compounds 2E+4 6E+4 2E-5 8E-8 3E-4 3E-3
82 Lead-210 D, all compounds 6E-1 2E-1 1E-10 - - -
Bone surf (1E+0) Bone surf (4E-1) - 6E-13 1E-8 1E-7
82 Lead-2112 D, all compounds 1E+4 6E+2 3E-7 9E-10 2E-4 2E-3
82 Lead-212 D, all compounds 8E+1 3E+1 1E-8 5E-11 - -
Bone surf (1E+2) - - - 2E-6 2E-5
82 Lead-2142 D, all compounds 9E+3 8E+2 3E-7 1E-9 1E-4 1E-3
83 Bismuth-2002 D, nitrates 3E+4 8E+4 4E-5 1E-7 4E-4 4E-3
W, all other compounds - 1E+5 4E-5 1E-7 - -
83 Bismuth-2012 D, see 200Bi 1E+4 3E+4 1E-5 4E-8 2E-4 2E-3
W, see 200Bi - 4E+4 2E-5 5E-8 - -
83 Bismuth-2022 D, see 200Bi 1E+4 4E+4 2E-5 6E-8 2E-4 2E-3
W, see 200Bi - 8E+4 3E-5 1E-7 - -
83 Bismuth-203 D, see 200Bi 2E+3 7E+3 3E-6 9E-9 3E-5 3E-4
W, see 200Bi - 6E+3 3E-6 9E-9 - -
83 Bismuth-205 D, see 200Bi 1E+3 3E+3 1E-6 3E-9 2E-5 2E-4
W, see 200Bi - 1E+3 5E-7 2E-9 - -
83 Bismuth-206 D, see 200Bi 6E+2 1E+3 6E-7 2E-9 9E-6 9E-5
W, see 200Bi - 9E+2 4E-7 1E-9 - -
83 Bismuth-207 D, see 200Bi 1E+3 2E+3 7E-7 2E-9 1E-5 1E-4
W, see 200Bi - 4E+2 1E-7 5E-10 - -
83 Bismuth-210m D, see 200Bi 4E+1 5E+0 2E-9 - - -
Kidneys (6E+1) Kidneys (6E+0) - 9E-12 8E-7 8E-6
W, see 200Bi - 7E-1 3E-10 9E-13 - -
83 Bismuth-210 D, see 200Bi 8E+2 2E+2 1E-7 - 1E-5 1E-4
-

-

 Kidneys (4E+2) - 5E-10 - -
W, see 200Bi - 3E+1 1E-8 4E-11 - -
83 Bismuth-2122 D, see 200Bi 5E+3 2E+2 1E-7 3E-10 7E-5 7E-4
W, see 200Bi - 3E+2 1E-7 4E-10 - -
83 Bismuth-2132 D, see 200Bi 7E+3 3E+2 1E-7 4E-10 1E-4 1E-3
W, see 200Bi - 4E+2 1E-7 5E-10 - -
83 Bismuth-2142 D, see 200Bi 2E+4 8E+2 3E-7 1E-9 - -
St wall

(2E+4)

 - - - 3E-4 3E-3
W, see 200Bi - 9E-2 4E-7 1E-9 - -
84 Polonium-2032 D, all compounds except

those given for W

 3E+4 6E+4 3E-5 9E-8 3E-4 3E-3
W, oxides, hydroxides,

and nitrates

 - 9E+4 4E-5 1E-7 - -
84 Polonium-2052 D, see 203Po 2E+4 4E+4 2E-5 5E-8 3E-4 3E-3
W, see 203Po - 7E+4 3E-5 1E-7 - -
84 Polonium-207 D, see 203Po 8E+3 3E+4 1E-5 3E-8 1E-4 1E-3
W, see 203Po - 3E+4 1E-5 4E-8 - -
84 Polonium-210 D, see 203Po 3E+0 6E-1 3E-10 9E-13 4E-8 4E-7
W, see 203Po - 6E-1 3E-10 9E-13 - -
85 Astatine-2072 D, halides 6E+3 3E+3 1E-6 4E-9 8E-5 8E-4
W - 2E+3 9E-7 3E-9 - -
85 Astatine-211 D, halides 1E+2 8E+1 3E-8 1E-10 2E-6 2E-5
W - 5E+1 2E-8 8E-11 - -
86 Radon-220 With daughters removed - 2E+4 7E-6 2E-8 - -
With daughters present - 2E+1 9E-9 3E-11 - -
(or 12 working level months) (or 1.0 working level)
86 Radon-222 With daughters removed - 1E+4 4E-6 1E-8 - -
With daughters present - 1E+2 3E-8 1E-10 - -
(or 4 working level months) (or 0.33 working level)
87 Francium-2222 D, all compounds 2E+3 5E+2 2E-7 6E-10 3E-5 3E-4
87 Francium-2232 D, all compounds 6E+2 8E+2 3E-7 1E-9 8E-6 8E-5
88 Radium-223 W, all compounds 5E+0 7E-1 3E-10 9E-13 - -
Bone surf (9E+0) - - - 1E-7 1E-6
88 Radium-224 W, all compounds 8E+0 2E+0 7E-10 2E-12 - -
Bone surf (2E+1) - - - 2E-7 2E-6
88 Radium-225 W, all compounds 8E+0 7E-1 3E-10 9E-13 - -
Bone surf (2E+1) - - - 2E-7 2E-6
88 Radium-226 W, all compounds 2E+0 6E-1 3E-10 9E-13 - -
Bone surf (5E+0) - - - 6E-8 6E-7
88 Radium-2272 W, all compounds 2E+4 1E+4 6E-6 - - -
Bone surf (2E+4) Bone surf (2E+4) - 3E-8 3E-4 3E-3
88 Radium-228 W, all compounds 2E+0 1E+0 5E-10 2E-12 - -
Bone surf (4E+0) - - - 6E-8 6E-7
89 Actinium-224 D, all compounds except

those given for W and Y

 2E+3 3E+1 1E-8 - - -
LLI wall (2E+3) Bone surf (4E+1) - 5E-11 3E-5 3E-4
W, halides and nitrates - 5E+1 2E-8 7E-11 - -
Y, oxides and hydroxides - 5E+1 2E-8 6E-11 - -
89 Actinium-225 D, see 224Ac 5E+1 3E-1 1E-10 - - -
LLI wall (5E+1) Bone surf (5E-1) - 7E-13 7E-7 7E-6
W, see 224Ac - 6E-1 3E-10 9E-13 - -
Y, see 224Ac - 6E-1 3E-10 9E-13 - -
89 Actinium-226 D, see 224Ac 1E+2 3E+0 1E-9 - - -
LLI wall (1E+2) Bone surf (4E+0) - 5E-12 2E-6 2E-5
W, see 224Ac - 5E+0 2E-9 7E-12 - -
Y, see 224Ac - 5E+0 2E-9 6E-12 - -
89 Actinium-227 D, see 224Ac 2E-1 4E-4 2E-13 - - -
Bone surf (4E-1) Bone surf (8E-4) - 1E-15 5E-9 5E-8
W, see 224Ac - 2E-3 7E-13 - - -
- Bone surf (3E-3) - 4E-15 - -
Y, see 224Ac - 4E-3 2E-12 6E-15 - -
89 Actinium-228 D, see 224Ac 2E+3 9E+0 4E-9 - 3E-5 3E-4
- Bone surf (2E+1) - 2E-11 - -
W, see 224Ac - 4E+1 2E-8 - - -
Bone surf
- (6E+1) - 8E-11 - -
Y, see 224Ac - 4E+1 2E-8 6E-11 - -
90 Thorium-2262 W, all compounds except
those given for Y 5E+3 2E+2 6E-8 2E-10 - -
St wall
(5E+3) - - - 7E-5 7E-4
Y, oxides and hydroxides - 1E+2 6E-8 2E-10 - -
90 Thorium-227 W, see 226Th 1E+2 3E-1 1E-10 5E-13 2E-6 2E-5
Y, see 226Th - 3E-1 1E-10 5E-13 - -
90 Thorium-228 W, see 226Th 6E+0 1E-2 4E-12 - - -
Bone surf

(1E+1)

 Bone surf

(2E-2)

 - 3E-14 2E-7 2E-6
Y, see 226Th - 2E-2 7E-12 2E-14 - -
90 Thorium-229 W, see 226Th 6E-1 9E-4 4E-13 - - -
Bone surf

(1E+0)

 Bone surf

(2E-3)

 - 3E-15 2E-8 2E-7
Y, see 226Th - 2E-3 1E-12 - - -
- Bone surf

(3E-3)

 - 4E-15 - -
90 Thorium-230 W, see 226Th 4E+0 6E-3 3E-12 - - -
Bone surf

(9E+0)

 Bone surf

(2E-2)

 - 2E-14 1E-7 1E-6
Y, see 226Th - 2E-2 6E-12 - - -
- Bone surf

(2E-2)

 - 3E-14 - -
90 Thorium-231 W, see 226Th 4E+3 6E+3 3E-6 9E-9 5E-5 5E-4
Y, see 226Th - 6E+3 3E-6 9E-9 - -
90 Thorium-232 W, see 226Th 7E-1 1E-3 5E-13 - - -
Bone surf

(2E+0)

 Bone surf

(3E-3)

 - 4E-15 3E-8 3E-7
Y, see 226Th - 3E-3 1E-12 - - -
- Bone surf

(4E-3)

 - 6E-15 - -
90 Thorium-234 W, see 226Th 3E+2 2E+2 8E-8 3E-10 - -
LLI wall (4E+2) - - - 5E-6 5E-5
Y, see 226Th - 2E+2 6E-8 2E-10 - -
91 Protactinium-2272 W, all compounds except

those given for Y

 4E+3 1E+2 5E-8 2E-10 5E-5 5E-4
Y, oxides and hydroxides - 1E+2 4E-8 1E-10 - -
91 Protactinium-228 W, see 227Pa 1E+3 1E+1 5E-9 - 2E-5 2E-4
- Bone surf

(2E+1)

 - 3E-11 - -
Y, see 227Pa - 1E+1 5E-9 2E-11 - -
91 Protactinium-230 W, see 227Pa 6E+2 5E+0 2E-9 7E-12 - -
Bone surf

(9E+2)

 - - - 1E-5 1E-4
Y, see 227Pa - 4E+0 1E-9 5E-12 - -
91 Protactinium-231 W, see 227Pa 2E-1 2E-3 6E-13 - - -
Bone surf

(5E-1)

 Bone surf

(4E-3)

 - 6E-15 6E-9 6E-8
Y, see 227Pa - 4E-3 2E-12 - - -
- Bone surf

(6E-3)

 - 8E-15 - -
91 Protactinium-232 W, see 227Pa 1E+3 2E+1 9E-9 - 2E-5 2E-4
- Bone surf

(6E+1)

 - 8E-11 - -
Y, see 227Pa - 6E+1 2E-8 - - -
- Bone surf

(7E+1)

 - 1E-10 - -
91 Protactinium-233 W, see 227Pa 1E+3 7E+2 3E-7 1E-9 - -
LLI wall (2E+3) - - - 2E-5 2E-4
Y, see 227Pa - 6E+2 2E-7 8E-10 - -
91 Protactinium-234 W, see 227Pa 2E+3 8E+3 3E-6 1E-8 3E-5 3E-4
Y, see 227Pa - 7E+3 3E-6 9E-9 - -
92 Uranium-230 D, UF6, UO2F2, UO2(NO3)2 4E+0 4E-1 2E-10 - - -
Bone surf

(6E+0)

 Bone surf

(6E-1)

 - 8E-13 8E-8 8E-7
W, UO3, UF4, UCl4 - 4E-1 1E-10 5E-13 - -
Y, UO2, U3O8 - 3E-1 1E-10 4E-13 - -
92 Uranium-231 D, see 230U 5E+3 8E+3 3E-6 1E-8 - -
LLI wall (4E+3) - - - 6E-5 6E-4
W, see 230U - 6E+3 2E-6 8E-9 - -
Y, see 230U - 5E+3 2E-6 6E-9 - -
92 Uranium-232 D, see 230U 2E+0 2E-1 9E-11 - - -
Bone surf

(4E+0)

 Bone surf

(4E-1)

 - 6E-13 6E-8 6E-7
W, see 230U - 4E-1 2E-10 5E-13 - -
Y, see 230U - 8E-3 3E-12 1E-14 - -
92 Uranium-233 D, see 230U 1E+1 1E+0 5E-10 - - -
Bone surf

(2E+1)

 Bone surf

(2E+0)

 - 3E-12 3E-7 3E-6
W, see 230U - 7E-1 3E-10 1E-12 - -
Y, see 230U - 4E-2 2E-11 5E-14 - -
92 Uranium-2343 D, see 230U 1E+1 1E+0 5E-10 - - -
Bone surf

(2E+1)

 Bone surf

(2E+0)

 - 3E-12 3E-7 3E-6
W, see 230U - 7E-1 3E-10 1E-12 - -
Y, see 230U - 4E-2 2E-11 5E-14 - -
92 Uranium-2353 D, see 230U 1E+1 1E+0 6E-10 - - -
Bone surf

(2E+1)

 Bone surf (2E+0) - 3E-12 3E-7 3E-6
W, see 230U - 8E-1 3E-10 1E-12 - -
Y, see 230U - 4E-2 2E-11 6E-14 - -
92 Uranium-236 D, see 230U 1E+1 1E+0 5E-10 - - -
Bone surf (2E+1) Bone surf (2E+0) - 3E-12 3E-7 3E-6
W, see 230U - 8E-1 3E-10 1E-12 - -
Y, see 230U - 4E-2 2E-11 6E-14 - -
92 Uranium-237 D, see 230U 2E+3 3E+3 1E-6 4E-9 - -
LLI wall (2E+3) - - - 3E-5 3E-4
W, see 230U - 2E+3 7E-7 2E-9 - -
Y, see 230U - 2E+3 6E-7 2E-9 - -
92 Uranium-2383 D, see 230U 1E+1 1E+0 6E-10 - - -
Bone surf (2E+1) Bone surf

(2E+0)

 - 3E-12 3E-7 3E-6
W, see 230U - 8E-1 3E-10 1E-12 - -
Y, see 230U - 4E-2 2E-11 6E-14 - -
92 Uranium-2392 D, see 230U 7E+4 2E+5 8E-5 3E-7 9E-4 9E-3
W, see 230U - 2E+5 7E-5 2E-7 - -
Y, see 230U - 2E+5 6E-5 2E-7 - -
92 Uranium-240 D, see 230U 1E+3 4E+3 2E-6 5E-9 2E-5 2E-4
W, see 230U - 3E+3 1E-6 4E-9 - -
Y, see 230U - 2E+3 1E-6 3E-9 - -
92 Uranium-natural3 D, see 230U 1E+1 1E+0 5E-10 - - -
Bone surf

(2E+1)

 Bone surf

(2E+0)

 - 3E-12 3E-7 3E-6
W, see 230U - 8E-1 3E-10 9E-13 - -
Y, see 230U - 5E-2 2E-11 9E-14 - -
93 Neptunium-2322 W, all compounds 1E+5 2E+3 7E-7 - 2E-3 2E-2
- Bone surf

(5E+2)

 - 6E-9 - -
93 Neptunium-2332 W, all compounds 8E+5 3E+6 1E-3 4E-6 1E-2 1E-1
93 Neptunium-234 W, all compounds 2E+3 3E+3 1E-6 4E-9 3E-5 3E-4
93 Neptunium-235 W, all compounds 2E+4 8E+2 3E-7 - - -
LLI wall (2E+4) Bone surf

(1E+3)

 - 2E-9 3E-4 3E-3
93 Neptunium-236 W, all compounds 3E+0 2E-2 9E-12 - - -
(1.15E+5 y) Bone surf

(6E+0)

 Bone surf

(5E-2)

 - 8E-14 9E-8 9E-7
93 Neptunium-236 W, all compounds 3E+3 3E+1 1E-8 - - -
(22.5 h) Bone surf

(4E+3)

 Bone surf

(7E+1)

 - 1E-10 5E-5 5E-4
93 Neptunium-237 W, all compounds 5E-1 4E-3 2E-12 - - -
Bone surf

(1E+0)

 Bone surf

(1E-2)

 - 1E-14 2E-8 2E-7
93 Neptunium-238 W, all compounds 1E+3 6E+1 3E-8 - 2E-5 2E-4
- Bone surf

(2E+2)

 - 2E-10 - -
93 Neptunium-239 W, all compounds 2E+3 2E+3 9E-7 3E-9 - -
LLI wall (2E+3) - - - 2E-5 2E-4
93 Neptunium-2402 W, all compounds 2E+4 8E+4 3E-5 1E-7 3E-4 3E-3
94 Plutonium-234 W, all compounds

except PuO2

 8E+3 2E+2 9E-8 3E-10 1E-4 1E-3
Y, PuO2 - 2E+2 8E-8 3E-10 - -
94 Plutonium-2352 W, see 234Pu 9E+5 3E+6 1E-3 4E-6 1E-2 1E-1
Y, see 234Pu - 3E+6 1E-3 3E-6 - -
94 Plutonium-236 W, see 234Pu 2E+0 2E-2 8E-12 - - -
Bone surf

(4E+0)

 Bone surf

(4E-2)

 - 5E-14 6E-8 6E-7
Y, see 234Pu - 4E-2 2E-11 6E-14 - -
94 Plutonium-237 W, see 234Pu 1E+4 3E+3 1E-6 5E-9 2E-4 2E-3
Y, see 234Pu - 3E+3 1E-6 4E-9 - -
94 Plutonium-238 W, see 234Pu 9E-1 7E-3 3E-12 - - -
Bone surf

(2E+0)

 Bone surf

(1E-2)

 - 2E-14 2E-8 2E-7
Y, see 234Pu - 2E-2 8E-12 2E-14 - -
94 Plutonium-239 W, see 234Pu 8E-1 6E-3 3E-12 - - -
Bone surf

(1E+0)

 Bone surf

(1E-2)

 - 2E-14 2E-8 2E-7
Y, see 234Pu - 2E-2 7E-12 - - -
- Bone surf

(2E-2)

 - 2E-14 - -
94 Plutonium-240 W, see 234Pu 8E-1 6E-3 3E-12 - - -
Bone surf

(1E+0)

 Bone surf

(1E-2)

 - 2E-14 2E-8 2E-7
Y, see 234Pu - 2E-2 7E-12 - - -
- Bone surf

(2E-2)

 - 2E-14 - -
94 Plutonium-241 W, see 234Pu 4E+1 3E-1 1E-10 - - -
Bone surf

(7E+1)

 Bone surf

(6E-1)

-

8E-13

1E-6

1E-5
Y, see 234Pu - 8E-1 3E-10 - - -
- Bone surf

(1E+0)

 - 1E-12 - -
94 Plutonium-242 W, see 234Pu 8E-1 7E-3 3E-12 - - -
Bone surf

(1E+0)

 Bone surf

(1E-2)

 - 2E-14 2E-8 2E-7
Y, see 234Pu - 2E-2 7E-12 - - -
- Bone surf

(2E-2)

 - 2E-14 - -
94 Plutonium-243 W, see 234Pu 2E+4 4E+4 2E-5 5E-8 2E-4 2E-3
Y, see 234Pu - 4E+4 2E-5 5E-8 - -
94 Plutonium-244 W, see 234Pu 8E-1 7E-3 3E-12 - - -
Bone surf

(2E+0)

 Bone surf

(1E-2)

 - 2E-14 2E-8 2E-7
Y, see 234Pu - 2E-2 7E-12 - - -
- Bone surf

(2E-2)

 - 2E-14 - -
94 Plutonium-245 W, see 234Pu 2E+3 5E+3 2E-6 6E-9 3E-5 3E-4
Y, see 234Pu - 4E+3 2E-6 6E-9 - -
94 Plutonium-246 W, see 234Pu 4E+2 3E+2 1E-7 4E-10 - -
LLI wall (4E+2) - - - 6E-6 6E-5
Y, see 234Pu - 3E+2 1E-7 4E-10 - -
95 Americium-2372 W, all compounds 8E+4 3E+5 1E-4 4E-7 1E-3 1E-2
95 Americium-2382 W, all compounds 4E+4 3E+3 1E-6 - 5E-4 5E-3
- Bone surf

(6E+3)

 - 9E-9 - -
95 Americium-239 W, all compounds 5E+3 1E+4 5E-6 2E-8 7E-5 7E-4
95 Americium-240 W, all compounds 2E+3 3E+3 1E-6 4E-9 3E-5 3E-4
95 Americium-241 W, all compounds 8E-1 6E-3 3E-12 - - -
Bone surf

(1E+0)

 Bone surf

(1E-2)

 - 2E-14 2E-8 2E-7
95 Americium-242m W, all compounds 8E-1 6E-3 3E-12 - - -
Bone surf

(1E+0)

 Bone surf

(1E-2)

 - 2E-14 2E-8 2E-7
95 Americium-242 W, all compounds 4E+3 8E+1 4E-8 - 5E-5 5E-4
- Bone surf

(9E+1)

 - 1E-10 - -
95 Americium-243 W, all compounds 8E-1 6E-3 3E-12 - - -
Bone surf

(1E+0)

 Bone surf

(1E-2)

 - 2E-14 2E-8 2E-7
95 Americium-244m2 W, all compounds 6E+4 4E+3 2E-6 - - -
St wall

(8E+4)

 Bone surf

(7E+3)

 - 1E-8 1E-3 1E-2
95 Americium-244 W, all compounds 3E+3 2E+2 8E-8 - 4E-5 4E-4
- Bone surf

(3E+2)

 - 4E-10 - -
95 Americium-245 W, all compounds 3E+4 8E+4 3E-5 1E-7 4E-4 4E-3
95 Americium-246m2 W, all compounds 5E+4 2E+5 8E-5 3E-7 - -
St wall

(6E+4)

 - - - 8E-4 8E-3
95 Americium-2462 W, all compounds 3E+4 1E+5 4E-5 1E-7 4E-4 4E-3
96 Curium-238 W, all compounds 2E+4 1E+3 5E-7 2E-9 2E-4 2E-3
96 Curium-240 W, all compounds 6E+1 6E-1 2E-10 - - -
Bone surf

(8E+1)

 Bone surf

(6E-1)

 - 9E-13 1E-6 1E-5
96 Curium-241 W, all compounds 1E+3 3E+1 1E-8 - 2E-5 2E-4
- Bone surf

(4E+1)

 - 5E-11 - -
96 Curium-242 W, all compounds 3E+1 3E-1 1E-10 - - -
Bone surf

(5E+1)

 Bone surf

(3E-1)

 - 4E-13 7E-7 7E-6
96 Curium-243 W, all compounds 1E+0 9E-3 4E-12 - - -
Bone surf

(2E+0)

 Bone surf

(2E-2)

 - 2E-14 3E-8 3E-7
96 Curium-244 W, all compounds 1E+0 1E-2 5E-12 - - -
Bone surf

(3E+0)

 Bone surf

(2E-2)

 - 3E-14 3E-8 3E-7
96 Curium-245 W, all compounds 7E-1 6E-3 3E-12 - - -
Bone surf

(1E+0)

 Bone surf

(1E-2)

 - 2E-14 2E-8 2E-7
96 Curium-246 W, all compounds 7E-1 6E-3 3E-12 - - -
Bone surf

(1E+0)

 Bone surf

(1E-2)

 - 2E-14 2E-8 2E-7
96 Curium-247 W, all compounds 8E-1 6E-3 3E-12 - - -
Bone surf

(1E+0)

 Bone surf

(1E-2)

 - 2E-14 2E-8 2E-7
96 Curium-248 W, all compounds 2E-1 2E-3 7E-13 - - -
Bone surf

(4E-1)

 Bone surf

(3E-3)

 - 4E-15 5E-9 5E-8
96 Curium-2492 W, all compounds 5E+4 2E+4 7E-6 - 7E-4 7E-3
- Bone surf

(3E+4)

 - 4E-8 - -
96 Curium-250 W, all compounds 4E-2 3E-4 1E-13 - - -
Bone surf

(6E-2)

 Bone surf

(5E-4)

 - 8E-16 9E-10 9E-9
97 Berkelium-245 W, all compounds 2E+3 1E+3 5E-7 2E-9 3E-5 3E-4
97 Berkelium-246 W, all compounds 3E+3 3E+3 1E-6 4E-9 4E-5 4E-4
97 Berkelium-247 W, all compounds 5E-1 4E-3 2E-12 - - -
Bone surf

(1E+0)

 Bone surf

(9E-3)

 - 1E-14 2E-8 2E-7
97 Berkelium-249 W, all compounds 2E+2 2E+0 7E-10 - - -
Bone surf

(5E+2)

 Bone surf

(4E+0)

 - 5E-12 6E-6 6E-5
97 Berkelium-250 W, all compounds 9E+3 3E+2 1E-7 - 1E-4 1E-3
- Bone surf

(7E+2)

 - 1E-9 - -
98 Californium-2442 W, all compounds except

those given for Y

 3E+4 6E+2 2E-7 8E-10 - -
St wall

(3E+4)

 - - - 4E-4 4E-3
Y, oxides and hydroxides - 6E+2 2E-7 8E-10 - -
98 Californium-246 W, see 244Cf 4E+2 9E+0 4E-9 1E-11 5E-6 5E-5
Y, see 244Cf - 9E+0 4E-9 1E-11 - -
98 Californium-248 W, see 244Cf 8E+0 6E-2 3E-11 - - -
Bone surf

(2E+1)

 Bone surf

(1E-1)

 - 2E-13 2E-7 2E-6
Y, see 244Cf - 1E-1 4E-11 1E-13 - -
98 Californium-249 W, see 244Cf 5E-1 4E-3 2E-12 - - -
Bone surf

(1E+0)

 Bone surf

(9E-3)

 - 1E-14 2E-8 2E-7
Y, see 244Cf - 1E-2 4E-12 - - -
- Bone surf

(1E-2)

 - 2E-14 - -
98 Californium-250 W, see 244Cf 1E+0 9E-3 4E-12 - - -
Bone surf

(2E+0)

 Bone surf

(2E-2)

 - 3E-14 3E-8 3E-7
Y, see 244Cf - 3E-2 1E-11 4E-14 - -
98 Californium-251 W, see 244Cf 5E-1 4E-3 2E-12 - - -
Bone surf

(1E+0)

 Bone surf

(9E-3)

 - 1E-14 2E-8 2E-7
Y, see 244Cf - 1E-2 4E-12 - - -
- Bone surf

(1E-2)

 - 2E-14 - -
98 Californium-252 W, see 244Cf 2E+0 2E-2 8E-12 - - -
Bone surf

(5E+0)

 Bone surf

(4E-2)

 - 5E-14 7E-8 7E-7
Y, see 244Cf - 3E-2 1E-11 5E-14 - -
98 Californium-253 W, see 244Cf 2E+2 2E+0 8E-10 3E-12 - -
Bone surf

(4E+2)

 - - - 5E-6 5E-5
Y, see 244Cf - 2E+0 7E-10 2E-12 - -
98 Californium-254 W, see 244Cf 2E+0 2E-2 9E-12 3E-14 3E-8 3E-7
Y, see 244Cf - 2E-2 7E-12 2E-14 - -
99 Einsteinium-250 W, all compounds 4E+4 5E+2 2E-7 - 6E-4 6E-3
- Bone surf

(1E+3)

 - 2E-9 - -
99 Einsteinium-251 W, all compounds 7E+3 9E+2 4E-7 - 1E-4 1E-3
- Bone surf

(1E+3)

 - 2E-9 - -
99 Einsteinium-253 W, all compounds 2E+2 1E+0 6E-10 2E-12 2E-6 2E-5
99 Einsteinium-254m W, all compounds 3E+2 1E+1 4E-9 1E-11 - -
LLI wall (3E+2) - - - 4E-6 4E-5
99 Einsteinium-254 W, all compounds 8E+0 7E-2 3E-11 - - -
Bone surf

(2E+1)

 Bone surf

(1E-1)

 - 2E-13 2E-7 2E-6
100 Fermium-252 W, all compounds 5E+2 1E+1 5E-9 2E-11 6E-6 6E-5
100 Fermium-253 W, all compounds 1E+3 1E+1 4E-9 1E-11 1E-5 1E-4
100 Fermium-254 W, all compounds 3E+3 9E+1 4E-8 1E-10 4E-5 4E-4
100 Fermium-255 W, all compounds 5E+2 2E+1 9E-9 3E-11 7E-6 7E-5
100 Fermium-257 W, all compounds 2E+1 2E-1 7E-11 - - -
Bone surf

(4E+1)

 Bone surf

(2E-1)

 - 3E-13 5E-7 5E-6
101 Mendelevium-257 W, all compounds 7E+3 8E+1 4E-8 - 1E-4 1E-3
- Bone surf

(9E+1)

 - 1E-10 - -
101 Mendelevium-258 W, all compounds 3E+1 2E-1 1E-10 - - -
Bone surf

(5E+1)

 Bone surf

(3E-1)

 - 5E-13 6E-7 6E-6
- Any single radionuclide not listed above with decay mode other than alpha emission or spontaneous fission and with radioactive half-life less than 2 hours Submersion1 - 2E+2 1E-7 1E-9 - -
- Any single radionuclide not listed above with decay mode other than alpha emission or ((spontaeneous)) spontaneous fission and with radioactive half-life less than 2 hours . . . . - 2E-1 1E-10 1E-12 1E-8 1E-7
- Any single radionuclide not listed above that decays by alpha emission or ((spontaeneous)) spontaneous fission, or any mixture for which either the identity or the concentration of any radionuclide in the mixture is not known
 . . . .
-
 4E-4
 2E-13
 1E-15
 2E-9
 2E-8

FOOTNOTES:

1"Submersion" means that values given are for submersion in a hemispherical semi-infinite cloud of airborne material.


2These radionuclides have radiological half-lives of less than 2 hours. The total effective dose equivalent received during operations with these radionuclides might include a significant contribution from external exposure. The DAC values for all radionuclides, other than those designated Class "Submersion," are based upon the committed effective dose equivalent due to the intake of the radionuclide into the body and do NOT include potentially significant contributions to dose equivalent from external exposures. The licensee may substitute 1E-7 µCi/ml for the listed DAC to account for the submersion dose prospectively, but should use individual monitoring devices or other radiation measuring instruments that measure external exposure to demonstrate compliance with the limits. (See WAC 246-221-015(5).)


3For soluble mixtures of U-238, U-234, and U-235 in air, chemical toxicity may be the limiting factor (see WAC 246-221-010(5)). If the percent by weight (enrichment) of U-235 is not greater than 5, the concentration value for a 40-hour workweek is 0.2 milligrams uranium per cubic meter of air average. For any enrichment, the product of the average concentration and time of exposure during a 40-hour workweek shall not exceed 8E-3 (SA) µCi-hr/ml, where SA is the specific activity of the uranium inhaled. The specific activity for natural uranium is 6.77E-7 curies per gram U. The specific activity for other mixtures of U-238, U-235, and U-234, if not known, shall be:


     SA = 3.6E-7 curies/gram U, U-depleted


     SA = [0.4 + 0.38 (enrichment) + 0.0034 (enrichment)2] E-6, enrichment ≥ 0.72


where enrichment is the percentage by weight of U-235, expressed as percent.


NOTE:

1.     If the identity of each radionuclide in a mixture is known but the concentration of one or more of the radionuclides in the mixture is not

     known, the DAC for the mixture shall be the most restrictive DAC of any radionuclide in the mixture.


2.     If the identity of each radionuclide in the mixture is not known, but it is known that certain radionuclides specified in this appendix are

     not present in the mixture, the inhalation ALI, DAC, and effluent and sewage concentrations for the mixture are the lowest values

     specified in this appendix for any radionuclide that is not known to be absent from the mixture; or

If it is known that Ac-227-D and Cm-250-W are not present    
-
7E-4
3E-13
-
-
-
If, in addition, it is known that Ac-227-W,Y, Th-229-W,Y, Th-230-W, Th-232-W,Y, Pa-231-W,Y, Np-237-W, Pu-239-W, Pu-240-W, Pu-242-W, Am-241-W, Am-242m-W, Am-243-W, Cm-245-W, Cm-246-W, Cm-247-W, Cm-248-W, Bk-247-W, Cf-249-W, and Cf-251-W are not present

-

7E-3

3E-12

-

-

-
If, in addition, it is known that Sm-146-W, Sm-147-W, Gd-148-D,W, Gd-152-D,W, Th-228-W,Y, Th-230-Y, U-232-Y, U-233-Y, U-234-Y, U-235-Y, U-236-Y, U-238-Y, Np-236-W, Pu-236-W,Y, Pu-238-W,Y, Pu-239-Y, Pu-240-Y, Pu-242-Y, Pu-244-W,Y, Cm-243-W, Cm-244-W, Cf-248-W, Cf-249-Y, Cf-250-W,Y, Cf-251-Y, Cf-252-W,Y, and Cf-254-W,Y are not present

-

7E-2

3E-11

-    

-    

-
If, in addition, it is known that Pb-210-D, Bi-210m-W, Po-210-D,W, Ra-223-W, Ra-225-W, Ra-226-W, Ac-225-D,W,Y, Th-227-W,Y, U-230-D,W,Y, U-232-D,W, Pu-241-W, Cm-240-W, Cm-242-W, Cf-248-Y, Es-254-W, Fm-257-W, and Md-258-W are not present

-

7E-1

3E-10

-

-

-
If, in addition, it is known that Si-32-Y, Ti-44-Y, Fe-60-D, Sr-90-Y, Zr-93-D, Cd-113m-D, Cd-113-D, In-115-D,W, La-138-D, Lu-176-W, Hf-178m-D,W, Hf-182-D,W, Bi-210m-D, Ra-224-W, Ra-228-W, Ac-226-D,W,Y, Pa-230-W,Y, U-233-D,W, U-234-D,W, U-235-D,W, U-236-D,W, U-238-D,W, Pu-241-Y, Bk-249-W, Cf-253-W,Y, and Es-253-W are not present

-

7E+0

3E-9

-

-

-
If it is known that Ac-227-D,W,Y, Th-229-W,Y, Th-232-W,Y, Pa-231-W,Y, Cm-248-W, and Cm-250-W are not present

-

-

-

1E-14

-

-
If, in addition, it is known that Sm-146-W, Gd-148-D,W, Gd-152-D, Th-228-W,Y, Th-230-W,Y, U-232-Y, U-233-Y, U-234-Y, U-235-Y, U-236-Y, U-238-Y, U-Nat-Y, Np-236-W, Np-237-W, Pu-236-W,Y, Pu-238-W,Y, Pu-239-W,Y, Pu-240-W,Y, Pu-242-W,Y, Pu-244-W,Y, Am-241-W, Am-242m-W, Am-243-W, Cm-243-W, Cm-244-W, Cm-245-W, Cm-246-W, Cm-247-W, Bk-247-W, Cf-249-W,Y, Cf-250-W,Y, Cf-251-W,Y, Cf-252-W,Y, and Cf-254-W,Y are not present

-

-

-

1E-13

-

-
If, in addition, it is known that Sm-147-W, Gd-152-W, Pb-210-D, Bi-210m-W, Po-210-D,W, Ra-223-W, Ra-225-W, Ra-226-W, Ac-225-D,W,Y, Th-227-W,Y, U-230-D,W,Y, U-232-D,W, U-Nat-W, Pu-241-W, Cm-240-W, Cm-242-W, Cf-248-W,Y, Es-254-W, Fm-257-W, and Md-258-W are not present

-

-

-

-

1E-12

-
If, in addition, it is known that Fe-60, Sr-90, Cd-113m, Cd-113, In-115, I-129, Cs-134, Sm-145, Sm-147, Gd-148, Gd-152, Hg-194 (organic), Bi-210m, Ra-223, Ra-224, Ra-225, Ac-225, Th-228, Th-230, U-233, U-234, U-235, U-236, U-238, U-Nat, Cm-242, Cf-248, Es-254, Fm-257, and Md-258 are not present

-

-

-

-

1E-6

1E-5

3.     If a mixture of radionuclides consists of uranium and its daughters in ore dust (10 µm AMAD particle distribution assumed) prior to

     chemical separation of the uranium from the ore, the following values may be used for the DAC of the mixture: 6E-11 µCi of gross

     alpha activity from uranium-238, uranium-234, thorium-230, and radium-226 per milliliter of air; 3E-11 µCi of natural uranium per

     milliliter of air; or 45 micrograms of natural uranium per cubic meter of air.


4.     If the identity and concentration of each radionuclide in a mixture are known, the limiting values should be derived as follows:

     Determine, for each radionuclide in the mixture, the ratio between the concentration present in the mixture and the concentration

     otherwise established in this section for the specific radionuclide when not in a mixture. The sum of such ratios for all of the

     radionuclides in the mixture may not exceed "1" (i.e., "unity").


     Example: If radionuclides "A," "B," and "C" are present in concentrations CA, CB, and CC, and if the applicable DACs are DACA,

     DACB, and DACC, respectively, then the concentrations shall be limited so that the following relationship exists:
CA

+

 CB

+

 CC

≤1
DACA DACB DACC

[Statutory Authority: RCW 70.98.050. 94-01-073, § 246-221-290, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 43.70 040. 91-02-049 (Order 121), recodified as § 246-221-290, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-24-220, filed 12/8/80; Order 1095, § 402-24-220, filed 2/6/76; Order 1, § 402-24-220, filed 1/8/69; Rules (part), filed 10/26/66.]

     Reviser's note: The brackets and enclosed material in the text of the above section occurred in the copy filed by the agency and appear in the Register pursuant to the requirements of RCW 34.08.040.

OTS-1822.1


AMENDATORY SECTION(Amending WSR 01-02-068, filed 12/29/00, effective 1/29/01)

WAC 246-232-006   Exemption of certain source material.   (1) A person is exempt from this chapter and chapters 246-233 and 246-235 WAC to the extent that the person receives, possesses, uses, owns, or transfers source material in any chemical mixture, compound, solution or alloy in which the source material is by weight less than 1/20 of one percent (0.05 percent) of the mixture, compound, solution, or alloy.

     (2) A person is exempt from this chapter and chapters 246-233 and 246-235 WAC to the extent that the person receives, possesses, uses or transfers unrefined and unprocessed ore containing source material, provided such person shall not refine or process such ore unless authorized to do so in a specific license.

     (3) A person is exempt from this chapter and chapters 246-233 and 246-235 WAC to the extent that the person receives, possesses, uses or transfers:

     (a) Any quantities of thorium contained in:

     (i) Incandescent gas mantles;

     (ii) Vacuum tubes;

     (iii) Welding rods;

     (iv) Electric lamps for illuminating purposes if each lamp contains fifty milligrams or less of thorium;

     (v) Germicidal lamps, sunlamps and lamps for outdoor or industrial lighting if each lamp contains two grams or less of thorium;

     (vi) Rare earth metals and compounds, mixtures, and products containing 0.25 percent or less by weight thorium, uranium, or any combination of these; or

     (vii) Personnel neutron dosimeters if each dosimeter contains 1.85 gigabecquerels (50 milligrams) or less of thorium;

     (b) Source material contained in the following products:

     (i) Glazed ceramic tableware if the glaze contains twenty percent or less by weight source material; and

     (ii) Piezoelectric ceramic containing two percent or less by weight source material;

     (c) Photographic film, negatives and prints containing uranium or thorium;

     (d) Any finished product or part fabricated of, or containing, tungsten-thorium or magnesium-thorium alloys if the thorium content of the alloy is four percent or less by weight. The exemption contained in this subparagraph shall not be deemed to authorize the chemical, physical or metallurgical treatment or processing of any such product or part;

     (e) Thorium contained in finished optical lenses if each lens contains thirty percent or less by weight of thorium. The exemption contained in this subparagraph shall not be deemed to authorize either:

     (i) The shaping, grinding or polishing of lens or manufacturing processes other than the assembly of such lens into optical systems and devices without alteration of the lens; or

     (ii) The receipt, possession, use or transfer of thorium contained in contact lenses, or in spectacles, or in eyepieces in binoculars or other optical instruments;

     (f) Uranium contained in detector heads for use in fire detection units if each detector head contains 185 becquerels (0.005 microcuries) or less of uranium; or

     (g) Thorium contained in any finished aircraft engine part containing nickel-thoria alloy if:

     (i) The thorium is dispersed in the nickel-thoria alloy in the form of finely divided thoria (thorium dioxide); and

     (ii) The thorium content in the nickel-thoria alloy is four percent or less by weight.

     (4) The exemptions in subsection (3) of this section do not authorize the manufacture of any of the products described.

[Statutory Authority: RCW 70.98.050. 01-02-068, § 246-232-006, filed 12/29/00, effective 1/29/01.]


AMENDATORY SECTION(Amending WSR 01-02-068, filed 12/29/00, effective 1/29/01)

WAC 246-232-008   Exemption of certain timepieces, hands or dials.   A person is exempt from these regulations to the extent the person receives, possesses, uses, transfers, owns or acquires, and does not apply radioactive material to, or incorporate radioactive material into, the following timepieces or hands or dials containing the following specified quantities of radioactive material and the following specified levels of radiation*:

*Note: Authority to transfer possession or control by the manufacturer, processor, or producer of any equipment, device, commodity, or other product containing source material or by-product material whose subsequent possession, use, transfer and disposal by all other persons who are exempted from regulatory requirements may be obtained only from the United States Nuclear Regulatory Commission, Washington, D.C. 20555.

     (1)(a) 925 megabecquerels (25 millicuries) or less of tritium per timepiece;

     (b) 185 megabecquerels (5 millicuries) or less of tritium per hand;

     (c) 555 megabecquerels (15 millicuries) or less of tritium per dial (bezels when used shall be considered as part of the dial);

     (d) 3.7 megabecquerels (100 microcuries) or less of promethium-147 per watch or 7.4 megabecquerels (200 microcuries) or less of promethium-147 per any other timepiece;

     (e) 740 kilobecquerels (20 microcuries) or less of promethium-147 per watch hand or 1.48 megabecquerels (40 microcuries) or less of promethium-147 per other timepiece hand;

     (f) 2.22 megabecquerels (60 microcuries) or less of promethium-147 per watch dial or 4.44 megabecquerels (120 microcuries) or less of promethium-147 per other timepiece dial (bezels when used shall be considered as part of the dial);

     (2) The levels of radiation from hands and dials containing promethium-147 will not exceed, when measured through 50 milligrams per square centimeter of absorber:

     (a) For wrist watches, 1 microgray (0.1 millirad) per hour at 10 centimeters from any surface;

     (b) For pocket watches, 1 microgray (0.1 millirad) per hour at 1 centimeter from any surface;

     (c) For any other timepiece, 2 micrograys (0.2 millirad) per hour at 10 centimeters from any surface.

     (3) ((One)) 37 kilobecquerels (1 microcurie) of radium-226 per timepiece in timepieces manufactured prior to the effective date of these regulations.

[Statutory Authority: RCW 70.98.050. 01-02-068, § 246-232-008, filed 12/29/00, effective 1/29/01.]


AMENDATORY SECTION(Amending WSR 01-02-068, filed 12/29/00, effective 1/29/01)

WAC 246-232-009   Exemption of certain items containing radioactive material.   A person is exempt from these regulations to the extent the person receives, possesses, uses, transfers, owns or acquires, and does not apply radioactive material to, or incorporate radioactive material into, the following products:*


*Note: Authority to transfer possession or control by the manufacturer, processor, or producer of any equipment, device, commodity, or other product containing source material or by-product material whose subsequent possession, use, transfer and disposal by all other persons who are exempted from regulatory requirements may be obtained only from the United States Nuclear Regulatory Commission, Washington, D.C. 20555.

     (1) Lock illuminators containing 555 megabecquerels (15 millicuries) or less of tritium or 74 megabecquerels (2 millicuries) or less of promethium-147 installed in automobile locks. The levels of radiation from each lock illuminator containing promethium-147 will not exceed 10 micrograys (1 millirad) per hour at 1 centimeter from any surface when measured through 50 milligrams per square centimeter of absorber.

     (2) Precision balances containing 37 megabecquerels (1 millicurie) or less of tritium per balance or 18.5 megabecquerels (0.5 millicurie) or less of tritium per balance part.

     (3) Automobile shift quadrants containing 925 megabecquerels (25 millicuries) or less of tritium.

     (4) Marine compasses containing 27.8 gigabecquerels (750 millicuries) or less of tritium gas and other marine navigational instruments containing 9.25 gigabecquerels (250 millicuries) or less of tritium gas.

     (5) Thermostat dials and pointers containing 925 megabecquerels (25 millicuries) or less of tritium per thermostat.

     (6) Electron tubes* if each tube contains no more than one of the following specified quantities of radioactive material and the levels of radiation from each electron tube do not exceed 10 micrograys (1 millirad) per hour at 1 centimeter from any surface when measured through 7 milligrams per square centimeter of absorber:

     (a) 5.55 gigabecquerels (150 millicuries) or less of tritium per microwave receiver protector tube or 370 megabecquerels (10 millicuries) or less of tritium per any other electron tube;

     (b) 37 kilobecquerels (1 microcurie) or less of cobalt-60;

     (c) 185 kilobecquerels (5 microcuries) or less of nickel-63;

     (d) 1.11 megabecquerels (30 microcuries) or less of krypton-85;

     (e) 185 kilobecquerels (5 microcuries) or less of cesium-137;

     (f) 1.11 megabecquerels (30 microcuries) or less of promethium-147;

     (g) 37 kilobecquerels (1 microcurie) or less of radium-226:


*Note: For purposes of this subdivision, "electron tubes" include spark gap tubes, power tubes, gas tubes including glow lamps, receiving tubes, microwave tubes, indicator tubes, pick-up tubes, radiation detection tubes, and any other completely sealed tube that is designed to conduct or control electrical currents.

     (7) Ionizing radiation measuring instruments containing, for purposes of internal calibration or standardization, one or more but not to exceed 10 exempt sources of radioactive material.

     (a) Each individual source shall not exceed 1.85 kilobecquerels (0.05 microcuries) of americium-241 or the applicable exempt quantity set forth in WAC 246-232-120, Schedule B.

     (b) An individual source may contain more than one radionuclide but the total quantity in the individual source shall not exceed unity based on the sum of the fractional parts of one or more of the exempt quantities set forth in WAC 246-232-120, Schedule B. For purposes of this subsection, 1.85 kilobecquerels (0.05 microcuries) of americium-241 is considered an exempt quantity.

     (8) Spark gap irradiators containing 37 kilobecquerels (1 microcurie) or less of cobalt-60 per spark gap irradiator for use in electrically ignited fuel oil burners having a firing rate of at least three gallons (11.4 liters) per hour.

[Statutory Authority: RCW 70.98.050. 01-02-068, § 246-232-009, filed 12/29/00, effective 1/29/01.]


AMENDATORY SECTION(Amending WSR 01-02-068, filed 12/29/00, effective 1/29/01)

WAC 246-232-011   Exemption of certain self-luminous products containing radioactive material(s).   (1) Tritium, krypton-85 or promethium-147. A person is exempt from these regulations to the extent that the person receives, possesses, uses, transfers, owns or acquires, and does not manufacture, process, produce, or initially transfer for sale or distribution, self-luminous products containing tritium, krypton-85 or promethium-147 in self-luminous products manufactured, processed, produced, imported or initially transferred in accordance with a specific license issued by the United States Nuclear Regulatory Commission under Section 32.22 of 10 C.F.R. Part 32, which license authorizes the transfer of the product to persons who are exempt from regulatory requirements. The exemption in this subsection does not apply to tritium, krypton-85 or promethium-147 used in products primarily for frivolous purposes or in toys or adornments.

     (2) Radium-226. A person is exempt from these regulations to the extent that the person receives, possesses, uses, transfers or owns articles containing less than 3.7 kilobecquerels (0.1 microcurie) of radium-226 which were manufactured prior to October 1983.

[Statutory Authority: RCW 70.98.050. 01-02-068, § 246-232-011, filed 12/29/00, effective 1/29/01.]


AMENDATORY SECTION(Amending WSR 01-02-068, filed 12/29/00, effective 1/29/01)

WAC 246-232-120   Schedule B, exempt quantities of radioactive materials.   (See also WAC 246-232-010(2).)


Radioactive Material Microcuries
Antimony-122 (Sb-122) 100
Antimony-124 (Sb-124) 10
Antimony-125 (Sb-125) 10
Arsenic-73 (As-73) 100
Arsenic-74 (As-74) 10
Arsenic-76 (As-76) 10
Arsenic-77 (As-77) 100
Barium-131 (Ba-131) 10
Barium-133 (Ba-133) 10
Barium-140 (Ba-140) 10
Bismuth-210 (Bi-210) 1
Bromine-82 (Br-82) 10
Cadmium-109 (Cd-109) 10
Cadmium-115m (Cd-115m) 10
Cadmium-115 (Cd-115) 100
Calcium-45 (Ca-45) 10
Calcium-47 (Ca-47) 10
Carbon-14 (C-14) 100
Cerium-141 (Ce-141) 100
Cerium-143 (Ce-143) 100
Cerium-144 (Ce-144) 1
Cesium-129 (Cs-129) 100
Cesium-131 (Cs-131) 1,000
Cesium-134m (Cs-134m) 100
Cesium-134 (Cs-134) 1
Cesium-135 (Cs-135) 10
Cesium-136 (Cs-136) 10
Cesium-137 (Cs-137) 10
Chlorine-36 (Cl-36) 10
Chlorine-38 (Cl-38) 10
Chromium-51 (Cr-51) 1,000
Cobalt-57 (Co-57) 100
Cobalt-58m (Co-58m) 10
Cobalt-58 (Co-58) 10
Cobalt-60 (Co-60) 1
Copper-64 (Cu-64) 100
Dysprosium-165 (Dy-165) 10
Dysprosium-166 (Dy-166) 100
Erbium-169 (Er-169) 100
Erbium-171 (Er-171) 100
Europium-152 (Eu-152) 9.2h 100
Europium-152 (Eu-152) 13 yr 1
Europium-154 (Eu-154) 1
Europium-155 (Eu-155) 10
Fluorine-18 (F-18) 1,000
Gadolinium-153 (Gd-153) 10
Gadolinium-159 (Gd-159) 100
Gallium-67 (Ga-67) 100
Gallium-72 (Ga-72) 10
Germanium-68 (Ge-68) 10
Germanium-71 (Ge-71) 100
Gold-195 (Au-195) 10
Gold-198 (Au-198) 100
Gold-199 (Au-199) 100
Hafnium-181 (Hf-181) 10
Holmium-166 (Ho-166) 100
Hydrogen-3 (H-3) 1,000
Indium-111 (In-111) 100
Indium-113m (In-113m) 100
Indium-114m (In-114m) 10
Indium-115m (In-115m) 100
Indium-115 (In-115) 10
Iodine-123 (I-123) 100
Iodine-125 (I-125) 1
Iodine-126 (I-126) 1
Iodine-129 (I-129) 0.1
Iodine-131 (I-131) 1
Iodine-132 (I-132) 10
Iodine-133 (I-133) 1
Iodine-134 (I-134) 10
Iodine-135 (I-135) 10
Iridium-192 (Ir-192) 10
Iridium-194 (Ir-194) 100
Iron-52 (Fe-52) 10
Iron-55 (Fe-55) 100
Iron-59 (Fe-59) 10
Krypton-85 (Kr-85) 100
Krypton-87 (Kr-87) 10
Lanthanum-140 (La-140) 10
Lutetium-177 (Lu-177) 100
Manganese-52 (Mn-52) 10
Manganese-54 (Mn-54) 10
Manganese-56 (Mn-56) 10
Mercury-197m (Hg-197m) 100
Mercury-197 (Hg-197) 100
Mercury-203 (Hg-203) 10
Molybdenum-99 (Mo-99) 100
Neodymium-147 (And-147) 100
Neodymium-149 (And-149) 100
Nickel-59 (Ni-59) 100
Nickel-63 (Ni-63) 10
Nickel-65 (Ni-65) 100
Niobium-93m (Nb-93m) 10
Niobium-95 (Nb-95) 10
Niobium-97 (Nb-97) 10
Osmium-185 (So-185) 10
Osmium-191m (So-191m) 100
Osmium-191 (So-191) 100
Osmium-193 (So-193) 100
Palladium-103 (Pd-103) 100
Palladium-109 (Pd-109) 100
Phosphorus-32 (P-32) 10
Platinum-191 (Pt-191) 100
Platinum-193m (Pt-193m) 100
Platinum-193 (Pt-193) 100
Platinum-197m (Pt-197m) 100
Platinum-197 (Pt-197) 100
Polonium-210 (Po-210) 0.1
Potassium-42 (K-42) 10
Potassium-43 (K-43) 10
Praseodymium-142 (Pr-142) 100
Praseodymium-143 (Pr-143) 100
Promethium-147 (Pm-147) 10
Promethium-149 (Pm-149) 10
Radium-226 (Ra-226) 0.1
Rhenium-186 (Re-186) 100
Rhenium-188 (Re-188) 100
Rhodium-103m (Rh-103m) 100
Rhodium-105 (Rh-105) 100
Rubidium-81 (Rb-81) 10
Rubidium-86 (Rb-86) 10
Rubidium-87 (Rb-87) 10
Ruthenium-97 (Ru-97) 100
Ruthenium-103 (Ru-103) 10
Ruthenium-105 (Ru-105) 10
Ruthenium-106 (Ru-106) 1
Samarium-151 (Sm-151) 10
Samarium-153 (Sm-153) 100
Scandium-46 (Sc-46) 10
Scandium-47 (Sc-47) 100
Scandium-48 (Sc-48) 10
Selenium-75 (Se-75) 10
Silicon-31 (Is-31) 100
Silver-105 (Ag-105) 10
Silver-110m (Ag-110m) 1
Silver-111 (Ag-111) 100
Sodium-22 (Na-22) 10
Sodium-24 (Na-24) 10
Strontium-85 (Sr-85) 10
Strontium-89 (Sr-89) 1
Strontium-90 (Sr-90) 0.1
Strontium-91 (Sr-91) 10
Strontium-92 (Sr-92) 10
Sulphur-35 (S-35) 100
Tantalum-182 (Ta-182) 10
Technetium-96 (Tc-96) 10
Technetium-97m (Tc-97m) 100
Technetium-97 (Tc-97) 100
Technetium-99m (Tc-99m) 100
Technetium-99 (Tc-99) 10
Tellurium-125m (Te-125m) 10
Tellurium-127m (Te-127m) 10
Tellurium-127 (Te-127) 100
Tellurium-129m (Te-129m) 10
Tellurium-129 (Te-129) 100
Tellurium-131m (Te-131m) 10
Tellurium-132 (Te-132) 10
Terbium-160 (Tb-160) 10
Thallium-200 (Tl-200) 100
Thallium-201 (Tl-201) 100
Thallium-202 (Tl-202) 100
Thallium-204 (Tl-204) 10
Thulium-170 (Tm-170) 10
Thulium-171 (Tm-171) 10
Tin-113 (Sn-113) 10
Tin-125 (Sn-125) 10
Tungsten-181 (W-181) 10
Tungsten-185 (W-185) 10
Tungsten-187 (W-187) 100
Vanadium-48 (V-48) 10
Xenon-131m (Xe-131m) 1,000
Xenon-133 (Xe-133) 100
Xenon-135 (Xe-135) 100
Ytterbium-169 (Yb-169) 10
Ytterbium-175 (Yb-175) 100
Yttrium-87 (Y-87) 10
Yttrium-88 (Y-88) 10
Yttrium-90 (Y-90) 10
Yttrium-91 (Y-91) 10
Yttrium-92 (Y-92) 100
Yttrium-93 (Y-93) 100
Zinc-65 (Zn-65) 10
Zinc-69m (Zn-69m) 100
Zinc-69 (Zn-69) 1,000
Zirconium-93 (Zr-93) 10
Zirconium-95 (Zr-95) 10
Zirconium-97 (Zr-97) 10
Any radioactive material not listed above other than alpha emitting radioactive material

0.1

[Statutory Authority: RCW 70.98.050. 01-02-068, § 246-232-120, filed 12/29/00, effective 1/29/01. Statutory Authority: RCW 70.98.050 and 70.98.080. 91-15-112 (Order 184), § 246-232-120, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-232-120, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 83-19-050 (Order 2026), § 402-19-550, filed 9/16/83; 79-12-073 (Order 1459), § 402-19-550, filed 11/30/79, effective 1/1/80. Formerly WAC 402-20-240.]


AMENDATORY SECTION(Amending Order 121, filed 12/27/90, effective 1/31/91)

WAC 246-232-140   Schedule D.  

align="center"

ACCEPTABLE SURFACE CONTAMINATION LEVELS

NUCLIDES A AVERAGE B C F MAXIMUM B D F REMOVABLE B E F

WIPE LIMITS
U-nat, U-235, U-238, and associated decay products 5,000 dpm ((α))/100 cm((2)) 2 15,000 dpm ((α))/100 cm((2)) 2 1,000 dpm α/100 cm((2)) 2
Transuranics, Ra-226, Ra-228, Th-230, Th-228, Pa-231, Ac-227, I-125, I-129 100 dpm/100 cm((2)) 2 300 dpm/100 cm((2)) 2 20 dpm/100 cm((2)) 2
Th-nat, Th-232, Sr-90, Ra-223, Ra-224, U-232, I-126, I-131, I-133 1000 dpm/100 cm((2)) 2 3000 dpm/100 cm((2)) 2 200 dpm/100 cm((2)) 2
Beta-gamma emitters (nuclides with decay modes other than alpha emission or spontaneous fission) except SR-90 and others noted above 5000 dpm ((&bgr;&ggr;))/100 cm((2)) 2 15,000 dpm ((&bgr;&ggr;))/100 cm((2)) 2 1000 dpm &bgr;&ggr;/100 cm((2)) 2

A Where surface contamination by both alpha- and beta-gamma-emitting nuclides exists, the limits established for alpha- and beta-gamma-emitting nuclides should apply independently.
B As used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, and geometric factors associated with the instrumentation.
C Measurements of average contaminant should not be averaged over more than 1 square meter. For objects of less surface area, the average should be derived for each such object.
D The maximum contamination level applies to an area of not more than 100 cm2.
E The amount of removable radioactive material per 100 cm2 of surface area should be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped.
F The average and maximum radiation levels associated with surface contamination resulting from beta-gamma emitters should not exceed 0.2 mrad/hr at 1 cm and 1.0 mrad/hr at 1 cm, respectively, measured through not more than 7 milligrams per square centimeter of total absorber.

[Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-232-140, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 87-01-031 (Order 2450), § 402-19-590, filed 12/11/86; 83-19-050 (Order 2026), § 402-19-590, filed 9/16/83.]

OTS-1825.3


NEW SECTION
WAC 246-233-012   General license for certain items and self-luminous products containing radium-226.   (1) A general license shall be issued to any person to acquire, receive, possess, use, or transfer, in accordance with the provisions of subsections (2), (3), and (4) of this section, radium-226 contained in:

     (a) Antiquities originally intended for use by the general public. For the purposes of this subsection, antiquities mean products originally intended for use by the general public and distributed in the late 19th and early 20th centuries, such as radium emanator jars, revigators, radium water jars, radon generators, refrigerator cards, radium bath salts, and healing pads.

     (b) Intact timepieces containing greater than 0.037 megabecquerel (1 microcurie), nonintact timepieces, and timepiece hands and dials no longer installed in timepieces.

     (c) Luminous items installed in air, marine, or land vehicles.

     (d) All other luminous products, provided that no more than one hundred items are used or stored at the same location at any one time.

     (e) Small radium sources containing no more than 0.037 megabecquerel (1 microcurie) of radium-226. For the purposes of this subsection, "small radium sources" means discrete survey instrument check sources, sources contained in radiation measuring instruments, sources used in educational demonstrations (such as cloud chambers and spinthariscopes), electron tubes, lightning rods, ionization sources, static eliminators, or as designated by the department of health.

     (2) Persons who acquire, receive, possess, use, or transfer radioactive materials under the general license issued in subsection (1) of this section are exempt from the provisions of chapters 246-221 and 246-222 WAC to the extent that such receipt, possession, use, or transfer is within the terms of such general license. This exemption shall not apply to any person who is also in possession of radioactive materials under a specific license issued under chapter 246-235 WAC.

     (3) Any person who acquires, receives, possesses, uses, or transfers by-product material in accordance with the general license in subsection (1) of this section:

     (a) Shall notify the department should there be any indication of possible damage to the product so that it appears it could result in a loss of the radioactive material. A report containing a brief description of the event, and the remedial action taken, must be furnished to the department within thirty days.

     (b) Shall not abandon products containing radium-226. The product, and any radioactive material from the product, may only be transferred or disposed of in accordance with chapter 246-232 WAC, or as otherwise approved by the department.

     (c) Shall not export products containing radium-226 except in accordance with chapter 246-231 WAC.

     (d) Shall dispose of products containing radium-226 at a disposal facility authorized to dispose of radioactive material in accordance with any federal or state solid or hazardous waste law, including the Solid Waste Disposal Act, as authorized under the Energy Policy Act of 2005, by transfer to a person authorized to receive radium-226 by a specific license issued under chapter 246-235 WAC, or equivalent regulations of an agreement state, or as otherwise approved by the NRC.

     (e) Shall respond to written requests from the department to provide information relating to the general license within thirty calendar days of the date of the request, or other time specified in the request. If the general licensee cannot provide the requested information within the allotted time, it shall, within that same time period, request a longer period to supply the information by providing a written justification for the request.

     (4) The general license in subsection (1) of this section does not authorize the manufacture, assembly, disassembly, repair, or import of products containing radium-226, except that timepieces may be disassembled and repaired.

[]


AMENDATORY SECTION(Amending WSR 04-04-055, filed 1/30/04, effective 3/1/04)

WAC 246-233-015   Certain devices and equipment.   A general license is hereby issued to transfer, receive, acquire, own, possess, and use radioactive material incorporated in the following devices or equipment which have been manufactured, tested and labeled by the manufacturer in accordance with a specific license issued to the manufacturer by the United States Nuclear Regulatory Commission for use pursuant to Section 31.3 of 10 CFR Part 31. This general license is subject to the provisions of WAC 246-220-020, 246-220-030, 246-220-040, 246-220-050, 246-220-060, 246-220-070, chapters 246-232, 246-221** and 246-222 WAC.

     (1) Static elimination device. Devices designed for use as static eliminators which contain, as a sealed source or sources, radioactive material consisting of a total of not more than 18.5 megabecquerels (500 microcuries) of Polonium-210 per device.

     (2) Ion generating tube. Devices designed for ionization of air which contain, as a sealed source or sources, radioactive material consisting of a total of not more than 18.5 megabecquerels (500 microcuries) of Polonium-210 per device or a total of not more than 18.5 megabecquerels (50 millicuries) of Hydrogen-3 (tritium) per device.

** Attention is directed particularly to the provisions of chapter 246-221 WAC which relate to the labeling of containers.

[Statutory Authority: RCW 70.98.050. 04-04-055, § 246-233-015, filed 1/30/04, effective 3/1/04.]


AMENDATORY SECTION(Amending WSR 04-04-055, filed 1/30/04, effective 3/1/04)

WAC 246-233-020   General license -- Certain measuring, gauging or controlling devices.   (1) A general license is hereby issued to commercial and industrial firms and research, educational and medical institutions, individuals in the conduct of their business, and state or local government agencies to own, acquire, receive, possess, use or transfer, in accordance with the provisions of subsections (2), (3), and (4) of this section, radioactive material excluding special nuclear material contained in devices designed and manufactured for the purpose of detecting, measuring, gauging or controlling thickness, density, level, interface location, radiation, leakage, or qualitative or quantitative chemical composition, or for producing light or an ionized atmosphere.

     (2) The general license in subsection (1) of this section applies only to radioactive material contained in devices which have been manufactured or initially transferred and labeled in accordance with the specifications contained in a specific license issued by the department pursuant to WAC 246-235-093 or in accordance with the Nuclear Regulatory Commission, an agreement state or a licensing state, which authorizes distribution or transfer of devices to persons generally licensed by the United States Nuclear Regulatory Commission, an agreement state or licensing state**. The devices shall have been received from one of the specific licensees described in this subsection or through a transfer made under subsection (3)(h) of this section.


**Note: Regulations under the Federal Food, Drug, and Cosmetic Act authorizing the use of radioactive control devices in food production require certain additional labeling thereon which is found in Section 179.21 of 21 CFR Part 179.

     (3) Any person who owns, acquires, receives, possesses, uses or transfers radioactive material in a device pursuant to the general license in subsection (1) of this section:

     (a) Shall assure that all labels affixed to the device at the time of receipt and bearing a statement that removal of the label is prohibited are maintained thereon and shall comply with all instructions and precautions provided by such labels;

     (b) Shall assure that the device is tested for leakage of radioactive material and proper operation of the on-off mechanism and indicator, if any, at no longer than six-month intervals or at such other intervals as are specified in the label, however:

     (i) Devices containing only krypton need not be tested for leakage of radioactive material; and

     (ii) Devices containing only tritium or not more than 3.7 megabecquerels (100 microcuries) of other beta and/or gamma emitting material or 370 kilobecquerels (10 microcuries) of alpha emitting material need not be tested for any purpose. Devices held in storage in the original shipping container prior to initial installation need not be tested until immediately prior to use;

     (c) Shall assure that the tests required by (b) of this subsection and other testing, installing, servicing, and removing from installation involving the radioactive materials, its shielding or containment, are performed:

     (i) In accordance with the instructions provided by the labels; or

     (ii) By a person holding a specific license from the department or from the United States Nuclear Regulatory Commission or from any agreement state or from a licensing state to perform such activities;

     (d) Shall maintain records showing compliance with the requirements of (b) and (c) of this subsection. The records shall show the results of tests. The records also shall show the dates of performance and the names of persons performing, testing, installing, servicing, and removing from installation concerning the radioactive material, its shielding or containment. Records of tests for leakage of radioactive material required by (b) of this subsection shall be maintained for three years after the next required leak test is performed or the sealed source is transferred or disposed. Records of tests of the on/off mechanism and indicator required by (b) of this subsection shall be maintained for three years after the next required test of the on/off mechanism and indicator is performed or the sealed source is transferred or disposed. Records of other testing, installation, servicing, and removal from installation required by (c) of this subsection shall be maintained for a period of three years from the date of the recorded event or until the device is transferred or disposed;

     (e) Upon the occurrence of a failure of or damage to, or any indication of a possible failure of or damage to, the shielding of the radioactive material or the on/off mechanism or indicator, or upon the detection of 185 becquerels (0.005 microcuries) or more removable radioactive material, shall immediately suspend operation of the device until it has been repaired by the manufacturer or other person holding a specific license from the department, the United States Nuclear Regulatory Commission, or from an agreement state or a licensing state to repair such devices, or disposed by transfer to a person authorized by a specific license to receive the radioactive material contained in the device and, within thirty days, furnish to the department a written report containing a brief description of the event and the remedial action taken; and, in the case of detection of 185 becquerels (0.005 microcuries) or more of removable radioactive material or failure of or damage to a source likely to result in contamination of the premises or the environs, a plan for ensuring that the premises and environs are acceptable for unrestricted use (see WAC 246-246-020);

     (f) Shall not abandon the device containing radioactive material;

     (g) Except as provided in (h) of this subsection, shall transfer or dispose the device containing radioactive material only by transfer to a person holding a specific license of the department, the United States Nuclear Regulatory Commission, or an agreement state, or a licensing state whose specific license authorizes the person to receive the device and within thirty days after transfer of a device to a specific licensee shall furnish to the department a report containing identification of the device by manufacturer's (or initial transferor's) name, model number, and serial number; the name, address, and license number of the person receiving the device, and the date of transfer. Prior written approval from the department is required before transferring the device to any other specific licensee not specifically identified in this subsection;

     (h) Shall transfer the device to another general licensee only:

     (i) Where the device remains in use at a particular location. In such case, the transferor shall give the transferee a copy of this section, a copy of WAC 246-221-240, 246-221-250, 246-232-050, and 246-232-060, and any safety documents identified in the label of the device and within thirty days of the transfer, report to the department the manufacturer's (or transferor's) name, model number, and serial number of device transferred, the transferee's name and mailing address for the location of use, and the name, title, and phone number of the responsible individual identified by the transferee in accordance with (j) of this subsection to have knowledge of and authority to take actions to ensure compliance with the appropriate regulations and requirements; or

     (ii) Where the device is held in storage in the original shipping container at its intended location of use prior to initial use by a general licensee;

     (i) Shall comply with the provisions of WAC 246-221-240 and 246-221-250 for reporting radiation incidents, theft or loss of licensed material, but shall be exempt from the other requirements of chapters 246-221 and 246-222 WAC;

     (j) Shall appoint an individual responsible for having knowledge of the appropriate regulations and requirements and the authority for taking required actions to comply with appropriate regulations and requirements. The general licensee, through this individual, shall ensure the day-to-day compliance with appropriate regulations and requirements. This appointment does not relieve the general licensee of any of its responsibility in this regard;

     (k)(i) Shall register, in accordance with (k)(((i))) (ii) and (iii) of this subsection, devices containing at least 370 ((MBq)) megabecquerels (10 ((mCi)) millicuries) of Cesium-137, 3.7 ((MBq)) megabecquerels (0.1 ((mCi)) millicuries) of Strontium-90, 37 ((MBq)) megabecquerels (1 ((mCi)) millicurie) of Cobalt-60, or 37 ((MBq)) megabecquerels (1 ((mCi)) millicurie) of Americium-241, 3.7 megabecquerels (0.1 millicurie) of Radium-226, or any other transuranic (i.e., element with atomic number greater than uranium (92)), based on the activity indicated on the label. Each address for a location of use, as described under (k)(iii)(D) of this subsection, represents a separate general licensee and requires a separate registration and fee;

     (ii) If in possession of a device meeting the criteria of (k)(i) of this subsection, shall register these devices annually with the department and shall pay the fee required by WAC 246-254-090. Registration must be done by verifying, correcting, and/or adding to the information provided in a request for registration received from the department. The registration information must be submitted to the department within thirty days of the date of the request for registration or as otherwise indicated in the request. In addition, a general licensee holding devices meeting the criteria of (k)(i) of this subsection is subject to the bankruptcy notification requirement in WAC 246-232-050;

     (iii) In registering devices, the general licensee shall furnish the following information and any other information specifically requested by the department:

     (A) Name and mailing address of the general licensee;

     (B) Information about each device: The manufacturer (or initial transferor), model number, serial number, the radionuclide and activity (as indicated on the label);

     (C) Name, title, and telephone number of the responsible person designated as a representative of the general licensee under (j) of this subsection;

     (D) Address or location at which the device(s) are used and/or stored. For portable devices, the address of the primary place of storage;

     (E) Certification by the responsible representative of the general licensee that the information concerning the device(s) has been verified through a physical inventory and checking of label information;

     (F) Certification by the responsible representative of the general licensee that they are aware of the requirements of the general license;

     (iv) Persons generally licensed by the U.S. Nuclear Regulatory Commission, or an agreement state with respect to devices meeting the criteria in (k)(i) of this subsection are not subject to registration requirements if the devices are used in areas subject to Washington state jurisdiction for a period less than one hundred eighty days in any calendar year. The department will not request registration information from such licensees;

     (l) Shall report changes to the mailing address for the location of use (including change in name of general licensee) to the department within thirty days of the effective date of the change. For a portable device, a report of address change is only required for a change in the device's primary place of storage;

     (m) Shall not hold devices that are not in use for longer than two years. If devices with shutters are not being used, the shutter must be locked in the closed position. The testing required by (b) of this subsection need not be performed during the period of storage only. However, when devices are put back into service or transferred to another person, and have not been tested within the required test interval, they must be tested for leakage before use or transfer and the shutter tested before use. Devices kept in standby for future use are excluded from the two-year time limit if the general licensee performs quarterly physical inventories of these devices while they are in standby.

     (4) The general license in subsection (1) of this section does not authorize the manufacture, import or export of devices containing radioactive material.

     (5) The general license provided in this subsection is subject to the provisions of WAC 246-220-020, 246-220-030, 246-220-040, 246-220-060, 246-220-070, 246-220-100, 246-221-240, 246-221-250, 246-232-050, 246-232-060, 246-232-070, 246-232-080, and 246-232-090.

[Statutory Authority: RCW 70.98.050. 04-04-055, § 246-233-020, filed 1/30/04, effective 3/1/04; 98-13-037, § 246-233-020, filed 6/8/98, effective 7/9/98. Statutory Authority: RCW 70.98.050 and 70.98.080. 91-15-112 (Order 184), § 246-233-020, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-233-020, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 87-01-031 (Order 2450), § 402-21-050, filed 12/11/86; 83-19-050 (Order 2026), § 402-21-050, filed 9/16/83. Statutory Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-21-050, filed 12/8/80. Statutory Authority: RCW 70.98.080. 79-12-073 (Order 1459), § 402-21-050, filed 11/30/79, effective 1/1/80. Formerly WAC 402-20-040.]


AMENDATORY SECTION(Amending WSR 04-04-055, filed 1/30/04, effective 3/1/04)

WAC 246-233-025   General license -- Luminous safety devices for aircraft.   (1) A general license is hereby issued to own, receive, acquire, possess and use tritium or Promethium-147 contained in luminous safety devices for use in aircraft, provided:

     (a) Each device contains not more than 370 gigabecquerels (10 curies) of tritium or 11.1 gigabecquerels (300 millicuries) of Promethium-147; and

     (b) Each device has been manufactured, assembled or imported in accordance with a specific license issued by the United States Nuclear Regulatory Commission, or each device has been manufactured or assembled in accordance with the specifications contained in a specific license issued by the department or any agreement state to the manufacturer or assembler of such device pursuant to licensing requirements equivalent to those in Section 32.53 of 10 CFR Part 32 of the regulations of the United States Nuclear Regulatory Commission.

     (2) Persons who own, receive, acquire, possess or use luminous safety devices pursuant to the general license in this subsection are exempt from the requirements of chapters 246-221 and 246-222 WAC except that they shall comply with the provisions of WAC 246-221-240 and 246-221-250.

     (3) This general license does not authorize the manufacture, assembly, or repair of luminous safety devices containing tritium or Promethium-147.

     (4) This general license does not authorize the ownership, receipt, acquisition, possession or use of Promethium-147 contained in instrument dials.

     (5) This general license is subject to the provisions of WAC 246-220-020, 246-220-030, 246-220-040, 246-220-050, 246-220-060, 246-220-070, 246-220-100, 246-232-050, 246-232-070, 246-232-080, and 246-232-090.

[Statutory Authority: RCW 70.98.050. 04-04-055, § 246-233-025, filed 1/30/04, effective 3/1/04.]


AMENDATORY SECTION(Amending WSR 04-04-055, filed 1/30/04, effective 3/1/04)

WAC 246-233-030   General license -- Ice detection devices.   (1) A general license is hereby issued to own, receive, acquire, possess, use and transfer Strontium-90 contained in ice detection devices, provided each device contains not more than 185 megabecquerels (50 microcuries) of Strontium-90 and each device has been manufactured or imported in accordance with a specific license issued by the United States Nuclear Regulatory Commission or each device has been manufactured in accordance with the specifications contained in a specific license issued by the department or any agreement state to the manufacturer of such device pursuant to licensing requirements equivalent to those in Section 32.61 of 10 CFR Part 32 of the regulations of the United States Nuclear Regulatory Commission.

     (2) Persons who own, receive, acquire, possess, use or transfer Strontium-90 contained in ice detection devices pursuant to the general license in (a) of this subsection:

     (a) Shall, upon occurrence of visually observable damage, such as a bend or crack or discoloration from overheating to the device, discontinue use of the device until it has been inspected, tested for leakage and repaired by a person holding a specific license from the United States Nuclear Regulatory Commission or an agreement state to manufacture or service such devices; or shall dispose of the device pursuant to the provisions of these regulations;

     (b) Shall assure that all labels affixed to the device at the time of receipt, and which bear a statement which prohibits removal of the labels, are maintained thereon; and

     (c) Are exempt from the requirements of chapters 246-221 and 246-222 WAC except that such persons shall comply with the provisions of WAC 246-221-170, 246-221-240, and 246-221-250.

     (3) This general license does not authorize the manufacture, assembly, disassembly or repair of Strontium-90 sources in ice detection devices.

     (4) This general license is subject to the provisions of WAC 246-220-020, 246-220-030, 246-220-040, 246-220-060, 246-220-070, 246-220-100, 246-232-050, 246-232-070, 246-232-080, and 246-232-090.

[Statutory Authority: RCW 70.98.050. 04-04-055, § 246-233-030, filed 1/30/04, effective 3/1/04.]


AMENDATORY SECTION(Amending WSR 04-04-055, filed 1/30/04, effective 3/1/04)

WAC 246-233-035   General license -- Calibration and reference sources.   (1) A general license is hereby issued to those persons listed below to own, receive, acquire, possess, use and transfer, in accordance with the provisions of subsections (4) and (5) of this section, Americium-241 in the form of calibration or reference sources:

     (a) Any person who holds a specific license issued by the department which authorizes that person to receive, possess, use and transfer radioactive material; or

     (b) Any person who holds a specific license issued by the United States Nuclear Regulatory Commission which authorizes that person to receive, possess, use and transfer special nuclear material.

     (2) A general license is hereby issued to own, receive, possess, use and transfer plutonium in the form of calibration or reference sources in accordance with the provisions of subsections (4) and (5) of this section to any person who holds a specific license issued by the department which authorizes that person to receive, possess, use and transfer radioactive material.

     (3) A general license is hereby issued to own, receive, possess, use and transfer Radium-226 in the form of calibration or reference sources in accordance with the provisions of subsections (4) and (5) of this section to any person who holds a specific license issued by the department which authorizes that person to receive, possess, use and transfer radioactive material.

     (4) The general licenses in subsections (1), (2) and (3) of this section apply only to calibration or reference sources which have been manufactured in accordance with the specifications contained in a specific license issued to the manufacturer or importer of the sources by the United States Nuclear Regulatory Commission pursuant to Section 32.57 of 10 CFR Part 32 or Section 70.39 of 10 CFR Part 70 or which have been manufactured in accordance with the specifications contained in a specific license issued to the manufacturer by the department or any agreement state or licensing state pursuant to licensing requirements equivalent to those contained in Section 32.57 of 10 CFR Part 32 or Section 70.39 of 10 CFR Part 70 of the regulations of the United States Nuclear Regulatory Commission.

     (5) The general licenses provided in subsections (1), (2) and (3) of this section are subject to the provisions of WAC 246-220-020, 246-220-030, 246-220-040, 246-220-060, 246-220-070, 246-220-100, 246-232-050, 246-232-070, 246-232-080, 246-232-090, chapters 246-221 and 246-222 WAC.

     In addition, persons who own, receive, acquire, possess, use or transfer one or more calibration or reference sources pursuant to these general licenses:

     (a) Shall not possess at any one time, at any one location of storage or use, more than 185 kilobecquerels (5 microcuries) of Americium-241 and 185 kilobecquerels (5 microcuries) of plutonium and 185 kilobecquerels (5 microcuries) of Radium-226 in such sources;

     (b) Shall not receive, possess, use or transfer such source unless the source, or the storage container, bears a label which includes one of the following statements or a substantially similar statement which contains the information called for in the following statement:

(i)          The receipt, possession, use and transfer of this source, Model . . . . . . . , Serial No.. . . . . . . , are subject to a general license and the regulations of the United States Nuclear Regulatory Commission or of a state with which the commission has entered into an agreement for the exercise of regulatory authority. Do not remove this label.

CAUTION - RADIOACTIVE MATERIAL - THIS SOURCE CONTAINS (AMERICIUM-241). (PLUTONIUM)*. DO NOT TOUCH RADIOACTIVE PORTION OF THIS SOURCE


. . . . . . . . . . . .

Name of manufacturer or importer

*Note: Showing only the name of the appropriate material.

(ii)          The receipt, possession, use and transfer of this source, Model . . . . . . . , Serial No. . . . . . . . , are subject to a general license and the regulations of any licensing state. Do not remove this label.

CAUTION - RADIOACTIVE MATERIAL - THIS SOURCE CONTAINS RADIUM-226. DO NOT TOUCH RADIOACTIVE PORTION OF THIS SOURCE


. . . . . . . . . . . .

Name of manufacturer or importer


     (c) Shall not transfer, abandon, or dispose of such source except by transfer to a person authorized by a license from the department, the United States Nuclear Regulatory Commission, or an agreement state or licensing state to receive the source;

     (d) Shall store such source, except when the source is being used, in a closed container adequately designed and constructed to contain Americium-241, plutonium, or Radium-226/Radon-222 which might otherwise escape during storage; and

     (e) Shall not use such source for any purpose other than the calibration of radiation detectors or the standardization of other sources.

     (6) These general licenses do not authorize the manufacture of calibration or reference sources containing Americium-241, plutonium, or Radium-226.

[Statutory Authority: RCW 70.98.050. 04-04-055, § 246-233-035, filed 1/30/04, effective 3/1/04.]


AMENDATORY SECTION(Amending WSR 04-04-055, filed 1/30/04, effective 3/1/04)

WAC 246-233-040   General license for use of radioactive material for certain in vitro clinical or laboratory testing.*   (1) A general license is hereby issued to any physician, veterinarian, clinical laboratory or hospital to receive, acquire, possess, transfer or use, for any of the following stated tests, in accordance with the provisions of subsections (2), (3), (4), (5), and (6) of this section the following radioactive materials in prepackaged units:

     (a) Iodine-125, in units not exceeding 370 kilobecquerels (10 microcuries) each for use in in vitro clinical or laboratory tests not involving internal or external administration of radioactive material, or the radiation therefrom, to human beings or animals.

     (b) Iodine-131, in units not exceeding 370 kilobecquerels (10 microcuries) each for use in in vitro clinical or laboratory tests not involving internal or external administration of radioactive material, or the radiation therefrom, to human beings or animals.

     (c) Carbon-14, in units not exceeding 370 kilobecquerels (10 microcuries) each for use in in vitro clinical or laboratory tests not involving internal or external administration of radioactive material, or the radiation therefrom, to human beings or animals.

     (d) Hydrogen-3 (tritium), in units not exceeding 1.85 megabecquerels (50 microcuries) each for use in in vitro clinical or laboratory tests not involving internal or external administration of radioactive material, or the radiation therefrom, to human beings or animals.

     (e) Iron-59, in units not exceeding 740 kilobecquerels (20 microcuries) each for use in in vitro clinical or laboratory tests not involving internal or external administration of radioactive material, or the radiation therefrom, to human beings or animals.

     (f) Cobalt-57, in units not exceeding 370 kilobecquerels (10 microcuries) each for use in in vitro clinical or laboratory tests not involving internal or external administration of radioactive material, or the radiation therefrom, to human beings or animals.

     (g) Selenium-75, in units not to exceed 370 kilobecquerels (10 microcuries) each for use in in vitro clinical or laboratory tests not involving internal or external administration of radioactive material, or the radiation therefrom, to human beings or animals.

     (h) Mock Iodine-125 reference or calibration sources, in units not exceeding 1.85 kilobecquerels (0.05 microcurie) of Iodine-129 and 185 becquerels (0.005 microcurie) of Americium-241 each for use in in vitro clinical or laboratory tests not involving internal or external administration of radioactive material, or the radiation therefrom, to human beings or animals.

*Note: The new drug provisions of the Federal Food, Drug and Cosmetic Act also govern the availability and use of any specific diagnostic drugs in interstate commerce.
     (2) No person shall receive, acquire, possess, use or transfer radioactive material pursuant to the general license established by subsection (1) of this section until that person has received a validated copy of department Form RHF-15 "Certificate - in vitro testing with radioactive material under general license." Annual validation requires resubmittal of revised department Form RHF-15 and submittal of the annual fee to the department. The physician, veterinarian, clinical laboratory or hospital shall furnish on department Form RHF-15 the following information and such other information as may be required by that form:

     (a) Name and address of the physician, veterinarian, clinical laboratory or hospital;

     (b) The location of use; and

     (c) A statement that the physician, veterinarian, clinical laboratory or hospital has appropriate radiation measuring instruments to carry out in vitro clinical or laboratory tests with radioactive material as authorized under the general license in subsection (1) of this section and that such tests will be performed only by personnel competent in the use of such instruments and in the handling of the radioactive material.

     (3) A person who receives, acquires, possesses or uses radioactive material pursuant to the general license established by subsection (1) of this section shall comply with the following:

     (a) The general licensee shall not possess at any one time, pursuant to the general license in subsection (1) of this section at any one location of storage or use, a total amount of Iodine-125, Iodine-131, Selenium-75, Iron-59, and/or Cobalt-57 in excess of 7.4 megabecquerels (200 microcuries).

     (b) The general licensee shall store the radioactive material, until used, in the original shipping container or in a container providing equivalent radiation protection.

     (c) The general licensee shall use the radioactive material only for the uses authorized by subsection (1) of this section.

     (d) The general licensee shall not transfer the radioactive material to a person who is not authorized to receive it pursuant to a license issued by the department, the United States Nuclear Regulatory Commission, any agreement state or licensing state, nor transfer the radioactive material in any manner other than in the unopened, labeled shipping container as received from the supplier.

     (e) The general licensee shall dispose of the Mock Iodine-125 reference or calibration sources described in subsection (1)(h) of this section as required by WAC 246-221-170.

     (4) The general licensee shall not receive, acquire, possess, or use radioactive material pursuant to subsection (1) of this section:

     (a) Except as prepackaged units which are labeled in accordance with the provision of an applicable specific license issued pursuant to WAC 246-235-097 or in accordance with the provisions of a specific license issued by the United States Nuclear Regulatory Commission, or any agreement state or licensing state which authorizes the manufacture and distribution of Iodine-125, Iodine-131, Carbon-14, Hydrogen-3 (tritium), Iron-59, Selenium-75, Cobalt-57, or Mock Iodine-125 to persons generally licensed under this subsection or its equivalent; and

     (b) Unless one of the following statements, as appropriate, or a substantially similar statement which contains the information called for in one of the following statements, appears on a label affixed to each prepackaged unit or appears in a leaflet or brochure which accompanies the package:

This radioactive material shall be received, acquired, possessed and used only by physicians, veterinarians, clinical laboratories or hospitals and only for in vitro clinical or laboratory tests not involving internal or external administration of the material, or the radiation therefrom, to human beings or animals. Its receipt, acquisition, possession, use and transfer are subject to the regulations and a general license of the United States Nuclear Regulatory Commission or of a state with which the commission has entered into an agreement for the exercise of regulatory authority.


. . . . . . . . . . . .

Name of manufacturer


This radioactive material shall be received, acquired, possessed and used only by physicians, veterinarians, clinical laboratories or hospitals and only for in vitro clinical or laboratory tests not involving internal or external administration of the material, or the radiation therefrom, to human beings or animals. Its receipt, acquisition, possession, use and transfer are subject to the regulations and a general license of a licensing state.


. . . . . . . . . . . .

Name of manufacturer


     (5) The physician, veterinarian, clinical laboratory or hospital possessing or using radioactive material under the general license of subsection (1) of this section shall report in writing to the department, any changes in the information previously furnished in the "Certificate - in vitro testing with radioactive material under general license," department Form RHF-15. The report shall be furnished within thirty days after the effective date of such change.

     (6) This general license is subject to the provisions of WAC 246-220-020, 246-220-030, 246-220-040, 246-220-060, 246-220-070, 246-220-090 and 246-220-100. In addition, any person using radioactive material pursuant to the general license of subsection (1) of this section is exempt from the requirements of chapters 246-221 and 246-222 WAC with respect to radioactive material covered by that general license, except that such persons using the Mock Iodine-125 described in subsection (1)(h) of this section shall comply with the provisions of WAC 246-221-170, 246-221-240, and 246-221-250 and of these regulations.

[Statutory Authority: RCW 70.98.050. 04-04-055, § 246-233-040, filed 1/30/04, effective 3/1/04.]

OTS-1823.3


AMENDATORY SECTION(Amending Order 121, filed 12/27/90, effective 1/31/91)

WAC 246-235-010   Filing application for specific licenses.   (1) Applications for specific licenses shall be filed on department form RHF-1.

     (2) The department may at any time after the filing of the original application, and before the expiration of the license, require further statements in order to enable the department to determine whether the application should be granted or denied or whether a license should be modified or revoked.

     (3) Each application shall be signed by the applicant or licensee or a person duly authorized to act for and on the applicant's behalf.

     (4) An application for a license may include a request for a license authorizing one or more activities.

     (5) In the application, the applicant may incorporate by reference information contained in previous applications, statements, or reports filed with the department provided such references are clear and specific.

     (6) An application for a specific license to use radioactive materials in the form of a sealed source or in a device that contains the sealed source must:

     (a) Identify the source or device by manufacturer and model number; or

     (b) Be registered with the U.S. Nuclear Regulatory Commission under 10 CFR 32.210; or

     (c) For sources not registered with the U.S. NRC, provide sufficient additional information to demonstrate that there is reasonable assurance that the radiation safety properties of the source or device are adequate to protect health and minimize danger to life and property. Such information must include a description of the source or device, a description of radiation safety features, the intended use, relevant operational safety history, and the results of the most recent leak test.

     (7) Applications and documents submitted to the department may be made available for public inspection except that the department may withhold any document or part thereof from public inspection if disclosure of its content is not required in the public interest and would adversely affect the interest of a person concerned.

[Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-235-010, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 79-12-073 (Order 1459), § 402-22-020, filed 11/30/79, effective 1/1/80. Formerly WAC 402-20-050.]


AMENDATORY SECTION(Amending WSR 06-05-019, filed 2/6/06, effective 3/9/06)

WAC 246-235-080   Special requirements for possession and use of medical calibration and reference sources.   (1) Leak tests.

     (a) Any licensee or registrant who possesses sealed sources as calibration or reference sources shall test for leakage each sealed source containing radioactive material, other than Hydrogen-3, with a half-life greater than thirty days in any form other than gas and/or contamination at least every six months. In the absence of a certificate from a transferor indicating that a test has been made within six months prior to the transfer, the sealed sources shall not be used until tested. However, leak tests are not required when: The source contains 3.7 megabecquerels (100 microcuries) or less of beta and/or gamma emitting material or 370 kilobecquerels (10 microcuries) or less of alpha emitting material or the sealed source is stored and is not being used: Provided, a physical inventory of the source and wipe surveys of the storage area or storage container are conducted as required by these rules or license condition.

     (b) The leak test shall be capable of detecting the presence of 185 becquerels (0.005 microcurie (((185 becquerels))) of radioactive material on the test sample. The test sample shall be taken from the sealed source or from the surfaces of the device in which the sealed source is mounted or stored on which contamination might be expected to accumulate. Records of leak test results shall be kept in units of microcuries and maintained for inspection by the department.

     (c) If the leak test reveals the presence of 185 becquerels (0.005 microcurie) or more of removable contamination, the licensee or registrant shall immediately withdraw the sealed source from use and shall cause it to be decontaminated and repaired or to be disposed of in accordance with chapters 246-235 and 246-221 WAC. The licensee must file a report within five days of the test with the department describing the equipment involved, the test results, and the corrective action taken.

     (2) Any licensee or registrant who possesses and uses calibration and reference sources shall:

     (a) Follow the radiation safety and handling instructions approved by the department, the United States Nuclear Regulatory Commission, an agreement state or a licensing state and furnished by the manufacturer on the label attached to the source, or permanent container thereof, or in the leaflet or brochure that accompanies the source, and maintain the instructions in a legible and conveniently available form; and

     (b) Conduct a quarterly physical inventory to account for all sources received and possessed. Records of the inventories shall be maintained for inspection by the department and shall include at a minimum the quantities and kinds of radioactive material, location of sources, name of person performing the inventory, and the date of the inventory.

[Statutory Authority: RCW 70.98.050. 06-05-019, § 246-235-080, filed 2/6/06, effective 3/9/06; 00-08-013, § 246-235-080, filed 3/24/00, effective 4/24/00; 98-13-037, § 246-235-080, filed 6/8/98, effective 7/9/98. Statutory Authority: RCW 70.98.050 and 70.98.080. 91-15-112 (Order 184), § 246-235-080, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-235-080, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 87-01-031 (Order 2450), § 402-22-070, filed 12/11/86; 83-19-050 (Order 2026), § 402-22-070, filed 9/16/83. Statutory Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-22-070, filed 12/8/80. Statutory Authority: RCW 70.98.080. 79-12-073 (Order 1459), § 402-22-070, filed 11/30/79, effective 1/1/80. Formerly WAC 402-20-070.]


AMENDATORY SECTION(Amending WSR 04-04-055, filed 1/30/04, effective 3/1/04)

WAC 246-235-097   Manufacture and distribution of radioactive material for certain in vitro clinical or laboratory testing under general license.   An application for a specific license to manufacture or distribute radioactive material for use under the general license of WAC 246-233-040 will be approved if:

     (1) The applicant satisfies the general requirements specified in WAC 246-235-020;

     (2) The radioactive material is to be prepared for distribution in prepackaged units of:

     (a) Iodine-125 in units not exceeding 370 kilobecquerels (10 microcuries) each;

     (b) Iodine-131 in units not exceeding 370 kilobecquerels (10 microcuries) each;

     (c) Carbon-14 in units not exceeding 370 kilobecquerels (10 microcuries) each;

     (d) Hydrogen-3 (tritium) in units not exceeding 1.85 megabecquerels (50 microcuries) each;

     (e) Iron-59 in units not exceeding 740 kilobecquerels (20 microcuries) each;

     (f) Cobalt-57 in units not exceeding 370 kilobecquerels (10 microcuries) each;

     (g) Selenium-75 in units not exceeding 370 kilobecquerels (10 microcuries) each;

     (h) Mock Iodine-125 in units not exceeding 1.85 kilobecquerels (0.05 microcurie) of iodine-129 and 185 becquerels (0.005 microcurie) of americium-241 each.

     (3) Each prepackaged unit bears a durable, clearly visible label:

     (a) Identifying the radioactive contents as to chemical form and radionuclide, and indicating that the amount of radioactivity does not exceed 370 kilobecquerels (10 microcuries) of iodine-125, iodine-131, carbon-14, cobalt-57, or selenium-75; 1850 kilobecquerels (50 microcuries) of hydrogen-3 (tritium); 740 kilobecquerels (20 microcuries) of iron-59; or Mock Iodine-125 in units not exceeding 1.85 kilobecquerels (0.05 microcurie) of iodine-129 and 185 becquerels (0.005 microcurie) of americium-241 each; and

     (b) Displaying the radiation caution symbol described in WAC 246-221-120 (1)(a) and the words, "CAUTION, RADIOACTIVE MATERIAL," and "Not for internal or external use in humans or animals."

     (4) One of the following statements, as appropriate, or a substantially similar statement which contains the information called for in one of the following statements, appears on a label affixed to each prepackaged unit or appears in a leaflet or brochure which accompanies the package:

     (a) This radioactive material may be received, acquired, possessed and used only by physicians, veterinarians, clinical laboratories or hospitals and only for in vitro clinical or laboratory tests not involving internal or external administration of the material, or the radiation therefrom, to human beings or animals. Its receipt, acquisition, possession, use and transfer are subject to the regulations and a general license of the United States Nuclear Regulatory Commission or of a state with which the commission has entered into an agreement for the exercise of regulatory authority.


. . . . . . . . . . . .

Name of manufacturer

     (b) This radioactive material may be received, acquired, possessed and used only by physicians, veterinarians, clinical laboratories or hospitals and only for in vitro clinical or laboratory tests not involving internal or external administration of the material, or the radiation therefrom, to human beings or animals. Its receipt, acquisition, possession, use and transfer are subject to the regulations and a general license of a licensing state.


. . . . . . . . . . . .

Name of manufacturer

     (5) The label affixed to the unit, or the leaflet or brochure which accompanies the package, contains adequate information as to the precautions to be observed in handling and storing such radioactive material. In the case of the Mock Iodine-125 reference or calibration source, the information accompanying the source must also contain directions to the licensee regarding the waste disposal requirements set out in WAC 246-221-170 of these regulations.

[Statutory Authority: RCW 70.98.050. 04-04-055, § 246-235-097, filed 1/30/04, effective 3/1/04; 98-13-037, § 246-235-097, filed 6/8/98, effective 7/9/98.]


AMENDATORY SECTION(Amending WSR 07-14-131, filed 7/3/07, effective 8/3/07)

WAC 246-235-100   Manufacture, production, preparation, and/or ((commercial)) transfer of radiopharmaceuticals for medical use.   (1) An application for a specific license to manufacture ((and)), produce, prepare, and/or transfer for ((commercial)) distribution radiopharmaceuticals containing radioactive material for use by persons licensed under chapter 246-240 WAC for medical use in humans will be approved if:

     (a) The applicant satisfies the general requirements specified in WAC 246-235-020;

     (b) The applicant submits evidence that the applicant is:

     (i) ((The applicant is)) Registered or licensed with the U.S. Food and Drug Administration (FDA) as a drug manufacturer, preparer, propagator, compounder or processor of a drug under 21 CFR 207.20(a); or

     (ii) ((The applicant is)) Licensed as a nuclear pharmacy by the state board of pharmacy;

     (iii) Registered or licensed as a radiopharmaceutical production facility or nuclear pharmacy with the U.S. Nuclear Regulatory Commission or a state agency;

     (iv) Operating as a nuclear pharmacy within a federal medical institution; or

     (v) A positron emission tomography drug production facility registered with a state agency.

     (c) The applicant submits information on the radionuclide, chemical and physical form, maximum activity per vial, syringe, generator, or other container of the radiopharmaceutical, and shielding provided by the packaging of the radioactive material which is appropriate for safe handling and storage of radiopharmaceuticals by medical use licensees; and

     (d) The applicant satisfies the following labeling requirements:

     (i) Those specified by the state board of pharmacy in WAC 246-903-020((.)) for both commercial and noncommercial distribution;

     (ii) A label is affixed to each transport radiation shield, whether it is constructed of lead, glass, plastic, or other material, of a radioactive drug to be transferred for commercial distribution. The label must include the radiation symbol, the words "caution-radioactive material" or "danger-radioactive material," the name of the radioactive drug or its abbreviation, and the quantity of radioactivity at a specified date and time. For radioactive drugs with a half-life greater than one hundred days, the time may be omitted;

     (iii) A label is affixed to each syringe, vial, or other container used to hold a radioactive drug to be transferred for commercial distribution. The label must include the radiation symbol, the words "caution-radioactive material" or "danger-radioactive material" and an identifier that allows the syringe, vial, or other container to be correlated with the information on the transport radiation shield label; and

     (iv) For a drug manufacturer, the labels required by this subsection are in addition to the labeling required by the Food and Drug Administration (FDA) and may be separate from or, with the approval of FDA, may be combined with the labeling required by FDA.

     (2) A medical facility or an educational institution, may produce positron emission tomography or other approved accelerator-produced radioactive drugs, for noncommercial transfer to licensees within their consortium, as defined in WAC 246-220-010 and 246-235-010, if they have a valid Washington radioactive materials license and are authorized for medical use under chapter 246-240 WAC or an equivalent agreement state or U.S. Nuclear Regulatory Commission license; and

     (a) Request authorization to produce accelerator-produced radionuclides at a radionuclide production facility within their consortium to prepare approved radioactive drugs for use only by licensees within that consortium. The applicant must have a current state radioactive materials license or evidence of an existing license issued by U.S. Nuclear Regulatory Commission or another agreement state.

     (b) The applicant must be qualified to produce radioactive drugs for medical use by meeting the criteria in subsections (1) and (3) of this section.

     (c) Identification of individual(s) authorized to prepare radioactive drugs if the applicant is a pharmacy, and documentation that each individual meets the requirements of an authorized nuclear pharmacist as specified in subsection (3) of this section.

     (d) Labeling information identified in subsection (1)(d) of this section is applied to any radiopharmaceuticals or radioactive materials to be noncommercially transferred to members of its consortium.

     (3) A nuclear pharmacy licensee:

     (a) May prepare radiopharmaceuticals for medical use provided the radiopharmaceutical is prepared by or under the supervision of an authorized nuclear pharmacist.

     (b) May allow a pharmacist to work as an authorized nuclear pharmacist if:

     (i) This individual qualifies as an authorized nuclear pharmacist as defined in WAC 246-240-010;

     (ii) This individual meets the state board of pharmacy requirements in WAC 246-903-030, Nuclear pharmacists, and the requirements of WAC 246-240-081 and the licensee has received an approved license amendment identifying this individual as an authorized nuclear pharmacist; or

     (iii) This individual is designated as an authorized nuclear pharmacist in accordance with (d) of this subsection.

     (c) The actions authorized in (a) and (b) of this subsection are permitted in spite of more restrictive language in license conditions.

     (d) May designate a pharmacist as an authorized nuclear pharmacist if:

     (i) The individual ((is)) was identified as of December 2, 1994, as an "authorized user" on a nuclear pharmacy license issued by the department, the U.S. NRC, or an agreement state; or

     (ii) The individual was a nuclear pharmacist preparing only radioactive drugs containing accelerator-produced radioactive material, and the individual practiced at a pharmacy at a government agency or federally recognized Indian tribe before November 30, 2007, or at any other pharmacies as of December 1, 2008.

     (e) Shall provide to the department a copy of each individual's letter of notification from the state board of pharmacy recognizing the individual as a nuclear pharmacist, within thirty days of the date the licensee allows the individual to work as an authorized nuclear pharmacist under (b), (c) or (d) of this subsection.

     (3) A manufacturer or nuclear pharmacy licensee shall possess and use instrumentation to measure the radioactivity of radiopharmaceuticals. The licensee shall have procedures for use of the instrumentation. The licensee shall measure, by direct measurement or by combination of measurements and calculations, the amount of radioactivity in dosages of alpha-, beta-, or photon-emitting radiopharmaceuticals, prior to transfer for commercial distribution. In addition, the licensee shall:

     (a) Perform tests before initial use, periodically, and following repair, on each instrument for accuracy, linearity, and geometry dependence, as appropriate for the use of the instrument; and make adjustments when necessary; and

     (b) Check each instrument for constancy and proper operation at the beginning of each day of use.

     (4) A licensee preparing radiopharmaceuticals from generators; (e.g., molybdenum-99/technetium-99m or rubidium-82 from strontium-82/rubidium-82) shall test generator eluates for breakthrough or contamination of the parent isotope, in accordance with WAC 246-240-160. The licensee shall record the results of each test and retain each record for three years after the record is made.

     (5) Nothing in this section relieves the licensee from complying with applicable FDA, other federal, and state requirements governing radiopharmaceuticals.

[Statutory Authority: RCW 70.98.050. 07-14-131, § 246-235-100, filed 7/3/07, effective 8/3/07; 06-05-019, § 246-235-100, filed 2/6/06, effective 3/9/06; 98-13-037, § 246-235-100, filed 6/8/98, effective 7/9/98. Statutory Authority: RCW 70.98.050 and 70.98.080. 91-15-112 (Order 184), § 246-235-100, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-235-100, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-22-110, filed 12/8/80. Statutory Authority: RCW 70.98.080. 79-12-073 (Order 1459), § 402-22-110, filed 11/30/79, effective 1/1/80. Formerly WAC 402-20-076.]


NEW SECTION
WAC 246-235-103   Prototype tests for manufacture of calibration or reference sources containing americium-241 or radium-226.   An applicant for a license under this chapter shall, for any type of source which is designed to contain more than 0.185 kilobecquerel (0.005 microcurie) of americium-241 or radium-226, conduct prototype tests, in the order listed, on each of no less than five prototypes of the source, which contains more than 0.185 kilobecquerel (0.005 microcurie) of americium-241 or radium-226, as follows:

     (1) Initial measurement. The quantity of radioactive material deposited on the source shall be measured by direct counting of the source.

     (2) Dry wipe test. The entire radioactive surface of the source shall be wiped with filter paper with the application of moderate finger pressure. Removal of radioactive material from the source shall be determined by measuring the radioactivity on the filter paper or by direct measurement of the radioactivity on the source following the dry wipe.

     (3) Wet wipe test. The entire radioactive surface of the source shall be wiped with filter paper, moistened with water, with the application of moderate finger pressure. Removal of radioactive material from the source shall be determined by measuring the radioactivity on the filter paper after it has dried or by direct measurement of the radioactivity remaining on the source following the wet wipe.

     (4) Water soak test. The source shall be immersed in water at room temperature for a period of twenty-four consecutive hours. The source shall then be removed from the water. Removal of radioactive material from the source shall be determined by direct measurement of the radioactivity on the source after it has dried or by measuring the radioactivity in the residue obtained by evaporation of the water in which the source was immersed.

     (5) Dry wipe test. On completion of the preceding test in this section, the dry wipe test described in subsection (2) of this section shall be repeated.

     (6) Observations. Removal of more than 0.005 microcurie (185 becquerels) of radioactivity in any test prescribed by this section shall be cause for rejection of the source design. Results of prototype tests submitted to the department or the U.S. Nuclear Regulatory Commission shall be given in terms of radioactivity in microcuries (or becquerels) and percent of removal from the total amount of radioactive material deposited on the source.

[]


AMENDATORY SECTION(Amending WSR 01-02-067, filed 12/29/00, effective 1/29/01)

WAC 246-235-105   Manufacture, assembly or distribution of radioactive material exempt from regulation.   (1) Licensing the introduction of radioactive material into products in exempt concentrations. In addition to the requirements set forth in WAC 246-235-020, a specific license authorizing the introduction of radioactive material into a product or material owned by or in the possession of the licensee or another to be transferred to persons exempt under WAC 246-232-010(1) will be issued if:

     (a) The applicant submits a description of the product or material into which the radioactive material will be introduced, intended use of the radioactive material and the product or material into which it is introduced, method of introduction, initial concentration of the radioactive material in the product or material, control methods to assure that no more than the specified concentration is introduced into the product or material, estimated time interval between introduction and transfer of the product or material, and estimated concentration of the radioactive material in the product or material at the time of transfer; and

     (b) The applicant provides reasonable assurance that the concentrations of radioactive material at the time of transfer will not exceed the concentrations in WAC 246-232-130, Schedule C, that reconstruction of the radioactive material in concentrations exceeding those in WAC 246-232-130, Schedule C, is not likely, that use of lower concentrations is not feasible, and that the product or material is not likely to be incorporated in any food, beverage, cosmetic, drug or other commodity or product designed for ingestion or inhalation by, or application to a human being.

     (c) Each person licensed under subsection (1) of this section shall file an annual report with the department which shall identify the type and quantity of each product or material into which radioactive material has been introduced during the reporting period; name and address of the person who owned or possessed the product and material, into which radioactive material has been introduced, at the time of introduction; the type and quantity of radionuclide introduced into each such product or material; and the initial concentrations of the radionuclide in the product or material at time of transfer of the radioactive material by the licensee. If no transfers of radioactive material have been made pursuant to subsection (1) of this section during the reporting period, the report shall so indicate. The report shall cover the year ending June 30, and shall be filed within thirty days thereafter.

     (2) Licensing the distribution of certain radioactive material in exempt quantities.*


*Note: Authority to transfer possession or control by the manufacturer, processor or producer of any equipment, device, commodity or other product containing source material or ((byproduct)) radioactive material whose subsequent possession, use, transfer and disposal by all other persons who are exempted from regulatory requirements may be obtained only from the department or the United States Nuclear Regulatory Commission, Washington, D.C. 20555.

     (a) An application for a specific license to distribute naturally occurring and accelerator-produced radioactive material (NARM) to persons exempted from these regulations pursuant to WAC 246-232-010 (2)(b) will be approved if:

     (i) The radioactive material is not contained in any food, beverage, cosmetic, drug or other commodity designed for ingestion or inhalation by, or application to, a human being;

     (ii) The radioactive material is in the form of processed chemical elements, compounds, or mixtures, tissue samples, bioassay samples, counting standards, plated or encapsulated sources, or similar substances, identified as radioactive and to be used for its radioactive properties, but is not incorporated into any manufactured or assembled commodity, product, or device intended for commercial distribution; and

     (iii) The applicant submits copies of prototype labels and brochures and the department approves such labels and brochures.

     (b) The license issued under ((paragraph (2)))(a) of this ((section)) subsection is subject to the following conditions:

     (i) No more than ten exempt quantities shall be sold or transferred in any single transaction. However, an exempt quantity may be composed of fractional parts of one or more of the exempt quantity provided the sum of the fractions shall not exceed unity.

     (ii) Each exempt quantity shall be separately and individually packaged. No more than ten such packaged exempt quantities shall be contained in any outer package for transfer to persons exempt pursuant to WAC 246-232-010 (2)(b). The outer package shall be such that the dose rate at the external surface of the package does not exceed 0.5 millirem per hour.

     (iii) The immediate container of each quantity or separately packaged fractional quantity of radioactive material shall bear a durable, legible label which:

     (A) Identifies the radionuclide and the quantity of radioactivity; and

     (B) Bears the words "radioactive material."

     (iv) In addition to the labeling information required by ((item (2)))(b)(iii) of this ((section)) subsection, the label affixed to the immediate container, or an accompanying brochure, shall:

     (A) State that the contents are exempt from licensing state requirements;

     (B) Bear the words "Radioactive material -- Not for human use -- Introduction into foods, beverages, cosmetics, drugs, or medicinals, or into products manufactured for commercial distribution is prohibited -- Exempt quantities should not be combined"; and

     (C) Set forth appropriate additional radiation safety precautions and instructions relating to the handling, use, storage and disposal of the radioactive material.

     (c) Each person licensed under ((paragraph (2)))(a) of this ((section)) subsection shall maintain records identifying, by name and address, each person to whom radioactive material is transferred for use under WAC 246-232-010 (2)(b) or the equivalent regulations of a licensing state, and stating the kinds and quantities of radioactive material transferred. An annual summary report stating the total quantity of each radionuclide transferred under the specific license shall be filed with the department. Each report shall cover the year ending June 30, and shall be filed within thirty days thereafter. If no transfers of radioactive material have been made pursuant to subsection (2) of this section during the reporting period, the report shall so indicate.

     (3) Licensing the incorporation of naturally occurring and accelerator-produced radioactive material into gas and aerosol detectors. An application for a specific license authorizing the incorporation of NARM into gas and aerosol detectors to be distributed to persons exempt under WAC 246-232-012 will be approved if the application satisfies requirements equivalent to those contained in Section 32.26 of 10 CFR Part 32.


*Note: Authority to transfer possession or control by the manufacturer, processor or producer of any equipment, device, commodity or other product containing source material or radioactive material whose subsequent possession, use, transfer and disposal by all other persons who are exempted from regulatory requirements may be obtained only from the department or the United States Nuclear Regulatory Commission, Washington, D.C. 20555.

[Statutory Authority: RCW 70.98.050. 01-02-067, § 246-235-105, filed 12/29/00, effective 1/29/01; 98-13-037, § 246-235-105, filed 6/8/98, effective 7/9/98.]


NEW SECTION
WAC 246-235-107   Serialization of nationally tracked sources.   Each licensee who manufactures a nationally tracked source after February 6, 2007, shall assign a unique serial number to each nationally tracked source. Serial numbers must be composed only of alpha-numeric characters.

[]


NEW SECTION
WAC 246-235-125   Special requirements to report transactions involving nationally tracked sources.   Each licensee who manufactures, transfers, receives, disassembles, or disposes of a nationally tracked source shall complete and submit a National Source Tracking Transaction Report as specified in subsections (1) through (5) of this section for each type of transaction.

     (1) Each licensee who manufactures a nationally tracked source shall complete and submit a National Source Tracking Transaction Report. The report must include the following information;

     (a) The name, address, and license number of the reporting licensee;

     (b) The name of the individual preparing the report;

     (c) The manufacturer, model, and serial number of the source;

     (d) The radioactive material in the source;

     (e) The initial source strength in becquerels (curies) at the time of manufacture; and

     (f) The manufacture date of the source.

     (2) Each licensee that transfers a nationally tracked source to another person shall complete and submit a National Source Tracking Transaction Report. The report must include the following information:

     (a) The name, address, and license number of the reporting licensee;

     (b) The name of the individual preparing the report;

     (c) The name and license number of the recipient facility and the shipping address;

     (d) The manufacturer, model, and serial number of the source or, if not available, other information to uniquely identify the source;

     (e) The radioactive material in the source;

     (f) The initial or current source strength in becquerels (curies);

     (g) The date for which the source strength is reported;

     (h) The shipping date;

     (i) The estimated arrival date; and

     (j) For nationally tracked sources transferred as waste under a Uniform Low-Level Radioactive Waste Manifest, the waste manifest number and the container identification of the container with the nationally tracked source.

     (3) Each licensee that receives a nationally tracked source shall complete and submit a National Source Tracking Transaction Report. The report must include the following information:

     (a) The name, address, and license number of the reporting licensee;

     (b) The name of the individual preparing the report;

     (c) The name, address, and license number of the person that provided the source;

     (d) The manufacturer, model, and serial number of the source or, if not available, other information to uniquely identify the source;

     (e) The radioactive material in the source;

     (f) The initial or current source strength in becquerels (curies);

     (g) The date for which the source strength is reported;

     (h) The date of receipt; and

     (i) For material received under a Uniform Low-Level Radioactive Waste Manifest, the waste manifest number and the container identification with the nationally tracked source.

     (4) Each licensee that disassembles a nationally tracked source shall complete and submit a National Source Tracking Transaction Report. The report must include the following information:

     (a) The name, address, and license number of the reporting licensee;

     (b) The name of the individual preparing the report;

     (c) The manufacturer, model, and serial number of the source or, if not available, other information to uniquely identify the source;

     (d) The radioactive material in the source;

     (e) The initial or current source strength in becquerels (curies);

     (f) The date for which the source strength is reported; and

     (g) The disassemble date of the source.

     (5) Each licensee who disposes of a nationally tracked source shall complete and submit a National Source Tracking Transaction Report. The report must include the following information:

     (a) The name, address, and license number of the reporting licensee;

     (b) The name of the individual preparing the report;

     (c) The waste manifest number;

     (d) The container identification with the nationally tracked source;

     (e) The date of disposal; and

     (f) The method of disposal.

     (6) The reports discussed in subsections (1) through (5) of this section must be submitted by the close of the next business day after the transaction. A single report may be submitted for multiple sources and transactions. The reports must be submitted to the National Source Tracking System by using:

     (a) The on-line National Source Tracking System;

     (b) Electronically using a computer-readable format;

     (c) By facsimile;

     (d) By mail to the address on the National Source Tracking Transaction Report Form (NRC Form 748); or

     (e) By telephone with follow-up by facsimile or mail.

     (7) Each licensee shall correct any error in previously filed reports or file a new report for any missed transaction within five business days of the discovery of the error or missed transaction. Such errors may be detected by a variety of methods such as administrative reviews or by physical inventories required by regulation. In addition, each licensee shall reconcile the inventory of nationally tracked sources possessed by the licensee against that licensee's data in the National Source Tracking System. The reconciliation must be conducted during the month of January in each year. The reconciliation process must include resolving any discrepancies between the National Source Tracking System and the actual inventory by filing the reports identified by subsections (1) through (5) of this section. By January 31 of each year, each licensee must submit to the National Source Tracking System confirmation that the data in the National Source Tracking System is correct.

     (8) Each licensee that possesses Category 1 nationally tracked sources shall report its initial inventory of Category 1 nationally tracked sources to the National Source Tracking System by January 31, 2009. Each licensee that possesses Category 2 nationally tracked sources shall report its initial inventory of Category 2 nationally tracked sources to the National Source Tracking System by January 9, 2009. The information may be submitted by using any of the methods identified by subsection (7)(a) through (d) of this section. The initial inventory report must include the following information:

     (a) The name, address, and license number of the reporting licensee;

     (b) The name of the individual preparing the report;

     (c) The manufacturer, model, and serial number of each nationally tracked source or, if not available, other information to uniquely identify the source;

     (d) The radioactive material in the sealed source;

     (e) The initial or current source strength in becquerels (curies); and

     (f) The date for which the source strength is reported.


Table 1 - Nationally Tracked Source Thresholds

Radioactive Material Category 1 (TBq) Category 1 (Ci) Category 2 (TBq) Category 2 (Ci)
Actinium-227 20 540 0.2 5.4
Americium-241 60 1,600 0.6 16
Americium-241/Be 60 1,600 0.6 16
Californium-252 20 540 0.2 5.4
Cobalt-60 30 810 0.3 8.1
Curium-244 50 1,400 0.5 14
Cesium-137 100 2,700 1 27
Gadolinium-153 1,000 27,000 10 270
Iridium-192 80 2,200 0.8 22
Plutonium-238 60 1,600 0.6 16
Plutonium-239/Be 60 1,600 0.6 16
Polonium-210 60 1,600 0.6 16
Promethium-147 40,000 1,100,000 400 11,000
Radium-226 40 1,100 0.4 11
Selenium-75 200 5,400 2 54
Strontium-90 1,000 27,000 10 270
Thorium-228 20 540 0.2 5.4
Thorium-229 20 540 0.2 5.4
Thulium-170 20,000 540,000 200 5,400
Ytterbium-169 300 8,100 3 81

[]


AMENDATORY SECTION(Amending WSR 95-01-108, filed 12/21/94, effective 1/21/95)

WAC 246-235-150   Schedule C -- Quantities of radioactive materials requiring consideration of the need for an emergency plan for responding to a release.  

Radioactive material1 Release

fraction

 Possession

limit (curies)
Actinium-228 0.001 4,000
Americium-241 .001 2
Americium-242 .001 2
Americium-243 .001 2
Antimony-124 .01 4,000
Antimony-126 .01 6,000
Barium-133 .01 10,000
Barium-140 .01 30,000
Bismuth-207 .01 5,000
Bismuth-210 .01 600
Cadmium-109 .01 1,000
Cadmium-113 .01 80
Calcium-45 .01 20,000
Californium-2522 .001 9
Carbon-143 .01 50,000
Cerium-141 .01 10,000
Cerium-144 .01 300
Cesium-134 .01 2,000
Cesium-137 .01 3,000
Chlorine-36 .5 100
Chromium-51 .01 300,000
Cobalt-60 .001 5,000
Copper-64 .01 200,000
Curium-242 .001 60
Curium-243 .001 3
Curium-244 .001 4
Curium-245 .001 2
Europium-152 .01 500
Europium-154 .01 400
Europium-155 .01 3,000
Germanium-68 .01 2,000
Gadolinium-153 .01 5,000
Gold-198 .01 30,000
Hafnium-172 .01 400
Hafnium-181 .01 7,000
Holmium-166m .01 100
Hydrogen-3 .5 20,000
Iodine-125 .5 10
Iodine-131 .5 10
Indium-114m .01 1,000
Iridium-192 .001 40,000
Iron-55 .01 40,000
Iron-59 .01 7,000
Krypton-85 1.0 6,000,000
Lead-210 .01 8
Manganese-56 .01 60,000
Mercury-203 .01 10,000
Molybdenum-99 .01 30,000
Neptunium-237 .001 2
Nickel-63 .01 20,000
Niobium-94 .01 300
Phosphorus-32 .5 100
Phosphorus-33 .5 1,000
Polonium-210 .01 10
Potassium-42 .01 9,000
Promethium-145 .01 4,000
Promethium-147 .01 4,000
Radium-226 0.001 100
Ruthenium-106 .01 200
Samarium-151 .01 4,000
Scandium-46 .01 3,000
Selenium-75 .01 10,000
Silver-110m .01 1,000
Sodium-22 .01 9,000
Sodium-24 .01 10,000
Strontium-89 .01 3,000
Strontium-90 .01 90
Sulfur-35 .5 900
Technetium-99 .01 10,000
Technetium-99m .01 400,000
Tellurium-127m .01 5,000
Tellurium-129m .01 5,000
Terbium-160 .01 4,000
Thulium-170 .01 4,000
Tin-113 .01 10,000
Tin-123 .01 3,000
Tin-126 .01 1,000
Titanium-44 .01 100
Uranium Hexafluoride .001 Note4
Vanadium-48 .01 7,000
Xenon-133 1.0 900,000
Yttrium-91 .01 2,000
Zinc-65 .01 5,000
Zirconium-93 .01 400
Zirconium-95 .01 5,000
Any other beta-gamma emitter .01 10,000
Mixed fission products .01 1,000
Mixed corrosion products .01 10,000
Contaminated equipment beta-gamma .001 10,000
Irradiated material, any form other than solid noncombustible .01 1,000
Irradiated material, solid noncombustible .001 10,000
Mixed radioactive waste, beta-gamma .01 1,000
Packaged mixed waste, beta-gamma5 .001 10,000
Any other alpha emitter .001 2
Contaminated equipment, alpha .0001 20
Packaged waste, alpha5 .0001 20
Combinations of radioactive materials listed above1


1 For combinations of radioactive materials, consideration of the need for an emergency plan is required if the sum of the ratios of the quantity of each radioactive material authorized to the quantity listed for that material in Schedule C exceeds one.
2 For Californium-252, the quantity may also be expressed as 20 milligrams.
3 Excludes Carbon-14 as carbon dioxide.
4 For uranium hexafluoride, the quantity is 50 kilograms in a single container or 1,000 kilograms total.
5 Waste packaged in Type B containers does not require an emergency plan.

[Statutory Authority: RCW 70.98.050. 95-01-108, § 246-235-150, filed 12/21/94, effective 1/21/95.]

OTS-1824.2


AMENDATORY SECTION(Amending WSR 07-14-131, filed 7/3/07, effective 8/3/07)

WAC 246-240-010   Definitions.   Address of use means the building or buildings that are identified on the license and where radioactive material may be received, prepared, used, or stored.

     Area of use means a portion of an address of use that has been set aside for the purpose of receiving, preparing, using, or storing radioactive material.

     Authorized medical physicist means an individual who:

     (1) Meets the requirements in WAC 246-240-072 and 246-240-081; or

     (2) Is identified as an authorized medical physicist or teletherapy physicist on:

     (a) A specific medical use license issued by the department, the U.S. Nuclear Regulatory Commission or an agreement state;

     (b) A medical use permit issued by a U.S. NRC master material licensee;

     (c) A permit issued by a U.S. NRC or agreement state broad scope medical use licensee; or

     (d) A permit issued by a U.S. NRC master material license broad scope medical use permittee.

     Authorized nuclear pharmacist means a pharmacist who:

     (1) Meets the requirements in WAC 246-240-075 and 246-240-081; or

     (2) Is identified as an authorized nuclear pharmacist on:

     (a) A specific license issued by the department, the U.S. NRC or an agreement state, that authorizes medical use or the practice of nuclear pharmacy;

     (b) A permit issued by a U.S. NRC master material licensee that authorizes medical use or the practice of nuclear pharmacy;

     (c) A permit issued by a U.S. NRC or agreement state broad scope medical use licensee that authorizes medical use or the practice of nuclear pharmacy; or

     (d) A permit issued by a U.S. NRC master material license broad scope medical use permittee that authorizes medical use or the practice of nuclear pharmacy; or

     (3) Is identified as an authorized nuclear pharmacist by a commercial nuclear pharmacy that has been authorized to identify authorized nuclear pharmacists; or

     (4) Is designated as an authorized nuclear pharmacist in accordance with WAC 246-235-100(2).

     Authorized user means a physician, dentist, or podiatrist who:

     (1) Meets the requirements in WAC 246-240-081 and 246-240-154, 246-240-163, 246-240-210, 246-240-213, 246-240-216, 246-240-278, 246-240-301, or 246-240-399; or

     (2) Is identified as an authorized user on:

     (a) A department, U.S. NRC, or agreement state license that authorizes the medical use of radioactive material;

     (b) A permit issued by a U.S. NRC master material licensee that is authorized to permit the medical use of radioactive material;

     (c) A permit issued by a department, U.S. NRC, or agreement state specific licensee of broad scope that is authorized to permit the medical use of radioactive material; or

     (d) A permit issued by a U.S. NRC master material license broad scope permittee that is authorized to permit the medical use of radioactive material.

     Brachytherapy means a method of radiation therapy in which sources are used to deliver a radiation dose at a distance of up to a few centimeters by surface, intracavitary, intraluminal, or interstitial application.

     Brachytherapy source means a radioactive source or a manufacturer-assembled source train or a combination of these sources that is designed to deliver a therapeutic dose within a distance of a few centimeters.

     Client's address means the area of use or a temporary job site for the purpose of providing mobile medical service in accordance with WAC 246-240-125.

     Cyclotron means a particle accelerator in which the charged particles travel in an outward spiral or circular path. A cyclotron accelerates charged particles at energies usually in excess of 10 megaelectron volts and is commonly used for production of short half-life radionuclides for medical use.

     Dedicated check source means a radioactive source that is used to assure the constant operation of a radiation detection or measurement device over several months or years.

     Dentist means an individual licensed by a state or territory of the United States, the District of Columbia, or the Commonwealth of Puerto Rico to practice dentistry.

     High dose-rate remote afterloader, as used in this chapter, means a brachytherapy device that remotely delivers a dose rate in excess of 12 gray (1200 rads) per hour at the point or surface where the dose is prescribed.

     Low dose-rate remote afterloader, as used in this chapter, means a brachytherapy device that remotely delivers a dose rate of less than or equal to 2 gray (200 rads) per hour at the point or surface where the dose is prescribed.

     Management means the chief executive officer or other individual having the authority to manage, direct, or administer the licensee's activities, or that person's delegate or delegates.

     Manual brachytherapy, as used in this chapter, means a type of brachytherapy in which the brachytherapy sources (e.g., seeds, ribbons) are manually placed topically on or inserted either into the body cavities that are in close proximity to a treatment site or directly into the tissue volume.

     Medical event means an event that meets the criteria in WAC 246-240-651.

     Medical institution means an organization in which more than one medical discipline is practiced.

     Medical use means the intentional internal or external administration of radioactive material or the radiation from radioactive material to patients or human research subjects under the supervision of an authorized user.

     Medium dose-rate remote afterloader, as used in this chapter, means a brachytherapy device that remotely delivers a dose rate of greater than 2 gray (200 rads), but less than or equal to 12 grays (1200 rads) per hour at the point or surface where the dose is prescribed.

     Mobile medical service means the transportation of radioactive material to and its medical use at the client's address.

     Output means the exposure rate, dose rate, or a quantity related in a known manner to these rates from a brachytherapy source or a teletherapy, remote afterloader, or gamma stereotactic radiosurgery unit for a specified set of exposure conditions.

     Patient intervention means actions by the patient or human research subject, whether intentional or unintentional, such as dislodging or removing treatment devices or prematurely terminating the administration.

     Podiatrist means an individual licensed by a state or territory of the United States, the District of Columbia, or the Commonwealth of Puerto Rico to practice podiatry.

     Positron emission tomography (PET) radionuclide production facility means a facility operating an accelerator for the purpose of producing PET radionuclides.

     Preceptor means an individual who provides, directs, or verifies training and experience required for an individual to become an authorized user, an authorized medical physicist, an authorized nuclear pharmacist, or a radiation safety officer.

     Prescribed dosage means the specified activity or range of activity of unsealed radioactive material as documented:

     (1) In a written directive; or

     (2) In accordance with the directions of the authorized user for procedures performed under WAC 246-240-151 and 246-240-157.

     Prescribed dose means:

     (1) For gamma stereotactic radiosurgery, the total dose as documented in the written directive;

     (2) For teletherapy, the total dose and dose per fraction as documented in the written directive;

     (3) For manual brachytherapy, either the total source strength and exposure time or the total dose, as documented in the written directive; or

     (4) For remote brachytherapy afterloaders, the total dose and dose per fraction as documented in the written directive.

     Pulsed dose-rate remote afterloader, as used in this chapter, means a special type of remote afterloading brachytherapy device that uses a single source capable of delivering dose rates in the "high dose-rate" range, but:

     (1) Is approximately one-tenth of the activity of typical high dose-rate remote afterloader sources; and

     (2) Is used to simulate the radiobiology of a low dose-rate treatment by inserting the source for a given fraction of each hour.

     Radiation safety officer means an individual who:

     (1) Meets the requirements in WAC 246-240-069 and 246-240-081; or

     (2) Is identified as a radiation safety officer on a specific medical use license issued by the department prior to October 5, 2005, the U.S. NRC or an agreement state; or

     (3) A medical use permit issued by a commission master material licensee.

     Sealed source and device registry means the national registry that contains all the registration certificates, generated by both the U.S. NRC and the agreement states, that summarize the radiation safety information for the sealed sources and devices and describe the licensing and use conditions approved for the product.

     Stereotactic radiosurgery means the use of external radiation in conjunction with a stereotactic guidance device to very precisely deliver a therapeutic dose to a tissue volume.

     Structured educational program means an educational program designed to impart particular knowledge and practical education through interrelated studies and supervised training.

     Teletherapy, as used in this chapter, means a method of radiation therapy in which collimated gamma rays are delivered at a distance from the patient or human research subject.

     Temporary job site means a location where mobile medical services are conducted other than those location(s) of use authorized on the license.

     Therapeutic dosage means a dosage of unsealed radioactive material that is intended to deliver a radiation dose to a patient or human research subject for palliative or curative treatment.

     Therapeutic dose means a radiation dose delivered from a source containing radioactive material to a patient or human research subject for palliative or curative treatment.

     Treatment site means the anatomical description of the tissue intended to receive a radiation dose, as described in a written directive.

     Type of use means use of radioactive material under WAC 246-240-151, 246-240-157, 246-240-201, 246-240-251, 246-240-301, 246-240-351, or 246-240-501.

     Unit dosage means a dosage prepared for medical use for administration as a single dosage to a patient or human research subject without any further manipulation of the dosage after it is initially prepared.

     Written directive means an authorized user's written order for the administration of radioactive material or radiation from radioactive material to a specific patient or human research subject, as specified in WAC 246-240-060.

[Statutory Authority: RCW 70.98.050. 07-14-131, § 246-240-010, filed 7/3/07, effective 8/3/07; 06-05-019, § 246-240-010, filed 2/6/06, effective 3/9/06; 98-13-037, § 246-240-010, filed 6/8/98, effective 7/9/98. Statutory Authority: RCW 70.98.050 and 70.98.080. 92-06-008 (Order 245), § 246-240-010, filed 2/21/92, effective 3/23/92.]


AMENDATORY SECTION(Amending WSR 06-05-019, filed 2/6/06, effective 3/9/06)

WAC 246-240-060   Written directives.   (1) A written directive must be dated and signed by an authorized user before the administration of I-131 sodium iodide greater than 1.11 megabecquerels (((MBq))) (30 microcuries (((µCi)))), any therapeutic dosage of unsealed radioactive material or any therapeutic dose of radiation from radioactive material.

     If, because of the emergent nature of the patient's condition, a delay in order to provide a written directive would jeopardize the patient's health, an oral directive is acceptable. The information contained in the oral directive must be documented as soon as possible in writing in the patient's record. A written directive must be prepared within forty-eight hours of the oral directive.

     (2) The written directive must contain the patient or human research subject's name and the following information:

     (a) For any administration of quantities greater than 1.11 ((MBq)) megabecquerels (30 ((µCi)) microcuries) of sodium iodide I-131: The dosage;

     (b) For an administration of a therapeutic dosage of unsealed radioactive material other than sodium iodide I-131: The radioactive drug, dosage, and route of administration;

     (c) For gamma stereotactic radiosurgery: The total dose, treatment site, and values for the target coordinate settings per treatment for each anatomically distinct treatment site;

     (d) For teletherapy: The total dose, dose per fraction, number of fractions, and treatment site;

     (e) For high dose-rate remote afterloading brachytherapy: The radionuclide, treatment site, dose per fraction, number of fractions, and total dose; or

     (f) For all other brachytherapy, including low, medium, and pulsed dose rate remote afterloaders:

     (i) Before implantation: Treatment site, the radionuclide, and dose; and

     (ii) After implantation but before completion of the procedure: The radionuclide, treatment site, number of sources, and total source strength and exposure time (or the total dose).

     (3) A written revision to an existing written directive may be made if the revision is dated and signed by an authorized user before the administration of the dosage of unsealed radioactive material, the brachytherapy dose, the gamma stereotactic radiosurgery dose, the teletherapy dose, or the next fractional dose.

     If, because of the patient's condition, a delay in order to provide a written revision to an existing written directive would jeopardize the patient's health, an oral revision to an existing written directive is acceptable. The oral revision must be documented as soon as possible in the patient's record. A revised written directive must be signed by the authorized user within forty-eight hours of the oral revision.

     (4) The licensee shall retain a copy of the written directive in accordance with WAC 246-240-557.

[Statutory Authority: RCW 70.98.050. 06-05-019, § 246-240-060, filed 2/6/06, effective 3/9/06.]


AMENDATORY SECTION(Amending WSR 06-05-019, filed 2/6/06, effective 3/9/06)

WAC 246-240-107   Determination of dosages of unsealed radioactive material for medical use.   (1) A licensee shall determine and record the activity of each dosage before medical use.

     (2) For a unit dosage, this determination must be made by:

     (a) Direct measurement of radioactivity; or

     (b) A decay correction, based on the activity or activity concentration determined by:

     (i) A manufacturer, producer, or preparer licensed under WAC 246-235-100 or equivalent U.S. NRC or agreement state requirements; or

     (ii) An agreement state or U.S. NRC licensee for use in research in accordance with a radioactive drug research committee-approved protocol or an investigational new drug (IND) protocol accepted by FDA.

     (3) For other than unit dosages, this determination must be made by:

     (a) Direct measurement of radioactivity;

     (b) Combination of measurement of radioactivity and mathematical calculations; or

     (c) Combination of volumetric measurements and mathematical calculations, based on the measurement made by a manufacturer, producer, or preparer licensed under WAC 246-235-100 or equivalent agreement state requirements.

     (4) Unless otherwise directed by the authorized user, a licensee may not use a dosage if the dosage does not fall within the prescribed dosage range or if the dosage differs from the prescribed dosage by more than twenty percent.

     (5) A licensee shall retain a record of the dosage determination required by this section in accordance with WAC 246-240-569.

[Statutory Authority: RCW 70.98.050. 06-05-019, § 246-240-107, filed 2/6/06, effective 3/9/06.]


AMENDATORY SECTION(Amending WSR 07-14-131, filed 7/3/07, effective 8/3/07)

WAC 246-240-110   Authorization for calibration, transmission, and reference sources.   Any person authorized by WAC 246-240-016 for medical use of radioactive material may receive, possess, and use any of the following radioactive material for check, calibration, transmission, and reference use:

     (1) Sealed sources, not exceeding 1.11 ((GBq)) gigabecquerels (30 ((mCi)) millicuries) each, manufactured and distributed by a person licensed under WAC 246-235-102 or equivalent agreement state or U.S. NRC regulations.

     (2) Sealed sources, not exceeding 1.11 ((GBq)) gigabecquerels (30 ((mCi)) millicuries) each, redistributed by a licensee authorized to redistribute the sealed sources manufactured and distributed by a person licensed under WAC 246-235-102, or equivalent agreement state or U.S. NRC regulations if the redistributed sealed sources are in the original packaging and shielding and are accompanied by the manufacturer's approved instructions.

     (3) Any radioactive material with a half-life not longer than one hundred twenty days in individual amounts not to exceed 0.56 ((GBq)) gigabecquerels (15 ((mCi)) millicuries).

     (4) Any radioactive material with a half-life longer than one hundred twenty days in individual amounts not to exceed the smaller of 7.4 ((MBq)) megabecquerels (200 ((µCi)) microcuries) or 1000 times the quantities in Schedule B of WAC 246-232-120.

     (5) Technetium-99m in amounts as needed.

[Statutory Authority: RCW 70.98.050. 07-14-131, § 246-240-110, filed 7/3/07, effective 8/3/07; 06-05-019, § 246-240-110, filed 2/6/06, effective 3/9/06.]


AMENDATORY SECTION(Amending WSR 06-05-019, filed 2/6/06, effective 3/9/06)

WAC 246-240-113   Requirements for possession of sealed sources and brachytherapy sources.   (1) A licensee in possession of any sealed source or brachytherapy source shall follow the radiation safety and handling instructions supplied by the manufacturer.

     (2) A licensee in possession of a sealed source shall:

     (a) Test the source for leakage before its first use unless the licensee has a certificate from the supplier indicating that the source was tested within six months before transfer to the licensee; and

     (b) Test the source for leakage at intervals not to exceed six months or at other intervals approved by the department, the U.S. NRC, or an agreement state in the sealed source and device registry.

     (3) To satisfy the leak test requirements of this section, the licensee shall ensure the sample is analyzed by such method that the leak test can detect the presence of 185 ((Bq)) becquerels (0.005 ((µCi)) microcuries) of radioactive material in the sample.

     (4) A licensee shall retain leak test records in accordance with WAC 246-240-572(1).

     (5) If the leak test reveals the presence of 185 ((Bq)) becquerels (0.005 ((µCi)) microcuries) or more of removable contamination, the licensee shall:

     (a) Immediately withdraw the sealed source from use and store, dispose, or cause it to be repaired in accordance with the requirements in chapters 246-221 and 246-232 WAC; and

     (b) File a report within five days of the leak test in accordance with WAC 246-240-657.

     (6) A licensee need not perform a leak test on the following sources:

     (a) Sources containing only radioactive material with a half-life of less than thirty days;

     (b) Sources containing only radioactive material as a gas;

     (c) Sources containing 3.7 ((MBq)) megabecquerels (100 ((µCi)) microcuries) or less of beta-or gamma-emitting material or 0.37 ((MBq)) megabecquerels (10 ((µCi)) microcuries) or less of alpha-emitting material;

     (d) Seeds of iridium-192 encased in nylon ribbon; and

     (e) Sources stored and not being used. However, the licensee shall test each source for leakage before any use or transfer unless it has been leak tested within six months before the date of use or transfer.

     (7) A licensee in possession of sealed sources or brachytherapy sources, except for gamma stereotactic radiosurgery sources, shall conduct a physical inventory of all the sources in its possession at intervals not to exceed six months. The licensee shall retain each inventory record in accordance with WAC 246-240-572.

[Statutory Authority: RCW 70.98.050. 06-05-019, § 246-240-113, filed 2/6/06, effective 3/9/06.]


AMENDATORY SECTION(Amending WSR 07-14-131, filed 7/3/07, effective 8/3/07)

WAC 246-240-151   Use of unsealed radioactive material for uptake, dilution, and excretion studies for which a written directive is not required.   Except for quantities that require a written directive under WAC 246-240-060(2), a licensee may use any unsealed radioactive material prepared for medical use for uptake, dilution, or excretion studies that is:

     (1) Obtained from a manufacturer, producer, or preparer licensed under WAC 246-235-100(1) or equivalent U.S. NRC or agreement state requirements; or

     (2) Prepared by an authorized nuclear pharmacist, or a physician who is an authorized user and who meets the requirements specified in WAC 246-240-163, or 246-240-210 and 246-240-163 (3)(a)(ii)(G), or an individual under the supervision of either as specified in WAC 246-240-057; or

     (3) Obtained from and prepared by an agreement state or U.S. NRC licensee for use in research in accordance with a radioactive drug research committee-approved protocol or an investigational new drug (IND) protocol accepted by FDA; or

     (4) Prepared by the licensee for use in research in accordance with a radioactive drug research committee-approved application or an investigational new drug (IND) protocol accepted by FDA.

[Statutory Authority: RCW 70.98.050. 07-14-131, § 246-240-151, filed 7/3/07, effective 8/3/07; 06-05-019, § 246-240-151, filed 2/6/06, effective 3/9/06.]


AMENDATORY SECTION(Amending WSR 07-14-131, filed 7/3/07, effective 8/3/07)

WAC 246-240-157   Use of unsealed radioactive material for imaging and localization studies for which a written directive is not required.   Except for quantities that require a written directive under WAC 246-240-060(2), a licensee may use any unsealed radioactive material prepared for medical use for imaging and localization studies that is:

     (1) Obtained from a manufacturer, producer, or preparer licensed under WAC 246-235-100(1) or equivalent agreement state or U.S. NRC requirements; or

     (2) Prepared by an authorized nuclear pharmacist, a physician who is an authorized user and who meets the requirements specified in WAC 246-240-163, or 246-240-210 and 246-240-163 (3)(a)(ii)(G), or an individual under the supervision of either as specified in WAC 246-240-057;

     (3) Obtained from and prepared by an agreement state or U.S. NRC licensee for use in research in accordance with a radioactive drug research committee-approved protocol or an investigational new drug (IND) protocol accepted by FDA; or

     (4) Prepared by the licensee for use in research in accordance with a radioactive drug research committee-approved application or an investigational new drug (IND) protocol accepted by FDA.

[Statutory Authority: RCW 70.98.050. 07-14-131, § 246-240-157, filed 7/3/07, effective 8/3/07; 06-05-019, § 246-240-157, filed 2/6/06, effective 3/9/06.]


AMENDATORY SECTION(Amending WSR 06-05-019, filed 2/6/06, effective 3/9/06)

WAC 246-240-160   Permissible molybdenum-99 concentration.   (1) A licensee may not administer to humans a radiopharmaceutical that contains more than:

     (a) 5.55 kilobecquerel of molybdenum-99 per 37 megabecquerel of technetium-99m (0.15 microcurie of molybdenum-99 per millicurie of technetium-99m); or

     (b) 0.02 kilobecquerel of strontium-82 per megabecquerel of rubidium-82 chloride injection, (0.02 microcurie of strontium-82 per millicurie of rubidium-82 chloride); or

     (c) 0.2 kilobecquerel of strontium-85 per megabecquerel of rubidium-82 chloride injection (0.2 microcurie of strontium-85 per millicurie of rubidium-82).

     (2) A licensee that uses molybdenum-99/technetium-99m generators for preparing a technetium-99m radiopharmaceutical shall measure the molybdenum-99 concentration of the first eluate after receipt of a generator to demonstrate compliance with subsection (1) of this section.

     (3) A licensee that uses a strontium-82/rubidium-82 generator for preparing a rubidium-82 radiopharmaceutical shall, before the first patient use of the day, measure the concentration of strontium-82 and strontium-85 to demonstrate compliance with subsection (1)(a) of this section.

     (4) If a licensee is required to measure the molybdenum-99 concentration, or strontium-82 and strontium-85 concentrations the licensee shall retain a record of each measurement in accordance with WAC 246-240-587.

[Statutory Authority: RCW 70.98.050. 06-05-019, § 246-240-160, filed 2/6/06, effective 3/9/06.]


AMENDATORY SECTION(Amending WSR 06-05-019, filed 2/6/06, effective 3/9/06)

WAC 246-240-201   Use of unsealed radioactive material for which a written directive is required.   A licensee may use any unsealed radioactive material prepared for medical use and for which a written directive is required that is:

     (1) Obtained from a manufacturer, producer, or preparer licensed under WAC 246-235-100(1) or equivalent agreement state or U.S. NRC requirements; or

     (2) Prepared by an authorized nuclear pharmacist, a physician who is an authorized user and who meets the requirements specified in WAC 246-240-163 or 246-240-210, or an individual under the supervision of either as specified in WAC 246-240-057; or

     (3) Obtained from and prepared by an agreement state or U.S. NRC licensee for use in research in accordance with an investigational new drug (IND) protocol accepted by FDA; or

     (4) Prepared by the licensee for use in research in accordance with an investigational new drug (IND) protocol accepted by FDA.

[Statutory Authority: RCW 70.98.050. 06-05-019, § 246-240-201, filed 2/6/06, effective 3/9/06.]


AMENDATORY SECTION(Amending WSR 06-05-019, filed 2/6/06, effective 3/9/06)

WAC 246-240-569   Records of dosages of unsealed radioactive material for medical use.   (1) A licensee shall maintain a record of dosage determinations required by WAC 246-240-107 for three years.

     (2) The record must contain:

     (a) The radiopharmaceutical;

     (b) The patient's or human research subject's name, or identification number if one has been assigned;

     (c) The prescribed dosage, the determined dosage, or a notation that the total activity is less than 1.1 ((MBq)) megabecquerels (30 ((µCi)) microcuries);

     (d) The date and time of the dosage determination; and

     (e) The name of the individual who determined the dosage.

[Statutory Authority: RCW 70.98.050. 06-05-019, § 246-240-569, filed 2/6/06, effective 3/9/06.]


AMENDATORY SECTION(Amending WSR 06-05-019, filed 2/6/06, effective 3/9/06)

WAC 246-240-587   Records of molybdenum-99, strontium-82, and strontium-85 concentrations.   A licensee shall maintain a record of the molybdenum-99, strontium-82, and/or strontium-85 concentration tests required by WAC 246-240-160(2) for three years.

     (1) The record must include, for each measured elution of technetium-99m, the ratio of the measures expressed as kilobecquerels of molybdenum-99 per megabecquerel of technetium-99m (or microcuries of molybdenum per millicurie of technetium), the time and date of the measurement, and the name of the individual who made the measurement.

     (2) For each measured elution of rubidium-82, the ratio of the measures expressed as kilobecquerels of strontium-82 per megabecquerel of rubidium-82 (or microcuries of strontium-82 per millicurie of rubidium), and/or kilobecquerels of strontium-85 per megabecquerel of rubidium-82 (or microcuries of strontium-85 per millicurie of rubidium), the time and date of the measurement, and the name of the individual who made the measurement.

[Statutory Authority: RCW 70.98.050. 06-05-019, § 246-240-587, filed 2/6/06, effective 3/9/06.]


AMENDATORY SECTION(Amending WSR 06-05-019, filed 2/6/06, effective 3/9/06)

WAC 246-240-657   Report of a leaking source.   A licensee shall file a report within five days if a leak test required by WAC 246-240-113 reveals the presence of 185 ((Bq)) becquerels (0.005 ((µCi)) microcuries) or more of removable contamination. The report must be filed with the department, and sent to the department at P.O. Box 47827, Olympia WA 98504-7827, (phone 360-236-3300). The written report must include the model number and serial number if assigned, of the leaking source; the radionuclide and its estimated activity; the results of the test; the date of the test; and the action taken.

[Statutory Authority: RCW 70.98.050. 06-05-019, § 246-240-657, filed 2/6/06, effective 3/9/06.]

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