ML23320A234
| ML23320A234 | |
| Person / Time | |
|---|---|
| Issue date: | 11/16/2023 |
| From: | Solomon Sahle NRC/NMSS/DMSST/ASPB |
| To: | Fordham E State of WA, Dept of Health |
| References | |
| Download: ML23320A234 (1) | |
Text
Chapter 246-221 WAC RADIATION PROTECTION STANDARDS Last Update: 10/4/18 WAC 246-221-001 Purpose and scope.
246-221-005 Radiation protection programs.
246-221-010 Occupational dose limits for adults.
246-221-015 Compliance with requirements for summation of external and internal doses.
246-221-020 Determination of prior occupational dose.
246-221-030 Requirements for planned special exposures.
246-221-040 Determination of internal exposure of individuals to concentrations of radioactive materials in restricted areas.
246-221-050 Occupational dose limits for minors.
246-221-055 Dose equivalent to an embryo/fetus.
246-221-060 Dose limits for individual members of the public.
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246-221-070 Compliance with dose limits for individual members of the public.
246-221-080 Leak tests.
246-221-090 Personnel monitoring for external dose.
246-221-100 Personnel monitoring for internal dose.
246-221-102 Control of access to high radiation areas.
246-221-104 Control of access to very high radiation areas.
246-221-106 Control of access to very high radiation areas Irradiators.
246-221-110 Surveys.
246-221-113 Use of process, engineering or other controls.
246-221-117 Use of individual respiratory protection equipment.
246-221-120 Caution signs, and labels.
246-221-130 Exceptions from posting and labeling requirements.
246-221-140 Instruction of personnel.
246-221-150 Security and control of radioactive material and radiation machines.
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246-221-160 Procedures for picking up, receiving, and opening packages.
246-221-170 Waste disposal, general requirement.
246-221-180 Method of obtaining approval of proposed disposal procedures.
246-221-190 Disposal by release into sanitary sewerage systems.
246-221-200 Disposal by burial in soil.
246-221-210 Disposal by incineration.
246-221-220 Disposal of specific wastes.
246-221-230 Records important to radiation safety.
246-221-235 Reports of transactions involving nationally tracked sources.
246-221-236 Nationally tracked source thresholds.
246-221-240 Reports of stolen, lost or missing radiation sources.
246-221-250 Notification of incidents.
246-221-260 Reports of overexposures and excessive levels and concentrations.
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246-221-265 Special reports to the departmentPlanned special exposures and leaking sources.
246-221-270 Vacating premises and release of equipment.
246-221-275 Notification of changes in a facility.
246-221-280 Notifications and reports to individuals.
246-221-285 Assigned protection factors for respiratorsa.
246-221-290 Appendix AAnnual limits on intake (ALI) and derived air concentrations (DAC) of radionuclides for occupational exposure; effluent concentrations; concentrations for release to sanitary sewerage.
246-221-300 Appendix BMinimum quantities of radioactive material requiring labeling.
WAC 246-221-001 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 WAC (2/17/2023 11:00 AM) [ 4 ] NOT FOR FILING
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-WAC (2/17/2023 11:00 AM) [ 5 ] NOT FOR FILING
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, § 402 010, filed 2/6/76; Order 1, § 402-24-010, filed 1/8/69; Rules (part), filed 10/26/66.]
WAC 246-221-005 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 the frequency specified in the license.
(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 WAC (2/17/2023 11:00 AM) [ 6 ] NOT FOR FILING
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 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.]
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WAC 246-221-010 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 WAC (2/17/2023 11:00 AM) [ 8 ] NOT FOR FILING
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 WAC (2/17/2023 11:00 AM) [ 9 ] NOT FOR FILING
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 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 WAC (2/17/2023 11:00 AM) [ 10 ] NOT FOR FILING
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.]
WAC 246-221-015 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 WAC (2/17/2023 11:00 AM) [ 11 ] NOT FOR FILING
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 ten 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 ten percent of the applicable oral ALI, WAC (2/17/2023 11:00 AM) [ 12 ] NOT FOR FILING
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.
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[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.]
WAC 246-221-020 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.
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(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 WAC (2/17/2023 11:00 AM) [ 15 ] NOT FOR FILING
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 WAC (2/17/2023 11:00 AM) [ 16 ] NOT FOR FILING
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.
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[Statutory Authority: RCW 70.98.050 and 70.98.110. WSR 16 054, § 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.]
WAC 246-221-030 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.
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(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 (c) Instructed in the measures to be taken to keep the dose ALARA considering other risks that may be present.
(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 WAC (2/17/2023 11:00 AM) [ 19 ] NOT FOR FILING
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; (c) What actions were necessary; (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 WAC (2/17/2023 11:00 AM) [ 20 ] NOT FOR FILING
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 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.]
WAC 246-221-040 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, WAC (2/17/2023 11:00 AM) [ 21 ] NOT FOR FILING
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 (c) Quantities of radionuclides excreted from 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 WAC (2/17/2023 11:00 AM) [ 22 ] NOT FOR FILING
(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 WAC (2/17/2023 11:00 AM) [ 23 ] NOT FOR FILING
(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 (c) The sum of these percentages for all of the radionuclides disregarded in the mixture does not exceed 30 percent.
(8) When determining the committed effective dose equivalent, the following information may be considered:
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(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 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:
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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.]
WAC 246-221-050 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.]
WAC 246-221-055 Dose equivalent to an embryo/fetus. (1)
The licensee or registrant shall ensure that the dose equivalent WAC (2/17/2023 11:00 AM) [ 26 ] NOT FOR FILING
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 WAC (2/17/2023 11:00 AM) [ 27 ] NOT FOR FILING
(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 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.]
WAC 246-221-060 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 WAC (2/17/2023 11:00 AM) [ 28 ] NOT FOR FILING
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 WAC (2/17/2023 11:00 AM) [ 29 ] NOT FOR FILING
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 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-WAC (2/17/2023 11:00 AM) [ 30 ] NOT FOR FILING
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, § 402 040, filed 2/6/76; Order 1, § 402-24-040, filed 1/8/69; Rules (part), filed 10/26/66.]
WAC 246-221-070 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 WAC (2/17/2023 11:00 AM) [ 31 ] NOT FOR FILING
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.
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[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.]
WAC 246-221-080 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 WAC (2/17/2023 11:00 AM) [ 33 ] NOT FOR FILING
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.
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(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 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-WAC (2/17/2023 11:00 AM) [ 35 ] NOT FOR FILING
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, § 402 060, filed 2/6/76; Order 1, § 402-24-060, filed 1/8/69; Rules (part), filed 10/26/66.]
WAC 246-221-090 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 ten percent of the applicable limits specified in WAC 246-221-010(1).
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(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; WAC (2/17/2023 11:00 AM) [ 37 ] NOT FOR FILING
(c) Shall not be worn by any individual other than that individual originally assigned to the device; (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 WAC (2/17/2023 11:00 AM) [ 38 ] NOT FOR FILING
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:
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(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 WAC (2/17/2023 11:00 AM) [ 40 ] NOT FOR FILING
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.
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[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.]
WAC 246-221-100 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 WAC (2/17/2023 11:00 AM) [ 42 ] NOT FOR FILING
(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; WAC (2/17/2023 11:00 AM) [ 43 ] NOT FOR FILING
(c) The specific information used to calculate the committed effective dose equivalent pursuant to WAC 246-221-040; (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 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, § 402 080, filed 2/6/76; Order 1, § 402-24-080, filed 1/8/69; Rules (part), filed 10/26/66.]
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WAC 246-221-102 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.
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(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, WAC (2/17/2023 11:00 AM) [ 46 ] NOT FOR FILING
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 70.98.050. WSR 94-01-073, § 246-221-102, filed 12/9/93, effective 1/9/94.]
WAC 246-221-104 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 WAC (2/17/2023 11:00 AM) [ 47 ] NOT FOR FILING
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.]
WAC 246-221-106 Control of access to very high radiation areasIrradiators. (1) This section applies to licensees or WAC (2/17/2023 11:00 AM) [ 48 ] NOT FOR FILING
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 WAC (2/17/2023 11:00 AM) [ 49 ] NOT FOR FILING
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 WAC (2/17/2023 11:00 AM) [ 50 ] NOT FOR FILING
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.
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(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 WAC (2/17/2023 11:00 AM) [ 52 ] NOT FOR FILING
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 WAC (2/17/2023 11:00 AM) [ 53 ] NOT FOR FILING
(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 WAC (2/17/2023 11:00 AM) [ 54 ] NOT FOR FILING
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.]
WAC 246-221-110 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 WAC (2/17/2023 11:00 AM) [ 55 ] NOT FOR FILING
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 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, § 402 085, filed 2/6/76.]
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WAC 246-221-113 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; (c) Use of respiratory protection equipment; or (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 WAC (2/17/2023 11:00 AM) [ 57 ] NOT FOR FILING
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.]
WAC 246-221-117 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 WAC (2/17/2023 11:00 AM) [ 58 ] NOT FOR FILING
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; WAC (2/17/2023 11:00 AM) [ 59 ] NOT FOR FILING
(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.
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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 WAC (2/17/2023 11:00 AM) [ 61 ] NOT FOR FILING
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%;
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(b) Hydrocarbon (condensed) content of five milligrams per cubic meter of air or less; (c) Carbon monoxide (CO) content of 10 ppm 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.
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(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.
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[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.]
WAC 246-221-120 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 WAC (2/17/2023 11:00 AM) [ 65 ] NOT FOR FILING
(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 WAC (2/17/2023 11:00 AM) [ 66 ] NOT FOR FILING
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 WAC (2/17/2023 11:00 AM) [ 67 ] NOT FOR FILING
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.
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(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.
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(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, § 402 090, filed 2/6/76; Order 1, § 402-24-090, filed 1/8/69; Rules (part), filed 10/26/66.]
WAC 246-221-130 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 WAC (2/17/2023 11:00 AM) [ 70 ] NOT FOR FILING
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.
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(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 WAC (2/17/2023 11:00 AM) [ 72 ] NOT FOR FILING
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 WAC (2/17/2023 11:00 AM) [ 73 ] NOT FOR FILING
(Order 1570), § 402-24-095, filed 12/8/80; Order 1095, § 402 095, filed 2/6/76.]
WAC 246-221-140 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.]
WAC 246-221-150 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.
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(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.]
WAC 246-221-160 Procedures for picking up, receiving, and opening packages. (1) Each licensee who expects to receive a package containing quantities of radioactive material in excess WAC (2/17/2023 11:00 AM) [ 75 ] NOT FOR FILING
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 WAC (2/17/2023 11:00 AM) [ 76 ] NOT FOR FILING
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 WAC (2/17/2023 11:00 AM) [ 77 ] NOT FOR FILING
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 WAC (2/17/2023 11:00 AM) [ 78 ] NOT FOR FILING
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 70.98.050 and 70.98.110. WSR 16 054, § 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 WAC (2/17/2023 11:00 AM) [ 79 ] NOT FOR FILING
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), § 402 125, filed 12/8/80; Order 1095, § 402-24-125, filed 2/6/76.]
WAC 246-221-170 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.
(c) By decay in storage as authorized in a specific license.
(2) A person shall be specifically licensed to receive waste containing licensed material from other persons for:
(a) Treatment prior to disposal; or WAC (2/17/2023 11:00 AM) [ 80 ] NOT FOR FILING
(b) Treatment or disposal by incineration; or (c) Decay in storage; 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 WAC (2/17/2023 11:00 AM) [ 81 ] NOT FOR FILING
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.]
WAC 246-221-180 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 WAC (2/17/2023 11:00 AM) [ 82 ] NOT FOR FILING
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.]
WAC 246-221-190 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 WAC (2/17/2023 11:00 AM) [ 83 ] NOT FOR FILING
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 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-WAC (2/17/2023 11:00 AM) [ 84 ] NOT FOR FILING
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, § 402 140, filed 2/6/76; Order 1, § 402-24-140, filed 1/8/69; Rules (part), filed 10/26/66.]
WAC 246-221-200 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.]
WAC 246-221-210 Disposal by incineration. No licensee shall incinerate radioactive material for the purpose of disposal or preparation for disposal except as specifically WAC (2/17/2023 11:00 AM) [ 85 ] NOT FOR FILING
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.]
WAC 246-221-220 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 WAC (2/17/2023 11:00 AM) [ 86 ] NOT FOR FILING
(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.]
WAC 246-221-230 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 WAC (2/17/2023 11:00 AM) [ 87 ] NOT FOR FILING
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 WAC (2/17/2023 11:00 AM) [ 88 ] NOT FOR FILING
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; WAC (2/17/2023 11:00 AM) [ 89 ] NOT FOR FILING
(c) Records of doses received during planned special exposures, accidents, and emergency conditions; (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.
WAC (2/17/2023 11:00 AM) [ 90 ] NOT FOR FILING
(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);
(c) Records of the provisions of the radiation protection program as required by WAC 246-221-005.
(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; WAC (2/17/2023 11:00 AM) [ 91 ] NOT FOR FILING
(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 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 WAC (2/17/2023 11:00 AM) [ 92 ] NOT FOR FILING
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, § 402 170, 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.]
WAC 246-221-235 Reports of transactions involving nationally tracked sources. Each licensee who manufactures, transfers, receives, disassembles, or disposes of a nationally tracked source shall complete and submit a National Source Tracking Transaction Report as specified in subsections (1) through (5) of this section for each type of transaction.
(1) Each licensee who manufactures a nationally tracked source shall complete and submit a National Source Tracking Transaction Report. The report must include the following information:
(a) The name, address, and license number of the reporting licensee; WAC (2/17/2023 11:00 AM) [ 93 ] NOT FOR FILING
(b) The name of the individual preparing the report; (c) The manufacturer, model, and serial number of the source; (d) The radioactive material in the source; (e) The initial source strength in becquerels (curies) at the time of manufacture; and (f) The manufacture date of the source.
(2) Each licensee that transfers a nationally tracked source to another person shall complete and submit a National Source Tracking Transaction Report. The report must include the following information:
(a) The name, address, and license number of the reporting licensee; (b) The name of the individual preparing the report; (c) The name and license number of the recipient facility and the shipping address; (d) The manufacturer, model, and serial number of the source or, if not available, other information to uniquely identify the source; (e) The radioactive material in the source; WAC (2/17/2023 11:00 AM) [ 94 ] NOT FOR FILING
(f) The initial or current source strength in becquerels (curies);
(g) The date for which the source strength is reported; (h) The shipping date; (i) The estimated arrival date; and (j) For nationally tracked sources transferred as waste under a Uniform Low-Level Radioactive Waste Manifest, the waste manifest number and the container identification of the container with the nationally tracked source.
(3) Each licensee that receives a nationally tracked source shall complete and submit a National Source Tracking Transaction Report. The report must include the following information:
(a) The name, address, and license number of the reporting licensee; (b) The name of the individual preparing the report; (c) The name, address, and license number of the person that provided the source; (d) The manufacturer, model, and serial number of the source or, if not available, other information to uniquely identify the source; WAC (2/17/2023 11:00 AM) [ 95 ] NOT FOR FILING
(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; WAC (2/17/2023 11:00 AM) [ 96 ] NOT FOR FILING
(e) The initial or current source strength in becquerels (curies);
(f) The date for which the source strength is reported; (g) The disassemble date of the source.
(5) Each licensee who disposes of a nationally tracked source shall complete and submit a National Source Tracking Transaction Report. The report must include the following information:
(a) The name, address, and license number of the reporting licensee; (b) The name of the individual preparing the report; (c) The waste manifest number; (d) The container identification with the nationally tracked source; (e) The date of disposal; and (f) The method of disposal.
(6) The reports discussed in subsections (1) through (5) of this section must be submitted by the close of the next business day after the transaction. A single report may be submitted for WAC (2/17/2023 11:00 AM) [ 97 ] NOT FOR FILING
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; (c) By facsimile; (d) By mail to the address on the National Source Tracking Transaction Report Form (NRC Form 748); or (e) By telephone with follow-up by facsimile or mail.
(7) Each licensee shall correct any error in previously filed reports or file a new report for any missed transaction within five business days of the discovery of the error or missed transaction. Such errors may be detected by a variety of methods such as administrative reviews or by physical inventories required by regulation. In addition, each licensee shall reconcile the inventory of nationally tracked sources possessed by the licensee against that licensee's data in the National Source Tracking System. The reconciliation must be conducted during the month of January in each year. The reconciliation process must include resolving any discrepancies between the National Source Tracking System and the actual WAC (2/17/2023 11:00 AM) [ 98 ] NOT FOR FILING
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 70.98.050 and 70.98.080. WSR 09 003, § 246-221-235, filed 2/18/09, effective 3/21/09.]
WAC 246-221-236 Nationally tracked source thresholds. The Terabecquerel (TBq) values are the regulatory standard. The curie (Ci) values specified are obtained by converting from the TBq value. The curie values are provided for practical usefulness only and are rounded after conversion.
Category 1 Category 1 Category 2 Category 2 Radioactive Material (TBq) (Ci) (TBq) (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 WAC (2/17/2023 11:00 AM) [ 99 ] NOT FOR FILING
Category 1 Category 1 Category 2 Category 2 Radioactive Material (TBq) (Ci) (TBq) (Ci)
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 09 003, § 246-221-236, filed 2/18/09, effective 3/21/09.]
WAC 246-221-240 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 WAC (2/17/2023 11:00 AM) [ 100 ] NOT FOR FILING
specified in WAC 246-221-300, Appendix B that is still missing or any item not exempted in chapter 246-232 WAC; or (c) Immediately after its occurrence becomes known to the registrant, a stolen, lost, or missing radiation machine.
(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 (c) A statement of disposition, or probable disposition, of the licensed or registered source of radiation involved; 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 WAC (2/17/2023 11:00 AM) [ 101 ] NOT FOR FILING
(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 70.98.050 and 70.98.110. WSR 16 054, § 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.
WAC (2/17/2023 11:00 AM) [ 102 ] NOT FOR FILING
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), § 402 180, 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.]
WAC 246-221-250 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 WAC (2/17/2023 11:00 AM) [ 103 ] NOT FOR FILING
(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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 WAC (2/17/2023 11:00 AM) [ 104 ] NOT FOR FILING
incident involving any radiation source possessed which may have caused or threatens to cause:
(a) An individual to receive, in a period of 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
(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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 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; (c) An unplanned contamination incident that:
(i) Requires access to the contaminated area, by workers or the general public, to be restricted for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by imposing additional radiological controls or by prohibiting entry into the area; WAC (2/17/2023 11:00 AM) [ 105 ] NOT FOR FILING
(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 twenty-four 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 WAC (2/17/2023 11:00 AM) [ 106 ] NOT FOR FILING
(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).
WAC (2/17/2023 11:00 AM) [ 107 ] NOT FOR FILING
(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 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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; (c) The exact location of the incident; (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 70.98.050 and 70.98.110. WSR 16 054, § 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 WAC (2/17/2023 11:00 AM) [ 108 ] NOT FOR FILING
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), § 402 190, 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.]
WAC 246-221-260 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:
WAC (2/17/2023 11:00 AM) [ 109 ] NOT FOR FILING
(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 (c) Levels of radiation or concentrations of radioactive material in:
(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 WAC (2/17/2023 11:00 AM) [ 110 ] NOT FOR FILING
(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 WAC (2/17/2023 11:00 AM) [ 111 ] NOT FOR FILING
(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 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:
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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.]
WAC 246-221-265 Special reports to the departmentPlanned 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 (c) Provide the information required by WAC 246-221-030.
(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; WAC (2/17/2023 11:00 AM) [ 113 ] NOT FOR FILING
(c) The equipment in which the source is installed; (d) The test results; and (e) The corrective action taken.
[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.]
WAC 246-221-270 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.
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(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 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, § 402 210, filed 2/6/76; Order 1, § 402-24-210, filed 1/8/69; Rules (part), filed 10/26/66.]
WAC 246-221-275 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 WAC (2/17/2023 11:00 AM) [ 115 ] NOT FOR FILING
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.]
WAC 246-221-280 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 WAC (2/17/2023 11:00 AM) [ 116 ] NOT FOR FILING
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.]
WAC 246-221-285 Assigned protection factors for respiratorsa.
Assigned Operating mode 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):
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Assigned Operating mode Protection Factors Facepiece, full .................. Demand .................. h 100 Facepiece, full .................. Pressure Demand ............. i 10,000 Facepiece, full .................. Demand, Recirculating .......... h 100 Facepiece, full .................. Positive Pressure Recirculating ..... i 10,000 III. Combination Respirators:
Any combination of air-purifying and Assigned protection factor for type and atmosphere-supplying respirators. 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 1 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 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.]
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WAC 246-221-290 Appendix AAnnual 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" WAC (2/17/2023 11:00 AM) [ 119 ] NOT FOR FILING
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 (fivr 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.
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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 WAC (2/17/2023 11:00 AM) [ 121 ] NOT FOR FILING
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 WAC (2/17/2023 11:00 AM) [ 122 ] NOT FOR FILING
equivalent contribution of Hd, then this sum must be less than 1
- (Hd/50), instead of 1.0.
The derived air concentration (DAC) values are derived limits intended to control chronic occupational exposures. The relationship between the DAC and the ALI is given by:
DAC = ALI (in µCi)/(2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> 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.
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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 WAC (2/17/2023 11:00 AM) [ 124 ] NOT FOR FILING
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 WAC (2/17/2023 11:00 AM) [ 125 ] NOT FOR FILING
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 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> per year to full-time exposure (8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br /> per year). Note that an additional factor of two for age considerations is not warranted in the submersion case.
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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.
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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 Atomic Atomic Name Symbol Number Name Symbol 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 WAC (2/17/2023 11:00 AM) [ 128 ] NOT FOR FILING
LIST OF ELEMENTS Atomic Atomic Name Symbol Number Name Symbol Number 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 III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml 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.
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Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 - 2E+4 8E-6 3E-8 - -
nitrates 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 - -
Compounds 4E+5 4E+5 2E-4 6E-7 6E-3 6E-2 6 Carbon-14 Monoxide - 2E+6 7E-4 2E-6 - -
Compounds 2E+3 2E+3 1E-6 3E-9 3E-5 3E-4 7 Nitrogen-132 Submersion1 - - 4E-6 2E-8 - -
8 Oxygen-15 2 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 - 9E+4 4E-5 1E-7 - -
Y, lanthanum fluoride - 8E+4 3E-5 1E-7 - -
11 Sodium-22 D, all compounds 4E+2 6E+2 3E-7 9E-10 6E-6 6E-5 11 Sodium-24 D, all compounds 4E+3 5E+3 2E-6 7E-9 5E-5 5E-4 12 Magnesium-28 D, all compounds except 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 - 3E+4 1E-5 5E-8 - -
Y, aluminosilicate glass - 3E+4 1E-5 4E-8 - -
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Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 14 Silicon-32 D, see 31Si 2E+3 2E+2 1E-7 3E-10 - -
LLI wall (3E+3) - - - 4E-5 4E-4 W, see Si31
Y, see Si 31
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, 6E+3 sulfides of Sr, Ba, Ge, Sn, Pb, As, Sb, Bi, Cu, Ag, Au, Zn, Cd, Hg, W, and Mo. Sulfates of Ca, Sr, Ba, Ra, As, Sb, and Bi 2E+3 9E-7 3E-9 - -
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 Cl36
17 Chlorine-39 2 D, see Cl 36 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 Submersion 1
WAC (2/17/2023 11:00 AM) [ 131 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 Bone surf (4E+3) (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-49 2 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 Ti 44 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 - - -
WAC (2/17/2023 11:00 AM) [ 132 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml LLI wall Bone surf (9E+4) (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 Cr48
Y, see Cr 48
24 Chromium-51 D, see 48Cr 4E+4 5E+4 2E-5 6E-8 5E-4 5E-3 W, see Cr48
Y, see Cr 48
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-52m 2 D, see Mn 51 3E+4 9E+4 4E-5 1E-7 - -
St wall (4E+4) - - - 5E-4 5E-3 W, see Mn51
25 Manganese-52 D, see Mn 51 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 Mn51
25 Manganese-54 D, see Mn 51 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 Fe 52 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 Fe 52 8E+2 3E+2 1E-7 5E-10 1E-5 1E-4 WAC (2/17/2023 11:00 AM) [ 133 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 Fe52
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 Co55 2E+3 1E+3 5E-7 2E-9 2E-5 2E-4 Y, see Co 55 1E+3 7E+2 3E-7 1E-9 - -
27 Cobalt-60m 2 W, see Co55 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 Co55 5E+2 2E+2 7E-8 2E-10 3E-6 3E-5 Y, see Co 55 2E+2 3E+1 1E-8 5E-11 - -
27 Cobalt-61 2 W, see Co55 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 Co 55
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 - -
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 - -
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 - -
WAC (2/17/2023 11:00 AM) [ 134 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 - -
28 Nickel-65 D, see Ni 56 8E+3 2E+4 1E-5 3E-8 1E-4 1E-3 W, see 56Ni - 3E+4 1E-5 4E-8 - -
28 Nickel-66 D, see Ni 56 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 - -
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 - 1E+5 5E-5 2E-7 - -
nitrates Y, oxides and hydroxides - 1E+5 4E-5 1E-7 - -
29 Copper-61 D, see Cu 60 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 Cu 60 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 Cu 60 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-63 2 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 excep
[except] those given for W 5E+4 2E+5 7E-5 2E-7 - -
WAC (2/17/2023 11:00 AM) [ 135 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 Ga 65 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 Ga65
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 - 2E+4 8E-6 3E-8 - -
halides 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 Ge66
32 Germanium-71 D, see Ge 66 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 Ge66
32 Germanium-77 D, see Ge 66 9E+3 1E+4 4E-6 1E-8 1E-4 1E-3 W, see 66Ge - 6E+3 2E-6 8E-9 - -
WAC (2/17/2023 11:00 AM) [ 136 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 32 Germanium-782 D, see 66Ge 2E+4 2E+4 9E-6 3E-8 - -
St wall (2E+4) - - - 3E-4 3E-3 W, see Ge66
33 Arsenic-69 2 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-78 2 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-73m 2 D, see Se 70 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 Se70
34 Selenium-75 D, see Se 70 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 Se70 2E+4 7E+4 3E-5 1E-7 - -
34 Selenium-81 2 D, see Se 70 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 Se70 3E+4 1E+5 5E-5 2E-7 - -
35 Bromine-74m 2 D, bromides of H, Li, Na, K, Rb, Cs, and Fr 1E+4 4E+4 2E-5 5E-8 - -
WAC (2/17/2023 11:00 AM) [ 137 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 5E-(4E+4) - - - 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 74m Br - 2E+4 8E-6 3E-8 - -
35 Bromine-80m D, see 74m Br 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 74m Br - 2E+5 9E-5 3E-7 - -
35 Bromine-82 D, see 74m Br 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 74m Br - 6E+4 3E-5 9E-8 - -
35 Bromine-84 2 D, see 74m Br 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 Submersion 1
36 Krypton-772 Submersion1 - - 4E-6 2E-8 - -
WAC (2/17/2023 11:00 AM) [ 138 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 Submersion 1
36 Krypton-85 Submersion1 - - 1E-4 7E-7 - -
36 Krypton-872 Submersion1 - - 5E-6 2E-8 - -
36 Krypton-88 Submersion 1
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-88 2 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-81 2 D, see Sr 80 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 Sr 80 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-85m 2 D, see Sr 80 2E+5 6E+5 3E-4 9E-7 3E-3 3E-2 Y, see Sr 80
38 Strontium-85 D, see Sr 80 3E+3 3E+3 1E-6 4E-9 4E-5 4E-4 Y, see 80Sr - 2E+3 6E-7 2E-9 - -
WAC (2/17/2023 11:00 AM) [ 139 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 Bone surf (4E+1) (2E+1) - 3E-11 5E-7 5E-6 Y, see Sr 80
38 Strontium-91 D, see Sr 80 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 86m Y 2E+3 3E+3 1E-6 5E-9 3E-5 3E-4 Y, see 86m Y - 3E+3 1E-6 5E-9 - -
39 Yttrium-88 W, see 86m Y 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 WAC (2/17/2023 11:00 AM) [ 140 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 Zr86
Y, see Zr 86
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 Zr 86
40 Zirconium-93 D, see 86Zr 1E+3 6E+0 3E-9 - - -
Bone surf Bone surf (3E+3) (2E+1) - 2E-11 4E-5 4E-4 W, see Zr86
- 2E+1 1E-8 - - -
Bone surf
- (6E+1) - 9E-11 - -
Y, see Zr 86
- 6E+1 2E-8 - - -
Bone surf
- (7E+1) - 9E-11 - -
40 Zirconium-95 D, see Zr 86 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 Zr 86 6E+2 2E+3 8E-7 3E-9 9E-6 9E-5 W, see Zr86
Y, see Zr 86
41 Niobium-882 W, all compounds except those given for Y 5E+4 2E+5 9E-5 3E-7 - -
WAC (2/17/2023 11:00 AM) [ 141 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml St wall (7E+4) - - - 1E-3 1E-2 Y, oxides and hydroxides - 2E+5 9E-5 3E-7 - -
41 Niobium-892 W, see 88Nb 1E+4 4E+4 2E-5 6E-8 1E-4 1E-3 (66 min)
Y, see 88Nb - 4E+4 2E-5 5E-8 - -
41 Niobium-89 W, see 88Nb 5E+3 2E+4 8E-6 3E-8 7E-5 7E-4 (122 min)
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-97 2 W, see Nb88 2E+4 8E+4 3E-5 1E-7 3E-4 3E-3 Y, see Nb 88
41 Niobium-98 2 W, see Nb88 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, 2E+3 5E+3 2E-6 6E-9 - -
and MoS 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 Mo 90 2E+3 3E+3 1E-6 4E-9 - -
WAC (2/17/2023 11:00 AM) [ 142 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 Mo 90
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 93m Tc 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 93m Tc - 2E+3 8E-7 3E-9 - -
43 Technetium-95 D, see 93m Tc 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 93m Tc 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 93m Tc 1E+3 2E+3 7E-7 2E-9 1E-5 1E-4 W, see 93m Tc - 3E+2 1E-7 4E-10 - -
43 Technetium-99m D, see 93m Tc 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 - -
WAC (2/17/2023 11:00 AM) [ 143 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 Ru94
Y, see Ru 94
44 Ruthenium-103 D, see 94Ru 2E+3 2E+3 7E-7 2E-9 3E-5 3E-4 W, see Ru94
Y, see Ru 94
44 Ruthenium-105 D, see 94Ru 5E+3 1E+4 6E-6 2E-8 7E-5 7E-4 W, see Ru94
Y, see Ru 94
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 - -
WAC (2/17/2023 11:00 AM) [ 144 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 99m Rh - 8E+3 4E-6 1E-8 - -
Y, see 99m Rh - 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 99m Rh - 8E+2 3E-7 1E-9 - -
Y, see 99m Rh - 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 99m Rh 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-103m 2 D, see 99m Rh 4E+5 1E+6 5E-4 2E-6 6E-3 6E-2 W, see 99m Rh - 1E+6 5E-4 2E-6 - -
Y, see 99m Rh - 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 99m Rh 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-107 2 D, see 99m Rh 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 100 Pd 1E+4 3E+4 1E-5 5E-8 2E-4 2E-3 WAC (2/17/2023 11:00 AM) [ 145 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 100 Pd - 4E+3 2E-6 6E-9 - -
Y, see 100 Pd - 4E+3 1E-6 5E-9 - -
46 Palladium-107 D, see 100Pd 3E+4 2E+4 9E-6 - - -
LLI wall Kidneys (4E+4) (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 100 Pd 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-102 2 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-103 2 D, see 102 Ag 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-104m 2 D, see 102 Ag 3E+4 9E+4 4E-5 1E-7 4E-4 4E-3 W, see 102 Ag - 1E+5 5E-5 2E-7 - -
Y, see 102 Ag - 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 102 Ag - 1E+5 6E-5 2E-7 - -
Y, see 102 Ag - 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 102 Ag - 2E+3 7E-7 2E-9 - -
Y, see 102 Ag - 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 - -
WAC (2/17/2023 11:00 AM) [ 146 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 102 Ag 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 102 Ag 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 102 Ag 9E+2 2E+3 6E-7 - - -
LLI wall Liver (1E+3) (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-115 2 D, see 102 Ag 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 102 Ag - 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 - 1E+5 5E-5 2E-7 - -
nitrates Y, oxides and hydroxides - 1E+5 5E-5 2E-7 - -
48 Cadmium-107 D, see 104 Cd 2E+4 5E+4 2E-5 8E-8 3E-4 3E-3 W, see 104 Cd - 6E+4 2E-5 8E-8 - -
Y, see 104 Cd - 5E+4 2E-5 7E-8 - -
48 Cadmium-109 D, see 104Cd 3E+2 4E+1 1E-8 - - -
Kidneys Kidneys (4E+2) (5E+1) - 7E-11 6E-6 6E-5 W, see 104Cd - 1E+2 5E-8 - - -
WAC (2/17/2023 11:00 AM) [ 147 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 Kidneys (4E+1) (4E+0) - 5E-12 5E-7 5E-6 W, see 104 Cd - 8E+0 4E-9 - - -
Kidneys
- (1E+1) - 2E-11 - -
Y, see 104 Cd - 1E+1 5E-9 2E-11 - -
48 Cadmium-113 D, see 104 Cd 2E+1 2E+0 9E-10 - - -
Kidneys Kidneys (3E+1) (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 104 Cd 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 104 Cd 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 104 Cd 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 WAC (2/17/2023 11:00 AM) [ 148 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml (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 109 In - 2E+4 8E-6 3E-8 - -
49 Indium-111 D, see 109 In 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 109 In - 2E+5 8E-5 3E-7 - -
49 Indium-114m D, see 109 In 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 109 In - 5E+4 2E-5 7E-8 - -
49 Indium-115 D, see 109 In 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 109 In - 4E+4 2E-5 6E-8 - -
49 Indium-117 2 D, see 109 In 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 109 In - 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 WAC (2/17/2023 11:00 AM) [ 149 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml W, see 110Sn - 5E+2 2E-7 8E-10 - -
50 Tin-117m D, see 110Sn 2E+3 1E+3 5E-7 - - -
LLI wall Bone surf (2E+3) (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 110 Sn - 5E+2 2E-7 8E-10 - -
50 Tin-121 D, see 110 Sn 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 110 Sn - 1E+5 6E-5 2E-7 - -
50 Tin-123 D, see 110 Sn 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 110 Sn - 2E+4 8E-6 3E-8 - -
50 Tin-128 2 D, see 110 Sn 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
51 Antimony-116m 2 D, see 115 Sb 2E+4 7E+4 3E-5 1E-7 3E-4 3E-3 WAC (2/17/2023 11:00 AM) [ 150 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 115 Sb 5E+3 2E+4 9E-6 3E-8 - -
51 Antimony-119 D, see 115 Sb 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 115 Sb - 5E+5 2E-4 7E-7 - -
51 Antimony-120 D, see 115 Sb 1E+3 2E+3 9E-7 3E-9 1E-5 1E-4 (5.76 d)
W, see 115Sb 9E+2 1E+3 5E-7 2E-9 - -
51 Antimony-122 D, see 115 Sb 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 115 Sb 2E+5 6E+5 2E-4 8E-7 - -
51 Antimony-124 D, see 115 Sb 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 - -
WAC (2/17/2023 11:00 AM) [ 151 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 115 Sb - 3E+3 1E-6 5E-9 - -
51 Antimony-129 D, see 115 Sb 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 Thyroid (2E+4) (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 Bone surf (7E+2) (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 Bone surf (1E+3) (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 Bone surf (1E+3) (5E+2) - 7E-10 2E-5 2E-4 W, see 116 Te - 4E+2 2E-7 - - -
Bone surf
- (1E+3) - 2E-9 - -
52 Tellurium-125m D, see 116 Te 1E+3 4E+2 2E-7 - - -
Bone surf Bone surf (1E+3) (1E+3) - 1E-9 2E-5 2E-4 W, see 116 Te - 7E+2 3E-7 1E-9 - -
WAC (2/17/2023 11:00 AM) [ 152 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 52 Tellurium-127m D, see 116Te 6E+2 3E+2 1E-7 - 9E-6 9E-5 Bone surf
- (4E+2) - 6E-10 - -
W, see 116 Te - 3E+2 1E-7 4E-10 - -
52 Tellurium-127 D, see 116 Te 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 Thyroid (6E+2) (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 Thyroid (6E+3) (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 Thyroid (7E+2) (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 Thyroid (6E+3) (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 Thyroid (3E+4) (6E+4) - 8E-8 4E-4 4E-3 W, see 116 Te - 2E+4 9E-6 - - -
Thyroid
- (6E+4) - 8E-8 - -
52 Tellurium-134 2 D, see 116 Te 2E+4 2E+4 1E-5 - - -
WAC (2/17/2023 11:00 AM) [ 153 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml Thyroid Thyroid (2E+4) (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-120 2 D, all compounds 4E+3 9E+3 4E-6 - - -
Thyroid Thyroid (8E+3) (1E+4) - 2E-8 1E-4 1E-3 53 Iodine-121 D, all compounds 1E+4 2E+4 8E-6 - - -
Thyroid Thyroid (3E+4) (5E+4) - 7E-8 4E-4 4E-3 53 Iodine-123 D, all compounds 3E+3 6E+3 3E-6 - - -
Thyroid Thyroid (1E+4) (2E+4) - 2E-8 1E-4 1E-3 53 Iodine-124 D, all compounds 5E+1 8E+1 3E-8 - - -
Thyroid Thyroid (2E+2) (3E+2) - 4E-10 2E-6 2E-5 53 Iodine-125 D, all compounds 4E+1 6E+1 3E-8 - - -
Thyroid Thyroid (1E+2) (2E+2) - 3E-10 2E-6 2E-5 53 Iodine-126 D, all compounds 2E+1 4E+1 1E-8 - - -
Thyroid Thyroid (7E+1) (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 Thyroid (2E+1) (3E+1) - 4E-11 2E-7 2E-6 53 Iodine-130 D, all compounds 4E+2 7E+2 3E-7 - - -
Thyroid Thyroid (1E+3) (2E+3) - 3E-9 2E-5 2E-4 53 Iodine-131 D, all compounds 3E+1 5E+1 2E-8 - - -
Thyroid Thyroid (9E+1) (2E+2) - 2E-10 1E-6 1E-5 53 Iodine-132m 2 D, all compounds 4E+3 8E+3 4E-6 - - -
Thyroid Thyroid (1E+4) (2E+4) - 3E-8 1E-4 1E-3 53 Iodine-132 D, all compounds 4E+3 8E+3 3E-6 - - -
Thyroid Thyroid (9E+3) (1E+4) - 2E-8 1E-4 1E-3 WAC (2/17/2023 11:00 AM) [ 154 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 53 Iodine-133 D, all compounds 1E+2 3E+2 1E-7 - - -
Thyroid Thyroid (5E+2) (9E+2) - 1E-9 7E-6 7E-5 53 Iodine-134 2 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 Thyroid (3E+3) (4E+3) - 6E-9 3E-5 3E-4 54 Xenon-120 2 Submersion 1
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 Submersion 1
54 Xenon-127 Submersion1 - - 1E-5 6E-8 - -
54 Xenon-129m Submersion1 - - 2E-4 9E-7 - -
54 Xenon-131m Submersion 1
54 Xenon-133m Submersion1 - - 1E-4 6E-7 - -
54 Xenon-133 Submersion1 - - 1E-4 5E-7 - -
54 Xenon-135m 2 Submersion 1
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-135m 2 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 WAC (2/17/2023 11:00 AM) [ 155 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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-142 2 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 - 2E+5 7E-5 2E-7 - -
hydroxides 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 131 La 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-143 2 D, see 131 La 4E+4 1E+5 4E-5 1E-7 - -
WAC (2/17/2023 11:00 AM) [ 156 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 134 Ce 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 134 Ce - 7E+2 3E-7 9E-10 - -
58 Cerium-141 W, see 134 Ce 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 134 Ce - 1E+1 6E-9 2E-11 - -
59 Praseodymium-136 2 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 - -
WAC (2/17/2023 11:00 AM) [ 157 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 59 Praseodymium- W, see 136Pr 1E+4 5E+4 2E-5 8E-8 1E-4 1E-3 138m 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- W, see 136Pr 8E+4 2E+5 7E-5 2E-7 1E-3 1E-2 142m2 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 136 Nd - 3E+5 1E-4 4E-7 - -
60 Neodymium-141 W, see 136 Nd 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 WAC (2/17/2023 11:00 AM) [ 158 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 136 Nd - 2E+4 1E-5 3E-8 - -
60 Neodymium-151 2 W, see 136 Nd 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 141 Pm 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 141 Pm - 2E+2 8E-8 3E-10 - -
61 Promethium-146 W, see 141 Pm 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 Bone surf (5E+3) (2E+2) - 3E-10 7E-5 7E-4 Y, see 141 Pm - 1E+2 6E-8 2E-10 - -
61 Promethium-148m W, see 141 Pm 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 141 Pm - 5E+2 2E-7 7E-10 - -
61 Promethium-149 W, see 141 Pm 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 141 Pm - 2E+4 7E-6 2E-8 - -
61 Promethium-151 W, see 141 Pm 2E+3 4E+3 1E-6 5E-9 2E-5 2E-4 Y, see 141Pm - 3E+3 1E-6 4E-9 - -
WAC (2/17/2023 11:00 AM) [ 159 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 Bone surf (3E+1) (6E-2) - 9E-14 3E-7 3E-6 62 Samarium-147 W, all compounds 2E+1 4E-2 2E-11 - - -
Bone surf Bone surf (3E+1) (7E-2) - 1E-13 4E-7 4E-6 62 Samarium-151 W, all compounds 1E+4 1E+2 4E-8 - - -
LLI wall Bone surf (1E+4) (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 W, all compounds 3E+3 8E+3 4E-6 1E-8 4E-5 4E-4 (12.62h) 63 Europium-150 W, all compounds 8E+2 2E+1 8E-9 3E-11 1E-5 1E-4 (34.2 y) 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-158 2 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 WAC (2/17/2023 11:00 AM) [ 160 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml (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 Bone surf (2E+1) (2E+2) - 2E-14 3E-7 3E-6 W, see 145Gd - 3E-2 1E-11 - - -
Bone surf
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 145 Gd - 1E+3 5E-7 2E-9 - -
64 Gadolinium-152 D, see 145 Gd 2E+1 1E-2 4E-12 - - -
Bone surf Bone surf (3E+1) (2E-2) - 3E-14 4E-7 4E-6 W, see 145Gd - 4E-2 2E-11 - - -
Bone surf
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 145 Gd - 6E+3 2E-6 8E-9 - -
65 Terbium-147 2 W, all compounds 9E+3 3E+4 1E-5 5E-8 1E-4 1E-3 65 Terbium-149 W, all compounds 5E+3 7E+2 3E-7 1E-9 7E-5 7E-4 65 Terbium-150 W, all compounds 5E+3 2E+4 9E-6 3E-8 7E-5 7E-4 65 Terbium-151 W, all compounds 4E+3 9E+3 4E-6 1E-8 5E-5 5E-4 65 Terbium-153 W, all compounds 5E+3 7E+3 3E-6 1E-8 7E-5 7E-4 65 Terbium-154 W, all compounds 2E+3 4E+3 2E-6 6E-9 2E-5 2E-4 65 Terbium-155 W, all compounds 6E+3 8E+3 3E-6 1E-8 8E-5 8E-4 65 Terbium-156m W, all compounds 2E+4 3E+4 1E-5 4E-8 2E-4 2E-3 (5.0 h)
WAC (2/17/2023 11:00 AM) [ 161 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 65 Terbium-156m W, all compounds 7E+3 8E+3 3E-6 1E-8 1E-4 1E-3 (24.4 h) 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 Bone surf (5E+4) (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-157 2 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-162 2 W, all compounds 5E+5 2E+6 1E-3 3E-6 - -
St wall (8E+5) - - - 1E-2 1E-1 67 Holmium-164m 2 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 - -
WAC (2/17/2023 11:00 AM) [ 162 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 Bone surf (1E+4) (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-175 2 W, all compounds 7E+4 3E+5 1E-4 4E-7 - -
St wall (9E+4) - - - 1E-3 1E-2 70 Ytterbium-162 2 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 162 Yb 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 162 Yb - 7E+5 3E-4 1E-6 - -
70 Ytterbium-169 W, see 162 Yb 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 162 Yb - 3E+3 1E-6 5E-9 - -
70 Ytterbium-177 2 W, see 162 Yb 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 WAC (2/17/2023 11:00 AM) [ 163 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 169 Lu 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 Bone surf (3E+3) (3E+2) - 5E-10 4E-5 4E-4 Y, see 169 Lu - 2E+2 9E-8 3E-10 - -
71 Lutetium-174 W, see 169 Lu 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 169 Lu - 2E+4 9E-6 3E-8 - -
71 Lutetium-176 W, see 169 Lu 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 169 Lu - 2E+3 9E-7 3E-9 - -
71 Lutetium-178m 2 W, see 169 Lu 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 - -
WAC (2/17/2023 11:00 AM) [ 164 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 170 Hf 1E+3 9E+0 4E-9 - 2E-5 2E-4 Bone surf
- (2E+1) - 3E-11 - -
W, see 170 Hf - 4E+1 2E-8 - - -
Bone surf
- (6E+1) - 8E-11 - -
72 Hafnium-173 D, see 170 Hf 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 170 Hf 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 WAC (2/17/2023 11:00 AM) [ 165 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml W, see 170Hf - 1E+5 6E-5 2E-7 - -
72 Hafnium-182 D, see 170Hf 2E+2 8E-1 3E-10 - - -
Bone surf Bone surf (4E+2) (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-174 2 W, see 172 Ta 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 172 Ta - 1E+4 5E-6 2E-8 - -
73 Tantalum-177 W, see 172 Ta 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 172 Ta 2E+4 7E+4 3E-5 9E-8 3E-4 3E-3 Y, see 172 Ta - 6E+4 2E-5 8E-8 - -
73 Tantalum-180 W, see 172 Ta 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 WAC (2/17/2023 11:00 AM) [ 166 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 172 Ta - 1E+2 6E-8 2E-10 - -
73 Tantalum-183 W, see 172 Ta 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 172 Ta - 5E+3 2E-6 7E-9 - -
73 Tantalum-185 2 W, see 172 Ta 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 172 Ta - 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-177 2 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 WAC (2/17/2023 11:00 AM) [ 167 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml (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 177 Re - 2E+3 9E-7 3E-9 - -
75 Rhenium-184m D, see 177 Re 2E+3 3E+3 1E-6 4E-9 3E-5 3E-4 W, see 177Re - 4E+2 2E-7 6E-10 - -
75 Rhenium-184 D, see 177Re 2E+3 4E+3 1E-6 5E-9 3E-5 3E-4 W, see 177Re - 1E+3 6E-7 2E-9 - -
75 Rhenium-186m D, see 177Re 1E+3 2E+3 7E-7 - - -
St wall St wall (2E+3) (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 177 Re - 3E+3 1E-6 4E-9 - -
75 Rhenium-189 D, see 177 Re 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-181 2 D, see 180 Os 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 180 Os 2E+3 6E+3 2E-6 8E-9 3E-5 3E-4 W, see 180 Os - 4E+3 2E-6 6E-9 - -
Y, see 180 Os - 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 180 Os - 8E+2 3E-7 1E-9 - -
Y, see 180 Os - 8E+2 3E-7 1E-9 - -
WAC (2/17/2023 11:00 AM) [ 168 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 180 Os 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 180 Os 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 180 Os - 3E+3 1E-6 4E-9 - -
Y, see 180 Os - 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-182 2 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 182 Ir - 3E+4 1E-5 5E-8 - -
Y, see 182 Ir - 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 182 Ir - 1E+4 5E-6 2E-8 - -
Y, see 182 Ir - 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 182 Ir - 6E+3 2E-6 8E-9 - -
WAC (2/17/2023 11:00 AM) [ 169 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 182 Ir 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 182 Ir 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 182 Ir 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 182 Ir 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 182 Ir 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 182 Ir 1E+3 3E+3 1E-6 4E-9 1E-5 1E-4 W, see 182 Ir - 2E+3 9E-7 3E-9 - -
Y, see 182 Ir - 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 182 Ir - 3E+4 1E-5 4E-8 - -
Y, see 182 Ir - 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 182 Ir - 5E+4 2E-5 7E-8 - -
WAC (2/17/2023 11:00 AM) [ 170 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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-199 2 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 193 Au 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 193 Au 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 193 Au 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 - -
WAC (2/17/2023 11:00 AM) [ 171 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 193 Au - 3E+3 1E-6 4E-9 - -
Y, see 193 Au - 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 193 Au - 8E+4 3E-5 1E-7 - -
Y, see 193 Au - 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 193m Hg - 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 193m Hg - 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 - -
WAC (2/17/2023 11:00 AM) [ 172 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 193m Hg - 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-194m 2 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-198m 2 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-195m 2 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 WAC (2/17/2023 11:00 AM) [ 173 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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 Bone surf (1E+0) (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-201 2 D, see 200 Bi 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 200 Bi - 1E+3 5E-7 2E-9 - -
83 Bismuth-206 D, see 200 Bi 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 Kidneys (6E+1) (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 200 Bi - 3E+1 1E-8 4E-11 - -
83 Bismuth-212 2 D, see 200 Bi 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 - -
WAC (2/17/2023 11:00 AM) [ 174 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 83 Bismuth-2142 D, see 200Bi 2E+4 8E+2 3E-7 1E-9 - -
St wall (2E+4) - - - 3E-4 3E-3 W, see 200 Bi - 9E-2 4E-7 1E-9 - -
84 Polonium-203 2 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 203 Po 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 (or 1.0 working working level level) months) 86 Radon-222 With daughters removed - 1E+4 4E-6 1E-8 - -
With daughters present - 1E+2 3E-8 1E-10 - -
(or 4 (or 0.33 working working level level) months) 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 - -
WAC (2/17/2023 11:00 AM) [ 175 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml Bone surf (5E+0) - - - 6E-8 6E-7 88 Radium-2272 W, all compounds 2E+4 1E+4 6E-6 - - -
Bone surf Bone surf (2E+4) (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 Bone surf (2E+3) (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 Bone surf (5E+1) (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 224 Ac 1E+2 3E+0 1E-9 - - -
LLI wall Bone surf (1E+2) (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 Bone surf (4E-1) (8E-4) - 1E-15 5E-9 5E-8 W, see 224 Ac - 2E-3 7E-13 - - -
Bone surf
Y, see 224 Ac - 4E-3 2E-12 6E-15 - -
89 Actinium-228 D, see 224 Ac 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 224 Ac - 4E+1 2E-8 6E-11 - -
90 Thorium-2262 W, all compounds except 5E+3 2E+2 6E-8 2E-10 - -
those given for Y WAC (2/17/2023 11:00 AM) [ 176 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml St wall (5E+3) - - - 7E-5 7E-4 Y, oxides and hydroxides - 1E+2 6E-8 2E-10 - -
90 Thorium-227 W, see 226 Th 1E+2 3E-1 1E-10 5E-13 2E-6 2E-5 Y, see 226Th - 3E-1 1E-10 5E-13 - -
90 Thorium-228 W, see 226Th 6E+0 1E-2 4E-12 - - -
Bone surf Bone surf (1E+1) (2E-2) - 3E-14 2E-7 2E-6 Y, see 226 Th - 2E-2 7E-12 2E-14 - -
90 Thorium-229 W, see 226 Th 6E-1 9E-4 4E-13 - - -
Bone surf Bone surf (1E+0) (2E-3) - 3E-15 2E-8 2E-7 Y, see 226Th - 2E-3 1E-12 - - -
Bone surf
90 Thorium-230 W, see 226Th 4E+0 6E-3 3E-12 - - -
Bone surf Bone surf (9E+0) (2E-2) - 2E-14 1E-7 1E-6 Y, see 226Th - 2E-2 6E-12 - - -
Bone surf
90 Thorium-231 W, see 226Th 4E+3 6E+3 3E-6 9E-9 5E-5 5E-4 Y, see 226Th - 6E+3 3E-6 9E-9 - -
90 Thorium-232 W, see 226Th 7E-1 1E-3 5E-13 - - -
Bone surf Bone surf (2E+0) (3E-3) - 4E-15 3E-8 3E-7 Y, see 226Th - 3E-3 1E-12 - - -
Bone surf
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 227 Pa - 1E+1 5E-9 2E-11 - -
WAC (2/17/2023 11:00 AM) [ 177 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 91 Protactinium-230 W, see 227Pa 6E+2 5E+0 2E-9 7E-12 - -
Bone surf (9E+2) - - - 1E-5 1E-4 Y, see 227 Pa - 4E+0 1E-9 5E-12 - -
91 Protactinium-231 W, see 227 Pa 2E-1 2E-3 6E-13 - - -
Bone surf Bone surf (5E-1) (4E-3) - 6E-15 6E-9 6E-8 Y, see 227Pa - 4E-3 2E-12 - - -
Bone surf
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 227 Pa 2E+3 8E+3 3E-6 1E-8 3E-5 3E-4 Y, see 227 Pa - 7E+3 3E-6 9E-9 - -
92 Uranium-230 D, UF6, UO2F2, 4E+0 4E-1 2E-10 - - -
UO2(NO3)2 Bone surf Bone surf (6E+0) (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 230 U 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 230 U - 5E+3 2E-6 6E-9 - -
92 Uranium-232 D, see 230U 2E+0 2E-1 9E-11 - - -
Bone surf Bone surf (4E+0) (4E-1) - 6E-13 6E-8 6E-7 W, see 230 U - 4E-1 2E-10 5E-13 - -
Y, see 230 U - 8E-3 3E-12 1E-14 - -
92 Uranium-233 D, see 230U 1E+1 1E+0 5E-10 - - -
Bone surf Bone surf
- 3E-12 3E-7 3E-6 WAC (2/17/2023 11:00 AM) [ 178 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml (2E+1) (2E+0)
W, see 230U - 7E-1 3E-10 1E-12 - -
Y, see 230U - 4E-2 2E-11 5E-14 - -
92 Uranium-234 3 D, see 230 U 1E+1 1E+0 5E-10 - - -
Bone surf Bone surf (2E+1) (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 Bone surf (2E+1) (2E+0) - 3E-12 3E-7 3E-6 W, see 230 U - 8E-1 3E-10 1E-12 - -
Y, see 230 U - 4E-2 2E-11 6E-14 - -
92 Uranium-236 D, see 230U 1E+1 1E+0 5E-10 - - -
Bone surf Bone surf (2E+1) (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 230 U 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 Bone surf (2E+1) (2E+0) - 3E-12 3E-7 3E-6 W, see 230 U - 8E-1 3E-10 1E-12 - -
Y, see 230 U - 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 230 U - 2E+5 7E-5 2E-7 - -
Y, see 230 U - 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 230 U - 2E+3 1E-6 3E-9 - -
92 Uranium-natural3 D, see 230U 1E+1 1E+0 5E-10 - - -
Bone surf Bone surf (2E+1) (2E+0) - 3E-12 3E-7 3E-6 WAC (2/17/2023 11:00 AM) [ 179 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 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-233 2 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 Bone surf (2E+4) (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 Bone surf (6E+0) (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 Bone surf (4E+3) (7E+1) - 1E-10 5E-5 5E-4 93 Neptunium-237 W, all compounds 5E-1 4E-3 2E-12 - - -
Bone surf Bone surf (1E+0) (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-240 2 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 Bone surf (4E+0) (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 Bone surf (2E+0) (1E-2) - 2E-14 2E-8 2E-7 Y, see 234Pu - 2E-2 8E-12 2E-14 - -
WAC (2/17/2023 11:00 AM) [ 180 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 94 Plutonium-239 W, see 234Pu 8E-1 6E-3 3E-12 - - -
Bone surf Bone surf (1E+0) (1E-2) - 2E-14 2E-8 2E-7 Y, see 234 Pu - 2E-2 7E-12 - - -
Bone surf
94 Plutonium-240 W, see 234 Pu 8E-1 6E-3 3E-12 - - -
Bone surf Bone surf (1E+0) (1E-2) - 2E-14 2E-8 2E-7 Y, see 234 Pu - 2E-2 7E-12 - - -
Bone surf
94 Plutonium-241 W, see 234 Pu 4E+1 3E-1 1E-10 - - -
Bone surf Bone surf (7E+1) (6E-1)
- 8E-13 1E-6 1E-5 Y, see 234 Pu - 8E-1 3E-10 - - -
Bone surf
- (1E+0) - 1E-12 - -
94 Plutonium-242 W, see 234 Pu 8E-1 7E-3 3E-12 - - -
Bone surf Bone surf (1E+0) (1E-2) - 2E-14 2E-8 2E-7 Y, see 234 Pu - 2E-2 7E-12 - - -
Bone surf
94 Plutonium-243 W, see 234 Pu 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 234 Pu 8E-1 7E-3 3E-12 - - -
Bone surf Bone surf (2E+0) (1E-2) - 2E-14 2E-8 2E-7 Y, see 234Pu - 2E-2 7E-12 - - -
Bone surf
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 234 Pu - 3E+2 1E-7 4E-10 - -
95 Americium-237 2 W, all compounds 8E+4 3E+5 1E-4 4E-7 1E-3 1E-2 95 Americium-2382 W, all compounds 4E+4 3E+3 1E-6 - 5E-4 5E-3 Bone surf
- - 9E-9 - -
WAC (2/17/2023 11:00 AM) [ 181 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml (6E+3) 95 Americium-239 W, all compounds 5E+3 1E+4 5E-6 2E-8 7E-5 7E-4 95 Americium-240 W, all compounds 2E+3 3E+3 1E-6 4E-9 3E-5 3E-4 95 Americium-241 W, all compounds 8E-1 6E-3 3E-12 - - -
Bone surf Bone surf (1E+0) (1E-2) - 2E-14 2E-8 2E-7 95 Americium-242m W, all compounds 8E-1 6E-3 3E-12 - - -
Bone surf Bone surf (1E+0) (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 Bone surf (1E+0) (1E-2) - 2E-14 2E-8 2E-7 95 Americium-244m2 W, all compounds 6E+4 4E+3 2E-6 - - -
St wall Bone surf (8E+4) (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 Bone surf (8E+1) (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 Bone surf (5E+1) (3E-1) - 4E-13 7E-7 7E-6 96 Curium-243 W, all compounds 1E+0 9E-3 4E-12 - - -
Bone surf Bone surf (2E+0) (2E-2) - 2E-14 3E-8 3E-7 96 Curium-244 W, all compounds 1E+0 1E-2 5E-12 - - -
Bone surf Bone surf (3E+0) (2E-2) - 3E-14 3E-8 3E-7 96 Curium-245 W, all compounds 7E-1 6E-3 3E-12 - - -
Bone surf Bone surf (1E+0) (1E-2) - 2E-14 2E-8 2E-7 WAC (2/17/2023 11:00 AM) [ 182 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 96 Curium-246 W, all compounds 7E-1 6E-3 3E-12 - - -
Bone surf Bone surf (1E+0) (1E-2) - 2E-14 2E-8 2E-7 96 Curium-247 W, all compounds 8E-1 6E-3 3E-12 - - -
Bone surf Bone surf (1E+0) (1E-2) - 2E-14 2E-8 2E-7 96 Curium-248 W, all compounds 2E-1 2E-3 7E-13 - - -
Bone surf Bone surf (4E-1) (3E-3) - 4E-15 5E-9 5E-8 96 Curium-249 2 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 Bone surf (6E-2) (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 Bone surf (1E+0) (9E-3) - 1E-14 2E-8 2E-7 97 Berkelium-249 W, all compounds 2E+2 2E+0 7E-10 - - -
Bone surf Bone surf (5E+2) (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-244 2 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 244 Cf - 9E+0 4E-9 1E-11 - -
98 Californium-248 W, see 244 Cf 8E+0 6E-2 3E-11 - - -
Bone surf Bone surf (2E+1) (1E-1) - 2E-13 2E-7 2E-6 Y, see 244Cf - 1E-1 4E-11 1E-13 - -
98 Californium-249 W, see 244 Cf 5E-1 4E-3 2E-12 - - -
Bone surf Bone surf (1E+0) (9E-3) - 1E-14 2E-8 2E-7 Y, see 244Cf - 1E-2 4E-12 - - -
Bone surf
WAC (2/17/2023 11:00 AM) [ 183 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml 98 Californium-250 W, see 244Cf 1E+0 9E-3 4E-12 - - -
Bone surf Bone surf (2E+0) (2E-2) - 3E-14 3E-8 3E-7 Y, see 244 Cf - 3E-2 1E-11 4E-14 - -
98 Californium-251 W, see 244 Cf 5E-1 4E-3 2E-12 - - -
Bone surf Bone surf (1E+0) (9E-3) - 1E-14 2E-8 2E-7 Y, see 244Cf - 1E-2 4E-12 - - -
Bone surf
98 Californium-252 W, see 244Cf 2E+0 2E-2 8E-12 - - -
Bone surf Bone surf (5E+0) (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 Bone surf (2E+1) (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 Bone surf (4E+1) (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
- - 1E-10 - -
WAC (2/17/2023 11:00 AM) [ 184 ] NOT FOR FILING
Table III Table II Releases Table 1 Effluent to Occupational Values Concentration Sewers Monthly Col. 1 Col. 2 Col. 3 Col. 1 Col. 2 Average Oral Concen-Ingestion Inhalation tration Atomic ALI ALI DAC Air Water µCi/ml No. Radionuclide Class µCi µCi µCi/ml µCi/ml µCi/ml (9E+1) 101 Mendelevium-258 W, all compounds 3E+1 2E-1 1E-10 - - -
Bone surf Bone surf (5E+1) (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.
2 These 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).)
3 For 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 WAC (2/17/2023 11:00 AM) [ 185 ] NOT FOR FILING
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").
WAC (2/17/2023 11:00 AM) [ 186 ] NOT FOR FILING
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 DACA + DACB + DACC 1
[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.
WAC 246-221-300 Appendix BMinimum 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 WAC (2/17/2023 11:00 AM) [ 187 ] NOT FOR FILING
Radionuclide Quantity*(µCi)
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 WAC (2/17/2023 11:00 AM) [ 188 ] NOT FOR FILING
Radionuclide Quantity*(µCi)
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 WAC (2/17/2023 11:00 AM) [ 189 ] NOT FOR FILING
Radionuclide Quantity*(µCi)
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 WAC (2/17/2023 11:00 AM) [ 190 ] NOT FOR FILING
Radionuclide Quantity*(µCi)
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 WAC (2/17/2023 11:00 AM) [ 191 ] NOT FOR FILING
Radionuclide Quantity*(µCi)
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 WAC (2/17/2023 11:00 AM) [ 192 ] NOT FOR FILING
Radionuclide Quantity*(µCi)
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 WAC (2/17/2023 11:00 AM) [ 193 ] NOT FOR FILING
Radionuclide Quantity*(µCi)
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 WAC (2/17/2023 11:00 AM) [ 194 ] NOT FOR FILING
Radionuclide Quantity*(µCi)
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 WAC (2/17/2023 11:00 AM) [ 195 ] NOT FOR FILING
Radionuclide Quantity*(µCi)
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 WAC (2/17/2023 11:00 AM) [ 196 ] NOT FOR FILING
Radionuclide Quantity*(µCi)
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 WAC (2/17/2023 11:00 AM) [ 197 ] NOT FOR FILING
Radionuclide Quantity*(µCi)
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 WAC (2/17/2023 11:00 AM) [ 198 ] NOT FOR FILING
Radionuclide Quantity*(µCi)
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 WAC (2/17/2023 11:00 AM) [ 199 ] NOT FOR FILING
Radionuclide Quantity*(µCi)
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 WAC (2/17/2023 11:00 AM) [ 200 ] NOT FOR FILING
Radionuclide Quantity*(µCi)
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 WAC (2/17/2023 11:00 AM) [ 201 ] NOT FOR FILING
Radionuclide Quantity*(µCi)
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 WAC (2/17/2023 11:00 AM) [ 202 ] NOT FOR FILING
Radionuclide Quantity*(µCi)
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 WAC (2/17/2023 11:00 AM) [ 203 ] NOT FOR FILING
Radionuclide Quantity*(µCi)
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 WAC (2/17/2023 11:00 AM) [ 204 ] NOT FOR FILING
Radionuclide Quantity*(µCi)
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 WAC (2/17/2023 11:00 AM) [ 205 ] NOT FOR FILING
Radionuclide Quantity*(µCi)
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 0.001 Any radionuclide other 0.01 radionuclide not listed than alpha-emitting above or mixtures of radionuclides not listed alpha-emitters of above, or mixtures of unknown composition beta emitters of unknown composition WAC (2/17/2023 11:00 AM) [ 206 ] NOT FOR FILING
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.
1 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, § 402 230, 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.]
WAC (2/17/2023 11:00 AM) [ 207 ] NOT FOR FILING