PROPOSED RULES
Original Notice.
Exempt from preproposal statement of inquiry under RCW 34.05.310(4).
Title of Rule and Other Identifying Information: Chapters 246-220, 246-221, 246-232, 246-233, 246-235, and 246-240 WAC, radiation protection.
Hearing Location(s): Department of Health, Town Center 2, Room 530, 111 Israel Road S.E., Olympia, WA 98504, on December 2, 2008, at 2:00 p.m.
Date of Intended Adoption: December 2, 2008.
Submit Written Comments to: C. DeMaris, P.O. Box 47827, Olympia, WA 98504-7827, web site http://www3.doh.wa.gov/policyreview/, fax (360) 236-2255, by November 25, 2008.
Assistance for Persons with Disabilities: Contact Joy Redman by November 25, 2008, TTY (800) 833-6388 or 711.
Purpose of the Proposal and Its Anticipated Effects, Including Any Changes in Existing Rules: The purpose of this proposal is to protect public health by better regulating sources of ionizing radiation, address two new federal rules, and correct minor grammatical errors in previously adopted rules. The proposed rules incorporate the nuclear regulatory commission's expanded definition of by-product material and National Source Tracking System (NSTS) requirements. The rules affect radium 226, accelerator-produced materials, and discrete sources of naturally occurring radioactive material. The NSTS adds a measure of security by fostering licensee awareness and concern for sources in their inventory.
Reasons Supporting Proposal: This rule is required for compliance with a formal agreement signed in 1966 between the state of Washington and the Atomic Energy Commission under section 274 of the Atomic Energy Act of 1954 as amended (42 U.S.C. Section 2021), the Energy Policy Act of 2005, and RCW 70.98.050.
Statutory Authority for Adoption: RCW 70.98.050 and 70.98.080.
Statute Being Implemented: RCW 70.98.050.
Rule is necessary because of federal law, 69 F.R. 3,698 (2004); 71 F.R. 65,686 (2006); 72 F.R. 45,147 (2007); 72 F.R. 55,864 (2007); 72 F.R. 59,162 (2007).
Name of Proponent: Department of health, governmental.
Name of Agency Personnel Responsible for Drafting: Anine Grumbles, 101 Israel Road S.E., Tumwater, WA, (360) 236-3222; Implementation and Enforcement: Arden Scroggs, 101 Israel Road S.E., Tumwater, WA, (360) 236-3221.
No small business economic impact statement has been prepared under chapter 19.85 RCW. A small business economic impact statement (SBEIS) was not prepared. Under RCW 19.85.025 and 34.05.310 (4)(c), an SBEIS is not required for proposed rules that adopt or incorporate by reference - without material change - federal statutes or regulations, the rules of other Washington state agencies, or national consensus codes that generally establish industry standards.
A cost-benefit analysis is not required under RCW 34.05.328. The agency did not complete a cost-benefit analysis under RCW 34.05.328. RCW 34.05.328 (5)(b)(iii) exempts rules that adopt or incorporate by reference without material change federal statutes or regulations, the rules of other Washington state agencies, or national consensus codes that generally establish industry standards.
October 15, 2008
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 |
EQUIVALENT FOR MONOENERGETIC NEUTRONS Energy (MeV) (Q) Dose
Equivalentb (neutrons cm-2 rem-1) Dose
Equivalentb (neutrons cm-2 Sv-1) (( (( (( (( (( (( (( (( (( (( (( (( (( (( (( (( (( (( (( (( (( (( (( (( (( (( (( (( (( (( (( (( (( (( (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. (( 350 200 200 (( (( (( (( (( (( (( (( (( (( (( (( (( "Waste handling licensees" mean persons licensed to
receive and store radioactive wastes prior to disposal and/or
persons licensed to dispose of radioactive waste. (( (( Tissue wT (( (( (( (( ((
[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-1821.2 (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.
[] (TBq) (Ci) (TBq) (Ci)
[] Number Number Occupational Values Effluent Concentration Releases
to Sewers Oral Ingestion Inhalation Average Concen- tration µCi µCi µCi/ml µCi/ml µCi/ml µCi/ml skin absorption 8E+4 8E+4 2E-5 1E-7 1E-3 1E-2 those given for Y Na, K, Rb, Cs, and Fr (5E+4) 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 - 8E+4 3E-5 1E-7 - - - those given for W carbides, halides, and
nitrates those given for W carbides, halides, and
nitrates those given for W and Y carbides, and nitrates Y, aluminosilicate glass - 3E+4 1E-5 4E-8 - - phosphates given for W S3+, Mg2+, Fe3+, Bi3+, and lanthanides except those given for W 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 - 2E+3 9E-7 3E-9 - - Na, K, Rb, Cs, and Fr 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 (3E+4) (4E+4) (4E+4) (5E+4) those given for W and Y carbides, halides, and
nitrates those given for W (3E+4) carbides, and halides those given for W and Y those given for W halides, and nitrates (4E+4) those given for W and halides those given for Y halides, and nitrates (1E+6) (5E+4) those given for W and carbides those given for W and Y (3E+4) and nitrates - 1E+5 5E-5 2E-7 - - (3E+4) those given for W (6E+4) carbides, halides, and
nitrates (7E+4) those given for W (4E+4) (7E+4) (2E+4) (4E+4) those given for W carbides, and elemental Se (8E+4) Na, K, Rb, Cs, and Fr (2E+4) 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) (4E+4) (9E+4) (7E+4) (3E+4) (6E+4) (3E+5) (3E+4) (6E+4) except SrTiO pounds and SrTi0 those given for Y (3E+4) (5E+4) those given for W and Y halides, and nitrates those given for Y (7E+4) (122 min) those given for Y and MoS 2E+3 5E+3 2E-6 6E-9 - - (5E+4) those given for W halides, and nitrates (7E+3) (6E+3) (1E+5) (3E+4) those given for W and Y those given for W and Y 2E+4 6E+4 2E-5 8E-8 2E-4 2E-3 (9E+4) those given for W and Y those given for W and Y (6E+4) (6E+4) (2E+3) (3E+4) those given for W and Y and nitrates - 1E+5 5E-5 2E-7 - - - - 1E-10 - - those given for W halides, and nitrates (5E+4) those given for W hydroxides, halides, nitrates, and stannic phosphate those given for W 8E+4 2E+5 1E-4 3E-7 1E-3 1E-2 halides, sulfides, sulfates, and nitrates - 3E+5 1E-4 4E-7 - - (9E+4) (5.76 d) (7E+4) (1E+5) - - - 1E-3 1E-2 those given for W and nitrates (2E+2) (6E+4) (9E+4) (1E+5) (1E+5) (3E+4) (5E+5) (7E+1) (3E+2) (4E+4) those given for Y and fluorides those given for Y carbides, and fluorides (4E+4) (8E+4) those given for Y carbides, and fluorides those given for Y (6E+4) carbides, and fluorides (6E+4) (8E+4) (12.62h) (34.2 y) those given for W and fluorides (5.0 h) (24.4 h) (8E+5) (2E+5) (7E+4) - 8E-10 2E-4 2E-3 (9E+4) those given for Y and fluorides those given for Y and fluorides (6E+4) (4E+4) those given for W carbides, and nitrates those given for Y hydroxides, halides, carbides, nitrates, and nitrides (2E+5) those given for W (1E+5) and nitrates (1E+5) (2E+3) (2E+3) (9E+5) those given for W and Y those given for W and Y (4E+4) and metallic iridium those given for W and Y (9E+4) halides, nitrates, and sulfides (1E+5) (7E+4) (3E+5) - (2E+4) those given for W and nitrates those given for W and Y (1E+1) (2E-2) (1E+0) (2E-3) (3E-3) (9E+0) (2E-2) (2E-2) (2E+0) (3E-3) (4E-3) those given for Y (2E+1) (9E+2) (5E-1) (4E-3) (6E-3) (6E+1) (7E+1) (6E+0) (6E-1) (4E+0) (4E-1) (2E+1) (2E+0) (2E+1) (2E+0) (2E+1) (2E+0) (2E+1) (2E+0) (5E+2) (1E+3) (6E+0) (5E-2) (4E+3) (7E+1) (1E+0) (1E-2) (2E+2) except PuO2 (4E+0) (4E-2) (2E+0) (1E-2) (1E+0) (1E-2) (2E-2) (1E+0) (1E-2) (2E-2) (7E+1) (6E-1) - 8E-13 1E-6 1E-5 (1E+0) (1E+0) (1E-2) (2E-2) (2E+0) (1E-2) (2E-2) (6E+3) (1E+0) (1E-2) (1E+0) (1E-2) (9E+1) (1E+0) (1E-2) (8E+4) (7E+3) (3E+2) (6E+4) (8E+1) (6E-1) (4E+1) (5E+1) (3E-1) (2E+0) (2E-2) (3E+0) (2E-2) (1E+0) (1E-2) (1E+0) (1E-2) (1E+0) (1E-2) (4E-1) (3E-3) (3E+4) (6E-2) (5E-4) (1E+0) (9E-3) (5E+2) (4E+0) (7E+2) those given for Y (3E+4) (2E+1) (1E-1) (1E+0) (9E-3) (1E-2) (2E+0) (2E-2) (1E+0) (9E-3) (1E-2) (5E+0) (4E-2) (4E+2) (1E+3) (1E+3) (2E+1) (1E-1) (4E+1) (2E-1) (9E+1) (5E+1) (3E-1) 1"Submersion" means that values given are for submersion in a hemispherical semi-infinite cloud of airborne material. 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. 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 - 7E-3 3E-12 - - - - 7E-2 3E-11 - - - - 7E-1 3E-10 - - - - 7E+0 3E-9 - - - - - - 1E-14 - - - - - 1E-13 - - - - - - 1E-12 - - - - - 1E-6 1E-5 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. 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"). DACB, and DACC, respectively, then the concentrations shall be limited so that the following relationship exists: + + ≤1
[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 spelling error in the above section occurred in the copy filed by the agency and appears in the Register pursuant to the requirements of RCW 34.08.040. 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 (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.] (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) ((
[Statutory Authority: RCW 70.98.050. 01-02-068, §
246-232-008, filed 12/29/00, effective 1/29/01.] (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: (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.] (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.] 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.] align="center" ACCEPTABLE SURFACE CONTAMINATION LEVELS WIPE LIMITS
[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-1823.2 (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.] (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 (( (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.] (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 Name of manufacturer
[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.] (a) The applicant satisfies the general requirements
specified in WAC 246-235-020; (b) The applicant submits evidence that: (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; or (ii) The applicant is licensed as a nuclear pharmacy by
the state board of pharmacy; (iii) The applicant is registered or licensed as a
radiopharmaceutical production facility or nuclear pharmacy
with the U.S. Nuclear Regulatory Commission or 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 labeling requirements
specified by the state board of pharmacy in WAC 246-903-020
for both commercial and noncommercial distribution. 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 (PET) 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 (( (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.] (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.
[] (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.* (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 (( (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
(( (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 (( (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.
[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.]
[] (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
[] fraction limit
(curies)
[Statutory Authority: RCW 70.98.050. 95-01-108, §
246-235-150, filed 12/21/94, effective 1/21/95.] OTS-1824.2 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.] 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 (( (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.] (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.] (1) Sealed sources, not exceeding 1.11 (( (2) Sealed sources, not exceeding 1.11 (( (3) Any radioactive material with a half-life not longer
than one hundred twenty days in individual amounts not to
exceed 0.56 (( (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 (( (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.] (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
(( (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 (( (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 (( (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.] (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.] (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.] (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.] (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.] (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 (( (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.] (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.]
[Statutory Authority: RCW 70.98.050. 06-05-019, §
246-240-657, filed 2/6/06, effective 3/9/06.] OTS-1825.2 (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.
[] (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.
[Statutory Authority: RCW 70.98.050. 04-04-055, §
246-233-015, filed 1/30/04, effective 3/1/04.] (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. (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) and
(iii) of this subsection, devices containing at least 370
(( (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.] (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.] (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.] (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: (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.] (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. (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: (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.]
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
Neutron
Quality
Factora
Fluence per
Unit
Fluence per
Unit
(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:(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)
+
50 (grams U-233)
+
50 (grams Pu)
< 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.(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
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.
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.
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
Category 1
Category 2
Category 2
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
100
2,700
1
27
Gadolinium-153
1,000
27,000
10
270
Iridium-192
80
2,200
0.8
22
Plutonium-328
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
Name
Symbol
Atomic
Actinium
Ac
89
((
Mercury)) Molbdenum((
Hg)) Mo((
80)) 42Aluminum
Al
13
((
Molybdenum))
Neodymium((
Mo)) Nd((
42)) 60Americium
Am
95
((
Neodymium))
Neptunium((
Nd)) Np((
60)) 93Antimony
Sb
51
((
Neptunium)) Nickel((
Np)) Ni((
93)) 28Argon
Ar
18
((
Nickel)) Nitrogen((
Ni)) N((
28)) 7Arsenic
As
33
Niobium
Nb
41
Astatine
At
85
Osmium
Os
76
Barium
Ba
56
((
Palladium)) Oxygen((
Pd)) O((
46)) 8Berkelium
Bk
97
((
Phosphorus)) Palladium((
P)) Pd((
15)) 46Beryllium
Be
4
((
Platinum)) Phosphorus((
Pt)) P((
78)) 15Bismuth
Bi
83
((
Plutonium)) Platinum((
Pu)) Pt((
94)) 78Bromine
Br
35
((
Polonium)) Plutonium((
Po)) Pu((
84)) 94Cadmium
Cd
48
((
Potassium)) Polonium((
K)) Po((
19)) 84Calcium
Ca
20
((
Praseodymium))
Potassium((
Pr)) K((
59)) 19Californium
Cf
98
((
Promethium))
Praseodymium((
Pm)) Pr((
61)) 59Carbon
C
6
((
Protactinium))
Promethium((
Pa)) Pm((
91)) 61Cerium
Ce
58
((
Radium)) Protactinium((
Ra)) Pa((
88)) 91Cesium
Cs
55
((
Radon)) Radium((
Rn)) Ra((
86)) 88Chlorine
Cl
17
((
Rhenium)) Radon((
Re)) Rn((
75)) 86Chromium
Cr
24
((
Rhodium)) Rhenium((
Rh)) Re((
45)) 75Cobalt
Co
27
((
Rubidium)) Rhodium((
Rb)) Rh((
37)) 45Copper
Cu
29
((
Ruthenium)) Rubidium((
Ru)) Rb((
44)) 37Curium
Cm
96
((
Samarium)) Ruthenium((
Sm)) Ru((
62)) 44Dysprosium
Dy
66
((
Scandium)) Samarium((
Sc)) Sm((
21)) 62Einsteinium
Es
99
((
Selenium)) Scandium((
Se)) Sc((
34)) 21Erbium
Er
68
((
Silicon)) Selenium((
Si)) Se((
14)) 34Europium
Eu
63
((
Silver)) Silicon((
Ag)) Si((
47)) 14Fermium
Fm
100
((
Sodium)) Silver((
Na)) Ag((
11)) 47Fluorine
F
9
((
Strontium)) Sodium((
Sr)) Na((
38)) 11Francium
Fr
87
((
Sulfur)) Strontium((
S)) Sr((
16)) 38Gadolinium
Gd
64
((
Tantalum)) Sulfur((
Ta)) S((
73)) 16Gallium
Ga
31
((
Technetium)) Tantalum((
Tc)) Ta((
43)) 73Germanium
Ge
32
((
Tellurium)) Technetium((
Te)) Tc((
52)) 43Gold
Au
79
((
Terbium)) Tellurium((
Tb)) Te((
65)) 52Hafnium
Hf
72
((
Thallium)) Terbium((
Tl)) Tb((
81)) 65Holmium
Ho
67
((
Thorium)) Thallium((
Th)) Tl((
90)) 81Hydrogen
H
1
((
Thulium)) Thorium((
Tm)) Th((
69)) 90Indium
In
49
((
Tin)) Thulium((
Sn)) Tm((
50)) 69Iodine
I
53
((
Titanium)) Tin((
Ti)) Sn((
22)) 50Iridium
Ir
77
((
Tungsten)) Titanium((
W)) Ti((
74)) 22Iron
Fe
26
((
Uranium)) Tungsten((
U)) W((
92)) 74Krypton
Kr
36
((
Vanadium)) Uraninium((
V)) U((
23)) 92Lanthanum
La
57
((
Xenon)) Vanadium((
Xe)) V((
54)) 23Lead
Pb
82
((
Ytterbium)) Xenon((
Yb)) Xe((
70)) 54Lutetium
Lu
71
((
Yttrium)) Ytterbium((
Y)) Yb((
39)) 70Magnesium
Mg
12
((
Zinc)) Yttrium((
Zn)) Y((
30)) 39Manganese
Mn
25
((
Zirconium)) Zinc((
Zr)) Zn((
40)) 30Mendelevium
Md
101
Zirconuim
Zr
40
Mercury
Hg
80
Table 1
Table II
Table III
Col. 1
Col. 2 Col.
3
Col. 1
Col. 2
MonthlyAtomic
No.
Radionuclide
Class
ALI
ALI
DAC
Air
Water
1
Hydrogen-3
Water, DAC includes
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
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,
5E+4
7E+4
3E-5
1E-7
-
-
St wall
-
-
-
7E-4
7E-3
W, fluorides of Be, Mg,
-
9E+4
4E-5
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
7E+2
2E+3
7E-7
2E-9
9E-6
9E-5
W, oxides, hydroxides,
-
1E+3
5E-7
2E-9
-
-
13
Aluminum-26
D, all compounds except
4E+2
6E+1
3E-8
9E-11
6E-6
6E-5
W, oxides, hydroxides,
-
9E+1
4E-8
1E-10
-
-
14
Silicon-31
D, all compounds except
9E+3
3E+4
1E-5
4E-8
1E-4
1E-3
W, oxides, hydroxides,
-
3E+4
1E-5
5E-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
6E+2
9E+2
4E-7
1E-9
9E-6
9E-5
W, phosphates of Zn2+,
-
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
1E+4
2E+4
7E-6
2E-8
-
-
LLI wall
(8E+3)
-
-
-
1E-4
1E-3
W, elemental sulfur,
6E+3
17
Chlorine-36
D, chlorides of H, Li,
2E+3
2E+3
1E-6
3E-9
2E-5
2E-4
W, chlorides of lantha-
-
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-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
-
-
-
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
-
-
-
5E-4
5E-3
19
Potassium-452
D, all compounds
3E+4
1E+5
5E-5
2E-7
-
-
St wall
-
-
-
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
3E+2
1E+1
5E-9
2E-11
4E-6
4E-5
W, oxides, hydroxides,
-
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
3E+4
8E+4
3E-5
1E-7
-
-
St wall
-
-
-
4E-4
4E-3
W, oxides, hydroxides,
-
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
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
2E+4
5E+4
2E-5
7E-8
3E-4
3E-3
W, oxides, hydroxides,
-
6E+4
3E-5
8E-8
-
-
25
Manganese-52m2
D, see 51Mn
3E+4
9E+4
4E-5
1E-7
-
-
St wall
-
-
-
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
9E+2
3E+3
1E-6
4E-9
1E-5
1E-4
W, oxides, hydroxides,
-
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
1E+3
3E+3
1E-6
4E-9
2E-5
2E-4
Y, oxides, hydroxides,
-
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
-
-
-
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
-
-
-
7E-4
7E-3
Y, see 55Co
-
2E+5
6E-5
2E-7
-
-
28
Nickel-56
D, all compounds except
1E+3
2E+3
8E-7
3E-9
2E-5
2E-4
W, oxides, hydroxides,
-
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
3E+4
9E+4
4E-5
1E-7
-
-
St wall
-
-
-
4E-4
4E-3
W, sulfides, halides,
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-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
5E+4
2E+5
7E-5
2E-7
-
-
St wall
-
-
-
9E-4
9E-3
W, oxides, hydroxides,
-
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
-
-
-
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
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
-
-
-
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
-
-
-
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
-
-
-
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
-
-
-
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
2E+4
4E+4
2E-5
5E-8
1E-4
1E-3
W, oxides, hydroxides,
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
-
-
-
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,
1E+4
4E+4
2E-5
5E-8
-
-
St wall
-
-
-
3E-4
3E-3
W, bromides of lantha-
-
4E+4
2E-5
6E-8
-
-
35
Bromine-742
D, see 74mBr
2E+4
7E+4
3E-5
1E-7
-
-
St wall
-
-
-
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
-
-
-
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
-
-
-
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
-
-
-
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
-
-
-
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
-
-
-
8E-4
8E-3
37
Rubidium-81m2
D, all compounds
2E+5
3E+5
1E-4
5E-7
-
-
St wall
-
-
-
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
-
-
-
4E-4
4E-3
37
Rubidium-892
D, all compounds
4E+4
1E+5
6E-5
2E-7
-
-
St wall
-
-
-
9E-4
9E-3
38
Strontium-802
D, all soluble compounds
4E+3
1E+4
5E-6
2E-8
6E-5
6E-4
Y, all insoluble com-
-
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
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
-
-
-
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
-
-
-
7E-4
7E-3
Y, see 86mY
-
1E+5
6E-5
2E-7
-
-
40
Zirconium-86
D, all compounds except
1E+3
4E+3
2E-6
6E-9
2E-5
2E-4
W, oxides, hydroxides,
-
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
5E+4
2E+5
9E-5
3E-7
-
-
St wall
-
-
-
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
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
4E+3
7E+3
3E-6
1E-8
3E-5
3E-4
Y, oxides, hydroxides,
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
-
-
-
7E-4
7E-3
Y, see 90Mo
-
1E+5
6E-5
2E-7
-
-
43
Technetium-93m2
D, all compounds except
7E+4
2E+5
6E-5
2E-7
1E-3
1E-2
W, oxides, hydroxides,
-
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
-
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
-
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
-
-
-
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
-
-
-
4E-4
4E-3
W, see 93mTc
-
9E+4
4E-5
1E-7
-
-
44
Ruthenium-942
D, all compounds except
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
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
-
-
-
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
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
5E+4
2E+5
8E-5
2E-7
-
-
St wall
-
-
-
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
-
-
-
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-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
-
-
-
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
2E+4
7E+4
3E-5
9E-8
3E-4
3E-3
W, sulfides, halides,
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)
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
2E+4
4E+4
2E-5
6E-8
3E-4
3E-3
W, oxides, hydroxides,
-
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
-
-
-
7E-4
7E-3
W, see 109In
-
1E+5
6E-5
2E-7
-
-
50
Tin-110
D, all compounds except
4E+3
1E+4
5E-6
2E-8
5E-5
5E-4
W, sulfides, oxides,
-
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
W, oxides, hydroxides,
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
-
-
-
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
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
-
-
-
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
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
8E+3
2E+4
9E-6
3E-8
1E-4
1E-3
W, oxides, hydroxides,
-
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
-
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
-
-
-
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
-
-
-
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-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
-
-
-
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
-
-
-
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
-
-
-
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
-
1E-10
-
-
W, see 131La
-
3E+2
1E-7
-
-
-
-
Liver
-
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
-
-
-
5E-4
5E-3
W, see 131La
-
9E+4
4E-5
1E-7
-
-
58
Cerium-134
W, all compounds except
5E+2
7E+2
3E-7
1E-9
-
-
LLI wall
(6E+2)
-
-
-
8E-6
8E-5
Y, oxides, hydroxides,
-
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
5E+4
2E+5
1E-4
3E-7
-
-
St wall
(7E+4)
-
-
-
1E-3
1E-2
Y, oxides, hydroxides,
-
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
-
-
-
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
-
-
-
1E-3
1E-2
Y, see 136Pr
-
2E+5
8E-5
3E-7
-
-
60
Neodymium-1362
W, all compounds except
1E+4
6E+4
2E-5
8E-8
2E-4
2E-3
Y, oxides, hydroxides,
-
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
5E+4
2E+5
8E-5
3E-7
-
-
St wall
-
-
-
8E-4
8E-3
Y, oxides, hydroxides,
-
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
-
-
-
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
-
-
-
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
W, all compounds
3E+3
8E+3
4E-6
1E-8
4E-5
4E-4
63
Europium-150
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
5E+4
2E+5
6E-5
2E-7
-
-
St wall
(5E+4)
-
-
-
6E-4
6E-3
W, oxides, hydroxides,
-
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
W, all compounds
2E+4
3E+4
1E-5
4E-8
2E-4
2E-3
65
Terbium-156m
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
-
-
-
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
-
-
-
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
-
-
-
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)
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
-
-
-
1E-3
1E-2
70
Ytterbium-1622
W, all compounds except
7E+4
3E+5
1E-4
4E-7
1E-3
1E-2
Y, oxides, hydroxides,
-
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
3E+3
4E+3
2E-6
6E-9
3E-5
3E-4
Y, oxides, hydroxides,
-
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
-
-
-
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
-
-
-
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
3E+3
6E+3
2E-6
8E-9
4E-5
4E-4
W, oxides, hydroxides,
-
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
4E+4
1E+5
5E-5
2E-7
5E-4
5E-3
Y, elemental Ta, oxides,
-
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
-
-
-
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
9E+4
3E+5
1E-4
4E-7
-
-
St wall
-
-
-
2E-3
2E-2
W, oxides, hydroxides,
-
4E+5
1E-4
5E-7
-
-
75
Rhenium-1782
D, see 177Re
7E+4
3E+5
1E-4
4E-7
-
-
St wall
-
-
-
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
St wall
-
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
-
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
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
4E+4
1E+5
6E-5
2E-7
-
-
St wall
-
-
-
6E-4
6E-3
W, halides, nitrates,
-
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
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
-
-
-
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,
-
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-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
-
-
-
1E-3
1E-2
81
Thallium-1942
D, all compounds
3E+5
6E+5
2E-4
8E-7
-
-
St wall
-
-
-
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
-
-
-
3E-4
3E-3
W, see 200Bi
-
9E-2
4E-7
1E-9
-
-
84
Polonium-2032
D, all compounds except
3E+4
6E+4
3E-5
9E-8
3E-4
3E-3
W, oxides, hydroxides,
-
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
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
Bone surf
-
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
Bone surf
-
3E-15
2E-8
2E-7
Y, see 226Th
-
2E-3
1E-12
-
-
-
-
Bone surf
-
4E-15
-
-
90
Thorium-230
W, see 226Th
4E+0
6E-3
3E-12
-
-
-
Bone surf
Bone surf
-
2E-14
1E-7
1E-6
Y, see 226Th
-
2E-2
6E-12
-
-
-
-
Bone surf
-
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
Bone surf
-
4E-15
3E-8
3E-7
Y, see 226Th
-
3E-3
1E-12
-
-
-
-
Bone surf
-
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
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
-
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
-
-
-
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
Bone surf
-
6E-15
6E-9
6E-8
Y, see 227Pa
-
4E-3
2E-12
-
-
-
-
Bone surf
-
8E-15
-
-
91
Protactinium-232
W, see 227Pa
1E+3
2E+1
9E-9
-
2E-5
2E-4
-
Bone surf
-
8E-11
-
-
Y, see 227Pa
-
6E+1
2E-8
-
-
-
-
Bone surf
-
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
Bone surf
-
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
Bone surf
-
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
Bone surf
-
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
Bone surf
-
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
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
-
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
Bone surf
-
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
-
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
-
2E-9
3E-4
3E-3
93
Neptunium-236
W, all compounds
3E+0
2E-2
9E-12
-
-
-
(1.15E+5 y)
Bone surf
Bone surf
-
8E-14
9E-8
9E-7
93
Neptunium-236
W, all compounds
3E+3
3E+1
1E-8
-
-
-
(22.5 h)
Bone surf
Bone surf
-
1E-10
5E-5
5E-4
93
Neptunium-237
W, all compounds
5E-1
4E-3
2E-12
-
-
-
Bone surf
Bone surf
-
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-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
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
Bone surf
-
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
Bone surf
-
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
Bone surf
-
2E-14
2E-8
2E-7
Y, see 234Pu
-
2E-2
7E-12
-
-
-
-
Bone surf
-
2E-14
-
-
94
Plutonium-240
W, see 234Pu
8E-1
6E-3
3E-12
-
-
-
Bone surf
Bone surf
-
2E-14
2E-8
2E-7
Y, see 234Pu
-
2E-2
7E-12
-
-
-
-
Bone surf
-
2E-14
-
-
94
Plutonium-241
W, see 234Pu
4E+1
3E-1
1E-10
-
-
-
Bone surf
Bone surf
Y, see 234Pu
-
8E-1
3E-10
-
-
-
-
Bone surf
-
1E-12
-
-
94
Plutonium-242
W, see 234Pu
8E-1
7E-3
3E-12
-
-
-
Bone surf
Bone surf
-
2E-14
2E-8
2E-7
Y, see 234Pu
-
2E-2
7E-12
-
-
-
-
Bone surf
-
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
Bone surf
-
2E-14
2E-8
2E-7
Y, see 234Pu
-
2E-2
7E-12
-
-
-
-
Bone surf
-
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
-
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
Bone surf
-
2E-14
2E-8
2E-7
95
Americium-242m
W, all compounds
8E-1
6E-3
3E-12
-
-
-
Bone surf
Bone surf
-
2E-14
2E-8
2E-7
95
Americium-242
W, all compounds
4E+3
8E+1
4E-8
-
5E-5
5E-4
-
Bone surf
-
1E-10
-
-
95
Americium-243
W, all compounds
8E-1
6E-3
3E-12
-
-
-
Bone surf
Bone surf
-
2E-14
2E-8
2E-7
95
Americium-244m2
W, all compounds
6E+4
4E+3
2E-6
-
-
-
St wall
Bone surf
-
1E-8
1E-3
1E-2
95
Americium-244
W, all compounds
3E+3
2E+2
8E-8
-
4E-5
4E-4
-
Bone surf
-
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
-
-
-
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
Bone surf
-
9E-13
1E-6
1E-5
96
Curium-241
W, all compounds
1E+3
3E+1
1E-8
-
2E-5
2E-4
-
Bone surf
-
5E-11
-
-
96
Curium-242
W, all compounds
3E+1
3E-1
1E-10
-
-
-
Bone surf
Bone surf
-
4E-13
7E-7
7E-6
96
Curium-243
W, all compounds
1E+0
9E-3
4E-12
-
-
-
Bone surf
Bone surf
-
2E-14
3E-8
3E-7
96
Curium-244
W, all compounds
1E+0
1E-2
5E-12
-
-
-
Bone surf
Bone surf
-
3E-14
3E-8
3E-7
96
Curium-245
W, all compounds
7E-1
6E-3
3E-12
-
-
-
Bone surf
Bone surf
-
2E-14
2E-8
2E-7
96
Curium-246
W, all compounds
7E-1
6E-3
3E-12
-
-
-
Bone surf
Bone surf
-
2E-14
2E-8
2E-7
96
Curium-247
W, all compounds
8E-1
6E-3
3E-12
-
-
-
Bone surf
Bone surf
-
2E-14
2E-8
2E-7
96
Curium-248
W, all compounds
2E-1
2E-3
7E-13
-
-
-
Bone surf
Bone surf
-
4E-15
5E-9
5E-8
96
Curium-2492
W, all compounds
5E+4
2E+4
7E-6
-
7E-4
7E-3
-
Bone surf
-
4E-8
-
-
96
Curium-250
W, all compounds
4E-2
3E-4
1E-13
-
-
-
Bone surf
Bone surf
-
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
Bone surf
-
1E-14
2E-8
2E-7
97
Berkelium-249
W, all compounds
2E+2
2E+0
7E-10
-
-
-
Bone surf
Bone surf
-
5E-12
6E-6
6E-5
97
Berkelium-250
W, all compounds
9E+3
3E+2
1E-7
-
1E-4
1E-3
-
Bone surf
-
1E-9
-
-
98
Californium-2442
W, all compounds except
3E+4
6E+2
2E-7
8E-10
-
-
St wall
-
-
-
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
Bone surf
-
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
Bone surf
-
1E-14
2E-8
2E-7
Y, see 244Cf
-
1E-2
4E-12
-
-
-
-
Bone surf
-
2E-14
-
-
98
Californium-250
W, see 244Cf
1E+0
9E-3
4E-12
-
-
-
Bone surf
Bone surf
-
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
Bone surf
-
1E-14
2E-8
2E-7
Y, see 244Cf
-
1E-2
4E-12
-
-
-
-
Bone surf
-
2E-14
-
-
98
Californium-252
W, see 244Cf
2E+0
2E-2
8E-12
-
-
-
Bone surf
Bone surf
-
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
-
-
-
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
-
2E-9
-
-
99
Einsteinium-251
W, all compounds
7E+3
9E+2
4E-7
-
1E-4
1E-3
-
Bone surf
-
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
Bone surf
-
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
Bone surf
-
3E-13
5E-7
5E-6
101
Mendelevium-257
W, all compounds
7E+3
8E+1
4E-8
-
1E-4
1E-3
-
Bone surf
-
1E-10
-
-
101
Mendelevium-258
W, all compounds
3E+1
2E-1
1E-10
-
-
-
Bone surf
Bone surf
-
5E-13
6E-7
6E-6
-
Any single
radionuclide not
listed above with
decay mode other
than alpha emission
or spontaeneous
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
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
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:
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:
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
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
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
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
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
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
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
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
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
3. If a mixture of radionuclides consists of uranium and its daughters in ore dust (10 µm AMAD particle distribution assumed)
prior to
4. If the identity and concentration of each radionuclide in a mixture are known, the limiting values should be derived as follows:
Example: If radionuclides "A," "B," and "C" are present in concentrations CA, CB, and CC, and if the applicable DACs are
DACA,
CA
CB
CC
DACA
DACB
DACC
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.
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;One)) 37 kilobecquerels (1 microcurie) of
radium-226 per timepiece in timepieces manufactured prior to
the effective date of these regulations.
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.
*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.
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.
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
AMENDATORY SECTION(Amending Order 121, filed 12/27/90,
effective 1/31/91)
WAC 246-232-140
Schedule D.
NUCLIDES A
AVERAGE B C F
MAXIMUM B D F
REMOVABLE B E F
U-nat, U-235, U-238, and
associated decay products
5,000 dpm ((
α))/100
cm((2)) 215,000 dpm ((
α))/100
cm((2)) 21,000 dpm α/100 cm((
2))
2Transuranics, Ra-226, Ra-228,
Th-230, Th-228, Pa-231, Ac-227,
I-125, I-129
100 dpm/100 cm((
2)) 2300 dpm/100 cm((
2)) 220 dpm/100 cm((
2)) 2Th-nat, Th-232, Sr-90, Ra-223,
Ra-224, U-232, I-126, I-131, I-133
1000 dpm/100 cm((
2)) 23000 dpm/100 cm((
2)) 2200 dpm/100 cm((
2)) 2Beta-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)) 215,000 dpm ((
&bgr;&ggr;))/100
cm((2)) 21000 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.
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.
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.(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.
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:
. . . . . . . . . . . .
(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.
. . . . . . . . . . . .
(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.
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: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
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:
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:
*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:paragraph (2)))(a) of this
((section)) subsection is subject to the following conditions:item (2)))(b)(iii) of this ((section)) subsection, the label
affixed to the immediate container, or an accompanying
brochure, shall: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.
*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.
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.
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
Possession
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.
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.
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.MBq)) megabecquerels (30 ((µCi)) microcuries) of sodium
iodide I-131: The dosage;
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.
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: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.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. GBq)) gigabecquerels (15 ((mCi)) millicuries).MBq)) megabecquerels (200 ((µCi))
microcuries) or 1000 times the quantities in Schedule B of WAC 246-232-120.
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. Bq)) becquerels (0.005 ((µCi)) microcuries) of radioactive
material in the sample.Bq))
becquerels (0.005 ((µCi)) microcuries) or more of removable
contamination, the licensee shall: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;
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:
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:
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:
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:
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.MBq))
megabecquerels (30 ((µCi)) microcuries);
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.
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.
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:
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.
**
Attention is directed particularly to the provisions of chapter 246-221 WAC which relate to the labeling of
containers.
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.
*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: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 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;
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:
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.
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:
*Note:
Showing only the name of the appropriate material.
(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;
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:
*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:
(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.
© Washington State Code Reviser's Office