Chapter 246-221 WAC:

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Chapter 246-221 WAC

Last Update: 10/11/23

RADIATION PROTECTION STANDARDS

WAC Sections

HTML PDF	246-221-001	Purpose and scope.
HTML PDF	246-221-005	Radiation protection programs.
HTML PDF	246-221-010	Occupational dose limits for adults.
HTML PDF	246-221-015	Compliance with requirements for summation of external and internal doses.
HTML PDF	246-221-020	Determination of prior occupational dose.
HTML PDF	246-221-030	Requirements for planned special exposures.
HTML PDF	246-221-040	Determination of internal exposure of individuals to concentrations of radioactive materials in restricted areas.
HTML PDF	246-221-050	Occupational dose limits for minors.
HTML PDF	246-221-055	Dose equivalent to an embryo/fetus.
HTML PDF	246-221-060	Dose limits for individual members of the public.
HTML PDF	246-221-070	Compliance with dose limits for individual members of the public.
HTML PDF	246-221-080	Leak tests.
HTML PDF	246-221-090	Personnel monitoring for external dose.
HTML PDF	246-221-100	Personnel monitoring for internal dose.
HTML PDF	246-221-102	Control of access to high radiation areas.
HTML PDF	246-221-104	Control of access to very high radiation areas.
HTML PDF	246-221-106	Control of access to very high radiation areas—Irradiators.
HTML PDF	246-221-110	Surveys.
HTML PDF	246-221-113	Use of process, engineering or other controls.
HTML PDF	246-221-117	Use of individual respiratory protection equipment.
HTML PDF	246-221-120	Caution signs, and labels.
HTML PDF	246-221-130	Exceptions from posting and labeling requirements.
HTML PDF	246-221-140	Instruction of personnel.
HTML PDF	246-221-150	Security and control of radioactive material and radiation machines.
HTML PDF	246-221-160	Procedures for picking up, receiving, and opening packages.
HTML PDF	246-221-170	Waste disposal, general requirement.
HTML PDF	246-221-180	Method of obtaining approval of proposed disposal procedures.
HTML PDF	246-221-190	Disposal by release into sanitary sewerage systems.
HTML PDF	246-221-200	Disposal by burial in soil.
HTML PDF	246-221-210	Disposal by incineration.
HTML PDF	246-221-220	Disposal of specific wastes.
HTML PDF	246-221-230	Records important to radiation safety.
HTML PDF	246-221-235	Reports of transactions involving nationally tracked sources.
HTML PDF	246-221-236	Nationally tracked source thresholds.
HTML PDF	246-221-240	Reports of stolen, lost or missing radiation sources.
HTML PDF	246-221-250	Notification of incidents.
HTML PDF	246-221-260	Reports of overexposures and excessive levels and concentrations.
HTML PDF	246-221-265	Special reports to the department—Planned special exposures and leaking sources.
HTML PDF	246-221-270	Vacating premises and release of equipment.
HTML PDF	246-221-275	Notification of changes in a facility.
HTML PDF	246-221-280	Notifications and reports to individuals.
HTML PDF	246-221-285	Assigned protection factors for respiratorsa.
HTML PDF	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.
HTML PDF	246-221-300	Appendix B—Minimum quantities of radioactive material requiring labeling.

PDF246-221-001

Purpose and scope.

(1) This chapter establishes standards for protection against radiation hazards. Except as otherwise specifically provided, this chapter applies to all licensees or registrants. The requirements of this chapter are designed to control the receipt, possession, use, transfer, and disposal of sources of radiation by any licensee or registrant so the total dose to an individual, including doses resulting from all sources of radiation other than background radiation, does not exceed the standards for protection against radiation prescribed in this chapter.

(2) The limits in this chapter do not apply to doses due to background radiation, to exposure of patients to radiation for the purpose of medical diagnosis or therapy, to exposure from individuals administered radioactive material and released under chapter 246-240 WAC, or to voluntary participation in medical research programs.

(3) Nothing in this chapter shall be interpreted as limiting actions that may be necessary to protect health and safety in an emergency.

(4) The definitions contained in WAC 246-220-010 also apply to this chapter. WAC 246-220-007, Statement of philosophy, is directly applicable to this chapter.

[Statutory Authority: RCW 70.98.050. WSR 06-05-019, § 246-221-001, filed 2/6/06, effective 3/9/06; WSR 98-13-037, § 246-221-001, filed 6/8/98, effective 7/9/98; WSR 94-01-073, § 246-221-001, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-221-001, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-001, filed 12/27/90, effective 1/31/91; Order 1095, § 402-24-010, filed 2/6/76; Order 1, § 402-24-010, filed 1/8/69; Rules (part), filed 10/26/66.]

PDF246-221-005

Radiation protection programs.

(1) Each specific licensee shall develop, document, and implement a radiation protection program sufficient to ensure compliance with the provisions of this chapter.

(2) The licensee shall use, to the extent practical, procedures and engineering controls based upon sound radiation protection principles to achieve occupational doses and doses to members of the public that are as low as is reasonably achievable (ALARA).

(3) The licensee shall review the radiation protection program content and implementation at least annually.

(4) To implement the ALARA requirements of subsection (2) of this section, and notwithstanding the requirements of WAC 246-221-060, a constraint on air emission of radioactive material to the environment, excluding radon-220, radon-222 and their daughters, shall be established by licensees such that the individual member of the public likely to receive the highest dose will not be expected to receive a total effective dose equivalent in excess of 0.1 mSv (10 mrem) per year from these emissions. This dose constraint does not apply to sealed sources or to accelerators less than 200MeV. If a licensee subject to this requirement exceeds this dose constraint, the licensee shall report the exceedance as provided in WAC 246-221-260 and promptly take appropriate corrective action to ensure against recurrence.

(5) Each licensee shall maintain records of the radiation protection program, including:

(a) The provisions of the program; and

(b) Audits, where required, and other reviews of program content and implementation.

[Statutory Authority: RCW 70A.388.040 and 70A.388.110. WSR 23-21-056, § 246-221-005, filed 10/11/23, effective 11/11/23. Statutory Authority: RCW 70.98.050. WSR 01-05-110, § 246-221-005, filed 2/21/01, effective 3/24/01; WSR 99-15-105, § 246-221-005, filed 7/21/99, effective 8/21/99; WSR 94-01-073, § 246-221-005, filed 12/9/93, effective 1/9/94.]

PDF246-221-010

Occupational dose limits for adults.

(1) The licensee or registrant shall control the occupational dose to individual adults, except for planned special exposures pursuant to WAC 246-221-030, to the following dose limits:

(a) An annual limit, which is the more limiting of:

(i) The total effective dose equivalent being equal to 0.05 Sv (five rem); or

(ii) The sum of the deep dose equivalent and the committed dose equivalent to any individual organ or tissue other than the lens of the eye being equal to 0.50 Sv (50 rem).

(b) The annual limits to the lens of the eye, to the skin of the whole body, and to the skin of the extremities which are:

(i) A lens dose equivalent of 0.15 Sv (15 rem); and

(ii) A shallow dose equivalent of 0.50 Sv (50 rem) to the skin of the whole body or to the skin of any extremity.

(2) Doses received in excess of the annual limits, including doses received during accidents, emergencies, and planned special exposures, must be subtracted from the limits specified in WAC 246-221-030 for planned special exposures that the individual may receive during the current year and during the individual's lifetime.

(3) When the external exposure is determined by measurement with an external personal monitoring device, the deep-dose equivalent must be used in place of the effective dose equivalent, unless the effective dose equivalent is determined by a dosimetry method approved by the NRC or the department. The assigned deep-dose equivalent must be for the part of the body receiving the highest exposure. The assigned shallow dose equivalent shall be the dose averaged over the contiguous 10 square centimeters of skin receiving the highest exposure. The deep dose equivalent, lens dose equivalent, and shallow dose equivalent may be assessed from surveys or other radiation measurements for the purpose of demonstrating compliance with the occupational dose limits, if the individual monitoring device was not in the region of highest potential exposure, or the results of the individual monitoring are unavailable.

(4) Derived air concentration (DAC) and annual limit on intake (ALI) values are specified in WAC 246-221-290 and may be used to determine the individual's dose and to demonstrate compliance with the occupational dose limits.

(5) Notwithstanding the annual dose limits, the licensee shall limit the soluble uranium intake by an individual to 10 milligrams in a week in consideration of chemical toxicity.

(6) The licensee or registrant shall reduce the dose that an individual may be allowed to receive in the current year by the amount of occupational dose received while employed by any other person during the current year as determined in accordance with WAC 246-221-020.

[Statutory Authority: RCW 70A.388.040 and 70A.388.110. WSR 23-21-056, § 246-221-010, filed 10/11/23, effective 11/11/23. Statutory Authority: RCW 70.98.050, 56 F.R. 23396, 10 C.F.R. 20.1201 (a)(1)(ii). WSR 18-21-020, § 246-221-010, filed 10/4/18, effective 11/4/18. Statutory Authority: RCW 70.98.050. WSR 14-01-077, § 246-221-010, filed 12/16/13, effective 1/16/14; WSR 04-23-093, § 246-221-010, filed 11/17/04, effective 12/18/04; WSR 01-05-110, § 246-221-010, filed 2/21/01, effective 3/24/01; WSR 94-01-073, § 246-221-010, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-221-010, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-010, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 87-01-031 (Order 2450), § 402-24-020, filed 12/11/86. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-24-020, filed 12/8/80; Order 1095, § 402-24-020, filed 2/6/76; Order 1, § 402-24-020, filed 1/8/69; Rules (part), filed 10/26/66.]

PDF246-221-015

Compliance with requirements for summation of external and internal doses.

(1) If the licensee is required to monitor under both WAC 246-221-090 and 246-221-100, the licensee shall demonstrate compliance with the dose limits by summing external and internal doses. If the licensee is required to monitor only under WAC 246-221-090 or only under WAC 246-221-100, then summation is not required to demonstrate compliance with the dose limits. The licensee may demonstrate compliance with the requirements for summation of external and internal doses under subsections (2), (3), and (4) of this section. The dose equivalents for the lens of the eye, the skin, and the extremities are not included in the summation, but are subject to separate limits.

(2) Intake by inhalation. If the only intake of radionuclides is by inhalation, the total effective dose equivalent limit is not exceeded if the sum of the deep dose equivalent divided by the total effective dose equivalent limit, and one of the following, does not exceed unity:

(a) The sum of the fractions of the inhalation ALI for each radionuclide; or

(b) The total number of derived air concentration-hours (DAC-hours) for all radionuclides divided by 2,000; or

(c) The sum of the calculated committed effective dose equivalents to all significantly irradiated organs or tissues (T) calculated from bioassay data using appropriate biological models and expressed as a fraction of the annual limit. For purposes of this requirement, an organ or tissue is deemed to be significantly irradiated if, for that organ or tissue, the product of the weighting factors, wT, and the committed dose equivalent, HT,50, per unit intake is greater than 10 percent of the maximum weighted value of H50, that is, wTHT,50, per unit intake for any organ or tissue.

(3) Intake by oral ingestion. If the occupationally exposed individual also receives an intake of radionuclides by oral ingestion greater than 10 percent of the applicable oral ALI, the licensee shall account for this intake and include it in demonstrating compliance with the limits.

(4) Intake through wounds or absorption through skin. The licensee shall evaluate and, to the extent practical, account for intakes through wounds or skin absorption. The intake through intact skin has been included in the calculation of DAC for hydrogen-3 and does not need to be evaluated or accounted for pursuant to this section.

(5) External dose from airborne radioactive material. Licensees shall, when determining the dose from airborne radioactive material, include the contribution to the deep dose equivalent, lens dose equivalent, and shallow dose equivalent from external exposure to the radioactive cloud. Airborne radioactivity measurements and DAC values shall not be used as the primary means to assess the deep dose equivalent when the airborne radioactive material includes radionuclides other than noble gases or if the cloud of airborne radioactive material is not relatively uniform. The determination of the deep dose equivalent to an individual shall be based upon measurements using instruments or individual monitoring devices.

[Statutory Authority: RCW 70A.388.040 and 70A.388.110. WSR 23-21-056, § 246-221-015, filed 10/11/23, effective 11/11/23. Statutory Authority: RCW 70.98.050. WSR 01-05-110, § 246-221-015, filed 2/21/01, effective 3/24/01; WSR 94-01-073, § 246-221-015, filed 12/9/93, effective 1/9/94.]

PDF246-221-020

Determination of prior occupational dose.

(1) For each individual who is likely to receive, in a year, an occupational dose requiring monitoring pursuant to WAC 246-221-090 and 246-221-100, the licensee or registrant shall:

(a) Determine the occupational radiation dose received during the current year; and

(b) Attempt to obtain the records of lifetime cumulative occupational radiation dose.

(2) Prior to permitting an individual to participate in a planned special exposure, the licensee or registrant shall determine:

(a) The internal and external doses from all previous planned special exposures; and

(b) All doses in excess of the limits, including doses received during accidents and emergencies, received during the lifetime of the individual.

(3) In complying with the requirements of subsection (1) of this section, a licensee or registrant may:

(a) Accept, as a record of the occupational dose that the individual received during the current year, a written signed statement from the individual, or from the individual's most recent employer for work involving radiation exposure, that discloses the nature and the amount of any occupational dose that the individual received during the current year; and

(b) Accept, as the record of lifetime cumulative radiation dose, an up-to-date Form RHF-4A, or equivalent, signed by the individual and countersigned by an appropriate official of the most recent employer for work involving radiation exposure, or the individual's current employer, if the individual is not employed by the licensee or registrant; and

(c) Obtain reports of the individual's dose equivalent from the most recent employer for work involving radiation exposure, or the individual's current employer, if the individual is not employed by the licensee or registrant, by telephone, facsimile, email, or letter. The licensee or registrant shall request a written verification of the dose data if the authenticity of the transmitted report cannot be established.

(4) The licensee or registrant shall record the exposure history, as required by subsection (1) of this section, on Form RHF-4A, or other clear and legible record, of all the information required on that form. The form or record shall show each period in which the individual received occupational exposure to radiation or radioactive material and shall be signed by the individual who received the exposure. For each period for which the licensee or registrant obtains reports, the licensee or registrant shall use the dose shown in the report in preparing Form RHF-4A. For any period in which the licensee or registrant does not obtain a report, the licensee or registrant shall place a notation on Form RHF-4A indicating the periods of time for which data are not available.

(5) Licensees or registrants are not required to reevaluate the separate external dose equivalents and internal committed dose equivalents or intakes of radionuclides assessed under the regulations in effect before January 1, 1994. Further, occupational exposure histories obtained and recorded on Form RHF-4 before January 1, 1994, would not have included effective dose equivalent, but may be used in the absence of specific information on the intake of radionuclides by the individual.

(6) If the licensee or registrant is unable to obtain a complete record of an individual's current and previously accumulated occupational dose, the licensee or registrant shall assume:

(a) In establishing administrative controls under WAC 246-221-010(6) for the current year, that the allowable dose limit for the individual is reduced by 12.5 mSv (1.25 rem) for each calendar quarter for which records were unavailable and the individual was engaged in activities that could have resulted in occupational radiation exposure; and

(b) That the individual is not available for planned special exposures.

(7) The licensee or registrant shall retain the records on Form RHF-4A or equivalent until the department terminates each pertinent license requiring this record. The licensee or registrant shall retain records used in preparing Form RHF-4 or RHF-4A for three years after the record is made.

[Statutory Authority: RCW 70.98.050 and 70.98.110. WSR 16-13-054, § 246-221-020, filed 6/10/16, effective 7/11/16. Statutory Authority: RCW 70.98.050. WSR 00-08-013, § 246-221-020, filed 3/24/00, effective 4/24/00; WSR 94-01-073, § 246-221-020, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-221-020, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-020, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-24-024, filed 12/8/80; Order 1095, § 402-24-024, filed 2/6/76.]

PDF246-221-030

Requirements for planned special exposures.

A licensee or registrant may authorize an adult worker to receive doses in addition to and accounted for separately from the doses received under the limits specified in WAC 246-221-010 provided that each of the following conditions is satisfied:

(1) The licensee or registrant authorizes a planned special exposure only in an exceptional situation when alternatives that might avoid the dose estimated to result from the planned special exposure are unavailable or impractical.

(2) The licensee or registrant, and employer if the employer is not the licensee or registrant, specifically authorizes the planned special exposure, in writing, before the exposure occurs.

(3) Before a planned special exposure, the licensee or registrant ensures that each individual involved is:

(a) Informed of the purpose of the planned operation; and

(b) Informed of the estimated doses and associated potential risks and specific radiation levels or other conditions that might be involved in performing the task; and

(4) Prior to permitting an individual to participate in a planned special exposure, the licensee or registrant ascertains prior doses as required by WAC 246-221-020(2) during the lifetime of the individual for each individual involved.

(5) Subject to WAC 246-221-010(2), the licensee or registrant shall not authorize a planned special exposure that would cause an individual to receive a dose from all planned special exposures and all doses in excess of the limits to exceed:

(a) The numerical values of any of the dose limits in WAC 246-221-010(1) in any year; and

(b) Five times the annual dose limits in WAC 246-221-010(1) during the individual's lifetime.

(6) The licensee or registrant maintains records that describe:

(a) The exceptional circumstances requiring the use of a planned special exposure;

(b) The name of the management official who authorized the planned special exposure and a copy of the signed authorization;

(d) Why the actions were necessary;

(e) What precautions were taken to assure that doses were maintained ALARA; and

(f) What individual and collective doses were expected to result.

(7) The licensee or registrant records the best estimate of the dose resulting from the planned special exposure in the individual's record and informs the individual, in writing, of the dose within 30 days from the date of the planned special exposure. The dose from planned special exposures shall not be considered in controlling future occupational dose of the individual under WAC 246-221-010(1) but shall be included in evaluations required by subsections (4) and (5) of this section.

(8) The licensee or registrant submits a written report in accordance with WAC 246-221-265.

[Statutory Authority: RCW 70A.388.040 and 70A.388.110. WSR 23-21-056, § 246-221-030, filed 10/11/23, effective 11/11/23. Statutory Authority: RCW 70.98.050. WSR 01-05-110, § 246-221-030, filed 2/21/01, effective 3/24/01; WSR 94-01-073, § 246-221-030, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-221-030, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-030, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-24-027, filed 12/8/80.]

PDF246-221-040

Determination of internal exposure of individuals to concentrations of radioactive materials in restricted areas.

(1) For purposes of assessing dose used to determine compliance with occupational dose equivalent limits, the licensee shall, when required under WAC 246-221-100, take suitable and timely measurements of:

(a) Concentrations of radioactive materials in air in work areas; or

(b) Quantities of radionuclides in the body; or

(d) Combinations of these measurements.

(2) Unless respiratory protective equipment is used, as provided in WAC 246-221-117, or the assessment of intake is based on bioassays, the licensee shall assume that an individual inhales radioactive material at the airborne concentration in which the individual is present.

(3) When specific information on the physical and biochemical properties of the radionuclides taken into the body or the behavior or the material in an individual is known, the licensee may:

(a) Use that information to calculate the committed effective dose equivalent, and, if used, the licensee shall document that information in the individual's record; and

(b) Upon prior approval of the department, adjust the DAC or ALI values to reflect the actual physical and chemical characteristics of airborne radioactive material, for example, aerosol size distribution or density; and

(c) Separately assess the contribution of fractional intakes of Class D, W, or Y compounds of a given radionuclide to the committed effective dose equivalent. See WAC 246-221-290.

(4) If the licensee chooses to assess intakes of Class Y material using the measurements given in subsection (1)(b) or (c) of this section, the licensee may delay the recording and reporting of the assessments for periods up to seven months, unless otherwise required by WAC 246-221-250 or 246-221-260. This delay permits the licensee to make additional measurements basic to the assessments.

(5) If the identity and concentration of each radionuclide in a mixture are known, the fraction of the DAC applicable to the mixture for use in calculating DAC-hours shall be either:

(a) The sum of the ratios of the concentration to the appropriate DAC value, that is, D, W, or Y, from WAC 246-221-290 for each radionuclide in the mixture; or

(b) The ratio of the total concentration for all radionuclides in the mixture to the most restrictive DAC value for any radionuclide in the mixture.

(6) 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.

(7) When a mixture of radionuclides in air exists, a licensee may disregard certain radionuclides in the mixture if:

(a) The licensee uses the total activity of the mixture in demonstrating compliance with the dose limits in WAC 246-221-010 and in complying with the monitoring requirements in WAC 246-221-100; and

(b) The concentration of any radionuclide disregarded is less than 10 percent of its DAC; and

(8) When determining the committed effective dose equivalent, the following information may be considered:

(a) In order to calculate the committed effective dose equivalent, the licensee may assume that the inhalation of one ALI, or an exposure of 2,000 DAC-hours, results in a committed effective dose equivalent of 0.05 Sv (five rem) for radionuclides that have their ALIs or DACs based on the committed effective dose equivalent.

(b) For an ALI and the associated DAC determined by the nonstochastic organ dose limit of 0.50 Sv (50 rem), the intake of radionuclides that would result in a committed effective dose equivalent of 0.05 Sv (five rem), that is, the stochastic ALI, is listed in parentheses in Table I of WAC 246-221-290. The licensee may, as a simplifying assumption, use the stochastic ALIs to determine committed effective dose equivalent. However, if the licensee uses the stochastic ALIs, the licensee shall also demonstrate that the limit in WAC 246-221-010 (1)(a)(ii) is met.

[Statutory Authority: RCW 70A.388.040 and 70A.388.110. WSR 23-21-056, § 246-221-040, filed 10/11/23, effective 11/11/23. Statutory Authority: RCW 70.98.050. WSR 14-01-077, § 246-221-040, filed 12/16/13, effective 1/16/14; WSR 94-01-073, § 246-221-040, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-221-040, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-040, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-24-030, filed 12/8/80; Order 1095, § 402-24-030, filed 2/6/76; Order 1, § 402-24-030, filed 1/8/69; Rules (part), filed 10/26/66.]

PDF246-221-050

Occupational dose limits for minors.

No licensee or registrant shall possess, use, or transfer sources of radiation in such a manner as to cause any occupationally exposed individual who is under 18 years of age, to receive a dose in excess of 10 percent of the annual occupational dose limits specified in WAC 246-221-010(1).

[Statutory Authority: RCW 70.98.050. WSR 94-01-073, § 246-221-050, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-221-050, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-050, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-24-035, filed 12/8/80; Order 1095, § 402-24-035, filed 2/6/76.]

PDF246-221-055

Dose equivalent to an embryo/fetus.

(1) The licensee or registrant shall ensure that the dose equivalent to an embryo/fetus during the entire pregnancy, due to occupational exposure of a declared pregnant woman, does not exceed five mSv (0.5 rem).

(2) Once pregnancy has been declared, the licensee or registrant shall make every effort to avoid substantial variation above a uniform monthly exposure rate to a declared pregnant woman in order to satisfy the limit in subsection (1) of this section.

(3) If by the time the woman declares pregnancy to the licensee or registrant, the dose equivalent to the embryo/fetus has exceeded five mSv (0.5 rem), or is within 0.50 mSv (0.05 rem) of this dose, the licensee or registrant shall be deemed to be in compliance with subsection (1) of this section if the additional dose equivalent to the embryo/fetus does not exceed 0.50 mSv (0.05 rem) during the remainder of the pregnancy.

(4) The dose equivalent to an embryo/fetus shall be taken as the sum of:

(a) The deep dose equivalent to the declared pregnant woman; and

(b) The dose equivalent to the embryo/fetus from radionuclides in the embryo/fetus and radionuclides in the declared pregnant woman.

(5) The licensee or registrant shall maintain the records of dose equivalent to an embryo/fetus with the records of dose equivalent to the declared pregnant woman. The declaration of pregnancy, including the estimated date of conception, shall also be kept on file, but may be maintained separately from the dose records.

[Statutory Authority: RCW 70A.388.040 and 70A.388.110. WSR 23-21-056, § 246-221-055, filed 10/11/23, effective 11/11/23. Statutory Authority: RCW 70.98.010, 70.98.050, and 70.98.080. WSR 17-12-046, § 246-221-055, filed 6/1/17, effective 7/2/17. Statutory Authority: RCW 70.98.050. WSR 01-05-110, § 246-221-055, filed 2/21/01, effective 3/24/01; WSR 94-01-073, § 246-221-055, filed 12/9/93, effective 1/9/94.]

PDF246-221-060

Dose limits for individual members of the public.

(1) Each licensee or registrant shall conduct operations so that:

(a) The total effective dose equivalent to individual members of the public from the licensed or registered operation does not exceed one mSv (0.1 rem) in a year, exclusive of the dose contributions 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, and from the licensee's or registrant's disposal of radioactive material into sanitary sewerage in accordance with WAC 246-221-190; and

(b) The dose in any unrestricted area from external sources, exclusive of the dose contributions from patients administered radioactive material and released under chapter 246-240 WAC, does not exceed 0.02 mSv (0.002 rem) in any one hour.

(2) If the licensee or registrant permits members of the public to have access to restricted areas, they shall be escorted and the limits for members of the public continue to apply to those individuals.

(3) Notwithstanding subsection (1) of this section, a licensee or registrant may continue to operate a facility constructed and put into operation prior to January 1, 1994, where the annual dose limit for an individual member of the public is more than one mSv (0.1 rem) and less than five mSv (0.5 rem) total effective dose equivalent, if:

(a) The facility's approved operating conditions for each radiation source remain the same. Any increase in the following operating conditions shall require reevaluation by the department and modification of the facility shielding applicable to the source of radiation to meet the one mSv (0.1 rem) total effective dose equivalent limit for individual members of the public: Size of the radiation source, workload, or occupancy factors associated with the source of radiation; and

(b) Any change in the permanent shielding of the facility due to remodeling, repair or replacement requires the facility to meet the one mSv (0.1 rem) total effective dose equivalent limit for individual members of the public for areas affected by that portion of the shielding.

(4) Each licensee or registrant shall maintain records sufficient to demonstrate compliance with the dose limit for individual members of the public.

[Statutory Authority: RCW 70A.388.040 and 70A.388.110. WSR 23-21-056, § 246-221-060, filed 10/11/23, effective 11/11/23. Statutory Authority: RCW 70.98.050. WSR 14-01-077, § 246-221-060, filed 12/16/13, effective 1/16/14; WSR 06-05-019, § 246-221-060, filed 2/6/06, effective 3/9/06; WSR 98-13-037, § 246-221-060, filed 6/8/98, effective 7/9/98; WSR 94-01-073, § 246-221-060, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-221-060, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-060, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 87-01-031 (Order 2450), § 402-24-040, filed 12/11/86. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-24-040, filed 12/8/80; Order 1095, § 402-24-040, filed 2/6/76; Order 1, § 402-24-040, filed 1/8/69; Rules (part), filed 10/26/66.]

PDF246-221-070

Compliance with dose limits for individual members of the public.

(1) The licensee shall make or cause to be made surveys of radiation levels in unrestricted areas and radioactive materials in effluents released to unrestricted areas to demonstrate compliance with the dose limits for individual members of the public in WAC 246-221-060.

(2) A licensee shall show compliance with the annual dose limit in WAC 246-221-060 by:

(a) Demonstrating by measurement or calculation that the total effective dose equivalent to the individual likely to receive the highest dose from the licensed operation does not exceed the annual dose limit; or

(b) Demonstrating that:

(i) The annual average concentrations of radioactive material released in gaseous and liquid effluents at the boundary of the unrestricted area do not exceed the values specified in Table II of WAC 246-221-290; and

(ii) If an individual were continually present in an unrestricted area, the dose from external sources would not exceed 0.02 mSv (0.002 rem) in an hour and 0.50 mSv (0.05 rem) in a year.

(3) Upon approval from the department, the licensee may adjust the effluent concentration values in WAC 246-221-290, Table II, for members of the public, to take into account the actual physical and chemical characteristics of the effluents, such as, aerosol size distribution, solubility, density, radioactive decay equilibrium, and chemical form.

(4) The provisions of this section do not apply to disposal of radioactive material into sanitary sewerage systems, which is governed by WAC 246-221-190.

[Statutory Authority: RCW 70.98.050. WSR 94-01-073, § 246-221-070, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-221-070, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-070, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 87-01-031 (Order 2450), § 402-24-050, filed 12/11/86; Order 1095, § 402-24-050, filed 2/6/76; Order 1, § 402-24-050, filed 1/8/69; Rules (part), filed 10/26/66.]

PDF246-221-080

Leak tests.

(1) Each sealed radioactive source possessed under the provisions of a specific license, other than hydrogen-3 (tritium), with a half-life greater than 30 days and in any form other than gas, shall be tested and results obtained for leakage or contamination prior to initial use and at six-month intervals or as specified by the license, except that each source designed for the purpose of emitting alpha particles shall be tested at intervals not to exceed three months. If at any other time there is reason to suspect that a sealed source might have been damaged, it shall be tested for leakage and results obtained before further use. In the absence of a certificate from a transferor indicating that a test for leakage has been made within six months prior to the transfer (three months for a source designed to emit alpha particles), the sealed source shall not be put into use until tested and the results received.

(2) Leak tests shall be capable of detecting the presence of 185 Bq (0.005 microcurie) of removable contamination. The results of leak tests made pursuant to subsection (1) of this section shall be recorded in units of becquerel or microcuries and shall be maintained for inspection by the department. Any test conducted pursuant to subsection (1) of this section which reveals the presence of 185 Bq (0.005 microcurie) or more of removable contamination shall be considered evidence that the sealed source is leaking. The licensee shall immediately withdraw the source from use shall take action to prevent the spread of contamination and shall cause it to be decontaminated and repaired or to be disposed in accordance with WAC 246-232-080. If a sealed source shows evidence of leaking, a report shall be filed with the department within five days of the test, describing the equipment involved, the test results, and the corrective action taken.

(3) Test samples shall be taken from the sealed source or from the internal surfaces or the opening of the container in which the sealed source is stored or from surfaces of devices or equipment in which the sealed source is permanently mounted. Tests for contamination and leakage may be made by wiping appropriate accessible surfaces on which one might expect contamination to accumulate and measuring these wipes for transferred contamination. Test samples shall also be taken from the interior surfaces of the container in which a sealed source of radium is stored.

(4) Leak tests are required for sealed radioactive sources that are greater than 3.7 MBq (100 microcuries) for beta and gamma emitting sources and greater than 370 KBq (10 microcuries) for sources designed to emit alpha particles.

(5) Tests for leakage or contamination shall be performed by persons specifically authorized by the department, an agreement state, or the NRC to perform such services.

[Statutory Authority: RCW 70A.388.040 and 70A.388.110. WSR 23-21-056, § 246-221-080, filed 10/11/23, effective 11/11/23. Statutory Authority: RCW 70.98.050. WSR 14-01-077, § 246-221-080, filed 12/16/13, effective 1/16/14; WSR 94-01-073, § 246-221-080, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-221-080, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-080, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 83-19-050 (Order 2026), § 402-24-060, filed 9/16/83. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-24-060, filed 12/8/80; Order 1095, § 402-24-060, filed 2/6/76; Order 1, § 402-24-060, filed 1/8/69; Rules (part), filed 10/26/66.]

PDF246-221-090

Personnel monitoring for external dose.

Each licensee or registrant shall monitor occupational exposure from sources of radiation at levels sufficient to demonstrate compliance with the occupational dose limits of WAC 246-221-010, 246-221-030, 246-221-050 and 246-221-055.

(1) Each licensee or registrant shall monitor occupational exposure to radiation from licensed (or registered) and unlicensed (or unregistered) radiation sources under the control of the licensee or registrant and shall supply and shall require the use of individual monitoring devices by:

(a) Each adult likely to receive, in one year from sources external to the body, a dose in excess of 10 percent of the applicable limits specified in WAC 246-221-010(1).

(b) Each minor likely to receive, in one year from sources external to the body, a deep dose equivalent in excess of one mSv (0.1 rem), a lens dose equivalent in excess of 1.5 mSv (0.15 rem), or a shallow dose equivalent to the skin or to the extremities in excess of five mSv (0.5 rem).

(c) Each declared pregnant woman likely to receive during the entire pregnancy, from radiation sources external to the body, a deep dose equivalent in excess of one mSv (0.1 rem). All of the occupational dose limits specified in WAC 246-221-010 continue to be applicable to the declared pregnant worker as long as the embryo/fetus dose limit is not exceeded.

(d) Each individual who enters a high or very high radiation area.

(2) Personnel monitoring devices assigned to an individual:

(a) Shall not intentionally be exposed to give a false or erroneous reading;

(b) Shall be assigned to one individual per exposure interval (i.e., weekly, monthly) and used to determine exposure for that individual only;

(d) Personnel monitoring devices that are exposed while not being worn by the assigned individual shall be processed and recorded as soon as possible. A replacement monitoring device shall be assigned to the individual immediately. A record of the circumstances of the exposure shall be retained.

(3) All personnel dosimeters, except for direct and indirect reading pocket ionization chambers and those dosimeters used to measure the dose to any extremities, that require processing to determine the radiation dose and that are utilized by licensees or registrants to comply with subsection (1) of this section, with other applicable provisions of chapters 246-220 through 246-255 WAC, or with conditions specified in a licensee's license must be processed and evaluated by a dosimetry processor:

(a) Holding current personnel dosimetry accreditation from either the National Voluntary Laboratory Accreditation Program (NVLAP) of the National Institute of Standards and Technology (formerly known as the National Bureau of Standards) or the United States Department of Energy Laboratory Accreditation Program for Personnel Dosimetry Systems (DOELAP); and

(b) Approved in this accreditation process for the type of radiation or radiations included in the NVLAP or DOELAP program that most closely approximate the type of radiation or radiations for which the individual wearing the dosimeter is monitored.

(4) For the purposes of this section "dosimetry processor" means an individual or an organization that processes and evaluates personnel monitoring devices in order to determine the radiation dose delivered to the device.

(5) Each licensee or registrant shall maintain records of doses received by all individuals for whom monitoring was required under subsection (1) of this section, and records of doses received during planned special exposures, accidents, and emergency conditions. Assessments of dose equivalent and records made using units in effect before January 1, 1994, need not be changed. These records shall include, when applicable:

(a) The deep dose equivalent to the whole body, lens dose equivalent, shallow dose equivalent to the skin, and shallow dose equivalent to the extremities; and

(b) The total effective dose equivalent when required by WAC 246-221-015; and

(c) The total of the deep dose equivalent and the committed dose to the organ receiving the highest total dose (total organ dose equivalent).

(6) The licensee or registrant shall maintain the records specified in subsection (5) of this section on department Form RHF-5A, in accordance with the instructions provided on the form, or in clear and legible records containing all the information required by Form RHF-5A; and shall update the information at least annually.

(7) Each licensee or registrant shall ensure that individuals, for whom they are required to monitor occupational doses in accordance with subsection (1) of this section, wear individual monitoring devices as follows:

(a) An individual monitoring device used for monitoring the dose to the whole body shall be worn at the unshielded or least shielded location of the whole body likely to receive the highest exposure. When a protective apron is worn, the location of the individual monitoring device is typically at the neck (collar).

(b) Any additional individual monitoring device used for monitoring the dose to an embryo/fetus of a declared pregnant woman, pursuant to WAC 246-221-055(1), shall be located at the waist under any protective apron being worn by the woman.

(c) An individual monitoring device used for monitoring the lens dose equivalent, to demonstrate compliance with WAC 246-221-010 (1)(b)(i), shall be located at the neck (collar), outside any protective apron being worn by the monitored individual, or at an unshielded location closer to the eye.

(d) An individual monitoring device used for monitoring the dose to the extremities, to demonstrate compliance with WAC 246-221-010 (1)(b)(ii), shall be worn on the extremity likely to receive the highest exposure. Each individual monitoring device shall be oriented to measure the highest dose to the extremity being monitored.

[Statutory Authority: RCW 70A.388.040 and 70A.388.110. WSR 23-21-056, § 246-221-090, filed 10/11/23, effective 11/11/23. Statutory Authority: RCW 70.98.050. WSR 01-05-110, § 246-221-090, filed 2/21/01, effective 3/24/01; WSR 94-01-073, § 246-221-090, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 92-06-008 (Order 245), § 246-221-090, filed 2/21/92, effective 3/23/92. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-090, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-24-070, filed 12/8/80; Order 1095, § 402-24-070, filed 2/6/76; Order 708, § 402-24-070, filed 8/24/72; Order 1, § 402-24-070, filed 1/8/69; Rules (part), filed 10/26/66.]

PDF246-221-100

Personnel monitoring for internal dose.

(1) Each licensee shall monitor, to determine compliance with WAC 246-221-040, the occupational intake of radioactive material by and assess the committed effective dose equivalent to:

(a) Adults likely to receive, in one year, an intake in excess of 10 percent of the applicable ALI in Table I, Columns 1 and 2, of WAC 246-221-290;

(b) Minors likely to receive, in one year, a committed effective dose equivalent in excess of one mSv (0.1 rem); and

(c) Declared pregnant women likely to receive, during the entire pregnancy, a committed effective dose equivalent in excess of one mSv (0.1 rem).

(2) Where necessary or desirable in order to aid in determining the extent of an individual's exposure to concentrations of radioactive material, the department may incorporate license provisions or issue an order requiring a licensee or registrant to make available to the individual appropriate bioassay services and to furnish a copy of the reports of such services to the department.

(3) Each licensee shall maintain records of doses received by all individuals for whom monitoring was required pursuant to subsections (1) and (2) of this section, and records of doses received during planned special exposures, accidents, and emergency conditions. Assessments of dose equivalent and records made using units in effect before January 1, 1994, need not be changed. These records shall include, when applicable:

(a) The estimated intake or body burden of radionuclides;

(b) The committed effective dose equivalent assigned to the intake or body burden of radionuclides;

(d) The total effective dose equivalent when required by WAC 246-221-015; and

(e) The total of the deep dose equivalent and the committed dose to the organ receiving the highest total dose (total organ dose equivalent).

(4) The licensee or registrant shall maintain the records specified in subsection (3) of this section on department Form RHF-5A, in accordance with the instructions provided on the form, or in clear and legible records containing all the information required by Form RHF-5A; and shall update the information at least annually.

[Statutory Authority: RCW 70A.388.040 and 70A.388.110. WSR 23-21-056, § 246-221-100, filed 10/11/23, effective 11/11/23. Statutory Authority: RCW 70.98.050. WSR 01-05-110, § 246-221-100, filed 2/21/01, effective 3/24/01; WSR 94-01-073, § 246-221-100, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-100, filed 12/27/90, effective 1/31/91; Order 1095, § 402-24-080, filed 2/6/76; Order 1, § 402-24-080, filed 1/8/69; Rules (part), filed 10/26/66.]

PDF246-221-102

Control of access to high radiation areas.

(1) The licensee or registrant shall ensure that each entrance or access point to a high radiation area has one or more of the following features:

(a) A control device that, upon entry into the area, causes the level of radiation to be reduced below that level at which an individual might receive a deep dose equivalent of one mSv (0.1 rem) in one hour at 30 centimeters from the source of radiation or from any surface that the radiation penetrates; or

(b) A control device that energizes a conspicuous visible or audible alarm signal so that the individual entering the high radiation area and the supervisor of the activity are made aware of the entry; or

(c) Entryways that are locked, except during periods when access to the areas is required, with positive control over each individual entry.

(2) In place of the controls required by subsection (1) of this section for a high radiation area, the licensee or registrant may substitute continuous direct or electronic surveillance that is capable of preventing unauthorized entry.

(3) The licensee or registrant may apply to the department for approval of alternative methods for controlling access to high radiation areas.

(4) The licensee or registrant shall establish the controls required by subsections (1) and (3) of this section in a way that does not prevent individuals from leaving a high radiation area.

(5) The licensee is not required to control each entrance or access point to a room or other area that is a high radiation area solely because of the presence of radioactive materials prepared for transport and packaged and labeled in accordance with the regulations of the United States Department of Transportation provided that:

(a) The packages do not remain in the area longer than three days; and

(b) The dose rate at one meter from the external surface of any package does not exceed 0.1 mSv (0.01 rem) per hour.

(6) The licensee is not required to control entrance or access to rooms or other areas in hospitals solely because of the presence of patients containing radioactive material, provided that there are personnel in attendance who are taking the necessary precautions to prevent the exposure of individuals to radiation or radioactive material in excess of the established limits and to operate within the ALARA provisions of the licensee's radiation protection program.

(7) The licensee or registrant is not required to control entrance or access to rooms or other areas as described in this section if the licensee or registrant has met all the specific requirements for access and control specified in other applicable chapters of these regulations, such as, chapter 246-243 WAC for industrial radiography, chapter 246-225 WAC for X-rays in the healing arts, and chapter 246-229 WAC for particle accelerators.

[Statutory Authority: RCW 70A.388.040 and 70A.388.110. WSR 23-21-056, § 246-221-102, filed 10/11/23, effective 11/11/23. Statutory Authority: RCW 70.98.050. WSR 94-01-073, § 246-221-102, filed 12/9/93, effective 1/9/94.]

PDF246-221-104

Control of access to very high radiation areas.

(1) In addition to the requirements in WAC 246-221-102, the licensee or registrant shall institute additional measures to ensure that an individual is not able to gain unauthorized or inadvertent access to areas in which radiation levels could be encountered at five Gy (500 rad) or more in one hour at one meter from a source of radiation or any surface through which the radiation penetrates. This requirement does not apply to rooms or areas in which diagnostic X-ray systems are the only source of radiation, or to nonself-shielded irradiators.

(2) The licensee or registrant is not required to control entrance or access to rooms or other areas containing sources of radiation capable of producing a very high radiation area as described in this section if the licensee or registrant has met all the specific requirements for access and control specified in other applicable chapters of these regulations, such as, chapter 246-243 WAC for industrial radiography, chapter 246-225 WAC for X-rays in the healing arts, and chapter 246-229 WAC for particle accelerators.

[Statutory Authority: RCW 70.98.050. WSR 94-01-073, § 246-221-104, filed 12/9/93, effective 1/9/94.]

PDF246-221-106

Control of access to very high radiation areas—Irradiators.

(1) This section applies to licensees or registrants with sources of radiation in nonself-shielded irradiators. This section does not apply to sources of radiation that are used in teletherapy, in industrial radiography, or in completely self-shielded irradiators in which the source of radiation is both stored and operated within the same shielding radiation barrier and, in the designed configuration of the irradiator, is always physically inaccessible to any individual and cannot create a radiation level of five Gy (500 rad) or more in one hour at one meter in an area that is accessible to any individual.

(2) Each area in which there may exist radiation levels in excess of five Gy (500 rad) in one hour at one meter from a source of radiation that is used to irradiate materials shall meet the following requirements:

(a) Each entrance or access point shall be equipped with entry control devices which:

(i) Function automatically to prevent any individual from inadvertently entering a very high radiation area; and

(ii) Permit deliberate entry into the area only after a control device is actuated that causes the radiation level within the area, from the source of radiation, to be reduced below that at which it would be possible for an individual to receive a deep dose equivalent in excess of one mSv (0.1 rem) in one hour; and

(iii) Prevent operation of the source of radiation if it would produce radiation levels in the area that could result in a deep dose equivalent to an individual in excess of one mSv (0.1 rem) in one hour.

(b) Additional control devices shall be provided so that, upon failure of the entry control devices to function as required by (a) of this subsection:

(i) The radiation level within the area, from the source of radiation, is reduced below that at which it would be possible for an individual to receive a deep dose equivalent in excess of one mSv (0.1 rem) in one hour; and

(ii) Conspicuous visible and audible alarm signals are generated to make an individual attempting to enter the area aware of the hazard and at least one other authorized individual, who is physically present, familiar with the activity, and prepared to render or summon assistance, aware of the failure of the entry control devices.

(c) The licensee or registrant shall provide control devices so that, upon failure or removal of physical radiation barriers other than the sealed source's shielded storage container:

(i) The radiation level from the source of radiation is reduced below that at which it would be possible for an individual to receive a deep dose equivalent in excess of one mSv (0.1 rem) in one hour; and

(ii) Conspicuous visible and audible alarm signals are generated to make potentially affected individuals aware of the hazard and the licensee or registrant or at least one other individual, who is familiar with the activity and prepared to render or summon assistance, aware of the failure or removal of the physical barrier.

(d) When the shield for stored sealed sources is a liquid, the licensee shall provide means to monitor the integrity of the shield and to signal, automatically, loss of adequate shielding.

(e) Physical radiation barriers that comprise permanent structural components, such as walls, that have no credible probability of failure or removal in ordinary circumstances need not meet the requirements of (c) and (d) of this subsection.

(f) Each area shall be equipped with devices that will automatically generate conspicuous visible and audible alarm signals to alert personnel in the area before the source of radiation can be put into operation and in time for any individual in the area to operate a clearly identified control device, which must be installed in the area and which can prevent the source of radiation from being put into operation.

(g) Each area shall be controlled by use of such administrative procedures and such devices as are necessary to ensure that the area is cleared of personnel prior to each use of the source of radiation.

(h) Each area shall be checked by a radiation measurement to ensure that, prior to the first individual's entry into the area after any use of the source of radiation, the radiation level from the source of radiation in the area is below that at which it would be possible for an individual to receive a deep dose equivalent in excess of one mSv (0.1 rem) in one hour.

(i) Entry and exit portals that are used in transporting materials to and from the irradiation area, and that are not intended for use by individuals, shall be controlled by such devices and administrative procedures as are necessary to physically protect and warn against inadvertent entry by any individual through these portals. Exit portals for irradiated materials shall be equipped to detect and signal the presence of any loose radioactive material that is carried toward such an exit and automatically to prevent loose radioactive material from being carried out of the area.

(3) The entry control devices required in subsection (2)(a) of this section shall be tested for proper functioning:

(a) Prior to initial operation with the source of radiation on any day, unless operations were continued uninterrupted from the previous day; and

(b) Prior to resumption of operation of the source of radiation after any unintentional interruption; and

(c) In accordance with a schedule for periodic tests of the entry control and warning systems submitted by the licensee or registrant and approved by the department.

(4) The licensee or registrant shall not conduct operations, other than those necessary to place the source of radiation in safe condition or to effect repairs on controls, unless control devices are functioning properly.

(5) Licensees, registrants, or applicants for licenses or registrations for sources of radiation within the purview of subsection (2) of this section which will be used in a variety of positions or in locations, such as open fields or forests, that make it impracticable to comply with certain requirements of subsection (2) of this section, such as those for the automatic control of radiation levels, may apply to the department for approval of alternative safety measures. Alternative safety measures shall provide personnel protection at least equivalent to those specified in subsection (2) of this section. At least one of the alternative measures shall include an entry-preventing interlock control based on a measurement of the radiation that ensures the absence of high radiation levels before an individual can gain access to the area where such sources of radiation are used.

(6) The entry control devices required by subsections (2) and (3) of this section shall be established in such a way that no individual will be prevented from leaving the area.

(7) The licensee shall maintain records of tests made pursuant to subsection (3) of this section on entry control devices for very high radiation areas. These records shall include the date, time, and results of each such test of function.

[Statutory Authority: RCW 70.98.050. WSR 94-01-073, § 246-221-106, filed 12/9/93, effective 1/9/94.]

PDF246-221-110

Surveys.

(1) Each licensee or registrant shall make or cause to be made such surveys, as defined in WAC 246-220-010, as may be necessary for the licensee or registrant to establish compliance with these regulations and are reasonable under the circumstances to evaluate the magnitude and extent of radiation levels, concentrations or quantities of radioactive material, and potential radiation hazards. Records of such surveys shall be preserved as specified in WAC 246-221-230. Information on performing surveys may be found in the NRC's Regulatory Guide 8.23 "Radiation Safety Surveys at Medical Institutions."

(2) The licensee shall ensure that instruments and equipment used for quantitative radiation measurements, for example, dose rate and effluent monitoring, are calibrated annually at intervals not to exceed 13 months for the radiation measured.

[Statutory Authority: RCW 70A.388.040 and 70A.388.110. WSR 23-21-056, § 246-221-110, filed 10/11/23, effective 11/11/23. Statutory Authority: RCW 70.98.050. WSR 14-01-077, § 246-221-110, filed 12/16/13, effective 1/16/14; WSR 01-05-110, § 246-221-110, filed 2/21/01, effective 3/24/01; WSR 94-01-073, § 246-221-110, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-221-110, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-110, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 87-01-031 (Order 2450), § 402-24-085, filed 12/11/86; WSR 83-19-050 (Order 2026), § 402-24-085, filed 9/16/83. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-24-085, filed 12/8/80; Order 1095, § 402-24-085, filed 2/6/76.]

PDF246-221-113

Use of process, engineering or other controls.

(1) The licensee shall use, to the extent practical, process or other engineering controls, such as, containment, decontamination, or ventilation, to control the concentrations of radioactive material in air.

(2) When it is not practical to apply process or other engineering controls to control the concentrations of radioactive material in air to values below those that define an airborne radioactivity area, the licensee shall, consistent with maintaining the total effective dose equivalent ALARA, increase monitoring and limit intakes by one or more of the following means:

(a) Control of access;

(b) Limitation of exposure times;

(d) Other controls.

(3) If the licensee performs an ALARA analysis to determine whether or not respirators should be used, the licensee may consider safety factors other than radiological factors. The licensee should also consider the impact of respirator use on workers' industrial health and safety.

[Statutory Authority: RCW 70.98.050. WSR 01-05-110, § 246-221-113, filed 2/21/01, effective 3/24/01; WSR 94-01-073, § 246-221-113, filed 12/9/93, effective 1/9/94.]

PDF246-221-117

Use of individual respiratory protection equipment.

If the licensee assigns or permits the use of respiratory protection equipment to limit the intake of radioactive material:

(1) The licensee shall use only respiratory protection equipment that is:

(a) Tested and certified by the National Institute for Occupational Safety and Health (NIOSH); or

(b) Approved by the department on the basis of the licensee's submittal of an application for authorized use of other respiratory protection equipment, including a demonstration by testing, or a demonstration on the basis of reliable test information, that the material and performance characteristics of the equipment are capable of providing the proposed degree of protection under anticipated conditions of use.

(2) The licensee shall implement and maintain a respiratory protection program that includes:

(a) Air sampling sufficient to identify the potential hazard, permit proper equipment selection, and estimate exposures;

(b) Surveys and bioassays, as appropriate, to evaluate actual intakes;

(c) Testing of respirators for operability (user seal check for face sealing devices and functional check for others) immediately prior to each use;

(d) Written procedures regarding:

(i) Monitoring, including air sampling and bioassays;

(ii) Supervision and training of respirator users;

(iii) Fit testing;

(iv) Respirator selection;

(v) Breathing air quality;

(vi) Inventory and control;

(vii) Storage, issuance, maintenance, repair, testing, and quality assurance of respiratory protection equipment;

(viii) Recordkeeping; and

(ix) Limitations on periods of respirator use and relief from respirator use;

(e) Determination by a physician that the individual user is medically fit to use respiratory protection equipment:

(i) Before the initial fitting of a face sealing respirator;

(ii) Before the first field use of nonface sealing respirators; and

(iii) Either every 12 months thereafter, or periodically at a frequency determined by a physician; and

(f) Fit testing, with a fit factor greater than or equal to 10 times the APF for negative pressure devices, and a fit factor greater than or equal to 500 for any positive pressure, continuous flow, and pressure-demand devices, before the first field use of tight fitting, face sealing respirators, and periodically thereafter at a frequency not to exceed one year. Fit testing must be performed with the facepiece operating in the negative pressure mode.

(3) The licensee shall advise each respirator user that the user may leave the area at any time for relief from respirator use in the event of equipment malfunction, physical or psychological distress, procedural or communication failure, significant deterioration of operating conditions, or any other conditions that might require relief.

(4) The licensee shall also consider limitations appropriate to the type and mode of use. When selecting respiratory devices the licensee shall provide for vision correction, adequate communication, low temperature work environments, and the concurrent use of other safety or radiological protection equipment. The licensee shall use equipment in such a way as not to interfere with the proper operation of the respirator.

(5) Standby rescue persons are required whenever one-piece atmosphere-supplying suits, or any combination of supplied air respiratory protection device and personnel protective equipment are used from which an unaided individual would have difficulty extricating himself or herself. The standby persons must be equipped with respiratory protection devices or other apparatus appropriate for the potential hazards. The standby rescue persons shall observe or otherwise maintain continuous communication with the workers (visual, voice, signal line, telephone, radio, or other suitable means), and be immediately available to assist them in case of a failure of the air supply or for any other reason that requires relief from distress. A sufficient number of standby rescue persons must be immediately available to assist all users of this type of equipment and to provide effective emergency rescue if needed.

(6) Atmosphere-supplying respirators must be supplied with respirable air of grade D quality or better as defined by the Compressed Gas Association in publication G-7.1, "Commodity Specification for Air," 1997 and included in the regulations of the Occupational Safety and Health Administration (29 C.F.R. 1910.134 (i)(1)(ii)(A) through (E)). Grade D quality air criteria include:

(a) Oxygen content (v/v) of 19.5-23.5%;

(b) Hydrocarbon (condensed) content of five milligrams per cubic meter of air or less;

(d) Carbon dioxide content of 1,000 ppm or less; and

(e) Lack of noticeable odor.

(7) The licensee shall ensure that no objects, materials or substances, such as facial hair, or any conditions that interfere with the face-to-facepiece seal or valve function, and that are under the control of the respirator wearer, are present between the skin of the wearer's face and the sealing surface of a tight-fitting respirator facepiece.

(8) In estimating the dose to individuals from intake of airborne radioactive materials, the concentration of radioactive material in the air that is inhaled when respirators are worn is initially assumed to be the ambient concentration in air without respiratory protection, divided by the assigned protection factor. If the dose is later found to be greater than the estimated dose, the corrected value must be used. If the dose is later found to be less than the estimated dose, the corrected value may be used.

(9) The department may impose restrictions in addition to the provisions of this section, WAC 246-221-113 and 246-221-285, in order to:

(a) Ensure that the respiratory protection program of the licensee is adequate to limit doses to individuals from intakes of airborne radioactive materials consistent with maintaining total effective dose equivalent ALARA; and

(b) Limit the extent to which a licensee may use respiratory protection equipment instead of process or other engineering controls.

(10) The licensee shall obtain authorization from the department before using assigned protection factors in excess of those specified in WAC 246-221-285. The department may authorize a licensee to use higher assigned protection factors on receipt of an application that:

(a) Describes the situation for which a need exists for higher protection factors; and

(b) Demonstrates that the respiratory protection equipment provides these higher protection factors under the proposed conditions of use.

[Statutory Authority: RCW 70A.388.040 and 70A.388.110. WSR 23-21-056, § 246-221-117, filed 10/11/23, effective 11/11/23. Statutory Authority: RCW 70.98.050. WSR 01-05-110, § 246-221-117, filed 2/21/01, effective 3/24/01; WSR 98-13-034, § 246-221-117, filed 6/8/98, effective 7/9/98; WSR 94-01-073, § 246-221-117, filed 12/9/93, effective 1/9/94.]

PDF246-221-120

Caution signs, and labels.

(1) The radiation symbol shall be used on all signs, labels, or other written means of warning individuals concerning radiation hazards.

(a) The symbol prescribed by this section is the conventional three-blade design: Radiation symbol

(b) The symbol prescribed by this section shall be:

(i) Magenta, purple, or black on a yellow background; or

(ii) Conspicuously etched or stamped without regard to a color requirement on sources, source holders or device components containing sources which are subjected to extreme environmental conditions which would cause the color to deteriorate.

(2) The conventional radiation symbol as described in subsection (1) of this section shall be used only for:

(a) Instructing individuals to be cognizant of a potential radiation hazard as prescribed in subsections (4) through (10) of this section.

(b) Indicating that information presented pertains to the topic of radiation.

(3) In addition to the contents of signs and labels prescribed in this section, a licensee or registrant may provide on or near such signs and labels any additional information which may be appropriate in aiding individuals to minimize exposure to radiation.

(4) Each radiation area and entrance thereto shall be conspicuously posted with a sign or signs bearing the radiation caution symbol and the words: caution* - radiation area. However, in an exceptionally large room where other activities of a nonradiological nature are conducted the entrance need not be posted provided a conspicuous barricade with an appropriate number of signs is established to delineate the radiation area.

(5) Each high radiation area and all entrances thereto shall be conspicuously posted with a sign or signs bearing the radiation caution symbol and the words: caution* - high radiation area or danger - high radiation area. To avoid unnecessary exposure, the licensee or registrant may satisfy this requirement by posting the sign at the estimated location or vicinity of the high radiation area.

(6) Each very high radiation area shall be conspicuously posted with a sign or signs bearing the radiation caution symbol and the words: grave danger - very high radiation area. To avoid unnecessary exposure, the licensee or registrant may satisfy this requirement by posting the sign at the estimated location or vicinity of the very high radiation area.

(7) Each airborne radioactivity area shall be conspicuously posted with a sign or signs bearing the radiation caution symbol and the words: caution* - airborne radioactivity area or danger - airborne radioactivity area.

(8) Each area or room in which any radioactive material is used or stored in an amount exceeding 10 times the quantity of radioactive material specified in WAC 246-221-300 shall be conspicuously posted with a sign or signs bearing the radiation caution symbol and the words: caution* - radioactive material or danger - radioactive material.

(9) Each container of radioactive material shall bear a durable, clearly visible label identifying the radioactive contents including:

(a) The radiation caution symbol and the words: caution* - radioactive material or danger - radioactive material.

(b) Sufficient information to permit individuals handling or using the containers, or working in the vicinity thereof, to take precautions to avoid or minimize exposures, such as radionuclides present, radiation levels, estimate of activity and mass enrichment.

(c) Where containers are used for storage, the quantities and kinds of radioactive materials in the containers and the date of measurement of the quantities.

(10) All radiation machines shall be labeled in a conspicuous manner so as to caution individuals that radiation is produced when the machine is being operated.

[Statutory Authority: RCW 70.98.050. WSR 94-01-073, § 246-221-120, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-221-120, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-120, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 87-01-031 (Order 2450), § 402-24-090, filed 12/11/86. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-24-090, filed 12/8/80; Order 1095, § 402-24-090, filed 2/6/76; Order 1, § 402-24-090, filed 1/8/69; Rules (part), filed 10/26/66.]

PDF246-221-130

Exceptions from posting and labeling requirements.

(1) A room or area is not required to be posted with a caution sign because of the presence of a sealed source, provided the radiation level 30 centimeters from the surface of the source container or housing does not exceed 0.05 mSv (five millirem) per hour.

(2) Rooms or other areas in hospitals that are occupied by patients are not required to be posted with caution signs because of the presence of patients containing radioactive material if the patient could be released from licensee control under chapter 246-240 WAC.

(3) Caution signs are not required to be posted in areas or rooms containing radioactive material for periods of less than eight hours if:

(a) The material is constantly attended during those periods by an individual who takes precautions necessary to prevent the exposure of any individual to radiation or radioactive material in excess of the limits established in these rules; and

(b) The area or room is subject to the licensee's or registrant's control.

(4) A room or other area is not required to be posted with a caution sign because of the presence of radioactive material prepared for transport and packaged and labeled in accordance with regulations of the United States Department of Transportation.

(5) A room or area is not required to be posted with a caution sign because of the presence of a diagnostic X-ray system used solely for healing arts purposes.

(6) The interior of a teletherapy room is not required to be posted with caution signs provided the posting is conspicuously placed at the entrance(s) to the rooms.

(7) A licensee is not required to label:

(a) Containers holding licensed material in quantities less than the quantities listed in WAC 246-221-300; or

(b) Containers holding licensed material in concentrations less than those specified in WAC 246-221-290, Table III; or

(c) Containers attended by an individual who takes the precautions necessary to prevent the exposure of any individual to radiation or radioactive material in excess of the limits established by this chapter; or

(d) Containers when they are in transport and packaged and labeled in accordance with the regulations of the United States Department of Transportation; or

(e) Containers such as those located in water-filled canals, storage vaults, or hot cells, that are accessible only to individuals authorized to handle or use them, or to work in the vicinity of the containers, provided the contents are identified to these individuals by a readily available written record. The record shall be retained as long as the containers are in use for the purpose indicated on the record; or

(f) Installed manufacturing or process equipment, such as chemical process equipment, piping, and tanks.

(8) Each licensee, prior to removal or disposal of empty uncontaminated containers to unrestricted areas, shall remove or deface the radioactive material label or otherwise clearly indicate that the container no longer contains radioactive materials.

[Statutory Authority: RCW 70.98.050. WSR 06-05-019, § 246-221-130, filed 2/6/06, effective 3/9/06; WSR 98-13-037, § 246-221-130, filed 6/8/98, effective 7/9/98; WSR 94-01-073, § 246-221-130, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-221-130, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-130, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 83-19-050 (Order 2026), § 402-24-095, filed 9/16/83. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-24-095, filed 12/8/80; Order 1095, § 402-24-095, filed 2/6/76.]

PDF246-221-140

Instruction of personnel.

Instructions required for individuals working in or frequenting any portion of a restricted area are specified in WAC 246-222-020, 246-222-030, and 246-222-040.

[Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-221-140, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-140, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 83-19-050 (Order 2026), § 402-24-110, filed 9/16/83; Order 1095, § 402-24-110, filed 2/6/76; Order 708, § 402-24-110, filed 8/24/72; Order 1, § 402-24-110, filed 7/2/71; Order 1, § 402-24-110, filed 1/8/69; Rules (part), filed 10/26/66.]

PDF246-221-150

Security and control of radioactive material and radiation machines.

(1) Licensed radioactive materials and registered radiation machines shall be secured from, or controlled in such a manner so as to prevent, unauthorized access or removal from the place of storage.

(2) Each portable gauge licensee shall use a minimum of two independent physical controls that form tangible barriers to secure portable gauges from unauthorized removal, whenever portable gauges are not under the control and constant surveillance of the licensee.

(3) Licensed radioactive materials in an unrestricted area and not in storage shall be tended under the constant surveillance and immediate control of the licensee.

(4) Registered radiation machines in an unrestricted area and not in storage shall be under the control of the registrant.

[Statutory Authority: RCW 70.98.050. WSR 07-17-028, § 246-221-150, filed 8/7/07, effective 9/7/07; WSR 94-01-073, § 246-221-150, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-150, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 83-19-050 (Order 2026), § 402-24-120, filed 9/16/83; Order 1095, § 402-24-120, filed 2/6/76; Order 1, § 402-24-120, filed 1/8/69; Rules (part), filed 10/26/66.]

PDF246-221-160

Procedures for picking up, receiving, and opening packages.

(1) Each licensee who expects to receive a package containing quantities of radioactive material in excess of the Type A1 or A2 quantities specified in WAC 246-231-200 shall make arrangements to receive:

(a) The package when it is offered for delivery by the carrier; or

(b) Immediate notification from the carrier of the arrival of the package at the carrier's terminal.

(2) Each licensee who picks up a package of radioactive material from a carrier's terminal shall pick up the package expeditiously upon receipt of notification from the carrier of its arrival.

(3) Each licensee shall:

(a) Monitor for radioactive contamination the external surfaces of any package labeled with a Radioactive White I, Yellow II or Yellow III label unless the package contains only radioactive material in the form of gas or in special form as defined in WAC 246-231-010; and

(b) Monitor the radiation levels of the external surfaces of any package labeled with a Radioactive White I, Yellow II or Yellow III label unless the package contains quantities of radioactive material that are less than or equal to the Type A quantity, as defined in WAC 246-231-200; and

(c) Monitor all packages known to contain radioactive material for radioactive contamination and radiation levels if the package has evidence of potential contamination, such as packages that are crushed, wet, or damaged.

(4) Monitoring shall be performed:

(a) Immediately upon receipt if there is evidence of package degradation or any other evidence of potential contamination or excessive radiation levels; or

(b) As soon as practicable after receipt, but no later than three hours after the package is received at the licensee's facility if received during the licensee's normal working hours, or no later than three hours from the beginning of the next working day if received after normal working hours.

(5) The licensee shall immediately notify the final delivery carrier and, by telephone, facsimile, or email, the department when:

(a) For normal shipments, removable radioactive surface contamination exceeds either 22 dpm/cm2 for beta-gamma emitting radionuclides, all radionuclides with half-lives less than 10 days, natural uranium, natural thorium, uranium-235, uranium-238, thorium-232, and thorium-228 and thorium 230 when contained in ores or concentrates; or 2.2 dpm/cm2 for all other alpha emitting radionuclides; or

(b) For exclusive use shipments, removable radioactive surface contamination exceeds either 220 dpm/cm2 for beta-gamma emitting radionuclides, all radionuclides with half-lives less than 10 days, natural uranium, natural thorium, uranium-235, uranium-238, thorium-232, and thorium-228 and thorium 230 when contained in ores or concentrates; or 22 dpm/cm2 for all other alpha emitting radionuclides; or

(c) For normal or exclusive use shipments, external radiation levels exceed two mSv/hour (200 millirem per hour) at any point on the external surface of the package; or

(d) For exclusive use shipments where the shipment is made in a closed transport vehicle, packages are secured in a fixed position, and no loading or unloading occurs between the beginning and end of transportation, external radiation levels exceed 10 mSv/hour (1000 millirem per hour) at any point on the external surface of the package.

(6) Each licensee shall establish and maintain procedures for safely opening packages in which radioactive material is received, and shall assure that such procedures are followed and that due consideration is given to instructions for the type of package being opened and the monitoring of potentially contaminated packaging material (including packages containing radioactive material in gaseous form) to assure that only background levels of radiation are present prior to disposal of such material as nonradioactive waste.

(7) Licensees transferring special form sources to and from a work site in vehicles owned or operated by the licensee are exempt from the contamination monitoring requirements of subsection (3)(a) of this section but are not exempt from the monitoring requirement in subsection (3)(b) of this section for measuring radiation levels to ensure that the source is still properly lodged in its shield.

[Statutory Authority: RCW 70A.388.040 and 70A.388.110. WSR 23-21-056, § 246-221-160, filed 10/11/23, effective 11/11/23. Statutory Authority: RCW 70.98.050 and 70.98.110. WSR 16-13-054, § 246-221-160, filed 6/10/16, effective 7/11/16. Statutory Authority: RCW 70.98.050. WSR 14-01-077, § 246-221-160, filed 12/16/13, effective 1/16/14; WSR 99-15-105, § 246-221-160, filed 7/21/99, effective 8/21/99; WSR 94-01-073, § 246-221-160, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-221-160, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-160, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 87-01-031 (Order 2450), § 402-24-125, filed 12/11/86; WSR 83-19-050 (Order 2026), § 402-24-125, filed 9/16/83. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-24-125, filed 12/8/80; Order 1095, § 402-24-125, filed 2/6/76.]

PDF246-221-170

Waste disposal, general requirement.

(1) No licensee shall dispose of any radioactive material except:

(a) By transfer to an authorized recipient as provided in WAC 246-232-080, or chapter 246-249 WAC; or

(b) As authorized pursuant to WAC 246-221-070, 246-221-180, 246-221-190, 246-221-200, 246-221-210, or 246-221-220.

(2) A person shall be specifically licensed to receive waste containing licensed material from other persons for:

(a) Treatment prior to disposal; or

(b) Treatment or disposal by incineration; or

(d) Disposal at a land disposal facility licensed pursuant to chapter 246-250 WAC; or

(e) Storage until transferred to a disposal facility authorized to receive the waste.

(3) Nothing in chapter 246-221 WAC relieves the licensee from complying with other applicable federal, state, and local regulations governing any other toxic or hazardous properties of materials that may be disposed pursuant to this chapter.

(4) Each licensee shall maintain records of all transfers and disposals of radioactive material. Requirements for the disposition of certain disposal records, prior to license termination, are located in WAC 246-232-060.

[Statutory Authority: RCW 70.98.050. WSR 99-15-105, § 246-221-170, filed 7/21/99, effective 8/21/99; WSR 94-01-073, § 246-221-170, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-221-170, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-170, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-24-130, filed 12/8/80; Order 1095, § 402-24-130, filed 2/6/76; Order 1, § 402-24-130, filed 1/8/69; Rules (part), filed 10/26/66.]

PDF246-221-180

Method of obtaining approval of proposed disposal procedures.

Any person may apply to the department for approval of proposed procedures to dispose of radioactive material in a manner not otherwise authorized in this chapter. Each application shall contain a description of the radioactive material, including the quantities and kinds of radioactive material and levels of radioactivity involved, the physical and chemical properties that have an impact on risk evaluation, and the proposed manner and conditions of disposal. The application, where appropriate, shall also include an analysis and evaluation of pertinent information as to the nature of the environment, including topographical, geological, meteorological, and hydrological characteristics; usage of ground and surface waters in the general area; the nature and location of other potentially affected facilities; analyses and procedures to ensure that doses are maintained ALARA within the dose limits of this chapter; and procedures to be observed to minimize the risk of unexpected or hazardous exposures.

The department will not approve any application for a license to receive radioactive material from other persons for disposal on land not owned by a state or the federal government.

[Statutory Authority: RCW 70.98.050. WSR 94-01-073, § 246-221-180, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-180, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 87-01-031 (Order 2450), § 402-24-135, filed 12/11/86; Order 1095, § 402-24-135, filed 2/6/76.]

PDF246-221-190

Disposal by release into sanitary sewerage systems.

(1) No licensee shall discharge radioactive material into a sanitary sewerage system unless:

(a) It is readily soluble or it is biological material which is readily dispersible in water;

(b) The quantity of any radioactive material released in any one month, if diluted by the average monthly quantity of water released by the licensee, will not result in an average concentration exceeding the limits specified in WAC 246-221-290, Table III; and

(c) The sum of the fractions for each radionuclide, if more than one radionuclide is released, will not exceed unity; where the fraction for each radionuclide is determined by dividing the actual monthly average concentration of each radionuclide released by the licensee into the sewer by the concentration of that radionuclide listed in Table III of WAC 246-221-290; and

(d) The total quantity of licensed and other radioactive material that the licensee releases into the sanitary sewerage system in a year does not exceed 185 GBq (five Ci) of hydrogen-3, 37 GBq (one Ci) of carbon-14, and 37 GBq (one Ci) of all other radioactive materials combined.

(2) Excreta from individuals undergoing medical diagnosis or therapy with radioactive material shall be exempt from any limitations contained in this section.

[Statutory Authority: RCW 70A.388.040 and 70A.388.110. WSR 23-21-056, § 246-221-190, filed 10/11/23, effective 11/11/23. Statutory Authority: RCW 70.98.050. WSR 94-01-073, § 246-221-190, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-221-190, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-190, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 83-19-050 (Order 2026), § 402-24-140, filed 9/16/83. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-24-140, filed 12/8/80; Order 1095, § 402-24-140, filed 2/6/76; Order 1, § 402-24-140, filed 1/8/69; Rules (part), filed 10/26/66.]

PDF246-221-200

Disposal by burial in soil.

No licensee shall dispose of radioactive material by burial in soil except as specifically approved by the department pursuant to WAC 246-221-180.

[Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-221-200, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-200, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-24-150, filed 12/8/80; Order 1095, § 402-24-150, filed 2/6/76; Order 1, § 402-24-150, filed 1/8/69; Rules (part), filed 10/26/66.]

PDF246-221-210

Disposal by incineration.

No licensee shall incinerate radioactive material for the purpose of disposal or preparation for disposal except as specifically approved by the department pursuant to WAC 246-221-070 and 246-221-180.

[Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-221-210, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-210, filed 12/27/90, effective 1/31/91; Order 1095, § 402-24-160, filed 2/6/76; Order 1, § 402-24-160, filed 1/8/69; Rules (part), filed 10/26/66.]

PDF246-221-220

Disposal of specific wastes.

(1) Any licensee may dispose of the following licensed material without regard to its radioactivity:

(a) 1.85 KBq (0.05 microcurie) or less of hydrogen-3 or carbon-14, per gram of medium, used for liquid scintillation counting; and

(b) 1.85 KBq (0.05 microcurie) or less of hydrogen-3 or carbon-14, per gram of animal tissue averaged over the weight of the entire animal.

(2) The licensee shall not dispose of tissue under this section in a manner that would permit its use either as food for humans or as animal feed; and

(3) Nothing in this section, however, relieves the licensee of maintaining records showing the receipt, transfer and disposal of such radioactive material as specified in WAC 246-220-020; and

(4) Nothing in this section relieves the licensee from complying with other applicable federal, state and local regulations governing any other toxic or hazardous property of these materials.

[Statutory Authority: RCW 70.98.050. WSR 14-01-077, § 246-221-220, filed 12/16/13, effective 1/16/14; WSR 94-01-073, § 246-221-220, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-221-220, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-220, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 83-19-050 (Order 2026), § 402-24-165, filed 9/16/83.]

PDF246-221-230

Records important to radiation safety.

(1) Each licensee or registrant shall make and retain records of activities, program reviews, measurements, and calculations which may be necessary to determine the extent of occupational and public exposure from sources of radiation under the control of the licensee or registrant.

(2) Each record required by this section shall be legible throughout the specified retention period.

(3) Each licensee or registrant shall use the SI units: Becquerel, gray, sievert and coulomb per kilogram, or the special units: Curie, rad, rem, and roentgen, including multiples and subdivisions, and shall clearly indicate the units of all quantities on records required by these regulations.

(4) The licensee or registrant shall make a clear distinction among the quantities entered on the records required by these regulations such as, total effective dose equivalent, total organ dose equivalent, shallow dose equivalent, lens dose equivalent, deep dose equivalent, or committed effective dose equivalent.

(5) Records which must be maintained under this part shall be the original or a reproduced copy or microform if such reproduced copy or microform is duly authenticated by authorized personnel and the microform is capable of producing a clear and legible copy after storage for the period specified by department regulations. The record may also be stored in electronic media with the capability for producing legible, accurate, and complete records during the required retention period. Electronic media data storage systems shall incorporate standard or universally recognized security measures. Records, such as letters, drawings, and specifications, shall include all pertinent information, such as stamps, initials, and signatures.

(6) The licensee shall maintain adequate safeguards against tampering with and loss of records.

(7) The licensee or registrant shall retain the following required records until the department terminates each pertinent license or registration requiring the record, and upon termination of the license or registration, the licensee or registrant shall store for at least 30 years:

(a) Records of prior occupational dose and exposure history as recorded on department Form RHF-4 or RHF-4A, or equivalent;

(b) Records on department Form RHF-5 or RHF-5A, or equivalent, of doses received by all individuals for whom monitoring was required pursuant to WAC 246-221-090 and 246-221-100;

(d) The specific information used to calculate the committed effective dose equivalent pursuant to WAC 246-221-040(3);

(e) Records of the results of surveys to determine the dose from external sources of radiation used, in the absence of or in combination with individual monitoring data, in the assessment of individual dose equivalents;

(f) Records of the results of measurements and calculations used to determine individual intakes of radioactive material and used in the assessment of internal dose;

(g) Records showing the results of air sampling, surveys, and bioassays required pursuant to WAC 246-221-117 (1)(b)(i) and (ii);

(h) Records of the results of measurements and calculations used to evaluate the release of radioactive effluents to the environment.

(8) The licensee or registrant shall retain the following records until the department terminates the pertinent license or registration requiring the record:

(a) Records of waste disposal made under the provisions of WAC 246-221-180, 246-221-190, 246-221-210 and 246-221-220, chapter 246-249 WAC, and any burials in soil as previously authorized;

(b) Records of dose to individual members of the public as required by WAC 246-221-060(4);

(9) The licensee or registrant shall retain the following records for three years after the record is made:

(a) Records of testing entry control devices for very high radiation areas as required by WAC 246-221-106(3);

(b) Records used in preparing department Form RHF-4 or RHF-4A;

(c) Records showing the results of general surveys required by WAC 246-221-110 and package surveys required by WAC 246-221-160;

(d) Records of calibrations required by WAC 246-221-110;

(e) Records of program audits and other reviews of the content and implementation of the radiation protection program required by WAC 246-221-005;

(f) Records of waste disposal by decay in storage.

(10) If there is a conflict between the department's regulations in this part, license condition, or other written department approval or authorization pertaining to the retention period for the same type of record, the retention period specified in the regulations in this part for such records shall apply unless the department, under WAC 246-220-050, has granted a specific exemption from the record retention requirements specified in the regulations in this part.

(11) The discontinuance or curtailment of activities does not relieve the licensee or registrant of responsibility for retaining all records required by this section.

[Statutory Authority: RCW 70A.388.040 and 70A.388.110. WSR 23-21-056, § 246-221-230, filed 10/11/23, effective 11/11/23. Statutory Authority: RCW 70.98.050. WSR 01-05-110, § 246-221-230, filed 2/21/01, effective 3/24/01; WSR 94-01-073, § 246-221-230, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-221-230, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-230, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 87-01-031 (Order 2450), § 402-24-170, filed 12/11/86; WSR 83-19-050 (Order 2026), § 402-24-170, filed 9/16/83. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-24-170, filed 12/8/80; Order 1095, § 402-24-170, filed 2/6/76; Order 708, § 402-24-170, filed 8/24/72; Order 1, § 402-24-170, filed 7/2/71; Order 1, § 402-24-170, filed 1/8/69; Rules (part), filed 10/26/66.]

PDF246-221-235

Reports of transactions involving nationally tracked sources.

Each licensee who manufactures, transfers, receives, disassembles, or disposes of a nationally tracked source shall complete and submit a National Source Tracking Transaction Report as specified in subsections (1) through (5) of this section for each type of transaction.

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

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

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

(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;

(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;

(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;

(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 online National Source Tracking System;

(b) Electronically using a computer-readable format;

(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.

[Statutory Authority: RCW 70A.388.040 and 70A.388.110. WSR 23-21-056, § 246-221-235, filed 10/11/23, effective 11/11/23. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 09-06-003, § 246-221-235, filed 2/18/09, effective 3/21/09.]

PDF246-221-236

Nationally tracked source thresholds.

The Terabecquerel (TBq) values are the regulatory standard. The curie (Ci) values specified are obtained by converting from the TBq value. The curie values are provided for practical usefulness only and are rounded after conversion.

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

[Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 09-06-003, § 246-221-236, filed 2/18/09, effective 3/21/09.]

PDF246-221-240

Reports of stolen, lost or missing radiation sources.

(1) Each licensee and registrant shall report by telephone ( 206-682-5327) and confirm promptly by letter, facsimile, or email to the State Department of Health, Office of Radiation Protection, P.O. Box 47827, Olympia, Washington 98504-7827.

(a) Immediately after its occurrence becomes known to the licensee, stolen, lost, or missing radioactive material in an aggregate quantity equal to or greater than 1,000 times the quantity specified in WAC 246-221-300, Appendix B; or

(b) Within 30 days after its occurrence becomes known to the licensee, lost, stolen, or missing radioactive material in an aggregate quantity greater than 10 times the quantity specified in WAC 246-221-300, Appendix B that is still missing or any item not exempted in chapter 246-232 WAC; or

(2) Each licensee or registrant required to make a report pursuant to subsection (1) of this section shall, within 30 days after making the telephone report, make a written report to the department setting forth the following information:

(a) A description of the licensed or registered source of radiation involved, including, for radioactive material, the kind, quantity, and chemical and physical form; and, for radiation machines, the manufacturer, model and serial number, type and maximum energy of radiation emitted; and

(b) A description of the circumstances under which the loss or theft occurred; and

(d) Exposures of individuals to radiation, circumstances under which the exposures occurred, and the possible total effective dose equivalent to persons in unrestricted areas; and

(e) Actions that have been taken, or will be taken, to recover the source of radiation; and

(f) Procedures or measures that have been, or will be, adopted to ensure against a recurrence of the loss or theft of licensed or registered sources of radiation.

(3) Subsequent to filing the written report, the licensee or registrant shall also report additional substantive information on the loss or theft within 30 days after the licensee or registrant learns of such information.

(4) The licensee or registrant shall prepare any report filed with the department pursuant to this section so that names of individuals who may have received exposure to radiation are stated in a separate and detachable portion of the report.

[Statutory Authority: RCW 70A.388.040 and 70A.388.110. WSR 23-21-056, § 246-221-240, filed 10/11/23, effective 11/11/23. Statutory Authority: RCW 70.98.050 and 70.98.110. WSR 16-13-054, § 246-221-240, filed 6/10/16, effective 7/11/16. Statutory Authority: RCW 70.98.050. WSR 14-01-077, § 246-221-240, filed 12/16/13, effective 1/16/14; WSR 94-01-073, § 246-221-240, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-221-240, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-240, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 87-01-031 (Order 2450), § 402-24-180, filed 12/11/86; WSR 83-19-050 (Order 2026), § 402-24-180, filed 9/16/83. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-24-180, filed 12/8/80; Order 1095, § 402-24-180, filed 2/6/76; Order 708, § 402-24-180, filed 8/24/72; Order 1, § 402-24-180, filed 7/2/71; Order 1, § 402-24-180, filed 1/8/69; Rules (part), filed 10/26/66.]

PDF246-221-250

Notification of incidents.

(1) Immediate notification. Notwithstanding other requirements for notification, each licensee and registrant shall immediately (as soon as possible but no later than four hours after discovery of an incident) notify the State Department of Health, Office of Radiation Protection, P.O. Box 47827, Olympia, Washington 98504-7827, by telephone ( 206-682-5327) and confirming letter, facsimile, or email with a follow-up written report within 30 days of any incident involving any radiation source which may have caused or threatens to cause:

(a) An individual to receive:

(i) A total effective dose equivalent of 0.25 Sv (25 rem) or more;

(ii) A lens dose equivalent of 0.75 Sv (75 rem) or more; or

(iii) A shallow dose equivalent to the skin or extremities or a total organ dose equivalent of 2.5 Sv (250 rem) or more;

(b) The release of radioactive material, inside or outside of a restricted area, so that, had an individual been present for 24 hours, the individual could have received an intake five times the occupational ALI. This provision does not apply to locations where personnel are not normally stationed during routine operations, such as hot-cells or process enclosures; or

(c) The loss of ability to take immediate protective actions necessary to avoid exposure to sources of radiation or releases of radioactive material that could exceed regulatory limits. Events which could cause such a loss of ability include fires, explosions, toxic gas releases, etc.

(2) Twenty-four hour notification. Each licensee and registrant shall within 24 hours of discovery of the event, notify the State Department of Health, Office of Radiation Protection, P.O. Box 47827, Olympia, Washington 98504-7827, by telephone ( 206-682-5327) and confirming letter, facsimile, or email with a follow-up written report within 30 days of any incident involving any radiation source possessed which may have caused or threatens to cause:

(a) An individual to receive, in a period of 24 hours:

(i) A total effective dose equivalent exceeding 0.05 Sv (five rem);

(ii) A lens dose equivalent exceeding 0.15 Sv (15 rem); or

(iii) A shallow dose equivalent to the skin or extremities or a total organ dose equivalent exceeding 0.5 Sv (50 rem);

(b) The release of radioactive material, inside or outside of a restricted area, so that, had an individual been present for 24 hours, the individual could have received an intake in excess of one occupational ALI. This provision does not apply to locations where personnel are not normally stationed during routine operations, such as hot-cells or process enclosures;

(i) Requires access to the contaminated area, by workers or the general public, to be restricted for more than 24 hours by imposing additional radiological controls or by prohibiting entry into the area;

(ii) Involves a quantity of material greater than five times the lowest annual limit on intake specified in WAC 246-221-290; and

(iii) Has access to the area restricted for a reason other than to allow radionuclides with a half-life of less than 24 hours to decay prior to decontamination;

(d) Equipment failure or inability to function as designed when:

(i) The equipment is required by regulation or license condition to prevent releases exceeding regulatory limits, to prevent exposures to radiation and radioactive material exceeding regulatory limits or to mitigate the consequences of an accident;

(ii) The equipment is required to be available and operable at the time it becomes disabled or fails to function; and

(iii) No redundant equipment is available and operable to perform the required safety functions;

(e) An unplanned medical treatment at a medical facility of an individual with removable radioactive contamination on the individual's clothing or body; or

(f) An unplanned fire or explosion damaging any radioactive material or any device, container or equipment containing radioactive material when:

(i) The quantity of radioactive material involved is greater than five times the lowest annual limit on intake specified in WAC 246-221-290; and

(ii) The damage affects the integrity of the radioactive material or its container.

(3) For each occurrence requiring notification pursuant to this section, a prompt investigation of the situation shall be initiated by the licensee/registrant. A written report of the findings of the investigation shall be sent to the department within 30 days.

(4) The licensee or registrant shall prepare each report filed with the department under this section so that names of individuals who have received exposure to sources of radiation are stated in a separate and detachable portion of the report.

Any report filed with the department under this section shall contain the information described in WAC 246-221-260 (2) and (3).

(5) The provisions of this section do not apply to doses that result from planned special exposures, provided such doses are within the limits for planned special exposures and are reported pursuant to WAC 246-221-265.

(6) Telephone notifications that do not involve immediate or 24 hour notification should be made to the Tumwater office ( 360-236-3300).

(7) Telephone notification required under this section shall include, to the extent that the information is available at the time of notification:

(a) The caller's name and call-back telephone number;

(b) A description of the incident including date and time;

(d) The radionuclides, quantities, and chemical and physical forms of the radioactive materials involved; and

(e) Any personnel radiation exposure data available.

[Statutory Authority: RCW 70A.388.040 and 70A.388.110. WSR 23-21-056, § 246-221-250, filed 10/11/23, effective 11/11/23. Statutory Authority: RCW 70.98.050 and 70.98.110. WSR 16-13-054, § 246-221-250, filed 6/10/16, effective 7/11/16. Statutory Authority: RCW 70.98.050. WSR 14-01-077, § 246-221-250, filed 12/16/13, effective 1/16/14; WSR 01-05-110, § 246-221-250, filed 2/21/01, effective 3/24/01; WSR 98-13-037, § 246-221-250, filed 6/8/98, effective 7/9/98; WSR 95-01-108, § 246-221-250, filed 12/21/94, effective 1/21/95; WSR 94-01-073, § 246-221-250, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-221-250, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-250, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 87-01-031 (Order 2450), § 402-24-190, filed 12/11/86; WSR 83-19-050 (Order 2026), § 402-24-190, filed 9/16/83. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-24-190, filed 12/8/80; Order 1095, § 402-24-190, filed 2/6/76; Order 708, § 402-24-190, filed 8/24/72; Order 1, § 402-24-190, filed 7/2/71; Order 1, § 402-24-190, filed 1/8/69; Rules (part), filed 10/26/66.]

PDF246-221-260

Reports of overexposures and excessive levels and concentrations.

(1) In addition to any notification required by WAC 246-221-250, each licensee or registrant shall submit a written report to the department within 30 days after learning of any of the following occurrences:

(a) Incidents for which notification is required by WAC 246-221-250; or

(b) Doses in excess of any of the following:

(i) The occupational dose limits for adults in WAC 246-221-010; or

(ii) The occupational dose limits for a minor in WAC 246-221-050; or

(iii) The limits for an embryo/fetus of a declared pregnant woman in WAC 246-221-055; or

(iv) The limits for an individual member of the public in WAC 246-221-060; or

(v) Any applicable limit in the license; or

(vi) The ALARA constraints for air emissions established under WAC 246-221-005; or

(i) A restricted area in excess of applicable limits in the license; or

(ii) An unrestricted area in excess of 10 times the applicable limit set forth in this chapter or in the license or registration, whether or not involving exposure of any individual in excess of the limits in WAC 246-221-060; or

(d) For source materials milling licensees and nuclear power plants subject to the provisions of United States Environmental Protection Agency's generally applicable environmental radiation standards in 40 C.F.R. 190, levels of radiation or releases of radioactive material in excess of those standards, or of license conditions related to those standards.

(2) Each report required by subsection (1) of this section shall describe:

(a) The incident and its exact location, time and date;

(b) The extent of exposure of individuals to radiation or to radioactive material, including estimates of each individual's dose as required by subsection (3) of this section;

(c) Levels of radiation and concentrations of radioactive material involved, including the radionuclides, quantities, and chemical and physical form;

(d) The cause or probable cause of the exposure, levels of radiation or concentrations;

(e) The manufacturer and model number (if applicable) of any equipment that failed or malfunctioned;

(f) The results of any evaluations or assessments; and

(g) Corrective steps taken or planned to assure against a recurrence, including the schedule for achieving conformance with applicable limits, ALARA constraints, generally applicable environmental standards, and associated license conditions.

(3) Each report filed with the department pursuant to this section shall include for each individual exposed the name, Social Security number, and date of birth, and an estimate of the individual's dose. With respect to the limit for the embryo/fetus in WAC 246-221-055, the identifiers should be those of the declared pregnant woman. The report shall be prepared so that this information is stated in a separate and detachable part of the report.

(4) Individuals shall be notified of reports in accordance with the requirements of WAC 246-222-040.

[Statutory Authority: RCW 70A.388.040 and 70A.388.110. WSR 23-21-056, § 246-221-260, filed 10/11/23, effective 11/11/23. Statutory Authority: RCW 70.98.050. WSR 99-15-105, § 246-221-260, filed 7/21/99, effective 8/21/99; WSR 95-01-108, § 246-221-260, filed 12/21/94, effective 1/21/95; WSR 94-01-073, § 246-221-260, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-221-260, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-260, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-24-200, filed 12/8/80; Order 1095, § 402-24-200, filed 2/6/76; Order 708, § 402-24-200, filed 8/24/72; Order 1, § 402-24-200, filed 7/2/71; Order 1, § 402-24-200, filed 1/8/69; Rules (part), filed 10/26/66.]

PDF246-221-265

Special reports to the department—Planned special exposures and leaking sources.

(1) The licensee or registrant shall submit a written report to the department within 30 days following any planned special exposure conducted in accordance with WAC 246-221-030. The written report shall:

(a) Inform the department that a planned special exposure was conducted;

(b) Indicate the date the planned special exposure occurred; and

(2) The licensee shall file a written report with the department within five days after learning that a sealed source is leaking or contaminated. The report shall describe:

(a) The source;

(b) The source holder;

(d) The test results; and

(e) The corrective action taken.

[Statutory Authority: RCW 70A.388.040 and 70A.388.110. WSR 23-21-056, § 246-221-265, filed 10/11/23, effective 11/11/23. Statutory Authority: RCW 70.98.050. WSR 99-05-013, § 246-221-265, filed 2/5/99, effective 3/8/99; WSR 94-01-073, § 246-221-265, filed 12/9/93, effective 1/9/94.]

PDF246-221-270

Vacating premises and release of equipment.

(1) Each specific licensee shall notify the department in writing of intent to vacate, at least 30 days before vacating or relinquishing possession or control of premises which may have been contaminated with radioactive material as a result of licensed activities.

(2) Each licensee shall permanently decontaminate the premise, before vacating any premise or transferring the premise, in accordance with the standards specified in chapter 246-246 WAC. A survey by the licensee shall be made after the decontamination and the department and the landlord or subsequent tenant or transferee shall be provided with a copy of the survey no later than the date of vacating or relinquishing possession or control of the premise.

(3) No machinery, instruments, laboratory equipment or any other property used in contact with, or close proximity to radioactive material at a licensed premise shall be assigned, sold, leased, or transferred to an unlicensed person unless the property has been decontaminated and meets the standards specified in WAC 246-232-140. A survey shall be made after the decontamination and the department and subsequent owner or transferee shall be provided with a copy of the survey report.

[Statutory Authority: RCW 70A.388.040 and 70A.388.110. WSR 23-21-056, § 246-221-270, filed 10/11/23, effective 11/11/23. Statutory Authority: RCW 70.98.050. WSR 00-07-085, § 246-221-270, filed 3/15/00, effective 4/15/00; WSR 94-01-073, § 246-221-270, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-270, filed 12/27/90, effective 1/31/91; Order 1095, § 402-24-210, filed 2/6/76; Order 1, § 402-24-210, filed 1/8/69; Rules (part), filed 10/26/66.]

PDF246-221-275

Notification of changes in a facility.

Each licensee or registrant shall notify the department of changes in any room or area in a facility where a source of radiation is used. Changes of interest to the department include, but are not limited to, new or replacement equipment containing or emitting radiation, increased occupancy, repair or replacement of existing shielding, new shielding, alteration of the ventilation system, and changes in procedures done in the room or area.

[Statutory Authority: RCW 70.98.050. WSR 94-01-073, § 246-221-275, filed 12/9/93, effective 1/9/94.]

PDF246-221-280

Notifications and reports to individuals.

(1) Requirements for notification and reports to individuals of exposure to radiation or radioactive material are specified in WAC 246-222-040.

(2) When a licensee or registrant is required pursuant to WAC 246-221-260 to report to the department any exposure of an identified occupationally exposed individual, or an identified member of the public, or dosimetry device assigned to any individual to radiation from any source, the licensee or registrant shall also notify the individual. Such notice shall be transmitted at a time not later than the transmittal to the department, and shall comply with the provisions of WAC 246-222-040(1).

[Statutory Authority: RCW 70.98.050. WSR 99-05-012, § 246-221-280, filed 2/5/99, effective 3/8/99. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-221-280, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-221-280, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 87-01-031 (Order 2450), § 402-24-215, filed 12/11/86; Order 1095, § 402-24-215, filed 2/6/76.]

PDF246-221-285

Assigned protection factors for respiratorsa.

		Operating mode	Assigned Protection Factors
I.	Air-Purifying Respirators (Particulate b only) c:
	Filtering facepiece disposable d	Negative Pressure . . . .	(d)
	Facepiece, half e. . . .	Negative Pressure . . . .	10
	Facepiece, full . . . .	Negative Pressure . . . .	100
	Facepiece, half . . . .	Powered air-purifying respirators . . . .	50
	Facepiece, full . . . .	Powered air-purifying respirators . . . .	1000
	Helmet/hood . . . .	Powered air-purifying respirators . . . .	1000
	Facepiece, loose-fitting . . . .	Powered air-purifying respirators . . . .	25
II.	Atmosphere-Supplying Respirators (Particulate, gases and vaporsf):
	1. Air-line respirator:
	Facepiece, half . . . .	Demand	10
	Facepiece, half . . . .	Continuous Flow . . . .	50
	Facepiece, half . . . .	Pressure Demand . . . .	50
	Facepiece, full . . . .	Demand . . . .	100
	Facepiece, full . . . .	Continuous Flow . . . .	1000
	Facepiece, full . . . .	Pressure Demand . . . .	1000
	Helmet/hood . . . .	Continuous Flow . . . .	1000
	Facepiece, loose-fitting . . . .	Continuous Flow . . . .	25
	Suit . . . .	Continuous Flow . . . .	(g)
	2. Self-contained breathing apparatus (SCBA):
	Facepiece, full . . . .	Demand . . . .	h100
	Facepiece, full . . . .	Pressure Demand . . . .	i10,000
	Facepiece, full . . . .	Demand, Recirculating . . . .	h100
	Facepiece, full . . . .	Positive Pressure Recirculating . . . .	i10,000
III.	Combination Respirators:
	Any combination of air-purifying and atmosphere-supplying respirators.	Assigned protection factor for type and mode of operation as listed above.

a	These assigned protection factors apply only in a respiratory protection program that meets the requirements of this chapter. They are applicable only to airborne radiological hazards and may not be appropriate to circumstances when chemical or other respiratory hazards exist instead of, or in addition to, radioactive hazards. Selection and use of respirators for these circumstances must also comply with Department of Labor regulations.
	Radioactive contaminants for which the concentration values in Table 1, Column 3 of WAC 246-221-290, Appendix A, are based on internal dose due to inhalation may, in addition, present external exposure hazards at higher concentrations. Under these circumstances, limitations on occupancy may have to be governed by external dose limits.
b	Air-purifying respirators with APF <100 must be equipped with particulate filters that are at least 95 percent efficient. Air-purifying respirators with APF = 100 must be equipped with particulate filters that are at least 99 percent efficient. Air-purifying respirators with APFs ˃100 must be equipped with particulate filters that are at least 99.97 percent efficient.
c	The licensee may apply to the department for the use of an APF greater than one for sorbent cartridges as protection against airborne radioactive gases and vapors (e.g., radioiodine).
d	Licensees may permit individuals to use this type of respirator who have not been medically screened or fit tested on the device provided that no credit be taken for their use in estimating intake or dose. It is also recognized that it is difficult to perform an effective positive or negative pressure preuse user seal check on this type of device. All other respiratory protection program requirements listed in WAC 246-221-117 apply. An assigned protection factor has not been assigned for these devices. However, an APF equal to 10 may be used if the licensee can demonstrate a fit factor of at least 100 by use of a validated or evaluated, qualitative or quantitative fit test.
e	Under-chin type only. No distinction is made in this section between elastomeric half-masks with replaceable cartridges and those designed with the filter medium as an integral part of the facepiece (e.g., disposable or reusable disposable). Both types are acceptable so long as the seal area of the latter contains some substantial type of seal-enhancing material such as rubber or plastic, the two or more suspension straps are adjustable, the filter medium is at least 95 percent efficient and all other requirements of this part are met.
f	The assigned protection factors for gases and vapors are not applicable to radioactive contaminants that present an absorption or submersion hazard. For tritium oxide vapor, approximately 1/3 of the intake occurs by absorption through the skin so that an overall protection factor of three is appropriate when atmosphere-supplying respirators are used to protect against tritium oxide. Exposure to radioactive noble gases is not considered a significant respiratory hazard, and protective actions for these contaminants should be based on external (submersion) dose considerations.
g	No NIOSH approval schedule is currently available for atmosphere-supplying suits. This equipment may be used in an acceptable respiratory protection program as long as all the other minimum program requirements, with the exception of fit testing, are met (i.e., WAC 246-221-117).
h	The licensee should implement institutional controls to assure that these devices are not used in areas immediately dangerous to life or health (IDLH).
i	This type of respirator may be used as an emergency device in unknown concentrations for protection against inhalation hazards. External radiation hazards and other limitations to permitted exposure such as skin absorption shall be taken into account in these circumstances. This device may not be used by any individual who experiences perceptible outward leakage of breathing gas while wearing the device.

[Statutory Authority: RCW 70A.388.040 and 70A.388.110. WSR 23-21-056, § 246-221-285, filed 10/11/23, effective 11/11/23. Statutory Authority: RCW 70.98.050. WSR 01-05-110, § 246-221-285, filed 2/21/01, effective 3/24/01; WSR 94-01-073, § 246-221-285, filed 12/9/93, effective 1/9/94.]

PDF246-221-290

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 one 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 10 days, for W from 10 to 100 days, and for Y greater than 100 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 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 (five 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 (five 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 one - (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 300. The factor of 300 includes the following components: A factor of 50 to relate the 0.05 Sv (five rem) annual occupational dose limit to the one 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 219. The factor of 219 is composed of a factor of 50, as described above, and a factor of 4.38 relating occupational exposure for 2,000 hours per year to full-time exposure (8,760 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 50 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 106 (ml). The factor of 7.3 x 106 (ml) is composed of a factor of 7.3 x 105 (ml), the annual water intake by Reference Man, and a factor of 10, 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 five mSv (0.5 rem).

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

			Table 1 Occupational Values			Table II Effluent Concentration		Table III Releases to Sewers
			Col. 1	Col. 2	Col. 3	Col. 1	Col. 2	Monthly Average Concen- tration
			Oral Ingestion	Inhalation				Monthly Average Concen- tration
Atomic No.	Radionuclide	Class	ALI µCi	ALI µCi	DAC µCi/ml	Air µCi/ml	Water µCi/ml	µCi/ml
1	Hydrogen-3	Water, DAC includes skin absorption	8E+4	8E+4	2E-5	1E-7	1E-3	1E-2
	Gas (HT or T2) Submersion1: Use above values as HT and T2 oxidize in air and in the body to HTO.
4	Beryllium-7	W, all compounds except those given for Y	4E+4	2E+4	9E-6	3E-8	6E-4	6E-3
		Y, oxides, halides, and nitrates	-	2E+4	8E-6	3E-8	-	-
4	Beryllium-10	W, see 7Be	1E+3	2E+2	6E-8	2E-10	-	-
			LLI wall (1E+3)	-	-	-	2E-5	2E-4
		Y, see 7Be	-	1E+1	6E-9	2E-11	-	-
6	Carbon-112	Monoxide	-	1E+6	5E-4	2E-6	-	-
		Dioxide	-	6E+5	3E-4	9E-7	-	-
		Compounds	4E+5	4E+5	2E-4	6E-7	6E-3	6E-2
6	Carbon-14	Monoxide	-	2E+6	7E-4	2E-6	-	-
		Dioxide	-	2E+5	9E-5	3E-7	-	-
		Compounds	2E+3	2E+3	1E-6	3E-9	3E-5	3E-4
7	Nitrogen-132	Submersion1	-	-	4E-6	2E-8	-	-
8	Oxygen-152	Submersion1	-	-	4E-6	2E-8	-	-
9	Fluorine-182	D, fluorides of H, Li, Na, K, Rb, Cs, and Fr	5E+4	7E+4	3E-5	1E-7	-	-
			St wall (5E+4)	-	-	-	7E-4	7E-3
		W, fluorides of Be, Mg, Ca, Sr, Ba, Ra, Al, Ga, In, Tl, As, Sb, Bi, Fe, Ru, Os, Co, Ni, Pd, Pt, Cu, Ag, Au, Zn, Cd, Hg, Sc, Y, Ti, Zr, V, Nb, Ta, Mn, Tc, and Re Y, lanthanum fluoride	- -	9E+4 8E+4	4E-5 3E-5	1E-7 1E-7	- -	- -
11	Sodium-22	D, all compounds	4E+2	6E+2	3E-7	9E-10	6E-6	6E-5
11	Sodium-24	D, all compounds	4E+3	5E+3	2E-6	7E-9	5E-5	5E-4
12	Magnesium-28	D, all compounds except those given for W	7E+2	2E+3	7E-7	2E-9	9E-6	9E-5
		W, oxides, hydroxides, carbides, halides, and nitrates	-	1E+3	5E-7	2E-9	-	-
13	Aluminum-26	D, all compounds except those given for W	4E+2	6E+1	3E-8	9E-11	6E-6	6E-5
		W, oxides, hydroxides, carbides, halides, and nitrates	-	9E+1	4E-8	1E-10	-	-
14	Silicon-31	D, all compounds except those given for W and Y	9E+3	3E+4	1E-5	4E-8	1E-4	1E-3
		W, oxides, hydroxides, carbides, and nitrates Y, aluminosilicate glass	- -	3E+4 3E+4	1E-5 1E-5	5E-8 4E-8	- -	- -
14	Silicon-32	D, see 31Si	2E+3	2E+2	1E-7	3E-10	-	-
			LLI wall (3E+3)	-	-	-	4E-5	4E-4
		W, see 31Si	-	1E+2	5E-8	2E-10	-	-
		Y, see 31Si	-	5E+0	2E-9	7E-12	-	-
15	Phosphorus-32	D, all compounds except phosphates given for W	6E+2	9E+2	4E-7	1E-9	9E-6	9E-5
		W, phosphates of Zn2+, S3+, Mg2+, Fe3+, Bi3+, and lanthanides	-	4E+2	2E-7	5E-10	-	-
15	Phosphorus-33	D, see 32P	6E+3	8E+3	4E-6	1E-8	8E-5	8E-4
		W, see 32P	-	3E+3	1E-6	4E-9	-	-
16	Sulfur-35	Vapor	-	1E+4	6E-6	2E-8	-	-
		D, sulfides and sulfates except those given for W	1E+4	2E+4	7E-6	2E-8	-	-
			LLI wall (8E+3)	-	-	-	1E-4	1E-3
		W, elemental sulfur, sulfides of Sr, Ba, Ge, Sn, Pb, As, Sb, Bi, Cu, Ag, Au, Zn, Cd, Hg, W, and Mo. Sulfates of Ca, Sr, Ba, Ra, As, Sb, and Bi	6E+3 -	2E+3	9E-7	3E-9	-	-
17	Chlorine-36	D, chlorides of H, Li, Na, K, Rb, Cs, and Fr	2E+3	2E+3	1E-6	3E-9	2E-5	2E-4
		W, chlorides of lantha-nides, Be, Mg, Ca, Sr, Ba, Ra, Al, Ga, In, Tl, Ge, Sn, Pb, As, Sb, Bi, Fe, Ru, Os, Co, Rh, Ir, Ni, Pd, Pt, Cu, Ag, Au, Zn, Cd, Hg, Sc, Y, Ti, Zr, Hf, V, Nb, Ta, Cr, Mo, W, Mn, Tc, and Re	-	2E+2	1E-7	3E-10	-	-
17	Chlorine-382	D, see 36Cl	2E+4	4E+4	2E-5	6E-8	-	-
			St wall (3E+4)	-	-	-	3E-4	3E-3
		W, see 36Cl	-	5E+4	2E-5	6E-8	-	-
17	Chlorine-392	D, see 36Cl	2E+4	5E+4	2E-5	7E-8	-	-
			St wall (4E+4)	-	-	-	5E-4	5E-3
		W, see 36Cl	-	6E+4	2E-5	8E-8	-	-
18	Argon-37	Submersion1	-	-	1E+0	6E-3	-	-
18	Argon-39	Submersion1	-	-	2E-4	8E-7	-	-
18	Argon-41	Submersion1	-	-	3E-6	1E-8	-	-
19	Potassium-40	D, all compounds	3E+2	4E+2	2E-7	6E-10	4E-6	4E-5
19	Potassium-42	D, all compounds	5E+3	5E+3	2E-6	7E-9	6E-5	6E-4
19	Potassium-43	D, all compounds	6E+3	9E+3	4E-6	1E-8	9E-5	9E-4
19	Potassium-442	D, all compounds	2E+4	7E+4	3E-5	9E-8	-	-
			St wall (4E+4)	-	-	-	5E-4	5E-3
19	Potassium-452	D, all compounds	3E+4	1E+5	5E-5	2E-7	-	-
			St wall (5E+4)	-	-	-	7E-4	7E-3
20	Calcium-41	W, all compounds	3E+3	4E+3	2E-6	-	-	-
			Bone surf (4E+3)	Bone surf (4E+3)	-	5E-9	6E-5	6E-4
20	Calcium-45	W, all compounds	2E+3	8E+2	4E-7	1E-9	2E-5	2E-4
20	Calcium-47	W, all compounds	8E+2	9E+2	4E-7	1E-9	1E-5	1E-4
21	Scandium-43	Y, all compounds	7E+3	2E+4	9E-6	3E-8	1E-4	1E-3
21	Scandium-44m	Y, all compounds	5E+2	7E+2	3E-7	1E-9	7E-6	7E-5
21	Scandium-44	Y, all compounds	4E+3	1E+4	5E-6	2E-8	5E-5	5E-4
21	Scandium-46	Y, all compounds	9E+2	2E+2	1E-7	3E-10	1E-5	1E-4
21	Scandium-47	Y, all compounds	2E+3	3E+3	1E-6	4E-9	-	-
			LLI wall (3E+3)	-	-	-	4E-5	4E-4
21	Scandium-48	Y, all compounds	8E+2	1E+3	6E-7	2E-9	1E-5	1E-4
21	Scandium-492	Y, all compounds	2E+4	5E+4	2E-5	8E-8	3E-4	3E-3
22	Titanium-44	D, all compounds except those given for W and Y	3E+2	1E+1	5E-9	2E-11	4E-6	4E-5
		W, oxides, hydroxides, carbides, halides, and nitrates	-	3E+1	1E-8	4E-11	-	-
		Y, SrTi0	-	6E+0	2E-9	8E-12	-	-
22	Titanium-45	D, see 44Ti	9E+3	3E+4	1E-5	3E-8	1E-4	1E-3
		W, see 44Ti	-	4E+4	1E-5	5E-8	-	-
		Y, see 44Ti	-	3E+4	1E-5	4E-8	-	-
23	Vanadium-472	D, all compounds except those given for W	3E+4	8E+4	3E-5	1E-7	-	-
			St wall (3E+4)	-	-	-	4E-4	4E-3
		W, oxides, hydroxides, carbides, and halides	-	1E+5	4E-5	1E-7	-	-
23	Vanadium-48	D, see 47V	6E+2	1E+3	5E-7	2E-9	9E-6	9E-5
		W, see 47V	-	6E+2	3E-7	9E-10	-	-
23	Vanadium-49	D, see 47V	7E+4	3E+4	1E-5	-	-	-
			LLI wall (9E+4)	Bone surf (3E+4)	-	5E-8	1E-3	1E-2
		W, see 47V	-	2E+4	8E-6	2E-8	-	-
24	Chromium-48	D, all compounds except those given for W and Y	6E+3	1E+4	5E-6	2E-8	8E-5	8E-4
		W, halides and nitrates	-	7E+3	3E-6	1E-8	-	-
		Y, oxides and hydroxides	-	7E+3	3E-6	1E-8	-	-
24	Chromium-492	D, see 48Cr	3E+4	8E+4	4E-5	1E-7	4E-4	4E-3
		W, see 48Cr	-	1E+5	4E-5	1E-7	-	-
		Y, see 48Cr	-	9E+4	4E-5	1E-7	-	-
24	Chromium-51	D, see 48Cr	4E+4	5E+4	2E-5	6E-8	5E-4	5E-3
		W, see 48Cr	-	2E+4	1E-5	3E-8	-	-
		Y, see 48Cr	-	2E+4	8E-6	3E-8	-	-
25	Manganese-512	D, all compounds except those given for W	2E+4	5E+4	2E-5	7E-8	3E-4	3E-3
		W, oxides, hydroxides, halides, and nitrates	-	6E+4	3E-5	8E-8	-	-
25	Manganese-52m2	D, see 51Mn	3E+4	9E+4	4E-5	1E-7	-	-
			St wall (4E+4)	-	-	-	5E-4	5E-3
		W, see 51Mn	-	1E+5	4E-5	1E-7	-	-
25	Manganese-52	D, see 51Mn	7E+2	1E+3	5E-7	2E-9	1E-5	1E-4
		W, see 51Mn	-	9E+2	4E-7	1E-9	-	-
25	Manganese-53	D, see 51Mn	5E+4	1E+4	5E-6	-	7E-4	7E-3
			-	Bone surf (2E+4)	-	3E-8	-	-
		W, see 51Mn	-	1E+4	5E-6	2E-8	-	-
25	Manganese-54	D, see 51Mn	2E+3	9E+2	4E-7	1E-9	3E-5	3E-4
		W, see 51Mn	-	8E+2	3E-7	1E-9	-	-
25	Manganese-56	D, see 51Mn	5E+3	2E+4	6E-6	2E-8	7E-5	7E-4
		W, see 51Mn	-	2E+4	9E-6	3E-8	-	-
26	Iron-52	D, all compounds except those given for W	9E+2	3E+3	1E-6	4E-9	1E-5	1E-4
		W, oxides, hydroxides, and halides	-	2E+3	1E-6	3E-9	-	-
26	Iron-55	D, see 52Fe	9E+3	2E+3	8E-7	3E-9	1E-4	1E-3
		W, see 52Fe	-	4E+3	2E-6	6E-9	-	-
26	Iron-59	D, see 52Fe	8E+2	3E+2	1E-7	5E-10	1E-5	1E-4
		W, see 52Fe	-	5E+2	2E-7	7E-10	-	-
26	Iron-60	D, see 52Fe	3E+1	6E+0	3E-9	9E-12	4E-7	4E-6
		W, see 52Fe	-	2E+1	8E-9	3E-11	-	-
27	Cobalt-55	W, all compounds except those given for Y	1E+3	3E+3	1E-6	4E-9	2E-5	2E-4
		Y, oxides, hydroxides, halides, and nitrates	-	3E+3	1E-6	4E-9	-	-
27	Cobalt-56	W, see 55Co	5E+2	3E+2	1E-7	4E-10	6E-6	6E-5
		Y, see 55Co	4E+2	2E+2	8E-8	3E-10	-	-
27	Cobalt-57	W, see 55Co	8E+3	3E+3	1E-6	4E-9	6E-5	6E-4
		Y, see 55Co	4E+3	7E+2	3E-7	9E-10	-	-
27	Cobalt-58m	W, see 55Co	6E+4	9E+4	4E-5	1E-7	8E-4	8E-3
		Y, see 55Co	-	6E+4	3E-5	9E-8	-	-
27	Cobalt-58	W, see 55Co	2E+3	1E+3	5E-7	2E-9	2E-5	2E-4
		Y, see 55Co	1E+3	7E+2	3E-7	1E-9	-	-
27	Cobalt-60m2	W, see 55Co	1E+6	4E+6	2E-3	6E-6	-	-
			St wall (1E+6)	-	-	-	2E-2	2E-1
		Y, see 55Co	-	3E+6	1E-3	4E-6	-	-
27	Cobalt-60	W, see 55Co	5E+2	2E+2	7E-8	2E-10	3E-6	3E-5
		Y, see 55Co	2E+2	3E+1	1E-8	5E-11	-	-
27	Cobalt-612	W, see 55Co	2E+4	6E+4	3E-5	9E-8	3E-4	3E-3
		Y, see 55Co	2E+4	6E+4	2E-5	8E-8	-	-
27	Cobalt-62m2	W, see 55Co	4E+4	2E+5	7E-5	2E-7	-	-
			St wall (5E+4)	-	-	-	7E-4	7E-3
		Y, see 55Co	-	2E+5	6E-5	2E-7	-	-
28	Nickel-56	D, all compounds except those given for W	1E+3	2E+3	8E-7	3E-9	2E-5	2E-4
		W, oxides, hydroxides, and carbides	-	1E+3	5E-7	2E-9	-	-
		Vapor	-	1E+3	5E-7	2E-9	-	-
28	Nickel-57	D, see 56Ni	2E+3	5E+3	2E-6	7E-9	2E-5	2E-4
		W, see 56Ni	-	3E+3	1E-6	4E-9	-	-
		Vapor	-	6E+3	3E-6	9E-9	-	-
28	Nickel-59	D, see 56Ni	2E+4	4E+3	2E-6	5E-9	3E-4	3E-3
		W, see 56Ni	-	7E+3	3E-6	1E-8	-	-
		Vapor	-	2E+3	8E-7	3E-9	-	-
28	Nickel-63	D, see 56Ni	9E+3	2E+3	7E-7	2E-9	1E-4	1E-3
		W, see 56Ni	-	3E+3	1E-6	4E-9	-	-
		Vapor	-	8E+2	3E-7	1E-9	-	-
28	Nickel-65	D, see 56Ni	8E+3	2E+4	1E-5	3E-8	1E-4	1E-3
		W, see 56Ni	-	3E+4	1E-5	4E-8	-	-
		Vapor	-	2E+4	7E-6	2E-8	-	-
28	Nickel-66	D, see 56Ni	4E+2	2E+3	7E-7	2E-9	-	-
			LLI wall (5E+2)	-	-	-	6E-6	6E-5
		W, see 56Ni	-	6E+2	3E-7	9E-10	-	-
		Vapor	-	3E+3	1E-6	4E-9	-	-
29	Copper-602	D, all compounds except those given for W and Y	3E+4	9E+4	4E-5	1E-7	-	-
			St wall (3E+4)	-	-	-	4E-4	4E-3
		W, sulfides, halides, and nitrates	-	1E+5	5E-5	2E-7	-	-
		Y, oxides and hydroxides	-	1E+5	4E-5	1E-7	-	-
29	Copper-61	D, see 60Cu	1E+4	3E+4	1E-5	4E-8	2E-4	2E-3
		W, see 60Cu	-	4E+4	2E-5	6E-8	-	-
		Y, see 60Cu	-	4E+4	1E-5	5E-8	-	-
29	Copper-64	D, see 60Cu	1E+4	3E+4	1E-5	4E-8	2E-4	2E-3
		W, see 60Cu	-	2E+4	1E-5	3E-8	-	-
		Y, see 60Cu	-	2E+4	9E-6	3E-8	-	-
29	Copper-67	D, see 60Cu	5E+3	8E+3	3E-6	1E-8	6E-5	6E-4
		W, see 60Cu	-	5E+3	2E-6	7E-9	-	-
		Y, see 60Cu	-	5E+3	2E-6	6E-9	-	-
30	Zinc-62	Y, all compounds	1E+3	3E+3	1E-6	4E-9	2E-5	2E-4
30	Zinc-632	Y, all compounds	2E+4	7E+4	3E-5	9E-8	-	-
			St wall (3E+4)	-	-	-	3E-4	3E-3
30	Zinc-65	Y, all compounds	4E+2	3E+2	1E-7	4E-10	5E-6	5E-5
30	Zinc-69m	Y, all compounds	4E+3	7E+3	3E-6	1E-8	6E-5	6E-4
30	Zinc-692	Y, all compounds	6E+4	1E+5	6E-5	2E-7	8E-4	8E-3
30	Zinc-71m	Y, all compounds	6E+3	2E+4	7E-6	2E-8	8E-5	8E-4
30	Zinc-72	Y, all compounds	1E+3	1E+3	5E-7	2E-9	1E-5	1E-4
31	Gallium-652	D, all compounds except those given for W	5E+4	2E+5	7E-5	2E-7	-	-
			St wall (6E+4)	-	-	-	9E-4	9E-3
		W, oxides, hydroxides, carbides, halides, and nitrates	-	2E+5	8E-5	3E-7	-	-
31	Gallium-66	D, see 65Ga	1E+3	4E+3	1E-6	5E-9	1E-5	1E-4
		W, see 65Ga	-	3E+3	1E-6	4E-9	-	-
31	Gallium-67	D, see 65Ga	7E+3	1E+4	6E-6	2E-8	1E-4	1E-3
		W, see 65Ga	-	1E+4	4E-6	1E-8	-	-
31	Gallium-682	D, see 65Ga	2E+4	4E+4	2E-5	6E-8	2E-4	2E-3
		W, see 65Ga	-	5E+4	2E-5	7E-8	-	-
31	Gallium-702	D, see 65Ga	5E+4	2E+5	7E-5	2E-7	-	-
			St wall (7E+4)	-	-	-	1E-3	1E-2
		W, see 65Ga	-	2E+5	8E-5	3E-7	-	-
31	Gallium-72	D, see 65Ga	1E+3	4E+3	1E-6	5E-9	2E-5	2E-4
		W, see 65Ga	-	3E+3	1E-6	4E-9	-	-
31	Gallium-73	D, see 65Ga	5E+3	2E+4	6E-6	2E-8	7E-5	7E-4
		W, see 65Ga	-	2E+4	6E-6	2E-8	-	-
32	Germanium-66	D, all compounds except those given for W	2E+4	3E+4	1E-5	4E-8	3E-4	3E-3
		W, oxides, sulfides, and halides	-	2E+4	8E-6	3E-8	-	-
32	Germanium-672	D, see 66Ge	3E+4	9E+4	4E-5	1E-7	-	-
			St wall (4E+4)	-	-	-	6E-4	6E-3
		W, see 66Ge	-	1E+5	4E-5	1E-7	-	-
32	Germanium-68	D, see 66Ge	5E+3	4E+3	2E-6	5E-9	6E-5	6E-4
		W, see 66Ge	-	1E+2	4E-8	1E-10	-	-
32	Germanium-69	D, see 66Ge	1E+4	2E+4	6E-6	2E-8	2E-4	2E-3
		W, see 66Ge	-	8E+3	3E-6	1E-8	-	-
32	Germanium-71	D, see 66Ge	5E+5	4E+5	2E-4	6E-7	7E-3	7E-2
		W, see 66Ge	-	4E+4	2E-5	6E-8	-	-
32	Germanium-752	D, see 66Ge	4E+4	8E+4	3E-5	1E-7	-	-
			St wall (7E+4)	-	-	-	9E-4	9E-3
		W, see 66Ge	-	8E+4	4E-5	1E-7	-	-
32	Germanium-77	D, see 66Ge	9E+3	1E+4	4E-6	1E-8	1E-4	1E-3
		W, see 66Ge	-	6E+3	2E-6	8E-9	-	-
32	Germanium-782	D, see 66Ge	2E+4	2E+4	9E-6	3E-8	-	-
			St wall (2E+4)	-	-	-	3E-4	3E-3
		W, see 66Ge	-	2E+4	9E-6	3E-8	-	-
33	Arsenic-692	W, all compounds	3E+4	1E+5	5E-5	2E-7	-	-
			St wall (4E+4)	-	-	-	6E-4	6E-3
33	Arsenic-702	W, all compounds	1E+4	5E+4	2E-5	7E-8	2E-4	2E-3
33	Arsenic-71	W, all compounds	4E+3	5E+3	2E-6	6E-9	5E-5	5E-4
33	Arsenic-72	W, all compounds	9E+2	1E+3	6E-7	2E-9	1E-5	1E-4
33	Arsenic-73	W, all compounds	8E+3	2E+3	7E-7	2E-9	1E-4	1E-3
33	Arsenic-74	W, all compounds	1E+3	8E+2	3E-7	1E-9	2E-5	2E-4
33	Arsenic-76	W, all compounds	1E+3	1E+3	6E-7	2E-9	1E-5	1E-4
33	Arsenic-77	W, all compounds	4E+3	5E+3	2E-6	7E-9	-	-
			LLI wall (5E+3)	-	-	-	6E-5	6E-4
33	Arsenic-782	W, all compounds	8E+3	2E+4	9E-6	3E-8	1E-4	1E-3
34	Selenium-702	D, all compounds except those given for W	2E+4	4E+4	2E-5	5E-8	1E-4	1E-3
		W, oxides, hydroxides, carbides, and elemental Se	1E+4	4E+4	2E-5	6E-8	-	-
34	Selenium-73m2	D, see 70Se	6E+4	2E+5	6E-5	2E-7	4E-4	4E-3
		W, see 70Se	3E+4	1E+5	6E-5	2E-7	-	-
34	Selenium-73	D, see 70Se	3E+3	1E+4	5E-6	2E-8	4E-5	4E-4
		W, see 70Se	-	2E+4	7E-6	2E-8	-	-
34	Selenium-75	D, see 70Se	5E+2	7E+2	3E-7	1E-9	7E-6	7E-5
		W, see 70Se	-	6E+2	3E-7	8E-10	-	-
34	Selenium-79	D, see 70Se	6E+2	8E+2	3E-7	1E-9	8E-6	8E-5
		W, see 70Se	-	6E+2	2E-7	8E-10	-	-
34	Selenium-81m2	D, see 70Se	4E+4	7E+4	3E-5	9E-8	3E-4	3E-3
		W, see 70Se	2E+4	7E+4	3E-5	1E-7	-	-
34	Selenium-812	D, see 70Se	6E+4	2E+5	9E-5	3E-7	-	-
			St wall (8E+4)	-	-	-	1E-3	1E-2
		W, see 70Se	-	2E+5	1E-4	3E-7	-	-
34	Selenium-832	D, see 70Se	4E+4	1E+5	5E-5	2E-7	4E-4	4E-3
		W, see 70Se	3E+4	1E+5	5E-5	2E-7	-	-
35	Bromine-74m2	D, bromides of H, Li, Na, K, Rb, Cs, and Fr	1E+4	4E+4	2E-5	5E-8	-	-
			St wall (2E+4)	-	-	-	3E-4	3E-3
		W, bromides of lantha-nides, Be, Mg, Ca, Sr, Ba, Ra, Al, Ga, In, Tl, Ge, Sn, Pb, As, Sb, Bi, Fe, Ru, Os, Co, Rh, Ir, Ni, Pd, Pt, Cu, Ag, Au, Zn, Cd, Hg, Sc, Y, Ti, Zr, Hf, V, Nb, Ta, Mn, Tc, and Re	-	4E+4	2E-5	6E-8	-	-
35	Bromine-742	D, see 74mBr	2E+4	7E+4	3E-5	1E-7	-	-
			St wall (4E+4)	-	-	-	5E-45E-3	-
		W, see 74mBr	-	8E+4	4E-5	1E-7	-	-
35	Bromine-752	D, see 74mBr	3E+4	5E+4	2E-5	7E-8	-	-
			St wall (4E+4)	-	-	-	5E-4	5E-3
		W, see 74mBr	-	5E+4	2E-5	7E-8	-	-
35	Bromine-76	D, see 74mBr	4E+3	5E+3	2E-6	7E-9	5E-5	5E-4
		W, see 74mBr	-	4E+3	2E-6	6E-9	-	-
35	Bromine-77	D, see 74mBr	2E+4	2E+4	1E-5	3E-8	2E-4	2E-3
		W, see 74mBr	-	2E+4	8E-6	3E-8	-	-
35	Bromine-80m	D, see 74mBr	2E+4	2E+4	7E-6	2E-8	3E-4	3E-3
		W, see 74mBr	-	1E+4	6E-6	2E-8	-	-
35	Bromine-802	D, see 74mBr	5E+4	2E+5	8E-5	3E-7	-	-
			St wall (9E+4)	-	-	-	1E-3	1E-2
		W, see 74mBr	-	2E+5	9E-5	3E-7	-	-
35	Bromine-82	D, see 74mBr	3E+3	4E+3	2E-6	6E-9	4E-5	4E-4
		W, see 74mBr	-	4E+3	2E-6	5E-9	-	-
35	Bromine-83	D, see 74mBr	5E+4	6E+4	3E-5	9E-8	-	-
			St wall (7E+4)	-	-	-	9E-4	9E-3
		W, see 74mBr	-	6E+4	3E-5	9E-8	-	-
35	Bromine-842	D, see 74mBr	2E+4	6E+4	2E-5	8E-8	-	-
			St wall (3E+4)	-	-	-	4E-4	4E-3
		W, see 74mBr	-	6E+4	3E-5	9E-8	-	-
36	Krypton-742	Submersion1	-	-	3E-6	1E-8	-	-
36	Krypton-76	Submersion1	-	-	9E-6	4E-8	-	-
36	Krypton-772	Submersion1	-	-	4E-6	2E-8	-	-
36	Krypton-79	Submersion1	-	-	2E-5	7E-8	-	-
36	Krypton-81	Submersion1	-	-	7E-4	3E-6	-	-
36	Krypton-83m2	Submersion1	-	-	1E-2	5E-5	-	-
36	Krypton-85m	Submersion1	-	-	2E-5	1E-7	-	-
36	Krypton-85	Submersion1	-	-	1E-4	7E-7	-	-
36	Krypton-872	Submersion1	-	-	5E-6	2E-8	-	-
36	Krypton-88	Submersion1	-	-	2E-6	9E-9	-	-
37	Rubidium-792	D, all compounds	4E+4	1E+5	5E-5	2E-7	-	-
			St wall (6E+4)	-	-	-	8E-4	8E-3
37	Rubidium-81m2	D, all compounds	2E+5	3E+5	1E-4	5E-7	-	-
			St wall (3E+5)	-	-	-	4E-3	4E-2
37	Rubidium-81	D, all compounds	4E+4	5E+4	2E-5	7E-8	5E-4	5E-3
37	Rubidium-82m	D, all compounds	1E+4	2E+4	7E-6	2E-8	2E-4	2E-3
37	Rubidium-83	D, all compounds	6E+2	1E+3	4E-7	1E-9	9E-6	9E-5
37	Rubidium-84	D, all compounds	5E+2	8E+2	3E-7	1E-9	7E-6	7E-5
37	Rubidium-86	D, all compounds	5E+2	8E+2	3E-7	1E-9	7E-6	7E-5
37	Rubidium-87	D, all compounds	1E+3	2E+3	6E-7	2E-9	1E-5	1E-4
37	Rubidium-882	D, all compounds	2E+4	6E+4	3E-5	9E-8	-	-
			St wall (3E+4)	-	-	-	4E-4	4E-3
37	Rubidium-892	D, all compounds	4E+4	1E+5	6E-5	2E-7	-	-
			St wall (6E+4)	-	-	-	9E-4	9E-3
38	Strontium-802	D, all soluble compound except SrTiO	4E+3	1E+4	5E-6	2E-8	6E-5	6E-4
		Y, all insoluble compounds and SrTi0	-	1E+4	5E-6	2E-8	-	-
38	Strontium-812	D, see 80Sr	3E+4	8E+4	3E-5	1E-7	3E-4	3E-3
		Y, see 80Sr	2E+4	8E+4	3E-5	1E-7	-	-
38	Strontium-82	D, see 80Sr	3E+2	4E+2	2E-7	6E-10	-	-
			LLI wall (2E+2)	-	-	-	3E-6	3E-5
		Y, see 80Sr	2E+2	9E+1	4E-8	1E-10	-	-
38	Strontium-83	D, see 80Sr	3E+3	7E+3	3E-6	1E-8	3E-5	3E-4
		Y, see 80Sr	2E+3	4E+3	1E-6	5E-9	-	-
38	Strontium-85m2	D, see 80Sr	2E+5	6E+5	3E-4	9E-7	3E-3	3E-2
		Y, see 80Sr	-	8E+5	4E-4	1E-6	-	-
38	Strontium-85	D, see 80Sr	3E+3	3E+3	1E-6	4E-9	4E-5	4E-4
		Y, see 80Sr	-	2E+3	6E-7	2E-9	-	-
38	Strontium-87m	D, see 80Sr	5E+4	1E+5	5E-5	2E-7	6E-4	6E-3
		Y, see 80Sr	4E+4	2E+5	6E-5	2E-7	-	-
38	Strontium-89	D, see 80Sr	6E+2	8E+2	4E-7	1E-9	-	-
			LLI wall (6E+2)	-	-	-	8E-6	8E-5
		Y, see 80Sr	5E+2	1E+2	6E-8	2E-10	-	-
38	Strontium-90	D, see 80Sr	3E+1	2E+1	8E-9	-	-	-
			Bone surf (4E+1)	Bone surf (2E+1)	-	3E-11	5E-7	5E-6
		Y, see 80Sr	-	4E+0	2E-9	6E-12	-	-
38	Strontium-91	D, see 80Sr	2E+3	6E+3	2E-6	8E-9	2E-5	2E-4
		Y, see 80Sr	-	4E+3	1E-6	5E-9	-	-
38	Strontium-92	D, see 80Sr	3E+3	9E+3	4E-6	1E-8	4E-5	4E-4
		Y, see 80Sr	-	7E+3	3E-6	9E-9	-	-
39	Yttrium-86m2	W, all compounds except those given for Y	2E+4	6E+4	2E-5	8E-8	3E-4	3E-3
		Y, oxides and hydroxides	-	5E+4	2E-5	8E-8	-	-
39	Yttrium-86	W, see 86mY	1E+3	3E+3	1E-6	5E-9	2E-5	2E-4
		Y, see 86mY	-	3E+3	1E-6	5E-9	-	-
39	Yttrium-87	W, see 86mY	2E+3	3E+3	1E-6	5E-9	3E-5	3E-4
		Y, see 86mY	-	3E+3	1E-6	5E-9	-	-
39	Yttrium-88	W, see 86mY	1E+3	3E+2	1E-7	3E-10	1E-5	1E-4
		Y, see 86mY	-	2E+2	1E-7	3E-10	-	-
39	Yttrium-90m	W, see 86mY	8E+3	1E+4	5E-6	2E-8	1E-4	1E-3
		Y, see 86mY	-	1E+4	5E-6	2E-8	-	-
39	Yttrium-90	W, see 86mY	4E+2	7E+2	3E-7	9E-10	-	-
			LLI wall (5E+2)	-	-	-	7E-6	7E-5
		Y, see 86mY	-	6E+2	3E-7	9E-10	-	-
39	Yttrium-91m2	W, see 86mY	1E+5	2E+5	1E-4	3E-7	2E-3	2E-2
		Y, see 86mY	-	2E+5	7E-5	2E-7	-	-
39	Yttrium-91	W, see 86mY	5E+2	2E+2	7E-8	2E-10	-	-
			LLI wall (6E+2)	-	-	-	8E-6	8E-5
		Y, see 86mY	-	1E+2	5E-8	2E-10	-	-
39	Yttrium-92	W, see 86mY	3E+3	9E+3	4E-6	1E-8	4E-5	4E-4
		Y, see 86mY	-	8E+3	3E-6	1E-8	-	-
39	Yttrium-93	W, see 86mY	1E+3	3E+3	1E-6	4E-9	2E-5	2E-4
		Y, see 86mY	-	2E+3	1E-6	3E-9	-	-
39	Yttrium-942	W, see 86mY	2E+4	8E+4	3E-5	1E-7	-	-
			St wall (3E+4)	-	-	-	4E-4	4E-3
		Y, see 86mY	-	8E+4	3E-5	1E-7	-	-
39	Yttrium-952	W, see 86mY	4E+4	2E+5	6E-5	2E-7	-	-
			St wall (5E+4)	-	-	-	7E-4	7E-3
		Y, see 86mY	-	1E+5	6E-5	2E-7	-	-
40	Zirconium-86	D, all compounds except those given for W and Y	1E+3	4E+3	2E-6	6E-9	2E-5	2E-4
		W, oxides, hydroxides, halides, and nitrates	-	3E+3	1E-6	4E-9	-	-
		Y, carbide	-	2E+3	1E-6	3E-9	-	-
40	Zirconium-88	D, see 86Zr	4E+3	2E+2	9E-8	3E-10	5E-5	5E-4
		W, see 86Zr	-	5E+2	2E-7	7E-10	-	-
		Y, see 86Zr	-	3E+2	1E-7	4E-10	-	-
40	Zirconium-89	D, see 86Zr	2E+3	4E+3	1E-6	5E-9	2E-5	2E-4
		W, see 86Zr	-	2E+3	1E-6	3E-9	-	-
		Y, see 86Zr	-	2E+3	1E-6	3E-9	-	-
40	Zirconium-93	D, see 86Zr	1E+3	6E+0	3E-9	-	-	-
			Bone surf (3E+3)	Bone surf (2E+1)	-	2E-11	4E-5	4E-4
		W, see 86Zr	-	2E+1	1E-8	-	-	-
			-	Bone surf (6E+1)	-	9E-11	-	-
		Y, see 86Zr	-	6E+1	2E-8	-	-	-
			-	Bone surf (7E+1)	-	9E-11	-	-
40	Zirconium-95	D, see 86Zr	1E+3	1E+2	5E-8	-	2E-5	2E-4
			-	Bone surf (3E+2)	-	4E-10	-	-
		W, see 86Zr	-	4E+2	2E-7	5E-10	-	-
		Y, see 86Zr	-	3E+2	1E-7	4E-10	-	-
40	Zirconium-97	D, see 86Zr	6E+2	2E+3	8E-7	3E-9	9E-6	9E-5
		W, see 86Zr	-	1E+3	6E-7	2E-9	-	-
		Y, see 86Zr	-	1E+3	5E-7	2E-9	-	-
41	Niobium-882	W, all compounds except those given for Y	5E+4	2E+5	9E-5	3E-7	-	-
			St wall (7E+4)	-	-	-	1E-3	1E-2
		Y, oxides and hydroxides	-	2E+5	9E-5	3E-7	-	-
41	Niobium-892 (66 min)	W, see 88Nb	1E+4	4E+4	2E-5	6E-8	1E-4	1E-3
		Y, see 88Nb	-	4E+4	2E-5	5E-8	-	-
41	Niobium-89 (122 min)	W, see 88Nb	5E+3	2E+4	8E-6	3E-8	7E-5	7E-4
		Y, see 88Nb	-	2E+4	6E-6	2E-8	-	-
41	Niobium-90	W, see 88Nb	1E+3	3E+3	1E-6	4E-9	1E-5	1E-4
		Y, see 88Nb	-	2E+3	1E-6	3E-9	-	-
41	Niobium-93m	W, see 88Nb	9E+3	2E+3	8E-7	3E-9	-	-
			LLI wall (1E+4)	-	-	-	2E-4	2E-3
		Y, see 88Nb	-	2E+2	7E-8	2E-10	-	-
41	Niobium-94	W, see 88Nb	9E+2	2E+2	8E-8	3E-10	1E-5	1E-4
		Y, see 88Nb	-	2E+1	6E-9	2E-11	-	-
41	Niobium-95m	W, see 88Nb	2E+3	3E+3	1E-6	4E-9	-	-
			LLI wall (2E+3)	-	-	-	3E-5	3E-4
		Y, see 88Nb	-	2E+3	9E-7	3E-9	-	-
41	Niobium-95	W, see 88Nb	2E+3	1E+3	5E-7	2E-9	3E-5	3E-4
		Y, see 88Nb	-	1E+3	5E-7	2E-9	-	-
41	Niobium-96	W, see 88Nb	1E+3	3E+3	1E-6	4E-9	2E-5	2E-4
		Y, see 88Nb	-	2E+3	1E-6	3E-9	-	-
41	Niobium-972	W, see 88Nb	2E+4	8E+4	3E-5	1E-7	3E-4	3E-3
		Y, see 88Nb	-	7E+4	3E-5	1E-7	-	-
41	Niobium-982	W, see 88Nb	1E+4	5E+4	2E-5	8E-8	2E-4	2E-3
		Y, see 88Nb	-	5E+4	2E-5	7E-8	-	-
42	Molybdenum-90	D, all compounds except those given for Y	4E+3	7E+3	3E-6	1E-8	3E-5	3E-4
		Y, oxides, hydroxides, and MoS	2E+3	5E+3	2E-6	6E-9	-	-
42	Molybdenum-93m	D, see 90Mo	9E+3	2E+4	7E-6	2E-8	6E-5	6E-4
		Y, see 90Mo	4E+3	1E+4	6E-6	2E-8	-	-
42	Molybdenum-93	D, see 90Mo	4E+3	5E+3	2E-6	8E-9	5E-5	5E-4
		Y, see 90Mo	2E+4	2E+2	8E-8	2E-10	-	-
42	Molybdenum-99	D, see 90Mo	2E+3	3E+3	1E-6	4E-9	-	-
			LLI wall (1E+3)	-	-	-	2E-5	2E-4
		Y, see 90Mo	1E+3	1E+3	6E-7	2E-9	-	-
42	Molybdenum-1012	D, see 90Mo	4E+4	1E+5	6E-5	2E-7	-	-
			St wall (5E+4)	-	-	-	7E-4	7E-3
		Y, see 90Mo	-	1E+5	6E-5	2E-7	-	-
43	Technetium-93m2	D, all compounds except those given for W	7E+4	2E+5	6E-5	2E-7	1E-3	1E-2
		W, oxides, hydroxides, halides, and nitrates	-	3E+5	1E-4	4E-7	-	-
43	Technetium-93	D, see 93mTc	3E+4	7E+4	3E-5	1E-7	4E-4	4E-3
		W, see 93mTc	-	1E+5	4E-5	1E-7	-	-
43	Technetium-94m2	D, see 93mTc	2E+4	4E+4	2E-5	6E-8	3E-4	3E-3
		W, see 93mTc	-	6E+4	2E-5	8E-8	-	-
43	Technetium-94	D, see 93mTc	9E+3	2E+4	8E-6	3E-8	1E-4	1E-3
		W, see 93mTc	-	2E+4	1E-5	3E-8	-	-
43	Technetium-95m	D, see 93mTc	4E+3	5E+3	2E-6	8E-9	5E-5	5E-4
		W, see 93mTc	-	2E+3	8E-7	3E-9	-	-
43	Technetium-95	D, see 93mTc	1E+4	2E+4	9E-6	3E-8	1E-4	1E-3
		W, see 93mTc	-	2E+4	8E-6	3E-8	-	-
43	Technetium-96m2	D, see 93mTc	2E+5	3E+5	1E-4	4E-7	2E-3	2E-2
		W, see 93mTc	-	2E+5	1E-4	3E-7	-	-
43	Technetium-96	D, see 93mTc	2E+3	3E+3	1E-6	5E-9	3E-5	3E-4
		W, see 93mTc	-	2E+3	9E-7	3E-9	-	-
43	Technetium-97m	D, see 93mTc	5E+3	7E+3	3E-6	-	6E-5	6E-4
			-	St wall (7E+3)	-	1E-8	-	-
		W, see 93mTc	-	1E+3	5E-7	2E-9	-	-
43	Technetium-97	D, see 93mTc	4E+4	5E+4	2E-5	7E-8	5E-4	5E-3
		W, see 93mTc	-	6E+3	2E-6	8E-9	-	-
43	Technetium-98	D, see 93mTc	1E+3	2E+3	7E-7	2E-9	1E-5	1E-4
		W, see 93mTc	-	3E+2	1E-7	4E-10	-	-
43	Technetium-99m	D, see 93mTc	8E+4	2E+5	6E-5	2E-7	1E-3	1E-2
		W, see 93mTc	-	2E+5	1E-4	3E-7	-	-
43	Technetium-99	D, see 93mTc	4E+3	5E+3	2E-6	-	6E-5	6E-4
			-	St wall (6E+3)	-	8E-9	-	-
		W, see 93mTc	-	7E+2	3E-7	9E-10	-	-
43	Technetium-1012	D, see 93mTc	9E+4	3E+5	1E-4	5E-7	-	-
			St wall (1E+5)	-	-	-	2E-3	2E-2
		W, see 93mTc	-	4E+5	2E-4	5E-7	-	-
43	Technetium-1042	D, see 93mTc	2E+4	7E+4	3E-5	1E-7	-	-
			St wall (3E+4)	-	-	-	4E-4	4E-3
		W, see 93mTc	-	9E+4	4E-5	1E-7	-	-
44	Ruthenium-942	D, all compounds except those given for W and Y	2E+4	4E+4	2E-5	6E-8	2E-4	2E-3
		W, halides	-	6E+4	3E-5	9E-8	-	-
		Y, oxides and hydroxides	-	6E+4	2E-5	8E-8	-	-
44	Ruthenium-97	D, see 94Ru	8E+3	2E+4	8E-6	3E-8	1E-4	1E-3
		W, see 94Ru	-	1E+4	5E-6	2E-8	-	-
		Y, see 94Ru	-	1E+4	5E-6	2E-8	-	-
44	Ruthenium-103	D, see 94Ru	2E+3	2E+3	7E-7	2E-9	3E-5	3E-4
		W, see 94Ru	-	1E+3	4E-7	1E-9	-	-
		Y, see 94Ru	-	6E+2	3E-7	9E-10	-	-
44	Ruthenium-105	D, see 94Ru	5E+3	1E+4	6E-6	2E-8	7E-5	7E-4
		W, see 94Ru	-	1E+4	6E-6	2E-8	-	-
		Y, see 94Ru	-	1E+4	5E-6	2E-8	-	-
44	Ruthenium-106	D, see 94Ru	2E+2	9E+1	4E-8	1E-10	-	-
			LLI wall (2E+2)	-	-	-	3E-6	3E-5
		W, see 94Ru	-	5E+1	2E-8	8E-11	-	-
		Y, see 94Ru	-	1E+1	5E-9	2E-11	-	-
45	Rhodium-99m	D, all compounds except those given for W and Y	2E+4	6E+4	2E-5	8E-8	2E-4	2E-3
		W, halides	-	8E+4	3E-5	1E-7	-	-
		Y, oxides and hydroxides	-	7E+4	3E-5	9E-8	-	-
45	Rhodium-99	D, see 99mRh	2E+3	3E+3	1E-6	4E-9	3E-5	3E-4
		W, see 99mRh	-	2E+3	9E-7	3E-9	-	-
		Y, see 99mRh	-	2E+3	8E-7	3E-9	-	-
45	Rhodium-100	D, see 99mRh	2E+3	5E+3	2E-6	7E-9	2E-5	2E-4
		W, see 99mRh	-	4E+3	2E-6	6E-9	-	-
		Y, see 99mRh	-	4E+3	2E-6	5E-9	-	-
45	Rhodium-101m	D, see 99mRh	6E+3	1E+4	5E-6	2E-8	8E-5	8E-4
		W, see 99mRh	-	8E+3	4E-6	1E-8	-	-
		Y, see 99mRh	-	8E+3	3E-6	1E-8	-	-
45	Rhodium-101	D, see 99mRh	2E+3	5E+2	2E-7	7E-10	3E-5	3E-4
		W, see 99mRh	-	8E+2	3E-7	1E-9	-	-
		Y, see 99mRh	-	2E+2	6E-8	2E-10	-	-
45	Rhodium-102m	D, see 99mRh	1E+3	5E+2	2E-7	7E-10	-	-
			LLI wall (1E+3)	-	-	-	2E-5	2E-4
		W, see 99mRh	-	4E+2	2E-7	5E-10	-	-
		Y, see 99mRh	-	1E+2	5E-8	2E-10	-	-
45	Rhodium-102	D, see 99mRh	6E+2	9E+1	4E-8	1E-10	8E-6	8E-5
		W, see 99mRh	-	2E+2	7E-8	2E-10	-	-
		Y, see 99mRh	-	6E+1	2E-8	8E-11	-	-
45	Rhodium-103m2	D, see 99mRh	4E+5	1E+6	5E-4	2E-6	6E-3	6E-2
		W, see 99mRh	-	1E+6	5E-4	2E-6	-	-
		Y, see 99mRh	-	1E+6	5E-4	2E-6	-	-
45	Rhodium-105	D, see 99mRh	4E+3	1E+4	5E-6	2E-8	-	-
			LLI wall (4E+3)	-	-	-	5E-5	5E-4
		W, see 99mRh	-	6E+3	3E-6	9E-9	-	-
		Y, see 99mRh	-	6E+3	2E-6	8E-9	-	-
45	Rhodium-106m	D, see 99mRh	8E+3	3E+4	1E-5	4E-8	1E-4	1E-3
		W, see 99mRh	-	4E+4	2E-5	5E-8	-	-
		Y, see 99mRh	-	4E+4	1E-5	5E-8	-	-
45	Rhodium-1072	D, see 99mRh	7E+4	2E+5	1E-4	3E-7	-	-
			St wall (9E+4)	-	-	-	1E-3	1E-2
		W, see 99mRh	-	3E+5	1E-4	4E-7	-	-
		Y, see 99mRh	-	3E+5	1E-4	3E-7	-	-
46	Palladium-100	D, all compounds except those given for W and Y	1E+3	1E+3	6E-7	2E-9	2E-5	2E-4
		W, nitrates	-	1E+3	5E-7	2E-9	-	-
		Y, oxides and hydroxides	-	1E+3	6E-7	2E-9	-	-
46	Palladium-101	D, see 100Pd	1E+4	3E+4	1E-5	5E-8	2E-4	2E-3
		W, see 100Pd	-	3E+4	1E-5	5E-8	-	-
		Y, see 100Pd	-	3E+4	1E-5	4E-8	-	-
46	Palladium-103	D, see 100Pd	6E+3	6E+3	3E-6	9E-9	-	-
			LLI wall (7E+3)	-	-	-	1E-4	1E-3
		W, see 100Pd	-	4E+3	2E-6	6E-9	-	-
		Y, see 100Pd	-	4E+3	1E-6	5E-9	-	-
46	Palladium-107	D, see 100Pd	3E+4	2E+4	9E-6	-	-	-
			LLI wall (4E+4)	Kidneys (2E+4)	-	3E-8	5E-4	5E-3
		W, see 100Pd	-	7E+3	3E-6	1E-8	-	-
		Y, see 100Pd	-	4E+2	2E-7	6E-10	-	-
46	Palladium-109	D, see 100Pd	2E+3	6E+3	3E-6	9E-9	3E-5	3E-4
		W, see 100Pd	-	5E+3	2E-6	8E-9	-	-
		Y, see 100Pd	-	5E+3	2E-6	6E-9	-	-
47	Silver-1022	D, all compounds except those given for W and Y	5E+4	2E+5	8E-5	2E-7	-	-
			St wall (6E+4)	-	-	-	9E-4	9E-3
		W, nitrates and sulfides	-	2E+5	9E-5	3E-7	-	-
		Y, oxides and hydroxides	-	2E+5	8E-5	3E-7	-	-
47	Silver-1032	D, see 102Ag	4E+4	1E+5	4E-5	1E-7	5E-4	5E-3
		W, see 102Ag	-	1E+5	5E-5	2E-7	-	-
		Y, see 102Ag	-	1E+5	5E-5	2E-7	-	-
47	Silver-104m2	D, see 102Ag	3E+4	9E+4	4E-5	1E-7	4E-4	4E-3
		W, see 102Ag	-	1E+5	5E-5	2E-7	-	-
		Y, see 102Ag	-	1E+5	5E-5	2E-7	-	-
47	Silver-1042	D, see 102Ag	2E+4	7E+4	3E-5	1E-7	3E-4	3E-3
		W, see 102Ag	-	1E+5	6E-5	2E-7	-	-
		Y, see 102Ag	-	1E+5	6E-5	2E-7	-	-
47	Silver-105	D, see 102Ag	3E+3	1E+3	4E-7	1E-9	4E-5	4E-4
		W, see 102Ag	-	2E+3	7E-7	2E-9	-	-
		Y, see 102Ag	-	2E+3	7E-7	2E-9	-	-
47	Silver-106m	D, see 102Ag	8E+2	7E+2	3E-7	1E-9	1E-5	1E-4
		W, see 102Ag	-	9E+2	4E-7	1E-9	-	-
		Y, see 102Ag	-	9E+2	4E-7	1E-9	-	-
47	Silver-1062	D, see 102Ag	6E+4	2E+5	8E-5	3E-7	-	-
			St. wall (6E+4)	-	-	-	9E-4	9E-3
		W, see 102Ag	-	2E+5	9E-5	3E-7	-	-
		Y, see 102Ag	-	2E+5	8E-5	3E-7	-	-
47	Silver-108m	D, see 102Ag	6E+2	2E+2	8E-8	3E-10	9E-6	9E-5
		W, see 102Ag	-	3E+2	1E-7	4E-10	-	-
		Y, see 102Ag	-	2E+1	1E-8	3E-11	-	-
47	Silver-110m	D, see 102Ag	5E+2	1E+2	5E-8	2E-10	6E-6	6E-5
		W, see 102Ag	-	2E+2	8E-8	3E-10	-	-
		Y, see 102Ag	-	9E+1	4E-8	1E-10	-	-
47	Silver-111	D, see 102Ag	9E+2	2E+3	6E-7	-	-	-
			LLI wall (1E+3)	Liver (2E+3)	-	2E-9	2E-5	2E-4
		W, see 102Ag	-	9E+2	4E-7	1E-9	-	-
		Y, see 102Ag	-	9E+2	4E-7	1E-9	-	-
47	Silver-112	D, see 102Ag	3E+3	8E+3	3E-6	1E-8	4E-5	4E-4
		W, see 102Ag	-	1E+4	4E-6	1E-8	-	-
		Y, see 102Ag	-	9E+3	4E-6	1E-8	-	-
47	Silver-1152	D, see 102Ag	3E+4	9E+4	4E-5	1E-7	-	-
			St wall (3E+4)	-	-	-	4E-4	4E-3
		W, see 102Ag	-	9E+4	4E-5	1E-7	-	-
		Y, see 102Ag	-	8E+4	3E-5	1E-7	-	-
48	Cadmium-1042	D, all compounds except those given for W and Y	2E+4	7E+4	3E-5	9E-8	3E-4	3E-3
		W, sulfides, halides, and nitrates	-	1E+5	5E-5	2E-7	-	-
		Y, oxides and hydroxides	-	1E+5	5E-5	2E-7	-	-
48	Cadmium-107	D, see 104Cd	2E+4	5E+4	2E-5	8E-8	3E-4	3E-3
		W, see 104Cd	-	6E+4	2E-5	8E-8	-	-
		Y, see 104Cd	-	5E+4	2E-5	7E-8	-	-
48	Cadmium-109	D, see 104Cd	3E+2	4E+1	1E-8	-	-	-
			Kidneys (4E+2)	Kidneys (5E+1)	-	7E-11	6E-6	6E-5
		W, see 104Cd	-	1E+2	5E-8	-	-	-
			-	Kidneys (1E+2)	-	2E-10	-	-
		Y, see 104Cd	-	1E+2	5E-8	2E-10	-	-
48	Cadmium-113m	D, see 104Cd	2E+1	2E+0	1E-9	-	-	-
			Kidneys (4E+1)	Kidneys (4E+0)	-	5E-12	5E-7	5E-6
		W, see 104Cd	-	8E+0	4E-9	-	-	-
			-	Kidneys (1E+1)	-	2E-11	-	-
		Y, see 104Cd	-	1E+1	5E-9	2E-11	-	-
48	Cadmium-113	D, see 104Cd	2E+1	2E+0	9E-10	-	-	-
			Kidneys (3E+1)	Kidneys (3E+0)	-	5E-12	4E-7	4E-6
		W, see 104Cd	-	8E+0	3E-9	-	-	-
			-	Kidneys (1E+1)	-	2E-11	-	-
		Y, see 104Cd	-	1E+1	6E-9	2E-11	-	-
48	Cadmium-115m	D, see 104Cd	3E+2	5E+1	2E-8	-	4E-6	4E-5
			-	Kidneys (8E+1)	-	1E-10	-	-
		W, see 104Cd	-	1E+2	5E-8	2E-10	-	-
		Y, see 104Cd	-	1E+2	6E-8	2E-10	-	-
48	Cadmium-115	D, see 104Cd	9E+2	1E+3	6E-7	2E-9	-	-
			LLI wall (1E+3)	-	-	-	1E-5	1E-4
		W, see 104Cd	-	1E+3	5E-7	2E-9	-	-
		Y, see 104Cd	-	1E+3	6E-7	2E-9	-	-
48	Cadmium-117m	D, see 104Cd	5E+3	1E+4	5E-6	2E-8	6E-5	6E-4
		W, see 104Cd	-	2E+4	7E-6	2E-8	-	-
		Y, see 104Cd	-	1E+4	6E-6	2E-8	-	-
48	Cadmium-117	D, see 104Cd	5E+3	1E+4	5E-6	2E-8	6E-5	6E-4
		W, see 104Cd	-	2E+4	7E-6	2E-8	-	-
		Y, see 104Cd	-	1E+4	6E-6	2E-8	-	-
49	Indium-109	D, all compounds except those given for W	2E+4	4E+4	2E-5	6E-8	3E-4	3E-3
		W, oxides, hydroxides, halides, and nitrates	-	6E+4	3E-5	9E-8	-	-
49	Indium-1102	D, see 109In	2E+4	4E+4	2E-5	6E-8	2E-4	2E-3
	(69.1 min)	W, see 109In	-	6E+4	2E-5	8E-8	-	-
49	Indium-110	D, see 109In	5E+3	2E+4	7E-6	2E-8	7E-5	7E-4
	(4.9 h)	W, see 109In	-	2E+4	8E-6	3E-8	-	-
49	Indium-111	D, see 109In	4E+3	6E+3	3E-6	9E-9	6E-5	6E-4
		W, see 109In	-	6E+3	3E-6	9E-9	-	-
49	Indium-1122	D, see 109In	2E+5	6E+5	3E-4	9E-7	2E-3	2E-2
		W, see 109In	-	7E+5	3E-4	1E-6	-	-
49	Indium-113m2	D, see 109In	5E+4	1E+5	6E-5	2E-7	7E-4	7E-3
		W, see 109In	-	2E+5	8E-5	3E-7	-	-
49	Indium-114m	D, see 109In	3E+2	6E+1	3E-8	9E-11	-	-
			LLI wall (4E+2)	-	-	-	5E-6	5E-5
		W, see 109In	-	1E+2	4E-8	1E-10	-	-
49	Indium-115m	D, see 109In	1E+4	4E+4	2E-5	6E-8	2E-4	2E-3
		W, see 109In	-	5E+4	2E-5	7E-8	-	-
49	Indium-115	D, see 109In	4E+1	1E+0	6E-10	2E-12	5E-7	5E-6
		W, see 109In	-	5E+0	2E-9	8E-12	-	-
49	Indium-116m2	D, see 109In	2E+4	8E+4	3E-5	1E-7	3E-4	3E-3
		W, see 109In	-	1E+5	5E-5	2E-7	-	-
49	Indium-117m2	D, see 109In	1E+4	3E+4	1E-5	5E-8	2E-4	2E-3
		W, see 109In	-	4E+4	2E-5	6E-8	-	-
49	Indium-1172	D, see 109In	6E+4	2E+5	7E-5	2E-7	8E-4	8E-3
		W, see 109In	-	2E+5	9E-5	3E-7	-	-
49	Indium-119m2	D, see 109In	4E+4	1E+5	5E-5	2E-7	-	-
			St wall (5E+4)	-	-	-	7E-4	7E-3
		W, see 109In	-	1E+5	6E-5	2E-7	-	-
50	Tin-110	D, all compounds except those given for W	4E+3	1E+4	5E-6	2E-8	5E-5	5E-4
		W, sulfides, oxides, hydroxides, halides, nitrates, and stannic phosphate	-	1E+4	5E-6	2E-8	-	-
50	Tin-1112	D, see 110Sn	7E+4	2E+5	9E-5	3E-7	1E-3	1E-2
		W, see 110Sn	-	3E+5	1E-4	4E-7	-	-
50	Tin-113	D, see 110Sn	2E+3	1E+3	5E-7	2E-9	-	-
			LLI wall (2E+3)	-	-	-	3E-5	3E-4
		W, see 110Sn	-	5E+2	2E-7	8E-10	-	-
50	Tin-117m	D, see 110Sn	2E+3	1E+3	5E-7	-	-	-
			LLI wall (2E+3)	Bone surf (2E+3)	-	3E-9	3E-5	3E-4
		W, see 110Sn	-	1E+3	6E-7	2E-9	-	-
50	Tin-119m	D, see 110Sn	3E+3	2E+3	1E-6	3E-9	-	-
			LLI wall (4E+3)	-	-	-	6E-5	6E-4
		W, see 110Sn	-	1E+3	4E-7	1E-9	-	-
50	Tin-121m	D, see 110Sn	3E+3	9E+2	4E-7	1E-9	-	-
			LLI wall (4E+3)	-	-	-	5E-5	5E-4
		W, see 110Sn	-	5E+2	2E-7	8E-10	-	-
50	Tin-121	D, see 110Sn	6E+3	2E+4	6E-6	2E-8	-	-
			LLI wall (6E+3)	-	-	-	8E-5	8E-4
		W, see 110Sn	-	1E+4	5E-6	2E-8	-	-
50	Tin-123m2	D, see 110Sn	5E+4	1E+5	5E-5	2E-7	7E-4	7E-3
		W, see 110Sn	-	1E+5	6E-5	2E-7	-	-
50	Tin-123	D, see 110Sn	5E+2	6E+2	3E-7	9E-10	-	-
			LLI wall (6E+2)	-	-	-	9E-6	9E-5
		W, see 110Sn	-	2E+2	7E-8	2E-10	-	-
50	Tin-125	D, see 110Sn	4E+2	9E+2	4E-7	1E-9	-	-
			LLI wall (5E+2)	-	-	-	6E-6	6E-5
		W, see 110Sn	-	4E+2	1E-7	5E-10	-	-
50	Tin-126	D, see 110Sn	3E+2	6E+1	2E-8	8E-11	4E-6	4E-5
		W, see 110Sn	-	7E+1	3E-8	9E-11	-	-
50	Tin-127	D, see 110Sn	7E+3	2E+4	8E-6	3E-8	9E-5	9E-4
		W, see 110Sn	-	2E+4	8E-6	3E-8	-	-
50	Tin-1282	D, see 110Sn	9E+3	3E+4	1E-5	4E-8	1E-4	1E-3
		W, see 110Sn	-	4E+4	1E-5	5E-8	-	-
51	Antimony-1152	D, all compounds except those given for W	8E+4	2E+5	1E-4	3E-7	1E-3	1E-2
		W, oxides, hydroxides, halides, sulfides, sulfates, and nitrates	-	3E+5	1E-4	4E-7	-	-
51	Antimony-116m2	D, see 115Sb	2E+4	7E+4	3E-5	1E-7	3E-4	3E-3
		W, see 115Sb	-	1E+5	6E-5	2E-7	-	-
51	Antimony-1162	D, see 115Sb	7E+4	3E+5	1E-4	4E-7	-	-
			St wall (9E+4)	-	-	-	1E-3	1E-2
		W, see 115Sb	-	3E+5	1E-4	5E-7	-	-
51	Antimony-117	D, see 115Sb	7E+4	2E+5	9E-5	3E-7	9E-4	9E-3
		W, see 115Sb	-	3E+5	1E-4	4E-7	-	-
51	Antimony-118m	D, see 115Sb	6E+3	2E+4	8E-6	3E-8	7E-5	7E-4
		W, see 115Sb	5E+3	2E+4	9E-6	3E-8	-	-
51	Antimony-119	D, see 115Sb	2E+4	5E+4	2E-5	6E-8	2E-4	2E-3
		W, see 115Sb	2E+4	3E+4	1E-5	4E-8	-	-
51	Antimony-1202	D, see 115Sb	1E+5	4E+5	2E-4	6E-7	-	-
	(16 min)		St wall (2E+5)	-	-	-	2E-3	2E-2
		W, see 115Sb	-	5E+5	2E-4	7E-7	-	-
51	Antimony-120 (5.76 d)	D, see 115Sb	1E+3	2E+3	9E-7	3E-9	1E-5	1E-4
		W, see 115Sb	9E+2	1E+3	5E-7	2E-9	-	-
51	Antimony-122	D, see 115Sb	8E+2	2E+3	1E-6	3E-9	-	-
			LLI wall (8E+2)	-	-	-	1E-5	1E-4
		W, see 115Sb	7E+2	1E+3	4E-7	2E-9	-	-
51	Antimony-124m2	D, see 115Sb	3E+5	8E+5	4E-4	1E-6	3E-3	3E-2
		W, see 115Sb	2E+5	6E+5	2E-4	8E-7	-	-
51	Antimony-124	D, see 115Sb	6E+2	9E+2	4E-7	1E-9	7E-6	7E-5
		W, see 115Sb	5E+2	2E+2	1E-7	3E-10	-	-
51	Antimony-125	D, see 115Sb	2E+3	2E+3	1E-6	3E-9	3E-5	3E-4
		W, see 115Sb	-	5E+2	2E-7	7E-10	-	-
51	Antimony-126m2	D, see 115Sb	5E+4	2E+5	8E-5	3E-7	-	-
			St wall (7E+4)	-	-	-	9E-4	9E-3
		W, see 115Sb	-	2E+5	8E-5	3E-7	-	-
51	Antimony-126	D, see 115Sb	6E+2	1E+3	5E-7	2E-9	7E-6	7E-5
		W, see 115Sb	5E+2	5E+2	2E-7	7E-10	-	-
51	Antimony-127	D, see 115Sb	8E+2	2E+3	9E-7	3E-9	-	-
			LLI wall (8E+2)	-	-	-	1E-5	1E-4
		W, see 115Sb	7E+2	9E+2	4E-7	1E-9	-	-
51	Antimony-1282	D, see 115Sb	8E+4	4E+5	2E-4	5E-7	-	-
	(10.4 min)		St wall (1E+5)	-	-	-	1E-3	1E-2
		W, see 115Sb	-	4E+5	2E-4	6E-7	-	-
51	Antimony-128	D, see 115Sb	1E+3	4E+3	2E-6	6E-9	2E-5	2E-4
	(9.01 h)	W, see 115Sb	-	3E+3	1E-6	5E-9	-	-
51	Antimony-129	D, see 115Sb	3E+3	9E+3	4E-6	1E-8	4E-5	4E-4
		W, see 115Sb	-	9E+3	4E-6	1E-8	-	-
51	Antimony-1302	D, see 115Sb	2E+4	6E+4	3E-5	9E-8	3E-4	3E-3
		W, see 115Sb	-	8E+4	3E-5	1E-7	-	-
51	Antimony-1312	D, see 115Sb	1E+4	2E+4	1E-5	-	-	-
			Thyroid (2E+4)	Thyroid (4E+4)	-	6E-8	2E-4	2E-3
		W, see 115Sb	-	2E+4	1E-5		-	-
			-	Thyroid (4E+4)	-	6E-8	-	-
52	Tellurium-116	D, all compounds except those given for W	8E+3	2E+4	9E-6	3E-8	1E-4	1E-3
		W, oxides, hydroxides, and nitrates	-	3E+4	1E-5	4E-8	-	-
52	Tellurium-121m	D, see 116Te	5E+2	2E+2	8E-8	-	-	-
			Bone surf (7E+2)	Bone surf (4E+2)	-	5E-10	1E-5	1E-4
		W, see 116Te	-	4E+2	2E-7	6E-10	-	-
52	Tellurium-121	D, see 116Te	3E+3	4E+3	2E-6	6E-9	4E-5	4E-4
		W, see 116Te	-	3E+3	1E-6	4E-9	-	-
52	Tellurium-123m	D, see 116Te	6E+2	2E+2	9E-8	-	-	-
			Bone surf (1E+3)	Bone surf (5E+2)	-	8E-10	1E-5	1E-4
		W, see 116Te	-	5E+2	2E-7	8E-10	-	-
52	Tellurium-123	D, see 116Te	5E+2	2E+2	8E-8	-	-	-
			Bone surf (1E+3)	Bone surf (5E+2)	-	7E-10	2E-5	2E-4
		W, see 116Te	-	4E+2	2E-7	-	-	-
			-	Bone surf (1E+3)	-	2E-9	-	-
52	Tellurium-125m	D, see 116Te	1E+3	4E+2	2E-7	-	-	-
			Bone surf (1E+3)	Bone surf (1E+3)	-	1E-9	2E-5	2E-4
		W, see 116Te	-	7E+2	3E-7	1E-9	-	-
52	Tellurium-127m	D, see 116Te	6E+2	3E+2	1E-7	-	9E-6	9E-5
			-	Bone surf (4E+2)	-	6E-10	-	-
		W, see 116Te	-	3E+2	1E-7	4E-10	-	-
52	Tellurium-127	D, see 116Te	7E+3	2E+4	9E-6	3E-8	1E-4	1E-3
		W, see 116Te	-	2E+4	7E-6	2E-8	-	-
52	Tellurium-129m	D, see 116Te	5E+2	6E+2	3E-7	9E-10	7E-6	7E-5
		W, see 116Te	-	2E+2	1E-7	3E-10	-	-
52	Tellurium-1292	D, see 116Te	3E+4	6E+4	3E-5	9E-8	4E-4	4E-3
		W, see 116Te	-	7E+4	3E-5	1E-7	-	-
52	Tellurium-131m	D, see 116Te	3E+2	4E+2	2E-7	-	-	-
			Thyroid (6E+2)	Thyroid (1E+3)	-	2E-9	8E-6	8E-5
		W, see 116Te	-	4E+2	2E-7	-	-	-
			-	Thyroid (9E+2)	-	1E-9	-	-
52	Tellurium-1312	D, see 116Te	3E+3	5E+3	2E-6	-	-	-
			Thyroid (6E+3)	Thyroid (1E+4)	-	2E-8	8E-5	8E-4
		W, see 116Te	-	5E+3	2E-6	-	-	-
			-	Thyroid (1E+4)	-	2E-8	-	-
52	Tellurium-132	D, see 116Te	2E+2	2E+2	9E-8	-	-	-
			Thyroid (7E+2)	Thyroid (8E+2)	-	1E-9	9E-6	9E-5
		W, see 116Te	-	2E+2	9E-8	-	-	-
			-	Thyroid (6E+2)	-	9E-10	-	-
52	Tellurium-133m2	D, see 116Te	3E+3	5E+3	2E-6	-	-	-
			Thyroid (6E+3)	Thyroid (1E+4)	-	2E-8	9E-5	9E-4
		W, see 116Te	-	5E+3	2E-6	-	-	-
			-	Thyroid (1E+4)	-	2E-8	-	-
52	Tellurium-1332	D, see 116Te	1E+4	2E+4	9E-6	-	-	-
			Thyroid (3E+4)	Thyroid (6E+4)	-	8E-8	4E-4	4E-3
		W, see 116Te	-	2E+4	9E-6	-	-	-
			-	Thyroid (6E+4)	-	8E-8	-	-
52	Tellurium-1342	D, see 116Te	2E+4	2E+4	1E-5	-	-	-
			Thyroid (2E+4)	Thyroid (5E+4)	-	7E-8	3E-4	3E-3
		W, see 116Te	-	2E+4	1E-5	-	-	-
				Thyroid
			-	(5E+4)	-	7E-8	-	-
53	Iodine-120m2	D, all compounds	1E+4	2E+4	9E-6	3E-8	-	-
			Thyroid (1E+4)	-	-	-	2E-4	2E-3
53	Iodine-1202	D, all compounds	4E+3	9E+3	4E-6	-	-	-
			Thyroid (8E+3)	Thyroid (1E+4)	-	2E-8	1E-4	1E-3
53	Iodine-121	D, all compounds	1E+4	2E+4	8E-6	-	-	-
			Thyroid (3E+4)	Thyroid (5E+4)	-	7E-8	4E-4	4E-3
53	Iodine-123	D, all compounds	3E+3	6E+3	3E-6	-	-	-
			Thyroid (1E+4)	Thyroid (2E+4)	-	2E-8	1E-4	1E-3
53	Iodine-124	D, all compounds	5E+1	8E+1	3E-8	-	-	-
			Thyroid (2E+2)	Thyroid (3E+2)	-	4E-10	2E-6	2E-5
53	Iodine-125	D, all compounds	4E+1	6E+1	3E-8	-	-	-
			Thyroid (1E+2)	Thyroid (2E+2)	-	3E-10	2E-6	2E-5
53	Iodine-126	D, all compounds	2E+1	4E+1	1E-8	-	-	-
			Thyroid (7E+1)	Thyroid (1E+2)	-	2E-10	1E-6	1E-5
53	Iodine-1282	D, all compounds	4E+4	1E+5	5E-5	2E-7	-	-
			St wall (6E+4)	-	-	-	8E-4	8E-3
53	Iodine-129	D, all compounds	5E+0	9E+0	4E-9	-	-	-
			Thyroid (2E+1)	Thyroid (3E+1)	-	4E-11	2E-7	2E-6
53	Iodine-130	D, all compounds	4E+2	7E+2	3E-7	-	-	-
			Thyroid (1E+3)	Thyroid (2E+3)	-	3E-9	2E-5	2E-4
53	Iodine-131	D, all compounds	3E+1	5E+1	2E-8	-	-	-
			Thyroid (9E+1)	Thyroid (2E+2)	-	2E-10	1E-6	1E-5
53	Iodine-132m2	D, all compounds	4E+3	8E+3	4E-6	-	-	-
			Thyroid (1E+4)	Thyroid (2E+4)	-	3E-8	1E-4	1E-3
53	Iodine-132	D, all compounds	4E+3	8E+3	3E-6	-	-	-
			Thyroid (9E+3)	Thyroid (1E+4)	-	2E-8	1E-4	1E-3
53	Iodine-133	D, all compounds	1E+2	3E+2	1E-7	-	-	-
			Thyroid (5E+2)	Thyroid (9E+2)	-	1E-9	7E-6	7E-5
53	Iodine-1342	D, all compounds	2E+4	5E+4	2E-5	6E-8	-	-
			Thyroid (3E+4)	-	-	-	4E-4	4E-3
53	Iodine-135	D, all compounds	8E+2	2E+3	7E-7	-	-	-
			Thyroid (3E+3)	Thyroid (4E+3)	-	6E-9	3E-5	3E-4
54	Xenon-1202	Submersion1	-	-	1E-5	4E-8	-	-
54	Xenon-1212	Submersion1	-	-	2E-6	1E-8	-	-
54	Xenon-122	Submersion1	-	-	7E-5	3E-7	-	-
54	Xenon-123	Submersion1	-	-	6E-6	3E-8	-	-
54	Xenon-125	Submersion1	-	-	2E-5	7E-8	-	-
54	Xenon-127	Submersion1	-	-	1E-5	6E-8	-	-
54	Xenon-129m	Submersion1	-	-	2E-4	9E-7	-	-
54	Xenon-131m	Submersion1	-	-	4E-4	2E-6	-	-
54	Xenon-133m	Submersion1	-	-	1E-4	6E-7	-	-
54	Xenon-133	Submersion1	-	-	1E-4	5E-7	-	-
54	Xenon-135m2	Submersion1	-	-	9E-6	4E-8	-	-
54	Xenon-135	Submersion1	-	-	1E-5	7E-8	-	-
54	Xenon-1382	Submersion1	-	-	4E-6	2E-8	-	-
55	Cesium-1252	D, all compounds	5E+4	1E+5	6E-5	2E-7	-	-
			St wall (9E+4)	-	-	-	1E-3	1E-2
55	Cesium-127	D, all compounds	6E+4	9E+4	4E-5	1E-7	9E-4	9E-3
55	Cesium-129	D, all compounds	2E+4	3E+4	1E-5	5E-8	3E-4	3E-3
55	Cesium-1302	D, all compounds	6E+4	2E+5	8E-5	3E-7	-	-
			St wall (1E+5)	-	-	-	1E-3	1E-2
55	Cesium-131	D, all compounds	2E+4	3E+4	1E-5	4E-8	3E-4	3E-3
55	Cesium-132	D, all compounds	3E+3	4E+3	2E-6	6E-9	4E-5	4E-4
55	Cesium-134m	D, all compounds	1E+5	1E+5	6E-5	2E-7	-	-
			St wall (1E+5)	-	-	-	2E-3	2E-2
55	Cesium-134	D, all compounds	7E+1	1E+2	4E-8	2E-10	9E-7	9E-6
55	Cesium-135m2	D, all compounds	1E+5	2E+5	8E-5	3E-7	1E-3	1E-2
55	Cesium-135	D, all compounds	7E+2	1E+3	5E-7	2E-9	1E-5	1E-4
55	Cesium-136	D, all compounds	4E+2	7E+2	3E-7	9E-10	6E-6	6E-5
55	Cesium-137	D, all compounds	1E+2	2E+2	6E-8	2E-10	1E-6	1E-5
55	Cesium-1382	D, all compounds	2E+4	6E+4	2E-5	8E-8	-	-
			St wall (3E+4)	-	-	-	4E-4	4E-3
56	Barium-1262	D, all compounds	6E+3	2E+4	6E-6	2E-8	8E-5	8E-4
56	Barium-128	D, all compounds	5E+2	2E+3	7E-7	2E-9	7E-6	7E-5
56	Barium-131m2	D, all compounds	4E+5	1E+6	6E-4	2E-6	-	-
			St wall (5E+5)	-	-	-	7E-3	7E-2
56	Barium-131	D, all compounds	3E+3	8E+3	3E-6	1E-8	4E-5	4E-4
56	Barium-133m	D, all compounds	2E+3	9E+3	4E-6	1E-8	-	-
			LLI wall (3E+3)	-	-	-	4E-5	4E-4
56	Barium-133	D, all compounds	2E+3	7E+2	3E-7	9E-10	2E-5	2E-4
56	Barium-135m	D, all compounds	3E+3	1E+4	5E-6	2E-8	4E-5	4E-4
56	Barium-1392	D, all compounds	1E+4	3E+4	1E-5	4E-8	2E-4	2E-3
56	Barium-140	D, all compounds	5E+2	1E+3	6E-7	2E-9	-	-
			LLI wall (6E+2)	-	-	-	8E-6	8E-5
56	Barium-1412	D, all compounds	2E+4	7E+4	3E-5	1E-7	3E-4	3E-3
56	Barium-1422	D, all compounds	5E+4	1E+5	6E-5	2E-7	7E-4	7E-3
57	Lanthanum-1312	D, all compounds except those given for W	5E+4	1E+5	5E-5	2E-7	6E-4	6E-3
		W, oxides and hydroxides	-	2E+5	7E-5	2E-7	-	-
57	Lanthanum-132	D, see 131La	3E+3	1E+4	4E-6	1E-8	4E-5	4E-4
		W, see 131La	-	1E+4	5E-6	2E-8	-	-
57	Lanthanum-135	D, see 131La	4E+4	1E+5	4E-5	1E-7	5E-4	5E-3
		W, see 131La	-	9E+4	4E-5	1E-7	-	-
57	Lanthanum-137	D, see 131La	1E+4	6E+1	3E-8	-	2E-4	2E-3
			-	Liver (7E+1)	-	1E-10	-	-
		W, see 131La	-	3E+2	1E-7	-	-	-
			-	Liver (3E+2)	-	4E-10	-	-
57	Lanthanum-138	D, see 131La	9E+2	4E+0	1E-9	5E-12	1E-5	1E-4
		W, see 131La	-	1E+1	6E-9	2E-11	-	-
57	Lanthanum-140	D, see 131La	6E+2	1E+3	6E-7	2E-9	9E-6	9E-5
		W, see 131La	-	1E+3	5E-7	2E-9	-	-
57	Lanthanum-141	D, see 131La	4E+3	9E+3	4E-6	1E-8	5E-5	5E-4
		W, see 131La	-	1E+4	5E-6	2E-8	-	-
57	Lanthanum-1422	D, see 131La	8E+3	2E+4	9E-6	3E-8	1E-4	1E-3
		W, see 131La	-	3E+4	1E-5	5E-8	-	-
57	Lanthanum-1432	D, see 131La	4E+4	1E+5	4E-5	1E-7	-	-
			St wall (4E+4)	-	-	-	5E-4	5E-3
		W, see 131La	-	9E+4	4E-5	1E-7	-	-
58	Cerium-134	W, all compounds except those given for Y	5E+2	7E+2	3E-7	1E-9	-	-
			LLI wall (6E+2)	-	-	-	8E-6	8E-5
		Y, oxides, hydroxides, and fluorides	-	7E+2	3E-7	9E-10	-	-
58	Cerium-135	W, see 134Ce	2E+3	4E+3	2E-6	5E-9	2E-5	2E-4
		Y, see 134Ce	-	4E+3	1E-6	5E-9	-	-
58	Cerium-137m	W, see 134Ce	2E+3	4E+3	2E-6	6E-9	-	-
			LLI wall (2E+3)	-	-	-	3E-5	3E-4
		Y, see 134Ce	-	4E+3	2E-6	5E-9	-	-
58	Cerium-137	W, see 134Ce	5E+4	1E+5	6E-5	2E-7	7E-4	7E-3
		Y, see 134Ce	-	1E+5	5E-5	2E-7	-	-
58	Cerium-139	W, see 134Ce	5E+3	8E+2	3E-7	1E-9	7E-5	7E-4
		Y, see 134Ce	-	7E+2	3E-7	9E-10	-	-
58	Cerium-141	W, see 134Ce	2E+3	7E+2	3E-7	1E-9	-	-
			LLI wall (2E+3)	-	-	-	3E-5	3E-4
		Y, see 134Ce	-	6E+2	2E-7	8E-10	-	-
58	Cerium-143	W, see 134Ce	1E+3	2E+3	8E-7	3E-9	-	-
			LLI wall (1E+3)	-	-	-	2E-5	2E-4
		Y, see 134Ce	-	2E+3	7E-7	2E-9	-	-
58	Cerium-144	W, see 134Ce	2E+2	3E+1	1E-8	4E-11	-	-
			LLI wall (3E+2)	-	-	-	3E-6	3E-5
		Y, see 134Ce	-	1E+1	6E-9	2E-11	-	-
59	Praseodymium-1362	W, all compounds except those given for Y	5E+4	2E+5	1E-4	3E-7	-	-
			St wall
			(7E+4)	-	-	-	1E-3	1E-2
		Y, oxides, hydroxides, carbides, and fluorides	-	2E+5	9E-5	3E-7	-	-
59	Praseodymium-1372	W, see 136Pr	4E+4	2E+5	6E-5	2E-7	5E-4	5E-3
		Y, see 136Pr	-	1E+5	6E-5	2E-7	-	-
59	Praseodymium-138m	W, see 136Pr	1E+4	5E+4	2E-5	8E-8	1E-4	1E-3
		Y, see 136Pr	-	4E+4	2E-5	6E-8	-	-
59	Praseodymium-139	W, see 136Pr	4E+4	1E+5	5E-5	2E-7	6E-4	6E-3
		Y, see 136Pr	-	1E+5	5E-5	2E-7	-	-
59	Praseodymium-142m2	W, see 136Pr	8E+4	2E+5	7E-5	2E-7	1E-3	1E-2
		Y, see 136Pr	-	1E+5	6E-5	2E-7	-	-
59	Praseodymium-142	W, see 136Pr	1E+3	2E+3	9E-7	3E-9	1E-5	1E-4
		Y, see 136Pr	-	2E+3	8E-7	3E-9	-	-
59	Praseodymium-143	W, see 136Pr	9E+2	8E+2	3E-7	1E-9	-	-
			LLI wall (1E+3)	-	-	-	2E-5	2E-4
		Y, see 136Pr	-	7E+2	3E-7	9E-10	-	-
59	Praseodymium-1442	W, see 136Pr	3E+4	1E+5	5E-5	2E-7	-	-
			St wall (4E+4)	-	-	-	6E-4	6E-3
		Y, see 136Pr	-	1E+5	5E-5	2E-7	-	-
59	Praseodymium-145	W, see 136Pr	3E+3	9E+3	4E-6	1E-8	4E-5	4E-4
		Y, see 136Pr	-	8E+3	3E-6	1E-8	-	-
59	Praseodymium-1472	W, see 136Pr	5E+4	2E+5	8E-5	3E-7	-	-
			St wall (8E+4)	-	-	-	1E-3	1E-2
		Y, see 136Pr	-	2E+5	8E-5	3E-7	-	-
60	Neodymium-1362	W, all compounds except those given for Y	1E+4	6E+4	2E-5	8E-8	2E-4	2E-3
		Y, oxides, hydroxides, carbides, and fluorides	-	5E+4	2E-5	8E-8	-	-
60	Neodymium-138	W, see 136Nd	2E+3	6E+3	3E-6	9E-9	3E-5	3E-4
		Y, see 136Nd	-	5E+3	2E-6	7E-9	-	-
60	Neodymium-139m	W, see 136Nd	5E+3	2E+4	7E-6	2E-8	7E-5	7E-4
		Y, see 136Nd	-	1E+4	6E-6	2E-8	-	-
60	Neodymium-1392	W, see 136Nd	9E+4	3E+5	1E-4	5E-7	1E-3	1E-2
		Y, see 136Nd	-	3E+5	1E-4	4E-7	-	-
60	Neodymium-141	W, see 136Nd	2E+5	7E+5	3E-4	1E-6	2E-3	2E-2
		Y, see 136Nd	-	6E+5	3E-4	9E-7	-	-
60	Neodymium-147	W, see 136Nd	1E+3	9E+2	4E-7	1E-9	-	-
			LLI wall (1E+3)	-	-	-	2E-5	2E-4
		Y, see 136Nd	-	8E+2	4E-7	1E-9	-	-
60	Neodymium-1492	W, see 136Nd	1E+4	3E+4	1E-5	4E-8	1E-4	1E-3
		Y, see 136Nd	-	2E+4	1E-5	3E-8	-	-
60	Neodymium-1512	W, see 136Nd	7E+4	2E+5	8E-5	3E-7	9E-4	9E-3
		Y, see 136Nd	-	2E+5	8E-5	3E-7	-	-
61	Promethium-1412	W, all compounds except those given for Y	5E+4	2E+5	8E-5	3E-7	-	-
			St wall (6E+4)	-	-	-	8E-4	8E-3
		Y, oxides, hydroxides, carbides, and fluorides	-	2E+5	7E-5	2E-7	-	-
61	Promethium-143	W, see 141Pm	5E+3	6E+2	2E-7	8E-10	7E-5	7E-4
		Y, see 141Pm	-	7E+2	3E-7	1E-9	-	-
61	Promethium-144	W, see 141Pm	1E+3	1E+2	5E-8	2E-10	2E-5	2E-4
		Y, see 141Pm	-	1E+2	5E-8	2E-10	-	-
61	Promethium-145	W, see 141Pm	1E+4	2E+2	7E-8	-	1E-4	1E-3
			-	Bone surf (2E+2)	-	3E-10	-	-
		Y, see 141Pm	-	2E+2	8E-8	3E-10	-	-
61	Promethium-146	W, see 141Pm	2E+3	5E+1	2E-8	7E-11	2E-5	2E-4
		Y, see 141Pm	-	4E+1	2E-8	6E-11	-	-
61	Promethium-147	W, see 141Pm	4E+3	1E+2	5E-8	-	-	-
			LLI wall (5E+3)	Bone surf (2E+2)	-	3E-10	7E-5	7E-4
		Y, see 141Pm	-	1E+2	6E-8	2E-10	-	-
61	Promethium-148m	W, see 141Pm	7E+2	3E+2	1E-7	4E-10	1E-5	1E-4
		Y, see 141Pm	-	3E+2	1E-7	5E-10	-	-
61	Promethium-148	W, see 141Pm	4E+2	5E+2	2E-7	8E-10	-	-
			LLI wall (5E+2)	-	-	-	7E-6	7E-5
		Y, see 141Pm	-	5E+2	2E-7	7E-10	-	-
61	Promethium-149	W, see 141Pm	1E+3	2E+3	8E-7	3E-9	-	-
			LLI wall (1E+3)	-	-	-	2E-5	2E-4
		Y, see 141Pm	-	2E+3	8E-7	2E-9	-	-
61	Promethium-150	W, see 141Pm	5E+3	2E+4	8E-6	3E-8	7E-5	7E-4
		Y, see 141Pm	-	2E+4	7E-6	2E-8	-	-
61	Promethium-151	W, see 141Pm	2E+3	4E+3	1E-6	5E-9	2E-5	2E-4
		Y, see 141Pm	-	3E+3	1E-6	4E-9	-	-
62	Samarium-141m2	W, all compounds	3E+4	1E+5	4E-5	1E-7	4E-4	4E-3
62	Samarium-1412	W, all compounds	5E+4	2E+5	8E-5	2E-7	-	-
			St wall (6E+4)	-	-	-	8E-4	8E-3
62	Samarium-1422	W, all compounds	8E+3	3E+4	1E-5	4E-8	1E-4	1E-3
62	Samarium-145	W, all compounds	6E+3	5E+2	2E-7	7E-10	8E-5	8E-4
62	Samarium-146	W, all compounds	1E+1	4E-2	1E-11	-	-	-
			Bone surf (3E+1)	Bone surf (6E-2)	-	9E-14	3E-7	3E-6
62	Samarium-147	W, all compounds	2E+1	4E-2	2E-11	-	-	-
			Bone surf (3E+1)	Bone surf (7E-2)	-	1E-13	4E-7	4E-6
62	Samarium-151	W, all compounds	1E+4	1E+2	4E-8	-	-	-
			LLI wall (1E+4)	Bone surf (2E+2)	-	2E-10	2E-4	2E-3
62	Samarium-153	W, all compounds	2E+3	3E+3	1E-6	4E-9	-	-
			LLI wall (2E+3)	-	-	-	3E-5	3E-4
62	Samarium-1552	W, all compounds	6E+4	2E+5	9E-5	3E-7	-	-
			St wall (8E+4)	-	-	-	1E-3	1E-2
62	Samarium-156	W, all compounds	5E+3	9E+3	4E-6	1E-8	7E-5	7E-4
63	Europium-145	W, all compounds	2E+3	2E+3	8E-7	3E-9	2E-5	2E-4
63	Europium-146	W, all compounds	1E+3	1E+3	5E-7	2E-9	1E-5	1E-4
63	Europium-147	W, all compounds	3E+3	2E+3	7E-7	2E-9	4E-5	4E-4
63	Europium-148	W, all compounds	1E+3	4E+2	1E-7	5E-10	1E-5	1E-4
63	Europium-149	W, all compounds	1E+4	3E+3	1E-6	4E-9	2E-4	2E-3
63	Europium-150 (12.62h)	W, all compounds	3E+3	8E+3	4E-6	1E-8	4E-5	4E-4
63	Europium-150 (34.2 y)	W, all compounds	8E+2	2E+1	8E-9	3E-11	1E-5	1E-4
63	Europium-152m	W, all compounds	3E+3	6E+3	3E-6	9E-9	4E-5	4E-4
63	Europium-152	W, all compounds	8E+2	2E+1	1E-8	3E-11	1E-5	1E-4
63	Europium-154	W, all compounds	5E+2	2E+1	8E-9	3E-11	7E-6	7E-5
63	Europium-155	W, all compounds	4E+3	9E+1	4E-8	-	5E-5	5E-4
			-	Bone surf (1E+2)	-	2E-10	-	-
63	Europium-156	W, all compounds	6E+2	5E+2	2E-7	6E-10	8E-6	8E-5
63	Europium-157	W, all compounds	2E+3	5E+3	2E-6	7E-9	3E-5	3E-4
63	Europium-1582	W, all compounds	2E+4	6E+4	2E-5	8E-8	3E-4	3E-3
64	Gadolinium-1452	D, all compounds except those given for W	5E+4	2E+5	6E-5	2E-7	-	-
			St wall
			(5E+4)	-	-	-	6E-4	6E-3
		W, oxides, hydroxides, and fluorides	-	2E+5	7E-5	2E-7	-	-
64	Gadolinium-146	D, see 145Gd	1E+3	1E+2	5E-8	2E-10	2E-5	2E-4
		W, see 145Gd	-	3E+2	1E-7	4E-10	-	-
64	Gadolinium-147	D, see 145Gd	2E+3	4E+3	2E-6	6E-9	3E-5	3E-4
		W, see 145Gd	-	4E+3	1E-6	5E-9	-	-
64	Gadolinium-148	D, see 145Gd	1E+1	8E+3	3E-12	-	-	-
			Bone surf (2E+1)	Bone surf (2E+2)	-	2E-14	3E-7	3E-6
		W, see 145Gd	-	3E-2	1E-11	-	-	-
			-	Bone surf (6E-2)	-	8E-14	-	-
64	Gadolinium-149	D, see 145Gd	3E+3	2E+3	9E-7	3E-9	4E-5	4E-4
		W, see 145Gd	-	2E+3	1E-6	3E-9	-	-
64	Gadolinium-151	D, see 145Gd	6E+3	4E+2	2E-7	-	9E-5	9E-4
			-	Bone surf (6E+2)	-	9E-10	-	-
		W, see 145Gd	-	1E+3	5E-7	2E-9	-	-
64	Gadolinium-152	D, see 145Gd	2E+1	1E-2	4E-12	-	-	-
			Bone surf (3E+1)	Bone surf (2E-2)	-	3E-14	4E-7	4E-6
		W, see 145Gd	-	4E-2	2E-11	-	-	-
			-	Bone surf (8E-2)	-	1E-13	-	-
64	Gadolinium-153	D, see 145Gd	5E+3	1E+2	6E-8	-	6E-5	6E-4
			-	Bone surf (2E+2)	-	3E-10	-	-
		W, see 145Gd	-	6E+2	2E-7	8E-10	-	-
64	Gadolinium-159	D, see 145Gd	3E+3	8E+3	3E-6	1E-8	4E-5	4E-4
		W, see 145Gd	-	6E+3	2E-6	8E-9	-	-
65	Terbium-1472	W, all compounds	9E+3	3E+4	1E-5	5E-8	1E-4	1E-3
65	Terbium-149	W, all compounds	5E+3	7E+2	3E-7	1E-9	7E-5	7E-4
65	Terbium-150	W, all compounds	5E+3	2E+4	9E-6	3E-8	7E-5	7E-4
65	Terbium-151	W, all compounds	4E+3	9E+3	4E-6	1E-8	5E-5	5E-4
65	Terbium-153	W, all compounds	5E+3	7E+3	3E-6	1E-8	7E-5	7E-4
65	Terbium-154	W, all compounds	2E+3	4E+3	2E-6	6E-9	2E-5	2E-4
65	Terbium-155	W, all compounds	6E+3	8E+3	3E-6	1E-8	8E-5	8E-4
65	Terbium-156m (5.0 h)	W, all compounds	2E+4	3E+4	1E-5	4E-8	2E-4	2E-3
65	Terbium-156m (24.4 h)	W, all compounds	7E+3	8E+3	3E-6	1E-8	1E-4	1E-3
65	Terbium-156	W, all compounds	1E+3	1E+3	6E-7	2E-9	1E-5	1E-4
65	Terbium-157	W, all compounds	5E+4	3E+2	1E-7	-	-	-
			LLI wall (5E+4)	Bone surf (6E+2)	-	8E-10	7E-4	7E-3
65	Terbium-158	W, all compounds	1E+3	2E+1	8E-9	3E-11	2E-5	2E-4
65	Terbium-160	W, all compounds	8E+2	2E+2	9E-8	3E-10	1E-5	1E-4
65	Terbium-161	W, all compounds	2E+3	2E+3	7E-7	2E-9	-	-
			LLI wall (2E+3)	-	-	-	3E-5	3E-4
66	Dysprosium-155	W, all compounds	9E+3	3E+4	1E-5	4E-8	1E-4	1E-3
66	Dysprosium-157	W, all compounds	2E+4	6E+4	3E-5	9E-8	3E-4	3E-3
66	Dysprosium-159	W, all compounds	1E+4	2E+3	1E-6	3E-9	2E-4	2E-3
66	Dysprosium-165	W, all compounds	1E+4	5E+4	2E-5	6E-8	2E-4	2E-3
66	Dysprosium-166	W, all compounds	6E+2	7E+2	3E-7	1E-9	-	-
			LLI wall (8E+2)	-	-	-	1E-5	1E-4
67	Holmium-1552	W, all compounds	4E+4	2E+5	6E-5	2E-7	6E-4	6E-3
67	Holmium-1572	W, all compounds	3E+5	1E+6	6E-4	2E-6	4E-3	4E-2
67	Holmium-1592	W, all compounds	2E+5	1E+6	4E-4	1E-6	3E-3	3E-2
67	Holmium-161	W, all compounds	1E+5	4E+5	2E-4	6E-7	1E-3	1E-2
67	Holmium-162m2	W, all compounds	5E+4	3E+5	1E-4	4E-7	7E-4	7E-3
67	Holmium-1622	W, all compounds	5E+5	2E+6	1E-3	3E-6	-	-
			St wall (8E+5)	-	-	-	1E-2	1E-1
67	Holmium-164m2	W, all compounds	1E+5	3E+5	1E-4	4E-7	1E-3	1E-2
67	Holmium-1642	W, all compounds	2E+5	6E+5	3E-4	9E-7	-	-
			St wall (2E+5)	-	-	-	3E-3	3E-2
67	Holmium-166m	W, all compounds	6E+2	7E+0	3E-9	9E-12	9E-6	9E-5
67	Holmium-166	W, all compounds	9E+2	2E+3	7E-7	2E-9	-	-
			LLI wall (9E+2)	-	-	-	1E-5	1E-4
67	Holmium-167	W, all compounds	2E+4	6E+4	2E-5	8E-8	2E-4	2E-3
68	Erbium-161	W, all compounds	2E+4	6E+4	3E-5	9E-8	2E-4	2E-3
68	Erbium-165	W, all compounds	6E+4	2E+5	8E-5	3E-7	9E-4	9E-3
68	Erbium-169	W, all compounds	3E+3	3E+3	1E-6	4E-9	-	-
			LLI wall (4E+3)	-	-	-	5E-5	5E-4
68	Erbium-171	W, all compounds	4E+3	1E+4	4E-6	1E-8	5E-5	5E-4
68	Erbium-172	W, all compounds	1E+3	1E+3	6E-7	2E-9	-	-
			LLI wall (E+3)	-	-	-	2E-5	2E-4
69	Thulium-1622	W, all compounds	7E+4	3E+5	1E-4	4E-7	-	-
			St wall (7E+4)	-	-	-	1E-3	1E-2
69	Thulium-166	W, all compounds	4E+3	1E+4	6E-6	2E-8	6E-5	6E-4
69	Thulium-167	W, all compounds	2E+3	2E+3	8E-7	3E-9	-	-
			LLI wall (2E+3)	-	-	-	3E-5	3E-4
69	Thulium-170	W, all compounds	8E+2	2E+2	9E-8	3E-10	-	-
			LLI wall (1E+3)	-	-	-	1E-5	1E-4
69	Thulium-171	W, all compounds	1E+4	3E+2	1E-7	-	-	-
			LLI wall (1E+4)	Bone surf (6E+2)	-	8E-10	2E-4	2E-3
69	Thulium-172	W, all compounds	7E+2	1E+3	5E-7	2E-9	-	-
			LLI wall (8E+2)	-	-	-	1E-5	1E-4
69	Thulium-173	W, all compounds	4E+3	1E+4	5E-6	2E-8	6E-5	6E-4
69	Thulium-1752	W, all compounds	7E+4	3E+5	1E-4	4E-7	-	-
			St wall (9E+4)	-	-	-	1E-3	1E-2
70	Ytterbium-1622	W, all compounds except those given for Y	7E+4	3E+5	1E-4	4E-7	1E-3	1E-2
		Y, oxides, hydroxides, and fluorides	-	3E+5	1E-4	4E-7	-	-
70	Ytterbium-166	W, see 162Yb	1E+3	2E+3	8E-7	3E-9	2E-5	2E-4
		Y, see 162Yb	-	2E+3	8E-7	3E-9	-	-
70	Ytterbium-1672	W, see 162Yb	3E+5	8E+5	3E-4	1E-6	4E-3	4E-2
		Y, see 162Yb	-	7E+5	3E-4	1E-6	-	-
70	Ytterbium-169	W, see 162Yb	2E+3	8E+2	4E-7	1E-9	2E-5	2E-4
		Y, see 162Yb	-	7E+2	3E-7	1E-9	-	-
70	Ytterbium-175	W, see 162Yb	3E+3	4E+3	1E-6	5E-9	-	-
			LLI wall (3E+3)	-	-	-	4E-5	4E-4
		Y, see 162Yb	-	3E+3	1E-6	5E-9	-	-
70	Ytterbium-1772	W, see 162Yb	2E+4	5E+4	2E-5	7E-8	2E-4	2E-3
		Y, see 162Yb	-	5E+4	2E-5	6E-8	-	-
70	Ytterbium-1782	W, see 162Yb	1E+4	4E+4	2E-5	6E-8	2E-4	2E-3
		Y, see 162Yb	-	4E+4	2E-5	5E-8	-	-
71	Lutetium-169	W, all compounds except those given for Y	3E+3	4E+3	2E-6	6E-9	3E-5	3E-4
		Y, oxides, hydroxides, and fluorides	-	4E+3	2E-6	6E-9	-	-
71	Lutetium-170	W, see 169Lu	1E+3	2E+3	9E-7	3E-9	2E-5	2E-4
		Y, see 169Lu	-	2E+3	8E-7	3E-9	-	-
71	Lutetium-171	W, see 169Lu	2E+3	2E+3	8E-7	3E-9	3E-5	3E-4
		Y, see 169Lu	-	2E+3	8E-7	3E-9	-	-
71	Lutetium-172	W, see 169Lu	1E+3	1E+3	5E-7	2E-9	1E-5	1E-4
		Y, see 169Lu	-	1E+3	5E-7	2E-9	-	-
71	Lutetium-173	W, see 169Lu	5E+3	3E+2	1E-7	-	7E-5	7E-4
			-	Bone surf (5E+2)	-	6E-10	-	-
		Y, see 169Lu	-	3E+2	1E-7	4E-10	-	-
71	Lutetium-174m	W, see 169Lu	2E+3	2E+2	1E-7	-	-	-
			LLI wall (3E+3)	Bone surf (3E+2)	-	5E-10	4E-5	4E-4
		Y, see 169Lu	-	2E+2	9E-8	3E-10	-	-
71	Lutetium-174	W, see 169Lu	5E+3	1E+2	5E-8	-	7E-5	7E-4
			-	Bone surf (2E+2)	-	3E-10	-	-
		Y, see 169Lu	-	2E+2	6E-8	2E-10	-	-
71	Lutetium-176m	W, see 169Lu	8E+3	3E+4	1E-5	3E-8	1E-4	1E-3
		Y, see 169Lu	-	2E+4	9E-6	3E-8	-	-
71	Lutetium-176	W, see 169Lu	7E+2	5E+0	2E-9	-	1E-5	1E-4
			-	Bone surf (1E+1)	-	2E-11	-	-
		Y, see 169Lu	-	8E+0	3E-9	1E-11	-	-
71	Lutetium-177m	W, see 169Lu	7E+2	1E+2	5E-8	-	1E-5	1E-4
			-	Bone surf (1E+2)	-	2E-10	-	-
		Y, see 169Lu	-	8E+1	3E-8	1E-10	-	-
71	Lutetium-177	W, see 169Lu	2E+3	2E+3	9E-7	3E-9	-	-
			LLI wall (3E+3)	-	-	-	4E-5	4E-4
		Y, see 169Lu	-	2E+3	9E-7	3E-9	-	-
71	Lutetium-178m2	W, see 169Lu	5E+4	2E+5	8E-5	3E-7	-	-
			St. wall (6E+4)	-	-	-	8E-4	8E-3
		Y, see 169Lu	-	2E+5	7E-5	2E-7	-	-
71	Lutetium-1782	W, see 169Lu	4E+4	1E+5	5E-5	2E-7	-	-
			St wall (4E+4)	-	-	-	6E-4	6E-3
		Y, see 169Lu	-	1E+5	5E-5	2E-7	-	-
71	Lutetium-179	W, see 169Lu	6E+3	2E+4	8E-6	3E-8	9E-5	9E-4
		Y, see 169Lu	-	2E+4	6E-6	3E-8	-	-
72	Hafnium-170	D, all compounds except those given for W	3E+3	6E+3	2E-6	8E-9	4E-5	4E-4
		W, oxides, hydroxides, carbides, and nitrates	-	5E+3	2E-6	6E-9	-	-
72	Hafnium-172	D, see 170Hf	1E+3	9E+0	4E-9	-	2E-5	2E-4
			-	Bone surf (2E+1)	-	3E-11	-	-
		W, see 170Hf	-	4E+1	2E-8	-	-	-
			-	Bone surf (6E+1)	-	8E-11	-	-
72	Hafnium-173	D, see 170Hf	5E+3	1E+4	5E-6	2E-8	7E-5	7E-4
		W, see 170Hf	-	1E+4	5E-6	2E-8	-	-
72	Hafnium-175	D, see 170Hf	3E+3	9E+2	4E-7	-	4E-5	4E-4
			-	Bone surf (1E+3)	-	1E-9	-	-
		W, see 170Hf	-	1E+3	5E-7	2E-9	-	-
72	Hafnium-177m2	D, see 170Hf	2E+4	6E+4	2E-5	8E-8	3E-4	3E-3
		W, see 170Hf	-	9E+4	4E-5	1E-7	-	-
72	Hafnium-178m	D, see 170Hf	3E+2	1E+0	5E-10	-	3E-6	3E-5
			-	Bone surf (2E+0)	-	3E-12	-	-
		W, see 170Hf	-	5E+0	2E-9	-	-	-
			-	Bone surf (9E+0)	-	1E-11	-	-
72	Hafnium-179m	D, see 170Hf	1E+3	3E+2	1E-7	-	1E-5	1E-4
			-	Bone surf (6E+2)	-	8E-10	-	-
		W, see 170Hf	-	6E+2	3E-7	8E-10	-	-
72	Hafnium-180m	D, see 170Hf	7E+3	2E+4	9E-6	3E-8	1E-4	1E-3
		W, see 170Hf	-	3E+4	1E-5	4E-8	-	-
72	Hafnium-181	D, see 170Hf	1E+3	2E+2	7E-8	-	2E-5	2E-4
			-	Bone surf (4E+2)	-	6E-10	-	-
		W, see 170Hf	-	4E+2	2E-7	6E-10	-	-
72	Hafnium-182m2	D, see 170Hf	4E+4	9E+4	4E-5	1E-7	5E-4	5E-3
		W, see 170Hf	-	1E+5	6E-5	2E-7	-	-
72	Hafnium-182	D, see 170Hf	2E+2	8E-1	3E-10	-	-	-
			Bone surf (4E+2)	Bone surf (2E+0)	-	2E-12	5E-6	5E-5
		W, see 170Hf	-	3E+0	1E-9	-	-	-
			-	Bone surf (7E+0)	-	1E-11	-	-
72	Hafnium-1832	D, see 170Hf	2E+4	5E+4	2E-5	6E-8	3E-4	3E-3
		W, see 170Hf	-	6E+4	2E-5	8E-8	-	-
72	Hafnium-184	D, see 170Hf	2E+3	8E+3	3E-6	1E-8	3E-5	3E-4
		W, see 170Hf	-	6E+3	3E-6	9E-9	-	-
73	Tantalum-1722	W, all compounds except those given for Y	4E+4	1E+5	5E-5	2E-7	5E-4	5E-3
		Y, elemental Ta, oxides, hydroxides, halides, carbides, nitrates, and nitrides	-	1E+5	4E-5	1E-7	-	-
73	Tantalum-173	W, see 172Ta	7E+3	2E+4	8E-6	3E-8	9E-5	9E-4
		Y, see 172Ta	-	2E+4	7E-6	2E-8	-	-
73	Tantalum-1742	W, see 172Ta	3E+4	1E+5	4E-5	1E-7	4E-4	4E-3
		Y, see 172Ta	-	9E+4	4E-5	1E-7	-	-
73	Tantalum-175	W, see 172Ta	6E+3	2E+4	7E-6	2E-8	8E-5	8E-4
		Y, see 172Ta	-	1E+4	6E-6	2E-8	-	-
73	Tantalum-176	W, see 172Ta	4E+3	1E+4	5E-6	2E-8	5E-5	5E-4
		Y, see 172Ta	-	1E+4	5E-6	2E-8	-	-
73	Tantalum-177	W, see 172Ta	1E+4	2E+4	8E-6	3E-8	2E-4	2E-3
		Y, see 172Ta	-	2E+4	7E-6	2E-8	-	-
73	Tantalum-178	W, see 172Ta	2E+4	9E+4	4E-5	1E-7	2E-4	2E-3
		Y, see 172Ta	-	7E+4	3E-5	1E-7	-	-
73	Tantalum-179	W, see 172Ta	2E+4	5E+3	2E-6	8E-9	3E-4	3E-3
		Y, see 172Ta	-	9E+2	4E-7	1E-9	-	-
73	Tantalum-180m	W, see 172Ta	2E+4	7E+4	3E-5	9E-8	3E-4	3E-3
		Y, see 172Ta	-	6E+4	2E-5	8E-8	-	-
73	Tantalum-180	W, see 172Ta	1E+3	4E+2	2E-7	6E-10	2E-5	2E-4
		Y, see 172Ta	-	2E+1	1E-8	3E-11	-	-
73	Tantalum-182m2	W, see 172Ta	2E+5	5E+5	2E-4	8E-7	-	-
			St wall (2E+5)	-	-	-	3E-3	3E-2
		Y, see 172Ta	-	4E+5	2E-4	6E-7	-	-
73	Tantalum-182	W, see 172Ta	8E+2	3E+2	1E-7	5E-10	1E-5	1E-4
		Y, see 172Ta	-	1E+2	6E-8	2E-10	-	-
73	Tantalum-183	W, see 172Ta	9E+2	1E+3	5E-7	2E-9	-	-
			LLI wall (1E+3)	-	-	-	2E-5	2E-4
		Y, see 172Ta	-	1E+3	4E-7	1E-9	-	-
73	Tantalum-184	W, see 172Ta	2E+3	5E+3	2E-6	8E-9	3E-5	3E-4
		Y, see 172Ta	-	5E+3	2E-6	7E-9	-	-
73	Tantalum-1852	W, see 172Ta	3E+4	7E+4	3E-5	1E-7	4E-4	4E-3
		Y, see 172Ta	-	6E+4	3E-5	9E-8	-	-
73	Tantalum-1862	W, see 172Ta	5E+4	2E+5	1E-4	3E-7	-	-
			St wall (7E+4)	-	-	-	1E-3	1E-2
		Y, see 172Ta	-	2E+5	9E-5	3E-7	-	-
74	Tungsten-176	D, all compounds	1E+4	5E+4	2E-5	7E-8	1E-4	1E-3
74	Tungsten-177	D, all compounds	2E+4	9E+4	4E-5	1E-7	3E-4	3E-3
74	Tungsten-178	D, all compounds	5E+3	2E+4	8E-6	3E-8	7E-5	7E-4
74	Tungsten-1792	D, all compounds	5E+5	2E+6	7E-4	2E-6	7E-3	7E-2
74	Tungsten-181	D, all compounds	2E+4	3E+4	1E-5	5E-8	2E-4	2E-3
74	Tungsten-185	D, all compounds	2E+3	7E+3	3E-6	9E-9	-	-
			LLI wall (3E+3)	-	-	-	4E-5	4E-4
74	Tungsten-187	D, all compounds	2E+3	9E+3	4E-6	1E-8	3E-5	3E-4
74	Tungsten-188	D, all compounds	4E+2	1E+3	5E-7	2E-9	-	-
			LLI wall (5E+2)	-	-	-	7E-6	7E-5
75	Rhenium-1772	D, all compounds except those given for W	9E+4	3E+5	1E-4	4E-7	-	-
			St wall (1E+5)	-	-	-	2E-3	2E-2
		W, oxides, hydroxides, and nitrates	-	4E+5	1E-4	5E-7	-	-
75	Rhenium-1782	D, see 177Re	7E+4	3E+5	1E-4	4E-7	-	-
			St wall (1E+5)	-	-	-	1E-3	1E-2
		W, see 177Re	-	3E+5	1E-4	4E-7	-	-
75	Rhenium-181	D, see 177Re	5E+3	9E+3	4E-6	1E-8	7E-5	7E-4
		W, see 177Re	-	9E+3	4E-6	1E-8	-	-
75	Rhenium-182	D, see 177Re	7E+3	1E+4	5E-6	2E-8	9E-5	9E-4
	(12.7 h)	W, see 177Re	-	2E+4	6E-6	2E-8	-	-
75	Rhenium-182	D, see 177Re	1E+3	2E+3	1E-6	3E-9	2E-5	2E-4
	(64.0 h)	W, see 177Re	-	2E+3	9E-7	3E-9	-	-
75	Rhenium-184m	D, see 177Re	2E+3	3E+3	1E-6	4E-9	3E-5	3E-4
		W, see 177Re	-	4E+2	2E-7	6E-10	-	-
75	Rhenium-184	D, see 177Re	2E+3	4E+3	1E-6	5E-9	3E-5	3E-4
		W, see 177Re	-	1E+3	6E-7	2E-9	-	-
75	Rhenium-186m	D, see 177Re	1E+3	2E+3	7E-7	-	-	-
			St wall (2E+3)	St wall (2E+3)	-	3E-9	2E-5	2E-4
		W, see 177Re	-	2E+2	6E-8	2E-10	-	-
75	Rhenium-186	D, see 177Re	2E+3	3E+3	1E-6	4E-9	3E-5	3E-4
		W, see 177Re	-	2E+3	7E-7	2E-9	-	-
75	Rhenium-187	D, see 177Re	6E+5	8E+5	4E-4	-	8E-3	8E-2
			-	St wall (9E+5)	-	1E-6	-	-
		W, see 177Re	-	1E+5	4E-5	1E-7	-	-
75	Rhenium-188m2	D, see 177Re	8E+4	1E+5	6E-5	2E-7	1E-3	1E-2
		W, see 177Re	-	1E+5	6E-5	2E-7	-	-
75	Rhenium-188	D, see 177Re	2E+3	3E+3	1E-6	4E-9	2E-5	2E-4
		W, see 177Re	-	3E+3	1E-6	4E-9	-	-
75	Rhenium-189	D, see 177Re	3E+3	5E+3	2E-6	7E-9	4E-5	4E-4
		W, see 177Re	-	4E+3	2E-6	6E-9	-	-
76	Osmium-1802	D, all compounds except those given for W and Y	1E+5	4E+5	2E-4	5E-7	1E-3	1E-2
		W, halides and nitrates	-	5E+5	2E-4	7E-7	-	-
		Y, oxides and hydroxides	-	5E+5	2E-4	6E-7	-	-
76	Osmium-1812	D, see 180Os	1E+4	4E+4	2E-5	6E-8	2E-4	2E-3
		W, see 180Os	-	5E+4	2E-5	6E-8	-	-
		Y, see 180Os	-	4E+4	2E-5	6E-8	-	-
76	Osmium-182	D, see 180Os	2E+3	6E+3	2E-6	8E-9	3E-5	3E-4
		W, see 180Os	-	4E+3	2E-6	6E-9	-	-
		Y, see 180Os	-	4E+3	2E-6	6E-9	-	-
76	Osmium-185	D, see 180Os	2E+3	5E+2	2E-7	7E-10	3E-5	3E-4
		W, see 180Os	-	8E+2	3E-7	1E-9	-	-
		Y, see 180Os	-	8E+2	3E-7	1E-9	-	-
76	Osmium-189m	D, see 180Os	8E+4	2E+5	1E-4	3E-7	1E-3	1E-2
		W, see 180Os	-	2E+5	9E-5	3E-7	-	-
		Y, see 180Os	-	2E+5	7E-5	2E-7	-	-
76	Osmium-191m	D, see 180Os	1E+4	3E+4	1E-5	4E-8	2E-4	2E-3
		W, see 180Os	-	2E+4	8E-6	3E-8	-	-
		Y, see 180Os	-	2E+4	7E-6	2E-8	-	-
76	Osmium-191	D, see 180Os	2E+3	2E+3	9E-7	3E-9	-	-
			LLI wall (3E+3)	-	-	-	3E-5	3E-4
		W, see 180Os	-	2E+3	7E-7	2E-9	-	-
		Y, see 180Os	-	1E+3	6E-7	2E-9	-	-
76	Osmium-193	D, see 180Os	2E+3	5E+3	2E-6	6E-9	-	-
			LLI wall (2E+3)	-	-	-	2E-5	2E-4
		W, see 180Os	-	3E+3	1E-6	4E-9	-	-
		Y, see 180Os	-	3E+3	1E-6	4E-9	-	-
76	Osmium-194	D, see 180Os	4E+2	4E+1	2E-8	6E-11	-	-
			LLI wall (6E+2)	-	-	-	8E-6	8E-5
		W, see 180Os	-	6E+1	2E-8	8E-11	-	-
		Y, see 180Os	-	8E+0	3E-9	1E-11	-	-
77	Iridium-1822	D, all compounds except those given for W and Y	4E+4	1E+5	6E-5	2E-7	-	-
			St wall (4E+4)	-	-	-	6E-4	6E-3
		W, halides, nitrates, and metallic iridium	-	2E+5	6E-5	2E-7	-	-
		Y, oxides and hydroxides	-	1E+5	5E-5	2E-7	-	-
77	Iridium-184	D, see 182Ir	8E+3	2E+4	1E-5	3E-8	1E-4	1E-3
		W, see 182Ir	-	3E+4	1E-5	5E-8	-	-
		Y, see 182Ir	-	3E+4	1E-5	4E-8	-	-
77	Iridium-185	D, see 182Ir	5E+3	1E+4	5E-6	2E-8	7E-5	7E-4
		W, see 182Ir	-	1E+4	5E-6	2E-8	-	-
		Y, see 182Ir	-	1E+4	4E-6	1E-8	-	-
77	Iridium-186	D, see 182Ir	2E+3	8E+3	3E-6	1E-8	3E-5	3E-4
		W, see 182Ir	-	6E+3	3E-6	9E-9	-	-
		Y, see 182Ir	-	6E+3	2E-6	8E-9	-	-
77	Iridium-187	D, see 182Ir	1E+4	3E+4	1E-5	5E-8	1E-4	1E-3
		W, see 182Ir	-	3E+4	1E-5	4E-8	-	-
		Y, see 182Ir	-	3E+4	1E-5	4E-8	-	-
77	Iridium-188	D, see 182Ir	2E+3	5E+3	2E-6	6E-9	3E-5	3E-4
		W, see 182Ir	-	4E+3	1E-6	5E-9	-	-
		Y, see 182Ir	-	3E+3	1E-6	5E-9	-	-
77	Iridium-189	D, see 182Ir	5E+3	5E+3	2E-6	7E-9	-	-
			LLI wall (5E+3)	-	-	-	7E-5	7E-4
		W, see 182Ir	-	4E+3	2E-6	5E-9	-	-
		Y, see 182Ir	-	4E+3	1E-6	5E-9	-	-
77	Iridium-190m2	D, see 182Ir	2E+5	2E+5	8E-5	3E-7	2E-3	2E-2
		W, see 182Ir	-	2E+5	9E-5	3E-7	-	-
		Y, see 182Ir	-	2E+5	8E-5	3E-7	-	-
77	Iridium-190	D, see 182Ir	1E+3	9E+2	4E-7	1E-9	1E-5	1E-4
		W, see 182Ir	-	1E+3	4E-7	1E-9	-	-
		Y, see 182Ir	-	9E+2	4E-7	1E-9	-	-
77	Iridium-192m	D, see 182Ir	3E+3	9E+1	4E-8	1E-10	4E-5	4E-4
		W, see 182Ir	-	2E+2	9E-8	3E-10	-	-
		Y, see 182Ir	-	2E+1	6E-9	2E-11	-	-
77	Iridium-192	D, see 182Ir	9E+2	3E+2	1E-7	4E-10	1E-5	1E-4
		W, see 182Ir	-	4E+2	2E-7	6E-10	-	-
		Y, see 182Ir	-	2E+2	9E-8	3E-10	-	-
77	Iridium-194m	D, see 182Ir	6E+2	9E+1	4E-8	1E-10	9E-6	9E-5
		W, see 182Ir	-	2E+2	7E-8	2E-10	-	-
		Y, see 182Ir	-	1E+2	4E-8	1E-10	-	-
77	Iridium-194	D, see 182Ir	1E+3	3E+3	1E-6	4E-9	1E-5	1E-4
		W, see 182Ir	-	2E+3	9E-7	3E-9	-	-
		Y, see 182Ir	-	2E+3	8E-7	3E-9	-	-
77	Iridium-195m	D, see 182Ir	8E+3	2E+4	1E-5	3E-8	1E-4	1E-3
		W, see 182Ir	-	3E+4	1E-5	4E-8	-	-
		Y, see 182Ir	-	2E+4	9E-6	3E-8	-	-
77	Iridium-195	D, see 182Ir	1E+4	4E+4	2E-5	6E-8	2E-4	2E-3
		W, see 182Ir	-	5E+4	2E-5	7E-8	-	-
		Y, see 182Ir	-	4E+4	2E-5	6E-8	-	-
78	Platinum-186	D, all compounds	1E+4	4E+4	2E-5	5E-8	2E-4	2E-3
78	Platinum-188	D, all compounds	2E+3	2E+3	7E-7	2E-9	2E-5	2E-4
78	Platinum-189	D, all compounds	1E+4	3E+4	1E-5	4E-8	1E-4	1E-3
78	Platinum-191	D, all compounds	4E+3	8E+3	4E-6	1E-8	5E-5	5E-4
78	Platinum-193m	D, all compounds	3E+3	6E+3	3E-6	8E-9	-	-
			LLI wall (3E+4)	-	-	-	4E-5	4E-4
78	Platinum-193	D, all compounds	4E+4	2E+4	1E-5	3E-8	-	-
			LLI wall (5E+4)	-	-	-	6E-4	6E-3
78	Platinum-195m	D, all compounds	2E+3	4E+3	2E-6	6E-9	-	-
			LLI wall (2E+3)	-	-	-	3E-5	3E-4
78	Platinum-197m2	D, all compounds	2E+4	4E+4	2E-5	6E-8	2E-4	2E-3
78	Platinum-197	D, all compounds	3E+3	1E+4	4E-6	1E-8	4E-5	4E-4
78	Platinum-1992	D, all compounds	5E+4	1E+5	6E-5	2E-7	7E-4	7E-3
78	Platinum-200	D, all compounds	1E+3	3E+3	1E-6	5E-9	2E-5	2E-4
79	Gold-193	D, all compounds except those given for W and Y	9E+3	3E+4	1E-5	4E-8	1E-4	1E-3
		W, halides and nitrates	-	2E+4	9E-6	3E-8	-	-
		Y, oxides and hydroxides	-	2E+4	8E-6	3E-8	-	-
79	Gold-194	D, see 193Au	3E+3	8E+3	3E-6	1E-8	4E-5	4E-4
		W, see 193Au	-	5E+3	2E-6	8E-9	-	-
		Y, see 193Au	-	5E+3	2E-6	7E-9	-	-
79	Gold-195	D, see 193Au	5E+3	1E+4	5E-6	2E-8	7E-5	7E-4
		W, see 193Au	-	1E+3	6E-7	2E-9	-	-
		Y, see 193Au	-	4E+2	2E-7	6E-10	-	-
79	Gold-198m	D, see 193Au	1E+3	3E+3	1E-6	4E-9	1E-5	1E-4
		W, see 193Au	-	1E+3	5E-7	2E-9	-	-
		Y, see 193Au	-	1E+3	5E-7	2E-9	-	-
79	Gold-198	D, see 193Au	1E+3	4E+3	2E-6	5E-9	2E-5	2E-4
		W, see 193Au	-	2E+3	8E-7	3E-9	-	-
		Y, see 193Au	-	2E+3	7E-7	2E-9	-	-
79	Gold-199	D, see 193Au	3E+3	9E+3	4E-6	1E-8	-	-
			LLI wall (3E+3)	-	-	-	4E-5	4E-4
		W, see 193Au	-	4E+3	2E-6	6E-9	-	-
		Y, see 193Au	-	4E+3	2E-6	5E-9	-	-
79	Gold-200m	D, see 193Au	1E+3	4E+3	1E-6	5E-9	2E-5	2E-4
		W, see 193Au	-	3E+3	1E-6	4E-9	-	-
		Y, see 193Au	-	2E+4	1E-6	3E-9	-	-
79	Gold-2002	D, see 193Au	3E+4	6E+4	3E-5	9E-8	4E-4	4E-3
		W, see 193Au	-	8E+4	3E-5	1E-7	-	-
		Y, see 193Au	-	7E+4	3E-5	1E-7	-	-
79	Gold-2012	D, see 193Au	7E+4	2E+5	9E-5	3E-7	-	-
			St wall (9E+4)	-	-	-	1E-3	1E-2
		W, see 193Au	-	2E+5	1E-4	3E-7	-	-
		Y, see 193Au	-	2E+5	9E-5	3E-7	-	-
80	Mercury-193m	Vapor	-	8E+3	4E-6	1E-8	-	-
		Organic D	4E+3	1E+4	5E-6	2E-8	6E-5	6E-4
		D, sulfates	3E+3	9E+3	4E-6	1E-8	4E-5	4E-4
		W, oxides, hydroxides, halides, nitrates, and sulfides	-	8E+3	3E-6	1E-8	-	-
80	Mercury-193	Vapor	-	3E+4	1E-5	4E-8	-	-
		Organic D	2E+4	6E+4	3E-5	9E-8	3E-4	3E-3
		D, see 193mHg	2E+4	4E+4	2E-5	6E-8	2E-4	2E-3
		W, see 193mHg	-	4E+4	2E-5	6E-8	-	-
80	Mercury-194	Vapor	-	3E+1	1E-8	4E-11	-	-
		Organic D	2E+1	3E+1	1E-8	4E-11	2E-7	2E-6
		D, see 193mHg	8E+2	4E+1	2E-8	6E-11	1E-5	1E-4
		W, see 193mHg	-	1E+2	5E-8	2E-10	-	-
80	Mercury-195m	Vapor	-	4E+3	2E-6	6E-9	-	-
		Organic D	3E+3	6E+3	3E-6	8E-9	4E-5	4E-4
		D, see 193mHg	2E+3	5E+3	2E-6	7E-9	3E-5	3E-4
		W, see 193mHg	-	4E+3	2E-6	5E-9	-	-
80	Mercury-195	Vapor	-	3E+4	1E-5	4E-8	-	-
		Organic D	2E+4	5E+4	2E-5	6E-8	2E-4	2E-3
		D, see 193mHg	1E+4	4E+4	1E-5	5E-8	2E-4	2E-3
		W, see 193mHg	-	3E+4	1E-5	5E-8	-	-
80	Mercury-197m	Vapor	-	5E+3	2E-6	7E-9	-	-
		Organic D	4E+3	9E+3	4E-6	1E-8	5E-5	5E-4
		D, see 193mHg	3E+3	7E+3	3E-6	1E-8	4E-5	4E-4
		W, see 193mHg	-	5E+3	2E-6	7E-9	-	-
80	Mercury-197	Vapor	-	8E+3	4E-6	1E-8	-	-
		Organic D	7E+3	1E+4	6E-6	2E-8	9E-5	9E-4
		D, see 193mHg	6E+3	1E+4	5E-6	2E-8	8E-5	8E-4
		W, see 193mHg	-	9E+3	4E-6	1E-8	-	-
80	Mercury-199m2	Vapor	-	8E+4	3E-5	1E-7	-	-
		Organic D	6E+4	2E+5	7E-5	2E-7	-	-
			St wall (1E+5)	-	-	-	1E-3	1E-2
		D, see 193mHg	6E+4	1E+5	6E-5	2E-7	8E-4	8E-3
		W, see 193mHg	-	2E+5	7E-5	2E-7	-	-
80	Mercury-203	Vapor	-	8E+2	4E-7	1E-9	-	-
		Organic D	5E+2	8E+2	3E-7	1E-9	7E-6	7E-5
		D, see 193mHg	2E+3	1E+3	5E-7	2E-9	3E-5	3E-4
		W, see 193mHg	-	1E+3	5E-7	2E-9	-	-
81	Thallium-194m2	D, all compounds	5E+4	2E+5	6E-5	2E-7	-	-
			St wall (7E+4)	-	-	-	1E-3	1E-2
81	Thallium-1942	D, all compounds	3E+5	6E+5	2E-4	8E-7	-	-
			St wall (3E+5)	-	-	-	4E-3	4E-2
81	Thallium-1952	D, all compounds	6E+4	1E+5	5E-5	2E-7	9E-4	9E-3
81	Thallium-197	D, all compounds	7E+4	1E+5	5E-5	2E-7	1E-3	1E-2
81	Thallium-198m2	D, all compounds	3E+4	5E+4	2E-5	8E-8	4E-4	4E-3
81	Thallium-198	D, all compounds	2E+4	3E+4	1E-5	5E-8	3E-4	3E-3
81	Thallium-199	D, all compounds	6E+4	8E+4	4E-5	1E-7	9E-4	9E-3
81	Thallium-200	D, all compounds	8E+3	1E+4	5E-6	2E-8	1E-4	1E-3
81	Thallium-201	D, all compounds	2E+4	2E+4	9E-6	3E-8	2E-4	2E-3
81	Thallium-202	D, all compounds	4E+3	5E+3	2E-6	7E-9	5E-5	5E-4
81	Thallium-204	D, all compounds	2E+3	2E+3	9E-7	3E-9	2E-5	2E-4
82	Lead-195m2	D, all compounds	6E+4	2E+5	8E-5	3E-7	8E-4	8E-3
82	Lead-198	D, all compounds	3E+4	6E+4	3E-5	9E-8	4E-4	4E-3
82	Lead-1992	D, all compounds	2E+4	7E+4	3E-5	1E-7	3E-4	3E-3
82	Lead-200	D, all compounds	3E+3	6E+3	3E-6	9E-9	4E-5	4E-4
82	Lead-201	D, all compounds	7E+3	2E+4	8E-6	3E-8	1E-4	1E-3
82	Lead-202m	D, all compounds	9E+3	3E+4	1E-5	4E-8	1E-4	1E-3
82	Lead-202	D, all compounds	1E+2	5E+1	2E-8	7E-11	2E-6	2E-5
82	Lead-203	D, all compounds	5E+3	9E+3	4E-6	1E-8	7E-5	7E-4
82	Lead-205	D, all compounds	4E+3	1E+3	6E-7	2E-9	5E-5	5E-4
82	Lead-209	D, all compounds	2E+4	6E+4	2E-5	8E-8	3E-4	3E-3
82	Lead-210	D, all compounds	6E-1	2E-1	1E-10	-	-	-
			Bone surf (1E+0)	Bone surf (4E-1)	-	6E-13	1E-8	1E-7
82	Lead-2112	D, all compounds	1E+4	6E+2	3E-7	9E-10	2E-4	2E-3
82	Lead-212	D, all compounds	8E+1	3E+1	1E-8	5E-11	-	-
			Bone surf (1E+2)	-	-	-	2E-6	2E-5
82	Lead-2142	D, all compounds	9E+3	8E+2	3E-7	1E-9	1E-4	1E-3
83	Bismuth-2002	D, nitrates	3E+4	8E+4	4E-5	1E-7	4E-4	4E-3
		W, all other compounds	-	1E+5	4E-5	1E-7	-	-
83	Bismuth-2012	D, see 200Bi	1E+4	3E+4	1E-5	4E-8	2E-4	2E-3
		W, see 200Bi	-	4E+4	2E-5	5E-8	-	-
83	Bismuth-2022	D, see 200Bi	1E+4	4E+4	2E-5	6E-8	2E-4	2E-3
		W, see 200Bi	-	8E+4	3E-5	1E-7	-	-
83	Bismuth-203	D, see 200Bi	2E+3	7E+3	3E-6	9E-9	3E-5	3E-4
		W, see 200Bi	-	6E+3	3E-6	9E-9	-	-
83	Bismuth-205	D, see 200Bi	1E+3	3E+3	1E-6	3E-9	2E-5	2E-4
		W, see 200Bi	-	1E+3	5E-7	2E-9	-	-
83	Bismuth-206	D, see 200Bi	6E+2	1E+3	6E-7	2E-9	9E-6	9E-5
		W, see 200Bi	-	9E+2	4E-7	1E-9	-	-
83	Bismuth-207	D, see 200Bi	1E+3	2E+3	7E-7	2E-9	1E-5	1E-4
		W, see 200Bi	-	4E+2	1E-7	5E-10	-	-
83	Bismuth-210m	D, see 200Bi	4E+1	5E+0	2E-9	-	-	-
			Kidneys (6E+1)	Kidneys (6E+0)	-	9E-12	8E-7	8E-6
		W, see 200Bi	-	7E-1	3E-10	9E-13	-	-
83	Bismuth-210	D, see 200Bi	8E+2	2E+2	1E-7	-	1E-5	1E-4
			- -	Kidneys (4E+2)	-	5E-10	-	-
		W, see 200Bi	-	3E+1	1E-8	4E-11	-	-
83	Bismuth-2122	D, see 200Bi	5E+3	2E+2	1E-7	3E-10	7E-5	7E-4
		W, see 200Bi	-	3E+2	1E-7	4E-10	-	-
83	Bismuth-2132	D, see 200Bi	7E+3	3E+2	1E-7	4E-10	1E-4	1E-3
		W, see 200Bi	-	4E+2	1E-7	5E-10	-	-
83	Bismuth-2142	D, see 200Bi	2E+4	8E+2	3E-7	1E-9	-	-
			St wall (2E+4)	-	-	-	3E-4	3E-3
		W, see 200Bi	-	9E-2	4E-7	1E-9	-	-
84	Polonium-2032	D, all compounds except those given for W	3E+4	6E+4	3E-5	9E-8	3E-4	3E-3
		W, oxides, hydroxides, and nitrates	-	9E+4	4E-5	1E-7	-	-
84	Polonium-2052	D, see 203Po	2E+4	4E+4	2E-5	5E-8	3E-4	3E-3
		W, see 203Po	-	7E+4	3E-5	1E-7	-	-
84	Polonium-207	D, see 203Po	8E+3	3E+4	1E-5	3E-8	1E-4	1E-3
		W, see 203Po	-	3E+4	1E-5	4E-8	-	-
84	Polonium-210	D, see 203Po	3E+0	6E-1	3E-10	9E-13	4E-8	4E-7
		W, see 203Po	-	6E-1	3E-10	9E-13	-	-
85	Astatine-2072	D, halides	6E+3	3E+3	1E-6	4E-9	8E-5	8E-4
		W	-	2E+3	9E-7	3E-9	-	-
85	Astatine-211	D, halides	1E+2	8E+1	3E-8	1E-10	2E-6	2E-5
		W	-	5E+1	2E-8	8E-11	-	-
86	Radon-220	With daughters removed	-	2E+4	7E-6	2E-8	-	-
		With daughters present	-	2E+1	9E-9	3E-11	-	-
				(or 12 working level months)		(or 1.0 working level)
86	Radon-222	With daughters removed	-	1E+4	4E-6	1E-8	-	-
		With daughters present	-	1E+2	3E-8	1E-10	-	-
				(or 4 working level months)		(or 0.33 working level)
87	Francium-2222	D, all compounds	2E+3	5E+2	2E-7	6E-10	3E-5	3E-4
87	Francium-2232	D, all compounds	6E+2	8E+2	3E-7	1E-9	8E-6	8E-5
88	Radium-223	W, all compounds	5E+0	7E-1	3E-10	9E-13	-	-
			Bone surf (9E+0)	-	-	-	1E-7	1E-6
88	Radium-224	W, all compounds	8E+0	2E+0	7E-10	2E-12	-	-
			Bone surf (2E+1)	-	-	-	2E-7	2E-6
88	Radium-225	W, all compounds	8E+0	7E-1	3E-10	9E-13	-	-
			Bone surf (2E+1)	-	-	-	2E-7	2E-6
88	Radium-226	W, all compounds	2E+0	6E-1	3E-10	9E-13	-	-
			Bone surf (5E+0)	-	-	-	6E-8	6E-7
88	Radium-2272	W, all compounds	2E+4	1E+4	6E-6	-	-	-
			Bone surf (2E+4)	Bone surf (2E+4)	-	3E-8	3E-4	3E-3
88	Radium-228	W, all compounds	2E+0	1E+0	5E-10	2E-12	-	-
			Bone surf (4E+0)	-	-	-	6E-8	6E-7
89	Actinium-224	D, all compounds except those given for W and Y	2E+3	3E+1	1E-8	-	-	-
			LLI wall (2E+3)	Bone surf (4E+1)	-	5E-11	3E-5	3E-4
		W, halides and nitrates	-	5E+1	2E-8	7E-11	-	-
		Y, oxides and hydroxides	-	5E+1	2E-8	6E-11	-	-
89	Actinium-225	D, see 224Ac	5E+1	3E-1	1E-10	-	-	-
			LLI wall (5E+1)	Bone surf (5E-1)	-	7E-13	7E-7	7E-6
		W, see 224Ac	-	6E-1	3E-10	9E-13	-	-
		Y, see 224Ac	-	6E-1	3E-10	9E-13	-	-
89	Actinium-226	D, see 224Ac	1E+2	3E+0	1E-9	-	-	-
			LLI wall (1E+2)	Bone surf (4E+0)	-	5E-12	2E-6	2E-5
		W, see 224Ac	-	5E+0	2E-9	7E-12	-	-
		Y, see 224Ac	-	5E+0	2E-9	6E-12	-	-
89	Actinium-227	D, see 224Ac	2E-1	4E-4	2E-13	-	-	-
			Bone surf (4E-1)	Bone surf (8E-4)	-	1E-15	5E-9	5E-8
		W, see 224Ac	-	2E-3	7E-13	-	-	-
			-	Bone surf (3E-3)	-	4E-15	-	-
		Y, see 224Ac	-	4E-3	2E-12	6E-15	-	-
89	Actinium-228	D, see 224Ac	2E+3	9E+0	4E-9	-	3E-5	3E-4
			-	Bone surf (2E+1)	-	2E-11	-	-
		W, see 224Ac	-	4E+1	2E-8	-	-	-
				Bone surf
			-	(6E+1)	-	8E-11	-	-
		Y, see 224Ac	-	4E+1	2E-8	6E-11	-	-
90	Thorium-2262	W, all compounds except those given for Y	5E+3	2E+2	6E-8	2E-10	-	-
			St wall
			(5E+3)	-	-	-	7E-5	7E-4
		Y, oxides and hydroxides	-	1E+2	6E-8	2E-10	-	-
90	Thorium-227	W, see 226Th	1E+2	3E-1	1E-10	5E-13	2E-6	2E-5
		Y, see 226Th	-	3E-1	1E-10	5E-13	-	-
90	Thorium-228	W, see 226Th	6E+0	1E-2	4E-12	-	-	-
			Bone surf (1E+1)	Bone surf (2E-2)	-	3E-14	2E-7	2E-6
		Y, see 226Th	-	2E-2	7E-12	2E-14	-	-
90	Thorium-229	W, see 226Th	6E-1	9E-4	4E-13	-	-	-
			Bone surf (1E+0)	Bone surf (2E-3)	-	3E-15	2E-8	2E-7
		Y, see 226Th	-	2E-3	1E-12	-	-	-
			-	Bone surf (3E-3)	-	4E-15	-	-
90	Thorium-230	W, see 226Th	4E+0	6E-3	3E-12	-	-	-
			Bone surf (9E+0)	Bone surf (2E-2)	-	2E-14	1E-7	1E-6
		Y, see 226Th	-	2E-2	6E-12	-	-	-
			-	Bone surf (2E-2)	-	3E-14	-	-
90	Thorium-231	W, see 226Th	4E+3	6E+3	3E-6	9E-9	5E-5	5E-4
		Y, see 226Th	-	6E+3	3E-6	9E-9	-	-
90	Thorium-232	W, see 226Th	7E-1	1E-3	5E-13	-	-	-
			Bone surf (2E+0)	Bone surf (3E-3)	-	4E-15	3E-8	3E-7
		Y, see 226Th	-	3E-3	1E-12	-	-	-
			-	Bone surf (4E-3)	-	6E-15	-	-
90	Thorium-234	W, see 226Th	3E+2	2E+2	8E-8	3E-10	-	-
			LLI wall (4E+2)	-	-	-	5E-6	5E-5
		Y, see 226Th	-	2E+2	6E-8	2E-10	-	-
91	Protactinium-2272	W, all compounds except those given for Y	4E+3	1E+2	5E-8	2E-10	5E-5	5E-4
		Y, oxides and hydroxides	-	1E+2	4E-8	1E-10	-	-
91	Protactinium-228	W, see 227Pa	1E+3	1E+1	5E-9	-	2E-5	2E-4
			-	Bone surf (2E+1)	-	3E-11	-	-
		Y, see 227Pa	-	1E+1	5E-9	2E-11	-	-
91	Protactinium-230	W, see 227Pa	6E+2	5E+0	2E-9	7E-12	-	-
			Bone surf (9E+2)	-	-	-	1E-5	1E-4
		Y, see 227Pa	-	4E+0	1E-9	5E-12	-	-
91	Protactinium-231	W, see 227Pa	2E-1	2E-3	6E-13	-	-	-
			Bone surf (5E-1)	Bone surf (4E-3)	-	6E-15	6E-9	6E-8
		Y, see 227Pa	-	4E-3	2E-12	-	-	-
			-	Bone surf (6E-3)	-	8E-15	-	-
91	Protactinium-232	W, see 227Pa	1E+3	2E+1	9E-9	-	2E-5	2E-4
			-	Bone surf (6E+1)	-	8E-11	-	-
		Y, see 227Pa	-	6E+1	2E-8	-	-	-
			-	Bone surf (7E+1)	-	1E-10	-	-
91	Protactinium-233	W, see 227Pa	1E+3	7E+2	3E-7	1E-9	-	-
			LLI wall (2E+3)	-	-	-	2E-5	2E-4
		Y, see 227Pa	-	6E+2	2E-7	8E-10	-	-
91	Protactinium-234	W, see 227Pa	2E+3	8E+3	3E-6	1E-8	3E-5	3E-4
		Y, see 227Pa	-	7E+3	3E-6	9E-9	-	-
92	Uranium-230	D, UF6, UO2F2, UO2(NO3)2	4E+0	4E-1	2E-10	-	-	-
			Bone surf (6E+0)	Bone surf (6E-1)	-	8E-13	8E-8	8E-7
		W, UO3, UF4, UCl4	-	4E-1	1E-10	5E-13	-	-
		Y, UO2, U3O8	-	3E-1	1E-10	4E-13	-	-
92	Uranium-231	D, see 230U	5E+3	8E+3	3E-6	1E-8	-	-
			LLI wall (4E+3)	-	-	-	6E-5	6E-4
		W, see 230U	-	6E+3	2E-6	8E-9	-	-
		Y, see 230U	-	5E+3	2E-6	6E-9	-	-
92	Uranium-232	D, see 230U	2E+0	2E-1	9E-11	-	-	-
			Bone surf (4E+0)	Bone surf (4E-1)	-	6E-13	6E-8	6E-7
		W, see 230U	-	4E-1	2E-10	5E-13	-	-
		Y, see 230U	-	8E-3	3E-12	1E-14	-	-
92	Uranium-233	D, see 230U	1E+1	1E+0	5E-10	-	-	-
			Bone surf (2E+1)	Bone surf (2E+0)	-	3E-12	3E-7	3E-6
		W, see 230U	-	7E-1	3E-10	1E-12	-	-
		Y, see 230U	-	4E-2	2E-11	5E-14	-	-
92	Uranium-2343	D, see 230U	1E+1	1E+0	5E-10	-	-	-
			Bone surf (2E+1)	Bone surf (2E+0)	-	3E-12	3E-7	3E-6
		W, see 230U	-	7E-1	3E-10	1E-12	-	-
		Y, see 230U	-	4E-2	2E-11	5E-14	-	-
92	Uranium-2353	D, see 230U	1E+1	1E+0	6E-10	-	-	-
			Bone surf (2E+1)	Bone surf (2E+0)	-	3E-12	3E-7	3E-6
		W, see 230U	-	8E-1	3E-10	1E-12	-	-
		Y, see 230U	-	4E-2	2E-11	6E-14	-	-
92	Uranium-236	D, see 230U	1E+1	1E+0	5E-10	-	-	-
			Bone surf (2E+1)	Bone surf (2E+0)	-	3E-12	3E-7	3E-6
		W, see 230U	-	8E-1	3E-10	1E-12	-	-
		Y, see 230U	-	4E-2	2E-11	6E-14	-	-
92	Uranium-237	D, see 230U	2E+3	3E+3	1E-6	4E-9	-	-
			LLI wall (2E+3)	-	-	-	3E-5	3E-4
		W, see 230U	-	2E+3	7E-7	2E-9	-	-
		Y, see 230U	-	2E+3	6E-7	2E-9	-	-
92	Uranium-2383	D, see 230U	1E+1	1E+0	6E-10	-	-	-
			Bone surf (2E+1)	Bone surf (2E+0)	-	3E-12	3E-7	3E-6
		W, see 230U	-	8E-1	3E-10	1E-12	-	-
		Y, see 230U	-	4E-2	2E-11	6E-14	-	-
92	Uranium-2392	D, see 230U	7E+4	2E+5	8E-5	3E-7	9E-4	9E-3
		W, see 230U	-	2E+5	7E-5	2E-7	-	-
		Y, see 230U	-	2E+5	6E-5	2E-7	-	-
92	Uranium-240	D, see 230U	1E+3	4E+3	2E-6	5E-9	2E-5	2E-4
		W, see 230U	-	3E+3	1E-6	4E-9	-	-
		Y, see 230U	-	2E+3	1E-6	3E-9	-	-
92	Uranium-natural3	D, see 230U	1E+1	1E+0	5E-10	-	-	-
			Bone surf (2E+1)	Bone surf (2E+0)	-	3E-12	3E-7	3E-6
		W, see 230U	-	8E-1	3E-10	9E-13	-	-
		Y, see 230U	-	5E-2	2E-11	9E-14	-	-
93	Neptunium-2322	W, all compounds	1E+5	2E+3	7E-7	-	2E-3	2E-2
			-	Bone surf (5E+2)	-	6E-9	-	-
93	Neptunium-2332	W, all compounds	8E+5	3E+6	1E-3	4E-6	1E-2	1E-1
93	Neptunium-234	W, all compounds	2E+3	3E+3	1E-6	4E-9	3E-5	3E-4
93	Neptunium-235	W, all compounds	2E+4	8E+2	3E-7	-	-	-
			LLI wall (2E+4)	Bone surf (1E+3)	-	2E-9	3E-4	3E-3
93	Neptunium-236	W, all compounds	3E+0	2E-2	9E-12	-	-	-
	(1.15E+5 y)		Bone surf (6E+0)	Bone surf (5E-2)	-	8E-14	9E-8	9E-7
93	Neptunium-236	W, all compounds	3E+3	3E+1	1E-8	-	-	-
	(22.5 h)		Bone surf (4E+3)	Bone surf (7E+1)	-	1E-10	5E-5	5E-4
93	Neptunium-237	W, all compounds	5E-1	4E-3	2E-12	-	-	-
			Bone surf (1E+0)	Bone surf (1E-2)	-	1E-14	2E-8	2E-7
93	Neptunium-238	W, all compounds	1E+3	6E+1	3E-8	-	2E-5	2E-4
			-	Bone surf (2E+2)	-	2E-10	-	-
93	Neptunium-239	W, all compounds	2E+3	2E+3	9E-7	3E-9	-	-
			LLI wall (2E+3)	-	-	-	2E-5	2E-4
93	Neptunium-2402	W, all compounds	2E+4	8E+4	3E-5	1E-7	3E-4	3E-3
94	Plutonium-234	W, all compounds except PuO2	8E+3	2E+2	9E-8	3E-10	1E-4	1E-3
		Y, PuO2	-	2E+2	8E-8	3E-10	-	-
94	Plutonium-2352	W, see 234Pu	9E+5	3E+6	1E-3	4E-6	1E-2	1E-1
		Y, see 234Pu	-	3E+6	1E-3	3E-6	-	-
94	Plutonium-236	W, see 234Pu	2E+0	2E-2	8E-12	-	-	-
			Bone surf (4E+0)	Bone surf (4E-2)	-	5E-14	6E-8	6E-7
		Y, see 234Pu	-	4E-2	2E-11	6E-14	-	-
94	Plutonium-237	W, see 234Pu	1E+4	3E+3	1E-6	5E-9	2E-4	2E-3
		Y, see 234Pu	-	3E+3	1E-6	4E-9	-	-
94	Plutonium-238	W, see 234Pu	9E-1	7E-3	3E-12	-	-	-
			Bone surf (2E+0)	Bone surf (1E-2)	-	2E-14	2E-8	2E-7
		Y, see 234Pu	-	2E-2	8E-12	2E-14	-	-
94	Plutonium-239	W, see 234Pu	8E-1	6E-3	3E-12	-	-	-
			Bone surf (1E+0)	Bone surf (1E-2)	-	2E-14	2E-8	2E-7
		Y, see 234Pu	-	2E-2	7E-12	-	-	-
			-	Bone surf (2E-2)	-	2E-14	-	-
94	Plutonium-240	W, see 234Pu	8E-1	6E-3	3E-12	-	-	-
			Bone surf (1E+0)	Bone surf (1E-2)	-	2E-14	2E-8	2E-7
		Y, see 234Pu	-	2E-2	7E-12	-	-	-
			-	Bone surf (2E-2)	-	2E-14	-	-
94	Plutonium-241	W, see 234Pu	4E+1	3E-1	1E-10	-	-	-
			Bone surf (7E+1)	Bone surf (6E-1)	-	8E-13	1E-6	1E-5
		Y, see 234Pu	-	8E-1	3E-10	-	-	-
			-	Bone surf (1E+0)	-	1E-12	-	-
94	Plutonium-242	W, see 234Pu	8E-1	7E-3	3E-12	-	-	-
			Bone surf (1E+0)	Bone surf (1E-2)	-	2E-14	2E-8	2E-7
		Y, see 234Pu	-	2E-2	7E-12	-	-	-
			-	Bone surf (2E-2)	-	2E-14	-	-
94	Plutonium-243	W, see 234Pu	2E+4	4E+4	2E-5	5E-8	2E-4	2E-3
		Y, see 234Pu	-	4E+4	2E-5	5E-8	-	-
94	Plutonium-244	W, see 234Pu	8E-1	7E-3	3E-12	-	-	-
			Bone surf (2E+0)	Bone surf (1E-2)	-	2E-14	2E-8	2E-7
		Y, see 234Pu	-	2E-2	7E-12	-	-	-
			-	Bone surf (2E-2)	-	2E-14	-	-
94	Plutonium-245	W, see 234Pu	2E+3	5E+3	2E-6	6E-9	3E-5	3E-4
		Y, see 234Pu	-	4E+3	2E-6	6E-9	-	-
94	Plutonium-246	W, see 234Pu	4E+2	3E+2	1E-7	4E-10	-	-
			LLI wall (4E+2)	-	-	-	6E-6	6E-5
		Y, see 234Pu	-	3E+2	1E-7	4E-10	-	-
95	Americium-2372	W, all compounds	8E+4	3E+5	1E-4	4E-7	1E-3	1E-2
95	Americium-2382	W, all compounds	4E+4	3E+3	1E-6	-	5E-4	5E-3
			-	Bone surf (6E+3)	-	9E-9	-	-
95	Americium-239	W, all compounds	5E+3	1E+4	5E-6	2E-8	7E-5	7E-4
95	Americium-240	W, all compounds	2E+3	3E+3	1E-6	4E-9	3E-5	3E-4
95	Americium-241	W, all compounds	8E-1	6E-3	3E-12	-	-	-
			Bone surf (1E+0)	Bone surf (1E-2)	-	2E-14	2E-8	2E-7
95	Americium-242m	W, all compounds	8E-1	6E-3	3E-12	-	-	-
			Bone surf (1E+0)	Bone surf (1E-2)	-	2E-14	2E-8	2E-7
95	Americium-242	W, all compounds	4E+3	8E+1	4E-8	-	5E-5	5E-4
			-	Bone surf (9E+1)	-	1E-10	-	-
95	Americium-243	W, all compounds	8E-1	6E-3	3E-12	-	-	-
			Bone surf (1E+0)	Bone surf (1E-2)	-	2E-14	2E-8	2E-7
95	Americium-244m2	W, all compounds	6E+4	4E+3	2E-6	-	-	-
			St wall (8E+4)	Bone surf (7E+3)	-	1E-8	1E-3	1E-2
95	Americium-244	W, all compounds	3E+3	2E+2	8E-8	-	4E-5	4E-4
			-	Bone surf (3E+2)	-	4E-10	-	-
95	Americium-245	W, all compounds	3E+4	8E+4	3E-5	1E-7	4E-4	4E-3
95	Americium-246m2	W, all compounds	5E+4	2E+5	8E-5	3E-7	-	-
			St wall (6E+4)	-	-	-	8E-4	8E-3
95	Americium-2462	W, all compounds	3E+4	1E+5	4E-5	1E-7	4E-4	4E-3
96	Curium-238	W, all compounds	2E+4	1E+3	5E-7	2E-9	2E-4	2E-3
96	Curium-240	W, all compounds	6E+1	6E-1	2E-10	-	-	-
			Bone surf (8E+1)	Bone surf (6E-1)	-	9E-13	1E-6	1E-5
96	Curium-241	W, all compounds	1E+3	3E+1	1E-8	-	2E-5	2E-4
			-	Bone surf (4E+1)	-	5E-11	-	-
96	Curium-242	W, all compounds	3E+1	3E-1	1E-10	-	-	-
			Bone surf (5E+1)	Bone surf (3E-1)	-	4E-13	7E-7	7E-6
96	Curium-243	W, all compounds	1E+0	9E-3	4E-12	-	-	-
			Bone surf (2E+0)	Bone surf (2E-2)	-	2E-14	3E-8	3E-7
96	Curium-244	W, all compounds	1E+0	1E-2	5E-12	-	-	-
			Bone surf (3E+0)	Bone surf (2E-2)	-	3E-14	3E-8	3E-7
96	Curium-245	W, all compounds	7E-1	6E-3	3E-12	-	-	-
			Bone surf (1E+0)	Bone surf (1E-2)	-	2E-14	2E-8	2E-7
96	Curium-246	W, all compounds	7E-1	6E-3	3E-12	-	-	-
			Bone surf (1E+0)	Bone surf (1E-2)	-	2E-14	2E-8	2E-7
96	Curium-247	W, all compounds	8E-1	6E-3	3E-12	-	-	-
			Bone surf (1E+0)	Bone surf (1E-2)	-	2E-14	2E-8	2E-7
96	Curium-248	W, all compounds	2E-1	2E-3	7E-13	-	-	-
			Bone surf (4E-1)	Bone surf (3E-3)	-	4E-15	5E-9	5E-8
96	Curium-2492	W, all compounds	5E+4	2E+4	7E-6	-	7E-4	7E-3
			-	Bone surf (3E+4)	-	4E-8	-	-
96	Curium-250	W, all compounds	4E-2	3E-4	1E-13	-	-	-
			Bone surf (6E-2)	Bone surf (5E-4)	-	8E-16	9E-10	9E-9
97	Berkelium-245	W, all compounds	2E+3	1E+3	5E-7	2E-9	3E-5	3E-4
97	Berkelium-246	W, all compounds	3E+3	3E+3	1E-6	4E-9	4E-5	4E-4
97	Berkelium-247	W, all compounds	5E-1	4E-3	2E-12	-	-	-
			Bone surf (1E+0)	Bone surf (9E-3)	-	1E-14	2E-8	2E-7
97	Berkelium-249	W, all compounds	2E+2	2E+0	7E-10	-	-	-
			Bone surf (5E+2)	Bone surf (4E+0)	-	5E-12	6E-6	6E-5
97	Berkelium-250	W, all compounds	9E+3	3E+2	1E-7	-	1E-4	1E-3
			-	Bone surf (7E+2)	-	1E-9	-	-
98	Californium-2442	W, all compounds except those given for Y	3E+4	6E+2	2E-7	8E-10	-	-
			St wall (3E+4)	-	-	-	4E-4	4E-3
		Y, oxides and hydroxides	-	6E+2	2E-7	8E-10	-	-
98	Californium-246	W, see 244Cf	4E+2	9E+0	4E-9	1E-11	5E-6	5E-5
		Y, see 244Cf	-	9E+0	4E-9	1E-11	-	-
98	Californium-248	W, see 244Cf	8E+0	6E-2	3E-11	-	-	-
			Bone surf (2E+1)	Bone surf (1E-1)	-	2E-13	2E-7	2E-6
		Y, see 244Cf	-	1E-1	4E-11	1E-13	-	-
98	Californium-249	W, see 244Cf	5E-1	4E-3	2E-12	-	-	-
			Bone surf (1E+0)	Bone surf (9E-3)	-	1E-14	2E-8	2E-7
		Y, see 244Cf	-	1E-2	4E-12	-	-	-
			-	Bone surf (1E-2)	-	2E-14	-	-
98	Californium-250	W, see 244Cf	1E+0	9E-3	4E-12	-	-	-
			Bone surf (2E+0)	Bone surf (2E-2)	-	3E-14	3E-8	3E-7
		Y, see 244Cf	-	3E-2	1E-11	4E-14	-	-
98	Californium-251	W, see 244Cf	5E-1	4E-3	2E-12	-	-	-
			Bone surf (1E+0)	Bone surf (9E-3)	-	1E-14	2E-8	2E-7
		Y, see 244Cf	-	1E-2	4E-12	-	-	-
			-	Bone surf (1E-2)	-	2E-14	-	-
98	Californium-252	W, see 244Cf	2E+0	2E-2	8E-12	-	-	-
			Bone surf (5E+0)	Bone surf (4E-2)	-	5E-14	7E-8	7E-7
		Y, see 244Cf	-	3E-2	1E-11	5E-14	-	-
98	Californium-253	W, see 244Cf	2E+2	2E+0	8E-10	3E-12	-	-
			Bone surf (4E+2)	-	-	-	5E-6	5E-5
		Y, see 244Cf	-	2E+0	7E-10	2E-12	-	-
98	Californium-254	W, see 244Cf	2E+0	2E-2	9E-12	3E-14	3E-8	3E-7
		Y, see 244Cf	-	2E-2	7E-12	2E-14	-	-
99	Einsteinium-250	W, all compounds	4E+4	5E+2	2E-7	-	6E-4	6E-3
			-	Bone surf (1E+3)	-	2E-9	-	-
99	Einsteinium-251	W, all compounds	7E+3	9E+2	4E-7	-	1E-4	1E-3
			-	Bone surf (1E+3)	-	2E-9	-	-
99	Einsteinium-253	W, all compounds	2E+2	1E+0	6E-10	2E-12	2E-6	2E-5
99	Einsteinium-254m	W, all compounds	3E+2	1E+1	4E-9	1E-11	-	-
			LLI wall (3E+2)	-	-	-	4E-6	4E-5
99	Einsteinium-254	W, all compounds	8E+0	7E-2	3E-11	-	-	-
			Bone surf (2E+1)	Bone surf (1E-1)	-	2E-13	2E-7	2E-6
100	Fermium-252	W, all compounds	5E+2	1E+1	5E-9	2E-11	6E-6	6E-5
100	Fermium-253	W, all compounds	1E+3	1E+1	4E-9	1E-11	1E-5	1E-4
100	Fermium-254	W, all compounds	3E+3	9E+1	4E-8	1E-10	4E-5	4E-4
100	Fermium-255	W, all compounds	5E+2	2E+1	9E-9	3E-11	7E-6	7E-5
100	Fermium-257	W, all compounds	2E+1	2E-1	7E-11	-	-	-
			Bone surf (4E+1)	Bone surf (2E-1)	-	3E-13	5E-7	5E-6
101	Mendelevium-257	W, all compounds	7E+3	8E+1	4E-8	-	1E-4	1E-3
			-	Bone surf (9E+1)	-	1E-10	-	-
101	Mendelevium-258	W, all compounds	3E+1	2E-1	1E-10	-	-	-
			Bone surf (5E+1)	Bone surf (3E-1)	-	5E-13	6E-7	6E-6
-	Any single radionuclide not listed above with decay mode other than alpha emission or spontaneous fission and with radioactive half-life less than two hours	Submersion1	-	2E+2	1E-7	1E-9	-	-
-	Any single radionuclide not listed above with decay mode other than alpha emission or spontaneous fission and with radioactive half-life greater than two 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:

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

2These radionuclides have radiological half-lives of less than two 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 five, the concentration value for a 40-hour workweek is 0.2 milligrams uranium per cubic meter of air average. For any enrichment, the product of the average concentration and time of exposure during a 40-hour workweek shall not exceed 8E-3 (SA) µCi-hr/ml, where SA is the specific activity of the uranium inhaled. The specific activity for natural uranium is 6.77E-7 curies per gram U. The specific activity for other mixtures of U-238, U-235, and U-234, if not known, shall be:

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

SA = [0.4 + 0.38 (enrichment) + 0.0034 (enrichment)2] E-6, enrichment ≥ 0.72 where enrichment is the percentage by weight of U-235, expressed as percent.

NOTE:

1. If the identity of each radionuclide in a mixture is known but the concentration of one or more of the radionuclides in the mixture is not known, the DAC for the mixture shall be the most restrictive DAC of any radionuclide in the mixture.

2. If the identity of each radionuclide in the mixture is not known, but it is known that certain radionuclides specified in this appendix are not present in the mixture, the inhalation ALI, DAC, and effluent and sewage concentrations for the mixture are the lowest values specified in this appendix for any radionuclide that is not known to be absent from the mixture; or

If it is known that Ac-227-D and Cm-250-W are not present	-	7E-4	3E-13	-	-	-
If, in addition, it is known that Ac-227-W,Y, Th-229-W,Y, Th-230-W, Th-232-W,Y, Pa-231-W,Y, Np-237-W, Pu-239-W, Pu-240-W, Pu-242-W, Am-241-W, Am-242m-W, Am-243-W, Cm-245-W, Cm-246-W, Cm-247-W, Cm-248-W, Bk-247-W, Cf-249-W, and Cf-251-W are not present	-	7E-3	3E-12	-	-	-
If, in addition, it is known that Sm-146-W, Sm-147-W, Gd-148-D,W, Gd-152-D,W, Th-228-W,Y, Th-230-Y, U-232-Y, U-233-Y, U-234-Y, U-235-Y, U-236-Y, U-238-Y, Np-236-W, Pu-236-W,Y, Pu-238-W,Y, Pu-239-Y, Pu-240-Y, Pu-242-Y, Pu-244-W,Y, Cm-243-W, Cm-244-W, Cf-248-W, Cf-249-Y, Cf-250-W,Y, Cf-251-Y, Cf-252-W,Y, and Cf-254-W,Y are not present	-	7E-2	3E-11	-	-	-
If, in addition, it is known that Pb-210-D, Bi-210m-W, Po-210-D,W, Ra-223-W, Ra-225-W, Ra-226-W, Ac-225-D,W,Y, Th-227-W,Y, U-230-D,W,Y, U-232-D,W, Pu-241-W, Cm-240-W, Cm-242-W, Cf-248-Y, Es-254-W, Fm-257-W, and Md-258-W are not present	-	7E-1	3E-10	-	-	-
If, in addition, it is known that Si-32-Y, Ti-44-Y, Fe-60-D, Sr-90-Y, Zr-93-D, Cd-113m-D, Cd-113-D, In-115-D,W, La-138-D, Lu-176-W, Hf-178m-D,W, Hf-182-D,W, Bi-210m-D, Ra-224-W, Ra-228-W, Ac-226-D,W,Y, Pa-230-W,Y, U-233-D,W, U-234-D,W, U-235-D,W, U-236-D,W, U-238-D,W, Pu-241-Y, Bk-249-W, Cf-253-W,Y, and Es-253-W are not present	-	7E+0	3E-9	-	-	-
If it is known that Ac-227-D,W,Y, Th-229-W,Y, Th-232-W,Y, Pa-231-W,Y, Cm-248-W, and Cm-250-W are not present	-	-	-	1E-14	-	-
If, in addition, it is known that Sm-146-W, Gd-148-D,W, Gd-152-D, Th-228-W,Y, Th-230-W,Y, U-232-Y, U-233-Y, U-234-Y, U-235-Y, U-236-Y, U-238-Y, U-Nat-Y, Np-236-W, Np-237-W, Pu-236-W,Y, Pu-238-W,Y, Pu-239-W,Y, Pu-240-W,Y, Pu-242-W,Y, Pu-244-W,Y, Am-241-W, Am-242m-W, Am-243-W, Cm-243-W, Cm-244-W, Cm-245-W, Cm-246-W, Cm-247-W, Bk-247-W, Cf-249-W,Y, Cf-250-W,Y, Cf-251-W,Y, Cf-252-W,Y, and Cf-254-W,Y are not present	-	-	-	1E-13	-	-
If, in addition, it is known that Sm-147-W, Gd-152-W, Pb-210-D, Bi-210m-W, Po-210-D,W, Ra-223-W, Ra-225-W, Ra-226-W, Ac-225-D,W,Y, Th-227-W,Y, U-230-D,W,Y, U-232-D,W, U-Nat-W, Pu-241-W, Cm-240-W, Cm-242-W, Cf-248-W,Y, Es-254-W, Fm-257-W, and Md-258-W are not present	-	-	-	-	1E-12	-
If, in addition, it is known that Fe-60, Sr-90, Cd-113m, Cd-113, In-115, I-129, Cs-134, Sm-145, Sm-147, Gd-148, Gd-152, Hg-194 (organic), Bi-210m, Ra-223, Ra-224, Ra-225, Ac-225, Th-228, Th-230, U-233, U-234, U-235, U-236, U-238, U-Nat, Cm-242, Cf-248, Es-254, Fm-257, and Md-258 are not present	-	-	-	-	1E-6	1E-5
3. If a mixture of radionuclides consists of uranium and its daughters in ore dust (10 µm AMAD particle distribution assumed) prior to chemical separation of the uranium from the ore, the following values may be used for the DAC of the mixture: 6E-11 µCi of gross alpha activity from uranium-238, uranium-234, thorium-230, and radium-226 per milliliter of air; 3E-11 µCi of natural uranium per milliliter of air; or 45 micrograms of natural uranium per cubic meter of air. 4. If the identity and concentration of each radionuclide in a mixture are known, the limiting values should be derived as follows: Determine, for each radionuclide in the mixture, the ratio between the concentration present in the mixture and the concentration otherwise established in this section for the specific radionuclide when not in a mixture. The sum of such ratios for all of the radionuclides in the mixture may not exceed "1" (i.e., "unity"). Example: If radionuclides "A," "B," and "C" are present in concentrations CA, CB, and CC, and if the applicable DACs are DACA, DACB, and DACC, respectively, then the concentrations shall be limited so that the following relationship exists:

	CA	+	CB	+	CC	≤1
	DACA		DACB		DACC

[Statutory Authority: RCW 70A.388.040 and 70A.388.110. WSR 23-21-056, § 246-221-290, filed 10/11/23, effective 11/11/23. Statutory Authority: RCW 70.98.050. WSR 11-03-068, § 246-221-290, filed 1/18/11, effective 2/18/11. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 09-06-003, § 246-221-290, filed 2/18/09, effective 3/21/09. Statutory Authority: RCW 70.98.050. WSR 94-01-073, § 246-221-290, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 43.70 040. WSR 91-02-049 (Order 121), recodified as § 246-221-290, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-24-220, filed 12/8/80; Order 1095, § 402-24-220, filed 2/6/76; Order 1, § 402-24-220, filed 1/8/69; Rules (part), filed 10/26/66.]

Reviser's note: The brackets and enclosed material in the text of the above section occurred in the copy filed by the agency.

PDF246-221-300

Appendix B—Minimum quantities of radioactive material requiring labeling.

Minimum Quantities1 of Radioactive

Material Requiring Labeling

Radionuclide	Quantity*(µCi)
Actinium-224		1
Actinium-225		0.01
Actinium-226		0.1
Actinium-227		0.001
Actinium-228		1
Aluminum-26		10
Americium-237		1,000
Americium-238		100
Americium-239		1,000
Americium-240		100
Americium-241		0.001
Americium-242		10
Americium-242m		0.001
Americium-243		0.001
Americium-244		10
Americium-244m		100
Americium-245		1,000
Americium-246		1,000
Americium-246m		1,000
Antimony-115		1,000
Antimony-116		1,000
Antimony-116m		1,000
Antimony-117		1,000
Antimony-118m		1,000
Antimony-119		1,000
Antimony-120 (16min)		1,000
Antimony-120 (5.76d)		100
Antimony-122		100
Antimony-124		10
Antimony-124m		1,000
Antimony-125		100
Antimony-126		100
Antimony-126m		1,000
Antimony-127		100
Antimony-128 (9.01h)		100
Antimony-128 (10.4min)		1,000
Antimony-129		100
Antimony-130		1,000
Antimony-131		1,000
Argon-39		1,000
Argon-41		1,000
Arsenic-69		1,000
Arsenic-70		1,000
Arsenic-71		100
Arsenic-72		100
Arsenic-73		100
Arsenic-74		100
Arsenic-76		100
Arsenic-77		100
Arsenic-78		1,000
Astatine-207		100
Astatine-211		10
Barium-126		1,000
Barium-128		100
Barium-131		100
Barium-131m		1,000
Barium-133		100
Barium-133m		100
Barium-135m		100
Barium-139		1,000
Barium-140		100
Barium-141		1,000
Barium-142		1,000
Berkelium-245		100
Berkelium-246		100
Berkelium-247		0.001
Berkelium-249		0.1
Berkelium-250		10
Beryllium-7		1,000
Beryllium-10		1
Bismuth-200		1,000
Bismuth-201		1,000
Bismuth-202		1,000
Bismuth-203		100
Bismuth-205		100
Bismuth-206		100
Bismuth-207		10
Bismuth-210		1
Bismuth-210m		0.1
Bismuth-212		10
Bismuth-213		10
Bismuth-214		100
Bromine-74		1,000
Bromine-74m		1,000
Bromine-75		1,000
Bromine-76		100
Bromine-77		1,000
Bromine-80		1,000
Bromine-80m		1,000
Bromine-82		100
Bromine-83		1,000
Bromine-84		1,000
Cadmium-104		1,000
Cadmium-107		1,000
Cadmium-109		1
Cadmium-113		100
Cadmium-113m		0.1
Cadmium-115		100
Cadmium-115m		10
Cadmium-117		1,000
Cadmium-117m		1,000
Calcium-41		100
Calcium-45		100
Calcium-47		100
Californium-244		100
Californium-246		1
Californium-248		0.01
Californium-249		0.001
Californium-250		0.001
Californium-251		0.001
Californium-252		0.001
Californium-253		0.1
Californium-254		0.001
Carbon-11		1,000
Carbon-14		1,000
Cerium-134		100
Cerium-135		100
Cerium-137		1,000
Cerium-137m		100
Cerium-139		100
Cerium-141		100
Cerium-143		100
Cerium-144		1
Cesium-125		1,000
Cesium-127		1,000
Cesium-129		1,000
Cesium-130		1,000
Cesium-131		1,000
Cesium-132		100
Cesium-134		10
Cesium-134m		1,000
Cesium-135		100
Cesium-135m		1,000
Cesium-136		10
Cesium-137		10
Cesium-138		1,000
Chlorine-36		10
Chlorine-38		1,000
Chlorine-39		1,000
Chromium-48		1,000
Chromium-49		1,000
Chromium-51		1,000
Cobalt-55		100
Cobalt-56		10
Cobalt-57		100
Cobalt-58		100
Cobalt-58m		1,000
Cobalt-60		1
Cobalt-60m		1,000
Cobalt-61		1,000
Cobalt-62m		1,000
Copper-60		1,000
Copper-61		1,000
Copper-64		1,000
Copper-67		1,000
Curium-238		100
Curium-240		0.1
Curium-241		1
Curium-242		0.01
Curium-243		0.001
Curium-244		0.001
Curium-245		0.001
Curium-246		0.001
Curium-247		0.001
Curium-248		0.001
Curium-249		1,000
Dysprosium-155		1,000
Dysprosium-157		1,000
Dysprosium-159		100
Dysprosium-165		1,000
Dysprosium-166		100
Einsteinium-250		100
Einsteinium-251		100
Einsteinium-253		0.1
Einsteinium-254		0.01
Einsteinium-254m		1
Erbium-161		1,000
Erbium-165		1,000
Erbium-169		100
Erbium-171		100
Erbium-172		100
Europium-145		100
Europium-146		100
Europium-147		100
Europium-148		10
Europium-149		100
Europium-150 (12.62h)		100
Europium-150 (34.2y)		1
Europium-152		1
Europium-152m		100
Europium-154		1
Europium-155		10
Europium-156		100
Europium-157		100
Europium-158		1,000
Fermium-252		1
Fermium-253		1
Fermium-254		10
Fermium-255		1
Fermium-257		0.01
Fluorine-18		1,000
Francium-222		100
Francium-223		100
Gadolinium-145		1,000
Gadolinium-146		10
Gadolinium-147		100
Gadolinium-148		0.001
Gadolinium-149		100
Gadolinium-151		10
Gadolinium-152		100
Gadolinium-153		10
Gadolinium-159		100
Gallium-65		1,000
Gallium-66		100
Gallium-67		1,000
Gallium-68		1,000
Gallium-70		1,000
Gallium-72		100
Gallium-73		1,000
Germanium-66		1,000
Germanium-67		1,000
Germanium-68		10
Germanium-69		1,000
Germanium-71		1,000
Germanium-75		1,000
Germanium-77		1,000
Germanium-78		1,000
Gold-193		1,000
Gold-194		100
Gold-195		10
Gold-198		100
Gold-198m		100
Gold-199		100
Gold-200		1,000
Gold-200m		100
Gold-201		1,000
Hafnium-170		100
Hafnium-172		1
Hafnium-173		1,000
Hafnium-175		100
Hafnium-177m		1,000
Hafnium-178m		0.1
Hafnium-179m		10
Hafnium-180m		1,000
Hafnium-181		10
Hafnium-182		0.1
Hafnium-182m		1,000
Hafnium-183		1,000
Hafnium-184		100
Holmium-155		1,000
Holmium-157		1,000
Holmium-159		1,000
Holmium-161		1,000
Holmium-162		1,000
Holmium-162m		1,000
Holmium-164		1,000
Holmium-164m		1,000
Holmium-166		100
Holmium-166m		1
Holmium-167		1,000
Hydrogen-3		1,000
Indium-109		1,000
Indium-110 (4.9h)		1,000
Indium-110m (69.1min)		1,000
Indium-111		100
Indium-112		1,000
Indium-113m		1,000
Indium-114m		10
Indium-115		100
Indium-115m		1,000
Indium-116m		1,000
Indium-117		1,000
Indium-117m		1,000
Indium-119m		1,000
Iodine-120		100
Iodine-120m		1,000
Iodine-121		1,000
Iodine-123		100
Iodine-124		10
Iodine-125		1
Iodine-126		1
Iodine-128		1,000
Iodine-129		1
Iodine-130		10
Iodine-131		1
Iodine-132		100
Iodine-132m		100
Iodine-133		10
Iodine-134		1,000
Iodine-135		100
Iridium-182		1,000
Iridium-184		1,000
Iridium-185		1,000
Iridium-186		100
Iridium-187		1,000
Iridium-188		100
Iridium-189		100
Iridium-190		100
Iridium-190m		1,000
Iridium-192 (73.8d)		1
Iridium-192m (1.4min)		10
Iridium-194		100
Iridium-194m		10
Iridium-195		1,000
Iridium-195m		1,000
Iron-52		100
Iron-55		100
Iron-59		10
Iron-60		1
Krypton-74		1,000
Krypton-76		1,000
Krypton-77		1,000
Krypton-79		1,000
Krypton-81		1,000
Krypton-83m		1,000
Krypton-85		1,000
Krypton-85m		1,000
Krypton-87		1,000
Krypton-88		1,000
Lanthanum-131		1,000
Lanthanum-132		100
Lanthanum-135		1,000
Lanthanum-137		10
Lanthanum-138		100
Lanthanum-140		100
Lanthanum-141		100
Lanthanum-142		1,000
Lanthanum-143		1,000
Lead-195m		1,000
Lead-198		1,000
Lead-199		1,000
Lead-200		100
Lead-201		1,000
Lead-202		10
Lead-202m		1,000
Lead-203		1,000
Lead-205		100
Lead-209		1,000
Lead-210		0.01
Lead-211		100
Lead-212		1
Lead-214		100
Lutetium-169		100
Lutetium-170		100
Lutetium-171		100
Lutetium-172		100
Lutetium-173		10
Lutetium-174		10
Lutetium-174m		10
Lutetium-176		100
Lutetium-176m		1,000
Lutetium-177		100
Lutetium-177m		10
Lutetium-178		1,000
Lutetium-178m		1,000
Lutetium-179		1,000
Magnesium-28		100
Manganese-51		1,000
Manganese-52		100
Manganese-52m		1,000
Manganese-53		1,000
Manganese-54		100
Manganese-56		1,000
Mendelevium-257		10
Mendelevium-258		0.01
Mercury-193		1,000
Mercury-193m		100
Mercury-194		1
Mercury-195		1,000
Mercury-195m		100
Mercury-197		1,000
Mercury-197m		100
Mercury-199m		1,000
Mercury-203		100
Molybdenum-90		100
Molybdenum-93		10
Molybdenum-93m		100
Molybdenum-99		100
Molybdenum-101		1,000
Neodymium-136		1,000
Neodymium-138		100
Neodymium-139		1,000
Neodymium-139m		1,000
Neodymium-141		1,000
Neodymium-147		100
Neodymium-149		1,000
Neodymium-151		1,000
Neptunium-232		100
Neptunium-233		1,000
Neptunium-234		100
Neptunium-235		100
Neptunium-236 (1.15E+5y)		0.001
Neptunium-236 (22.5h)		1
Neptunium-237		0.001
Neptunium-238		10
Neptunium-239		100
Neptunium-240		1,000
Nickel-56		100
Nickel-57		100
Nickel-59		100
Nickel-63		100
Nickel-65		1,000
Nickel-66		10
Niobium-88		1,000
Niobium-89 (122min)		1,000
Niobium-89m (66min)		1,000
Niobium-90		100
Niobium-93m		10
Niobium-94		1
Niobium-95		100
Niobium-95m		100
Niobium-96		100
Niobium-97		1,000
Niobium-98		1,000
Osmium-180		1,000
Osmium-181		1,000
Osmium-182		100
Osmium-185		100
Osmium-189m		1,000
Osmium-191		100
Osmium-191m		1,000
Osmium-193		100
Osmium-194		1
Palladium-100		100
Palladium-101		1,000
Palladium-103		100
Palladium-107		10
Palladium-109		100
Phosphorus-32		10
Phosphorus-33		100
Platinum-186		1,000
Platinum-188		100
Platinum-189		1,000
Platinum-191		100
Platinum-193		1,000
Platinum-193m		100
Platinum-195m		100
Platinum-197		100
Platinum-197m		1,000
Platinum-199		1,000
Platinum-200		100
Plutonium-234		10
Plutonium-235		1,000
Plutonium-236		0.001
Plutonium-237		100
Plutonium-238		0.001
Plutonium-239		0.001
Plutonium-240		0.001
Plutonium-241		0.01
Plutonium-242		0.001
Plutonium-243		1,000
Plutonium-244		0.001
Plutonium-245		100
Polonium-203		1,000
Polonium-205		1,000
Polonium-207		1,000
Polonium-210		0.1
Potassium-40		100
Potassium-42		1,000
Potassium-43		1,000
Potassium-44		1,000
Potassium-45		1,000
Praseodymium-136		1,000
Praseodymium-137		1,000
Praseodymium-138m		1,000
Praseodymium-139		1,000
Praseodymium-142		100
Praseodymium-142m		1,000
Praseodymium-143		100
Praseodymium-144		1,000
Praseodymium-145		100
Praseodymium-147		1,000
Promethium-141		1,000
Promethium-143		100
Promethium-144		10
Promethium-145		10
Promethium-146		1
Promethium-147		10
Promethium-148		10
Promethium-148m		10
Promethium-149		100
Promethium-150		1,000
Promethium-151		100
Protactinium-227		10
Protactinium-228		1
Protactinium-230		0.1
Protactinium-231		0.001
Protactinium-232		1
Protactinium-233		100
Protactinium-234		100
Radium-223		0.1
Radium-224		0.1
Radium-225		0.1
Radium-226		0.1
Radium-227		1,000
Radium-228		0.1
Radon-220		1
Radon-222		1
Rhenium-177		1,000
Rhenium-178		1,000
Rhenium-181		1,000
Rhenium-182 (64.0h)		100
Rhenium-182 (12.7h)		1,000
Rhenium-184		100
Rhenium-184m		10
Rhenium-186		100
Rhenium-186m		10
Rhenium-187		1,000
Rhenium-188		100
Rhenium-188m		1,000
Rhenium-189		100
Rhodium-99		100
Rhodium-99m		1,000
Rhodium-100		100
Rhodium-101		10
Rhodium-101m		1,000
Rhodium-102		10
Rhodium-102m		10
Rhodium-103m		1,000
Rhodium-105		100
Rhodium-106m		1,000
Rhodium-107		1,000
Rubidium-79		1,000
Rubidium-81		1,000
Rubidium-81m		1,000
Rubidium-82m		1,000
Rubidium-83		100
Rubidium-84		100
Rubidium-86		100
Rubidium-87		100
Rubidium-88		1,000
Rubidium-89		1,000
Ruthenium-94		1,000
Ruthenium-97		1,000
Ruthenium-103		100
Ruthenium-105		1,000
Ruthenium-106		1
Samarium-141		1,000
Samarium-141m		1,000
Samarium-142		1,000
Samarium-145		100
Samarium-146		1
Samarium-147		100
Samarium-151		10
Samarium-153		100
Samarium-155		1,000
Samarium-156		1,000
Scandium-43		1,000
Scandium-44		100
Scandium-44m		100
Scandium-46		10
Scandium-47		100
Scandium-48		100
Scandium-49		1,000
Selenium-70		1,000
Selenium-73		100
Selenium-73m		1,000
Selenium-75		100
Selenium-79		100
Selenium-81		1,000
Selenium-81m		1,000
Selenium-83		1,000
Silicon-31		1,000
Silicon-32		1
Silver-102		1,000
Silver-103		1,000
Silver-104		1,000
Silver-104m		1,000
Silver-105		100
Silver-106		1,000
Silver-106m		100
Silver-108m		1
Silver-111		100
Silver-112		100
Silver-115		1,000
Silver-110m		10
Sodium-22		10
Sodium-24		100
Strontium-80		100
Strontium-81		1,000
Strontium-83		100
Strontium-85		100
Strontium-85m		1,000
Strontium-87m		1,000
Strontium-89		10
Strontium-90		0.1
Strontium-91		100
Strontium-92		100
Sulfur-35		100
Tantalum-172		1,000
Tantalum-173		1,000
Tantalum-174		1,000
Tantalum-175		1,000
Tantalum-176		100
Tantalum-177		1,000
Tantalum-178		1,000
Tantalum-179		100
Tantalum-180		100
Tantalum-180m		1,000
Tantalum-182		10
Tantalum-182m		1,000
Tantalum-183		100
Tantalum-184		100
Tantalum-185		1,000
Tantalum-186		1,000
Technetium-93		1,000
Technetium-93m		1,000
Technetium-94		1,000
Technetium-94m		1,000
Technetium-96		100
Technetium-96m		1,000
Technetium-97		1,000
Technetium-97m		100
Technetium-98		10
Technetium-99		100
Technetium-99m		1,000
Technetium-101		1,000
Technetium-104		1,000
Tellurium-116		1,000
Tellurium-121		100
Tellurium-121m		10
Tellurium-123		100
Tellurium-123m		10
Tellurium-125m		10
Tellurium-127		1,000
Tellurium-127m		10
Tellurium-129		1,000
Tellurium-129m		10
Tellurium-131		100
Tellurium-131m		10
Tellurium-132		10
Tellurium-133		1,000
Tellurium-133m		100
Tellurium-134		1,000
Terbium-147		1,000
Terbium-149		100
Terbium-150		1,000
Terbium-151		100
Terbium-153		1,000
Terbium-154		100
Terbium-155		1,000
Terbium-156		100
Terbium-156m (24.4h)		1,000
Terbium-156m (5.0h)		1,000
Terbium-157		10
Terbium-158		1
Terbium-160		10
Terbium-161		100
Thallium-194		1,000
Thallium-194m		1,000
Thallium-195		1,000
Thallium-197		1,000
Thallium-198		1,000
Thallium-198m		1,000
Thallium-199		1,000
Thallium-200		1,000
Thallium-201		1,000
Thallium-202		100
Thallium-204		100
Thorium-226		10
Thorium-227		0.01
Thorium-228		0.001
Thorium-229		0.001
Thorium-230		0.001
Thorium-231		100
Thorium-232		100
Thorium-234		10
Thorium-natural		100
Thulium-162		1,000
Thulium-166		100
Thulium-167		100
Thulium-170		10
Thulium-171		10
Thulium-172		100
Thulium-173		100
Thulium-175		1,000
Tin-110		100
Tin-111		1,000
Tin-113		100
Tin-117m		100
Tin-119m		100
Tin-121		1,000
Tin-121m		100
Tin-123		10
Tin-123m		1,000
Tin-125		10
Tin-126		10
Tin-127		1,000
Tin-128		1,000
Titanium-44		1
Titanium-45		1,000
Tungsten-176		1,000
Tungsten-177		1,000
Tungsten-178		1,000
Tungsten-179		1,000
Tungsten-181		1,000
Tungsten-185		100
Tungsten-187		100
Tungsten-188		10
Uranium-230		0.01
Uranium-231		100
Uranium-232		0.001
Uranium-233		0.001
Uranium-234		0.001
Uranium-235		0.001
Uranium-236		0.001
Uranium-237		100
Uranium-238		100
Uranium-239		1,000
Uranium-240		100
Uranium-natural		100
Vanadium-47		1,000
Vanadium-48		100
Vanadium-49		1,000
Xenon-120		1,000
Xenon-121		1,000
Xenon-122		1,000
Xenon-123		1,000
Xenon-125		1,000
Xenon-127		1,000
Xenon-129m		1,000
Xenon-131m		1,000
Xenon-133		1,000
Xenon-133m		1,000
Xenon-135		1,000
Xenon-135m		1,000
Xenon-138		1,000
Ytterbium-162		1,000
Ytterbium-166		100
Ytterbium-167		1,000
Ytterbium-169		100
Ytterbium-175		100
Ytterbium-177		1,000
Ytterbium-178		1,000
Yttrium-86		100
Yttrium-86m		1,000
Yttrium-87		100
Yttrium-88		10
Yttrium-90		10
Yttrium-90m		1,000
Yttrium-91		10
Yttrium-91m		1,000
Yttrium-92		100
Yttrium-93		100
Yttrium-94		1,000
Yttrium-95		1,000
Zinc-62		100
Zinc-63		1,000
Zinc-65		10
Zinc-69		1,000
Zinc-69m		100
Zinc-71m		1,000
Zinc-72		100
Zirconium-86		100
Zirconium-88		10
Zirconium-89		100
Zirconium-93		1
Zirconium-95		10
Zirconium-97		100

Any alpha-emitting

radionuclide not listed above or mixtures of alpha-emitters of unknown composition

0.001

Any radionuclide other

than alpha-emitting

radionuclides not listed

above, or mixtures of

beta emitters of unknown

composition

0.01

Note:

For purposes of WAC 246 221 120(8), 246 221 130 (7)(a), and 246 221 240(1) where there is involved a combination of radionuclides in known amounts, the limit for the combination shall be derived as follows: Determine, for each radionuclide in the combination, the ratio between the quantity present in the combination and the limit otherwise established for the specific radionuclide when not in combination. The sum of such ratios for all radionuclides in the combination may not exceed "1" — that is, unity.

The quantities listed above were derived by taking 1/10th of the most restrictive ALI listed in Table I, Columns 1 and 2, of WAC 246-221-290, rounding to the nearest factor of 10, and constraining the values listed between 37 Bq and 37 MBq (0.001 and 1,000µCi). Values of 3.7 MBq (100 µCi) have been assigned for radionuclides having a radioactive half-life in excess of E+9 years, except rhenium, 37 MBq (1,000 µCi), to take into account their low specific activity.

To convert µCi to kBq, multiply the µCi value by 37.

[Statutory Authority: RCW 70.98.050. WSR 94-01-073, § 246-221-300, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-221-300, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70 040. WSR 91-02-049 (Order 121), recodified as § 246-221-300, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 83-19-050 (Order 2026), § 402-24-230, filed 9/16/83. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-24-230, filed 12/8/80; Order 1095, § 402-24-230, filed 2/6/76; Order 708, § 402-24-230, filed 8/24/72; Order 1, § 402-24-230, filed 7/2/71; Order 1, § 402-24-230, filed 1/8/69; Rules (part), filed 10/26/66.]