007.14.12 Ark. Code R. 001
Current through Register Vol. 49, No. 10, October, 2024
1961, as Amended.
Department pursuant to these Regulations.
Regulations for Control of Sources of Ionizing Radiation, Section 1.
impose upon any registrant such requirements in addition to those established in this Regulation as it deems appropriate or necessary to minimize danger to public health and safety or property.
If for a specific case, the two (2) day period would impose an undue hardship on the person, upon application to the Department, permission to proceed sooner may be granted. In addition, the out-of-state person must:
In accordance with Arkansas Code Annotated § 20-21-217, annual fees for registration shall be paid. Nonpayment of fees shall result in escalated enforcement action and/or revocation of registration.
In accordance with Arkansas Code Annotated § 20-21-217, X-ray Registration Fees are as follows:
(FOOTNOTES APPEAR AT THE END OF THIS SECTION)
In accordance with Act 596 of 2011, codified at Arkansas Code Annotated § 20-21-217, annual fees for licensing shall be paid. Nonpayment of fees shall result in escalated enforcement action and/or revocation of license.
The following Radioactive Material Fees are based upon 15% of the U. S. Nuclear Regulatory Commission's Federal Fiscal Year 2012 annual fees found in 10 CFR 171.16.
CATEGORY | CODE | FEE |
Academic Broad Scope | 01120 | $2,115.00 |
Academic R&D | 03620 | $1,215.00 |
Accelerator Produced Radionuclides | 03210 | $2,280.00 |
Consultant Services | 03225 | $2,145.00 |
Eye Applicator (Sr-90) | 02210 | $1,260.00 |
Gamma Knife | 02310 | $2,625.00 |
Gas Chromatographs | 03123 | $720.00 |
High Dose Rate Remote Afterloader | 02230 | $1,260.00 |
Industrial Radiography | 03310 | $3,855.00 |
Instrument Calibration | 03221; 03222 | $720.00 |
In-vitro Testing | 02410 | $720.00 |
Irradiators - Activity [LESS THAN] 10,000 Curies | 03511 | $2,280.00 |
Irradiators - Activity [GRATER THAN OR EQUAL TO] 10,000 Curies | 03521 | $20,625.00 |
Irradiators - Self-shielded | 03510 | $1,305.00 |
Manufacturing & Distributing | 03214 | $1,770.00 |
Measuring Systems - Analytical Devices | 03122 | $720.00 |
Measuring Systems - Fixed Gauge | 03120 | $720.00 |
Measuring Systems - Portable Gauge | 03121 | $720.00 |
Medical Broad Scope | 02110 | $6,810.00 |
Medical Facility - No Written Directive Required | 02121 | $1,260.00 |
Medical Facility - Written Directive Required | 02120 | $1,260.00 |
Medical Private Practice | 02200; 02201 | $1,260.00 |
Medical Therapy | 02240 | $1,260.00 |
Mobile Medical Services | 02231 | $1,260.00 |
Nuclear Pharmacy | 02500 | $2,430.00 |
Veterinary | 02400 | $720.00 |
Well Logging - Including Tracers | 03110; 03111; 03112 | $1,500.00 |
Other Radioactive Material (non-NORM) Decommissioning | $5,000.00 |
CATEGORY | FEE |
Particle accelerator, non-medical | $200.00 |
Medical, therapy, non-hospital unit | $250.00 per unit ($175.00 for each additional unit) |
Particle accelerator, medical, non-hospital unit | $450.00 per unit ($300.00 for each additional unit) |
Cyclotron/accelerator for the production of radioactive material | $3,750.00 |
CATEGORY | FEE |
Certain measuring, gauging, and controlling devices | $720.00 |
Generally licensed gas chromatographs | $720.00 |
Static elimination devices | $125.00 |
Source material devices | $500.00 |
Devices containing depleted uranium | $500.00 |
Public safety devices containing radioactive material | $25.00 |
All other general license registrations other than those specified above | $300.00 |
Portable and fixed gauges | $1,125.00 |
CATEGORY | FEE |
Naturally Occurring Radioactive Material (NORM) License | $2,500.00 |
Naturally Occurring Radioactive Material (NORM) Site - General License | $500.00 |
Arkansas State Board of Health Rules and Regulations for Control of Sources of Ionizing | $0.00 for first copy $30.00 for each additional copy |
Radiation | |
Amendment to existing license | $50.00 per amendment |
CATEGORY | FEE |
Naturally Occurring Radioactive Material (NORM) Decommissioning | $2,500.00 |
Other Radioactive Material (non-NORM) Decommissioning | $5,000.00 |
Radiography, Field | $3,855.00 |
Well Logging with Sealed Sources Only | $1,500.00 |
Well Logging with Tracer Studies | $1,500.00 |
Nuclear Gauge | $720.00 |
Consultant | $2,145.00 |
Gas Chromatograph, Lead Paint Analyzer | $720.00 |
hydroxycarboxylic acids and polycarboxylic acids (e.g., citric acid, carbolic acid and glucinic acid).
Uranium-235 is less than 0.711 weight percent of the total Uranium present. Depleted Uranium does not include special nuclear material.
Environmental Protection Agency regulations in 40 CFR Part 261.
Research and Development used in these Regulations does not include the internal or external administration of radiation or radioactive material to human beings.
Uranium enriched in the isotope 235 in quantities not exceeding 350 grams of contained Uranium-235; Uranium-233 in quantities not exceeding 200 grams; Plutonium in quantities not exceeding 200 grams or any combination of them in accordance with the following formula:
For each kind of special nuclear material, determine the ratio between the quantity of that special nuclear material and the quantity specified above for the same kind of special nuclear material. The sum of such ratios for all of the kinds of special nuclear material in combination shall not exceed "1" (i.e., unity). For example, the following quantities in combination would not exceed the limitation and are within the formula, as follows:
175 (grams contained U-235) + 50 (grams U-233) + 50 (grams Pu) = 1 350 200 200
PROHIBITED;"2/ and
legend "CAUTION - RADIOACTIVE SHIELDING -URANIUM" and which meets the specifications for containers for radioactive materials prescribed by Section 173.394 or 173.395 of 49 CFR Part 173, of the regulations published by the U.S. Department of Transportation.
centimeters from any surface;
And provided further, that the level of radiation due to radioactive material contained in each electron tube does not exceed one (1) millirad per hour at one (1) centimeter from any surface when measured through seven (7) milligrams per square centimeter of absorber.4/
Radioactive drug: Capsules containing carbon-14 urea for "in vivo" diagnostic use for humans. Except as provided in paragraphs RH-301.f.2. and RH-301.f.3., any person is exempt from the requirements for a license set forth in Section 5(c) of the Atomic Energy Act of 1954, as amended and from the regulations in this Section provided that such person receives, possesses, uses, transfers, owns, or acquires capsules containing one (1) microcurie (37 kBq) carbon-14 urea (allowing for nominal variation that may occur during the manufacturing process) each, for "in vivo" diagnostic use for humans.
Commission Contractors. Any U.S. Department Energy (DOE) contractor or subcontractor and any U.S. Nuclear of Regulatory Commission (NRC) contractor or subcontractor of the following categories operating within this state is exempt from these Regulations to the extent that such contractor or subcontractor under his contract receives, possesses, uses, transfers or acquires sources of radiation:
General and Specific.
A General License- is provided by regulation, grants authority to a person for certain activities involving radioactive material, and is effective without the filing of an application with the Department the issuance of a licensing document to a particular person. However, registration with the Department may be required by the particular general license.
Specific Licenses- is issued to named person who has filed an application with the Department for the license under to provisions of these Regulations.
The general license provided in this RH-402.a is subject to the provision of RH-56., RH-60., RH-301.a.2., RH-409., RH-416., RH-500., RH-501., RH-600., RH-601., RH-602., RH-4012., Section 36/ and Section 4 of these Regulations.
Certain detecting, measuring, gauging, or controlling devices and certain devices for producing light or an ionized atmosphere. *
* Persons possessing radioactive material in devices under a general license in RH-402.b. before January 15, 1975, may continue to possess, use, or transfer that material in accordance with the labeling requirements of RH-402.b. in effect on January 14, 1975.
The devices must have been received from one of the specific licensees described in above in RH-402.b.2.A. or through a transfer made under RH-402.b.3.H.
The device and any radioactive material from the device may only be disposed of by transfer to a person authorized by a specific license to receive the radioactive material in the device or as otherwise approved by the Department A report containing a brief description of the event and the remedial action taken; and, in the case of detection of 0.005 microcurie or more removable radioactive material or failure of or damage to a source likely to result in contamination of the premises or the environs, a plan for ensuring that the premises and environs are acceptable for unrestricted use, must be furnished within thirty (30) days to:
Arkansas Department of Health & Human Services
Radiation Control
ATTN: General License Registration Program
P.O. Box 1437, Mail Slot H-30
Little Rock, Arkansas 72203-1437
Under these circumstances, the criteria set out in RH-1218., ''Radiological criteria for unrestricted use,'' may be applicable, as determined by the Department on a case-by-case basis;
Shall transfer or dispose of the device containing
Radioactive material only by transfer to another general licensee as authorized by RH-402.b.3.H., or to a person authorized to receive the device by a specific license issued under Section 2 that authorizes waste collection, or equivalent regulations of the U.S. Nuclear Regulatory Commission or an Agreement State, or as otherwise approved under RH-402.b.3.G.iii.
Arkansas Department of Health & Human Services
Radiation Control
ATTN: General License Registration Program
P.O. Box 1437, Mail Slot H-30
Little Rock, Arkansas 72203-1437
within 30 days after the transfer of a device to a specific licensee. The report must contain:
Arkansas Department of Health & Human Services
Radiation Control
ATTN: General License Registration Program
P.O. Box 1437, Mail Slot H-30
Little Rock, Arkansas 72203-1437
Shall register, in accordance with RH-402.b.3.L.ii.
and iii. devices containing at least ten (10) mCi (370 MBq) of Cesium-137, 0.1 mCi (3.7 MBq) of Strontium-90, one (1) mCi (37 MBq) of Cobalt-60, or one (1) mCi (37 MBq) of Americium-241 or any other transuranic (i.e., element with atomic number greater than uranium (92)), based on the activity indicated on the label. Each address for a location of use, as described under RH-402.b.3.m.iii., represents a separate general licensee and requires a separate registration and fee.
Regulatory Commission or an Agreement State with respect to devices meeting the criteria in RH-402.b.3.L.i. are subject to registration requirements if the devices are used in areas subject to Arkansas Department of Health and Human Services jurisdiction. The Department will request registration information from such licensees
Arkansas Department of Health & Human Services
Radiation Control
Attention: General License Registration Program,
P.O. Box 1437 Mail Slot H-30,
Little Rock, Arkansas 72203-1437
within thirty (30) days of the effective date of the change. For a portable device, a report of address change is only required for a change in the device's primary place of storage.
Luminous Safety Devices in Aircraft. A general license is hereby issued to own, receive, acquire, possess and use Tritium or Promethium-147 contained in luminous safety devices for use in aircraft, provided each device contains not more than ten (10) curies of Tritium or 300 millicuries of Promethium-147 and that each device has been manufactured, assembled or imported in accordance with a specific license issued by the U.S. Nuclear Regulatory Commission or each device has been manufactured or assembled in accordance with the specifications contained in a specific license or equivalent licensing document issued by the Department or any Agreement State to the manufacturer or assembler such device pursuant to licensing requirements of equivalent to those in Section 32.53 of CFR Part 32 of the Regulations of the U.S. Nuclear Regulatory Commission.
Calibration and Reference Sources. A general license is hereby issued to those persons listed below to own, receive, acquire, possess, use and transfer, in accordance with provisions of Subparagraphs 4 and 5 of this Paragraph d, Americium-241 in the form of calibration or reference sources:
The receipt, possession, use and transfer of this source,
Model ______, Serial No. _______, are subject to a general license and the regulations of the U.S. Nuclear Regulatory Commission or of a State with which the Commission has entered into an agreement for the exercise of regulatory authority. Do not remove this label.
CAUTION-RADIOACTIVE MATERIAL- THIS SOURCE CONTAINS (AMERICIUM-241) (PLUTONIUM)*. DO NOT TOUCH RADIOACTIVE PORTION OF THIS SOURCE.
(Name of Manufacturer or Importer)
* Showing only the name of the appropriate material.
Clinical or Laboratory Testing.8/
clinical laboratory or hospital to receive, acquire, possess, transfer or use, for any of the following stated tests, in accordance with the provisions of RH-402.h., 2., 3., 4., 5. and 6. of this Section, the following radioactive materials in prepackaged units:
Unless one of the following statements or a substantially similar statement which contains the information called for in the following statements, appears on a label affixed to each prepackaged unit or appears in a leaflet or brochure which accompanies the package:
"This radioactive material may be received, acquired, possessed and used only by physicians, veterinarians in the practice of veterinary medicine, clinical laboratories or hospitals and only for In Vitro clinical or laboratory tests not involving internal or external administration of the material or the radiation therefrom, to human beings or animals. Its receipt, acquisition, possession, use and transfer are subject to these Regulations and a general license of the U.S. Nuclear Regulatory Commission or of a State with which the Commission has entered into an agreement for the exercise of regulatory authority."
( Name of Manufacturer)
on foils or plated sources, or sealed in glass in excess of the quantities in RH-905., Schedule F - "Quantities of Radioactive Materials Requiring Consideration of the Need for an Emergency Plan for Responding to a Release," must contain either:
performance objectives and plans for the training that the licensee will provide workers on how to respond to an emergency including any special instructions and orientation tours the licensee would offer to fire, police, medical and other emergency personnel. The training shall familiarize personnel with site-specific emergency procedures.
Also, the training shall thoroughly prepare site personnel for their responsibilities in the event of accident scenarios postulated as most probable for the specific site, including the use of team training for such scenarios.
The licensee shall critique each exercise using individuals not having direct implementation responsibility for the plan. Critiques of exercises must evaluate the appropriateness of the plan, emergency procedures, facilities, equipment, training of personnel, and overall effectiveness of the response. Deficiencies found by the critiques must be corrected.
manufacture, prototype testing, quality control, labels, proposed uses, installation, servicing, leak testing, operating and safety instructions and potential hazards of the device to provide reasonable assurance that:
Whole body; head and trunk; active blood-forming organs;
gonads; or lens of eye ...... ........ ..........15 rems
Hands and forearms; feet and ankles; localized areas of skin averaged over areas no larger than one (1) square centimeters ............. 200 rems
Other organs ..................... .............. ..... 50 rems
The receipt, possession, use and transfer of this device Model ______, 9/ Serial No. _____ 9/ are subject to a general license or the equivalent and the regulations of the U.S. NRC or a State with which the NRC has entered into an agreement for the exercise of regulatory authority. This label shall be maintained on the device in a legible condition. Removal of this label is prohibited.
CAUTION - RADIOACTIVE MATERIAL
____________________________________
(Name of manufacturer or initial transferor)
Each person licensed under RH-405.e. to initially transfer devices to generally licensed persons shall comply with the requirements of this section.
Exempt Concentrations. In addition to the requirements set forth in Section RH-404. above, a specific license authorizing the introduction of radioactive material into a product or material owned by or in the possession of the licensee or another to be transferred to persons exempt under RH-301.a.1. will be issued only if:
Each person licensed under this Paragraph g shall file an annual report with the Department which shall identify the type and quantity of each product or material into which radioactive material has been introduced during the reporting period; name and address of the person who owned or possessed the product or material, into which radioactive material has been introduced, at the time of introduction; the type and quantity of radionuclide introduced into each such product or material; and the initial concentrations of the radionuclide in the product or material at time of transfer of the radioactive material by the licensee. If no transfers of radioactive material have been made pursuant to this Paragraph during the reporting period, the report shall so indicate. The report shall cover the year ending June 30 and shall be filed within thirty (30) days thereafter.
Americium-241, Plutonium or Radium-226 for Distribution to Persons Generally Licensed Under RH-402.d. An application for a specific license to manufacture calibration and reference sources containing Americium-241, Plutonium or Radium-226 to persons generally licensed under RH-402.d. will be approved if:
Certain In Vitro Clinical or Laboratory Testing Under General License. An application for a specific license to manufacture or distribute radioactive material for use under the general license of RH-402.h. will be approved if:
"This radioactive material may be received, acquired, possessed and used only by physicians, veterinarians, clinical laboratories or hospitals and only for In Vitro clinical or laboratory tests not involving internal or external administration of the material or the radiation therefrom, to human beings or animals. Its receipt, acquisition, possession, use and transfer are subject to these Regulations and a general license of the U.S. Nuclear Regulatory Commission or of a State with which the
Commission has entered into an agreement for the exercise of regulatory authority."
___________________________________
(Name of Manufacturer)
Radiopharmaceuticals Containing Radioactive Material for Medical Use Under Group Licenses.
Administration (FDA) as a drug manufacturer;
whether it is constructed of lead, glass, plastic, or other material, of a radiopharmaceutical to be transferred for commercial distribution. The label must include the radiation symbol and the words
"CAUTION, RADIOACTIVE MATERIAL"
or
"DANGER, RADIOACTIVE MATERIAL";
the name of the radiopharmaceutical or its abbreviation; and the quantity of radioactivity at a specified date and time. For radiopharmaceuticals with a half life greater than 100 (one hundred) days, the time may be omitted.
"CAUTION, RADIOACTIVE MATERIAL"
or
"DANGER, RADIOACTIVE MATERIAL"
and an identifier that ensures that the syringe, vial, or other container can be correlated with the information on the transport radiation shield label.
An application for a specific license to manufacture and distribute sources and devices containing radioactive material to persons licensed pursuant to RH-402. for use as a calibration or reference source or for the uses listed in RH-8600., RH-8620., and RH-8630. will be approved if:
Manufacture, preparation, or transfer for commercial distribution of capsules containing carbon-14 urea for "in vivo" diagnostic use for humans to persons exempt from licensing. Requirements for a license:
produce, package, repackage, or transfer for commercial distribution of capsules containing carbon-14 capsules containing one (1) microcurie (37 kBq) carbon-14 urea (allowing for nominal variation that may occur during the manufacturing process) each, for "in vivo" diagnostic use, to persons exempt from licensing under RH-301.f. or the equivalent regulations of the Nuclear Regulatory Commission or of an Agreement State will be approved if:
Manufacture, preparation, or transfer for commercial distribution of capsules containing carbon-14 urea for "in vivo" diagnostic use for humans to persons exempt from licensing. Conditions of each license issued under RH-405.o. is subject to the following conditions:
"Radioactive Material. For "In Vivo" Diagnostic Use Only. This Material Is Not To Be Used For Research Involving Human Subjects and Must Not Be Introduced into Foods, Beverages, Cosmetics, or Other Drugs or Medicinals, or into Products Manufactured For Commercial Distribution. This Material May Be Disposed of in Ordinary Trash."
This Paragraph prescribes requirements for the issuance of specific licenses of broad scope for radioactive material ("broad licenses")11/ and certain regulations governing holders of such licenses.
The description must also include a description of the methods to be employed in the handling and disposal of wastes containing chelating agents or other non-radiological substances that might affect meeting the performance objectives in Subpart C of this Paragraph.
LLW disposal, developed and applied by the applicant for the determination of natural disposal site characteristics and for quality assurance during the design, construction, operation and closure of the land disposal facility and the receipt, handling and emplacement of waste.
The analyses must clearly identify and differentiate between the roles performed by the natural disposal site characteristics and design features in isolating and segregating the wastes.
The analyses must clearly demonstrate that there is reasonable assurance that the exposure to humans from the release of radioactivity will not exceed the limits set forth in RH-407.c.2.
Decontamination and/or dismantlement of surface facilities;
Backfilling of excavated areas; or
Stabilization of the disposal site for post-closure care.
closure observation and maintenance, the licensee may apply for an amendment to transfer the license to the disposal site owner. The license shall be transferred when the Department finds:
designed, operated, closed and controlled after closure so that reasonable assurance exists that exposures to humans are within the limits established in the performance objectives in RH-407.c.2. through 5.
If radioactive waste contains only radionuclides listed in Table 1, classification shall be determined as follows:
TABLE 1.
Radionuclide | Concentration, curies per cubic meter |
C-14 | 8 |
C-14 in activated metal | 80 |
Ni-59 in activated metal | 220 |
Nb-94 in activated metal | 0.2 |
Tc-99 | 3 |
I-129 | 0.08 |
Alpha emitting transuranic | |
nuclides with half-life | |
greater than five years | 1100 |
Pu-241 | 13,500 |
Cm-242 | 120,000 |
1 Units are nanocuries per gram.
TABLE 2.
Radionuclide | Concentration, curies per cubic meter | ||
Col. 1 | Col. 2 | Col. 3 | |
Total of all nuclides less than 5 year half life | 700 | (1) | (1) |
H-3 | 40 | (1) | (1) |
Co-60 | 700 | (1) | (1) |
Ni-63 | 3.5 | 70 | 700 |
Ni-63 in activated metal | 35 | 700 | 7000 |
Sr-90 | 0.04 | 150 | 7000 |
Cs-137 | 1 | 44 | 4600 |
1 There are no limits established for these radionuclides in Class B or C wastes. Practical consideration such as the effects of external radiation and internal heat generation on transportation, handling and disposal will limit the concentrations for these wastes. These wastes shall be Class B unless the concentrations of other nuclides in Table 2 determine the waste to the Class C independent of these nuclides.
If radioactive waste contains a mixture of radionuclides, some of which are listed in Table 1 and some of which are listed in Table 2, classification shall be determined as follows:
Example: A waste contains Sr-90 in a concentration of 50 Ci/m3 and Cs-137 in a concentration of 22 Ci/m3. Since the concentrations both exceed the values in Column1, Table 2, they must be compared to Column 2 values. For Sr-90 fraction 50/150 = 0.33; for Cs-137 fraction, 22/44 = 0.5; the sum of the fractions = 0.83. Since the sum is less than 1.0, the waste is Class B.
quantities of toxic gases, vapors or fumes harmful to persons transporting, handling or disposing of the waste. This does not apply to radioactive gaseous waste packaged in accordance with RH-407.d.6.G.
Act and these Regulations of the Department, the Department will issue a specific license authorizing the proposed activity in such form and containing such conditions and limitations as it deems appropriate and necessary to effectuate the purposes of the Act.
and each specific licensee shall notify the Department in writing immediately following the filing of a voluntary or involuntary petition for bankruptcy under any chapter of Title 11 (Bankruptcy) of the United States Code by or against:
December 2, 2007.
July 27, 1993, which is of a type described in RH-409.h.1. of this section, shall provide financial assurance for decommissioning in accordance with the criteria set forth in this section.
Table of required amounts of financial assurance for decommissioning by quantity of material. Greater than 104 but less than or equal to 105 times the applicable quantities of Appendix B of RH-2300. in unsealed form. (For a combination of isotopes, if R, as defined in RH-409.h.1. divided by 104 is greater than 1 but R divided by 105 is less than or equal to)...................$1,125,000
Greater than 103 but less than or equal to 104 times the applicable quantities of Appendix B of RH-2300. in unsealed form. (For a combination of isotopes, if R, As defined RH-409.h.1. divided by 103 is greater than 1 but R divided by 104 is less than or equal to 1.)...............................................................$225,000
Greater than 1010 times the applicable quantities of Appendix B of RH-2300. in sealed sources or plated foils. (For a combination of isotopes, if R, as defined in RH-409.h.1., divided by1010 is greater than.)............................................................ $113,000
For commercial corporations that issue bonds, a guarantee of funds by the applicant or licensee for decommissioning costs based on a financial test may be used if the guarantee and test are as contained in Appendix B of this Section. For commercial corporations that do not issue bonds, a guarantee of funds by the applicant or licensee for decommissioning costs may be used if the guarantee and test are as contained in Appendix C of this Section. For nonprofit entities, such as colleges, universities, and nonprofit hospitals, a guarantee of funds by the applicant or licensee may be used if the guarantee and test are as contained in Appendix D of this Section.
A guarantee of funds by the applicant or licensee for decommissioning costs based on a financial test may be used if the guarantee and test are contained in Appendix B of this Part. A guarantee by the applicant or licensee may not be used in combination with any other financial methods to satisfy the requirements of this Section or in any situation where the applicant or licensee has a parent company holding majority control of the voting stock of the company. Any surety method or insurance used to provide financial assurance for decommissioning must contain the following conditions:
An external sinking fund may be in the form of a trust, escrow account, government fund, certificate of deposit, or deposit of government securities. The surety or insurance provisions must be as stated in RH-409.h.6.B.
If records important to the decommissioning of a facility are kept for other purposes, reference to these records and their locations may be used. Information the Department considers important to decommissioning consists of:
Separate Buildings or Outdoor Areas.
A decommissioning plan must be submitted if required by license conditions or if the procedures and activities necessary to carry out decommissioning of the site or separate building or outdoor area have not been previously approved by the Department and these procedures could increase potential health and safety impacts to workers or to the public, such as in any of the following cases:
comparison of that estimate with present funds set aside for decommissioning, and a plan for assuring the availability of adequate funds for completion of decommissioning.
Department if the information therein demonstrates that the decommissioning will be completed as soon as practicable and that the health and safety of workers and the public will be adequately protected.
Except as provided in RH-410.h., licensees shall complete decommissioning of the site or separate building or outdoor area as soon as practicable but no later than twenty-four (24) months following the initiation of decommissioning.
notice to the licensee when the Department determines that:
Records which must be maintained pursuant to this Section may be the original or a reproduced copy or microform if such reproduced copy or microform is duly authenticated by authorized personnel and the microform is capable of producing a clear and legible copy after storage for the period specified by Department regulations. The record may also be stored in electronic media with the capability for producing legible, accurate, and complete records during the required retention period. Records such as letters, drawings, specifications, must include all pertinent information such as stamps, initials, and signatures. The licensee or registrant shall maintain adequate safeguards against tampering with and loss of records.
Upon instruction from the Department, each licensee shall perform or cause to have performed and shall permit the Department to perform, such reasonable tests as the Department deems appropriate or necessary, including, but not limited to, tests of:
Any person who violates any of the provisions of the Act or rules, regulations or orders in effect pursuant thereto, of the Department shall, upon conviction thereof, be punished by a fine of not less that one hundred dollars ($100.00) nor more than two thousand dollars ($2,000.00) or by imprisonment for not more than six (6) months or be both fined and imprisoned.
Sources of radiation shall be subject to impounding pursuant to Section 5 of these Regulations.
The Department may, by rule, regulation or order, impose upon any licensee such requirements in addition to those established in these Regulations as it deems appropriate or necessary to minimize danger to public health and safety or property.
Accordance With Specific License.
The following devices and equipment incorporating radioactive material, when manufactured, tested and labeled by the manufacturer in accordance with the specifications contained in a specific license or equivalent licensing document issued by the Department, the U.S. Nuclear Regulatory Commission or any Agreement State, are placed under a general license pursuant to Section 2, Part D, RH-402.a.
Radioactive M Material c | icro-uries |
Antimony-122 (Sb 122) | 100 |
Antimony-124 (Sb 124) | 10 |
Antimony-125 (Sb 125) | 10 |
Arsenic-73 (As 73) | 100 |
Arsenic-74 (As 74) | 10 |
Arsenic-76 (As 76) | 10 |
Arsenic-77 (As 77) | 100 |
Barium-131 (Ba 131) | 10 |
Barium-133 (Ba 133) | 10 |
Barium-140 (Ba 140) | 10 |
Bismuth-210 (Bi 210) | 1 |
Bromine-82 (Br 82) | 10 |
Cadmium-109 (Cd 109) | 10 |
Cadmium-115m (Cd 115m) | 10 |
Cadmium-115 (Cd 115) | 100 |
Calcium-45 (Ca 45) | 10 |
Calcium-47 (Ca 47) | 10 |
Carbon-14 (C 14) | 100 |
Cerium-141 (Ce 141) | 100 |
Cerium-143 (Ce 143) | 100 |
Cerium-144 (Ce 144) | 1 |
Cesium-129 (Cs 129) | 100 |
Cesium-131 (Cs 131) | 1,000 |
Cesium-134m (Cs 134m) | 100 |
Cesium-134 (Cs 134) | 1 |
Cesium-135 (Cs 135) | 10 |
Cesium-136 (Cs 136) | 10 |
Cesium-137 (Cs 137) | 10 |
Chlorine-36 (Cl 36) | 10 |
Chlorine-38 (Cl 38) | 10 |
Chromium-51 (Cr 51) | 1,000 |
Cobalt-57 (Co 57) | 100 |
Cobalt-58m (Co 58m) | 10 |
Cobalt-58 (Co 58) | 10 |
Cobalt-60 (Co 60) | 1 |
Copper-64 (Cu 64) | 100 |
Dysprosium-165 (Dy 165) | 10 |
Dysprosium-166 (Dy 166) | 100 |
Erbium-169 (Er 169) | 100 |
Erbium-171 (Er 171) | 100 |
Europium-152 (Eu 152) 9.2 | h 100 |
Europium-152 (Eu 152) 13 | yr 1 |
Europium-154 (Eu 154) | 1 |
Europium-155 (Eu 155) | 10 |
Fluorine-18 (F 18) | 1,000 |
Gadolinium-153 (Gd 153) | 10 |
Gadolinium-159 (Gd 159) | 100 |
Gallium-67 (Ga 67) | 100 |
Gallium-72 (Ga 72) | 10 |
Germanium-68 (Ge 68) | 10 |
Germanium-71 (Ge 71) | 100 |
Gold-195 (Au 195) | 10 |
Gold-198 (Au 198) | 100 |
Gold-199 (Au 199) | 100 |
Hafnium-181 (Hf 181) | 10 |
Holmium-166 (Ho 166) | 100 |
Hydrogen-3 (H 3) | 1,000 |
Indium-111 (In 111) | 100 |
Indium-113m (In 113m) | 100 |
Indium-114m (In 114m) | 10 |
Indium-115m (In 115m) | 100 |
Indium-115 (In 115) | 10 |
Iodine-123 (I 123) | 100 |
Iodine-125 (I 125) | 1 |
Iodine-126 (I 126) | 1 |
Iodine-129 (I 129) | 0.1 |
Iodine-131 (I 131) | 1 |
Iodine-132 (I 132) | 10 |
Iodine-133 (I-133) | 1 |
Iodine-134 (I-134) | 10 |
Iodine-135 (I-135) | 10 |
Iridium-192 (Ir 192) | 10 |
Iridium-194 (Ir 194) | 10 |
Iron-52 (Fe 52) | 10 |
Iron-55 (Fe 55) | 100 |
Iron-59 (Fe 59) | 10 |
Krypton-85 (Kr 85) | 100 |
Krypton-87 (Kr 87) | 10 |
Lanthanum-140 (La 140) | 10 |
Lutetium-177 (Lu 177) | 100 |
Manganese-52 (Mn 52) | 10 |
Manganese-54 (Mn 54) | 10 |
Manganese-56 (Mn 56) | 10 |
Mercury-197m (Hg 197m) | 100 |
Mercury-197 (Hg 197) | 100 |
Mercury-203 (Hg 203) | 10 |
Molybdenum-99 (Mo 99) | 100 |
Neodymium-147 (Nd 147) | 100 |
Neodymium-149 (Nd 149) | 100 |
Nickel-59 (Ni 59) | 100 |
Nickel-63 (Ni 63) | 10 |
Nickel-65 (Ni 65) | 100 |
Niobium-93m (Nb 93m) | 10 |
Niobium-95 (Nb 95) | 10 |
Niobium-97 (Nb 97) | 10 |
Osmium-185 (Os 185) | 100 |
Osmium-191m (Os 191m) | 100 |
Osmium-191 (Os 191) | 10 |
Osmium-193 (Os 193) | 100 |
Palladium-103 (Pd 103) | 100 |
Palladium-109 (Pd 109) | 100 |
Phosphorus-32 (P 32) | 10 |
Platinum-191 (Pt 191) | 100 |
Platinum-193m (Pt 193m) | 100 |
Platinum-193 (Pt 193) | 100 |
Platinum-197m (Pt 197m) | 100 |
Platinum-197 (Pt 197) | 100 |
Polonium-210 (Po 210) | 0.1 |
Potassium-42 (K 42) | 10 |
Potassium-43 (K 43) | 10 |
Praseodymium-142 (Pr 142) | 100 |
Praseodymium-143 (Pr 143) | 100 |
Promethium-147 (Pm 147) | 10 |
Promethium-149 (Pm 149) | 10 |
Rhenium-186 (Re 186) | 100 |
Rhenium-188 (Re 188) | 100 |
Rhodium-103m (Rh 103m) | 100 |
Rhodium-105 (Rh 105) | 100 |
Rubidium-81 (Rh 81) | 10 |
Rubidium-86 (Rb 86) | 10 |
Rubidium-87 (Rb 87) | 10 |
Ruthenium-97 (Ru 97) | 100 |
Ruthenium-103 (Ru 103) | 10 |
Ruthenium-105 (Ru 105) | 10 |
Ruthenium-106 (Ru 106) | 1 |
Samarium-151 (Sm 151) | 10 |
Samarium-153 (Sm 153) | 100 |
Scandium-46 (Sc 46) | 10 |
Scandium-47 (Sc 47) | 100 |
Scandium-48 (Sc 48) | 10 |
Selenium-75 (Se 75) | 10 |
Silicon-31 (Si 31) | 100 |
Silver-105 (Ag 105) | 10 |
Silver-110m (Ag 110m) | 1 |
Silver-111 (Ag 111) | 100 |
Sodium-22 (Na 22) | 10 |
Sodium-24 (Na 24) | 10 |
Strontium-85 (Sr 85) | 10 |
Strontium-89 (Sr 89) | 1 |
Strontium-90 (Sr 90) | 0.1 |
Strontium-91 (Sr 91) | 10 |
Strontium-92 (Sr 92) | 10 |
Sulphur-35 (S 35) | 100 |
Tantalum-182 (Ta 182) | 10 |
Technetium-96 (Tc 96) | 10 |
Technetium-97m (Tc 97m) | 100 |
Technetium-97 (Tc 97) | 100 |
Technetium-99m (Tc 99m) | 100 |
Technetium-99 (Tc 99) | 10 |
Tellurium-125m (Te 125m) | 10 |
Tellurium-127m (Te 127m) | 10 |
Tellurium-127 (Te 127) | 100 |
Tellurium-129m (Te 129m) | 10 |
Tellurium-129 (Te 129) | 100 |
Tellurium-131m (Te 131m) | 10 |
Tellurium-132 (Te 132) | 10 |
Terbium-160 (Tb 160) | 10 |
Thallium-200 (Tl 200) | 100 |
Thallium-201 (Tl 201) | 100 |
Thallium-202 (Tl 202) | 100 |
Thallium-204 (Tl 204) | 10 |
Thulium-170 (Tm 170) | 10 |
Thulium-171 (Tm 171) | 10 |
Tin-113 (Sn 113) | 10 |
Tin-125 (Sn 125) | 10 |
Tungsten-181 (W 181) | 10 |
Tungsten-185 (W 185) | 10 |
Tungsten-187 (W 187) | 100 |
Vanadium-48 (V 48) | 10 |
Xenon-131m (Xe 131m) | 1,000 |
Xenon-133 (Xe 133) | 100 |
Xenon-135 (Xe 135) | 100 |
Ytterbium-175 (Yb 175) | 100 |
Yttrium-87 (Y 87) | 10 |
Yttrium-88 (Y 88) | 10 |
Yttrium-90 (Y 90) | 10 |
Yttrium-91 (Y 91) | 10 |
Yttrium-92 (Y 92) | 100 |
Yttrium-93 (Y 93) | 100 |
Zinc-65 (Zn 65) | 10 |
Zinc-69m (Zn 69m) | 100 |
Zinc-69 (Zn 69) | 1,000 |
Zirconium-93 (Zr 93) | 10 |
Zirconium-95 (Zr 95) | 10 |
Zirconium-97 (Zr 97) | 10 |
Alpha emitting radioactive material not listed above | 0.01 |
Any radioactive material listed above other than alpha emitting radioactive material | 0.1 |
Note 1:For purposes of RH-305.a., where there is involved a combination of isotopes, the limit for the combination should be derived as follows:
Determine the amount of each isotope possessed and 1,000 times the amount in Schedule B for each of those isotopes when not in combination. The sum of the ratios of those quantities may not exceed 1. Example.
Element (atomic number) | Isotope | Column I Gas concentration Ci/ml12/ | Column II Liquid and solid concentration Ci/ml13/ |
Antimony (51) ---- Sb 122 | ------- | 3 X 10-4 | |
Sb 124 | ------- | 2 X 10-4 | |
Sb 125 | 1 X 10-3 | ||
Argon (18) ------ | A 37 | 1 X 10-3 | ----- |
A 41 | 4 X 10-7 | ||
Arsenic (33) ----- | As 73 | ------- | 5 X 10-3 |
As 74 | ------- | 5 X 10-4 | |
As 76 | ------- | 2 X 10-4 | |
As 77 | ------- | 8 X 10-4 | |
Barium (56) ----- | Ba 131 | ------- | 2 X 10-3 |
Ba 140 | ------- | 3 X 10-4 | |
Beryllium (4) ---- | Be 7 | ------- | 2 X 10-2 |
Bismuth (83) ---- | Bi 206 | 4 X 10-4 | |
Bromine (35) ---- | Br 82 | 4 X 10-7 | 3 X 10-3 |
Cadmium (48) --- | Cd 109 | ------- | 2 X 10-3 |
Cd 115m | ------- | 3 X 10-4 | |
Cd 115 | ------- | 3 X 10-4 | |
Calcium (20) ---- | Ca 45 | ------- | 9 X 10-5 |
Ca 47 | 5 X 10-4 | ||
Carbon (6) ------ | C 14 | 1 X 10-6 | 8 X 10-3 |
Cerium (58) ----- | Ce 141 | ------- | 9 X 10-4 |
Ce 143 | ------- | 4 X 10-4 | |
Ce 144 | ------- | 1 X 10-4 | |
Cesium (55) ---- | Cs 131 | ------- | 2 X 10-2 |
Cs 134m | ------- | 6 X 10-2 | |
Cs 134 | 9 X 10-5 | ||
Chlorine (17) ---- | Cl 38 | 9 X 10-7 | 4 X 10-3 |
Chromium (24) -- | Cr 51 | ------- | 2 X 10-2 |
Cobalt (27) ----- | Co 57 | ------- | 5 X 10-3 |
Co 58 | ------- | 1 X 10-3 | |
Co 60 | ------- | 5 X 10-4 | |
Copper (29) ---- | Cu 64 | ------- | 3 X 10-3 |
Dysprosium (66) - | Dy 165 | ------- | 4 X 10-3 |
Dy 166 | ------- | 4 X 10-4 | |
Erbium (68) --- | Er 169 | ------- | 9 X 10-4 |
Er 171 | ------- | 1 X 10-3 | |
Europium (63) - | Eu 152 - | ------- | 6 X 10-4 |
(T/2=9.2 hrs) | ------- | ||
Eu 155 | 2 X 10-3 | ||
Fluorine (9) --- | F 18 | 2 X 10-6 | 8 X 10-3 |
Gadolinium (64) | Gd 153 | ------- | 2 X 10-3 |
Gd 159 | ------- | 8 X 10-4 | |
Gallium (31) -- | Ga 72 | ------- | 4 X 10-4 |
Germanium (32) | Ge 71 | ------- | 2 X 10-2 |
Gold (79) ---- | Au 196 | ------- | 2 X 10-3 |
Au 198 | ------- | 5 X 10-4 | |
Au 199 | ------- | 2 X 10-3 | |
Hafnium (72) -- | Hf 181 | ------- | 7 X 10-4 |
Hydrogen (1) --- Indium (49) ---- | H 3 In 113m | 5 X 10-6 ------- | 3 X 10-2 1 X 10-2 |
In 114m | 2 X 10-4 | ||
Iodine (53) ---- | I 126 | 3 X 10-9 | 2 X 10-5 |
I 131 | 3 X 10-9 | 2 X 10-5 | |
I 132 | 8 X 10-8 | 6 X 10-4 | |
I 133 | 1 X 10-8 | 7 X 10-5 | |
I 134 | 2 X 10-7 | 1 X 10-3 | |
Iridium (77) --- | Ir 190 | ------- | 2 X 10-3 |
Ir 192 | ------- | 4 X 10-4 | |
Ir 194 | ------- | 3 X 10-4 | |
Iron (26) ----- | Fe 55 | ------- | 8 X 10-3 |
Fe 59 | 6 X 10-4 | ||
Krypton (36) -- | Kr 85m | 1 X 10-6 | ---- |
Kr 85 | 3 X 10-6 | ---- | |
Lanthanum (57) | La 140 | ------- | 2 X 10-4 |
Lead (82) ---- | Pb 203 | ------- | 4 X 10-3 |
Lutetium (71) -- | Lu 177 | ------- | 1 X 10-3 |
Manganese (25) | Mn 52 | ------- | 3 X 10-4 |
Mn 54 | ------- | 1 X 10-3 | |
Mn 56 | ------- | 1 X 10-3 | |
Mercury (80) -- | Hg 197m | ------- | 2 X 10-3 |
Hg 197 | ------- | 3 X 10-3 | |
Hg 203 | ------- | 2 X 10-4 | |
Molybdenum (42) | Mo 99 | ------- | 2 X 10-3 |
Neodymium (60) | Nd 147 | ------- | 6 X 10-4 |
Nd 149 | ------- | 3 X 10-3 | |
Nickel (28) --- | Ni 65 | ------- | 1 X 10-3 |
Niobium | |||
(Columbium)(41) | Nb 95 | ------- | 1 X 10-3 |
Nb 97 | ------- | 9 X 10-3 | |
Osmium (76) -- | Os 185 | ------- | 7 X 10-4 |
Os 191m | ------- | 3 X 10-2 | |
Os 191 | ------- | 2 X 10-3 | |
Os 193 | ------- | 6 X 10-4 | |
Palladium (46) - | Pd 103 | ------- | 3 X 10-3 |
Pd 109 | ------- | 9 X 10-4 | |
Phosphorus (15) | P 32 | ------- | 2 X 10-4 |
Platinum (78) - | Pt 191 | ------- | 1 X 10-3 |
Pt 193m | ------- | 1 X 10-2 | |
Pt 197m | ------- | 1 X 10-2 | |
Pt 197 | ------- | 1 X 10-3 | |
Polonium (84) - | Po 210 | ------- | 7 X 10-6 |
Potassium (19) | K 42 | ------- | 3 X 10-3 |
Praseodymium (50) - Pr 142 | ------- | 3 X 10-4 | |
Pr 143 | ------- | 5 X 10-4 | |
Pm 149 | ------- | 4 X 10-4 | |
Radium (88) -- | Ra 226 | ------- | 1 X 10-7 |
Ra 228 | ------- | 3 X 10-7 | |
Rhenium (75) - | Re 183 | ------- | 6 X 10-3 |
Re 186 | ------- | 9 X 10-4 | |
Re 188 | ------- | 6 X 10-4 | |
Rhodium (45) - | Rh 103m | ------- | 1 X 10-1 |
Rh 105 | ------- | 1 X 10-3 | |
Rubidium (37) - | Rb 86 | ------- | 7 X 10-4 |
Ruthenium (44) | Ru 97 | ------- | 4 X 10-3 |
Ru 103 | ------- | 8 X 10-4 | |
Ru 105 | ------- | 1 X 10-3 | |
Ru 106 | ------- | 1 X 10-4 | |
Samarium (62) | Sm 153 | ------- | 8 X 10-4 |
Scandium (21) | Sc 46 | ------- | 4 X 10-4 |
Sc 47 | ------- | 9 X 10-4 | |
Sc 48 | ------- | 3 X 10-4 | |
Selenium (34) -- | Se 75 | ------- | 3 X 10-3 |
Silicon (14) --- | Si 31 | ------- | 9 X 10-3 |
Silver (47) ---- | Ag 105 | ------- | 1 X 10-3 |
Ag 110m | ------- | 3 X 10-4 | |
Ag 111 | ------- | 4 X 10-4 | |
Sodium (11) -- | Na 24 | ------- | 2 X 10-3 |
Strontium (38) - | Sr 85 | ------- | 1 X 10-3 |
Sr 89 | ------- | 1 X 10-4 | |
Sr 91 | ------- | 7 X 10-4 | |
Sr 92 | 7 X 10-4 | ||
Sulfur (16) --- | S 35 | 9 X 10-8 | 6 X 10-4 |
Tantalum (73) - | Ta 182 | ------- | 4 X 10-4 |
Technetium (43) | Tc 96m | ------- | 1 X 10-1 |
Tc 96 | ------- | 1 X 10-3 | |
Tellurium (52) - | Te 125m | ------- | 2 X 10-3 |
Te 127m | ------- | 6 X 10-4 | |
Te 127 | ------- | 3 X 10-3 | |
Te 129m | ------- | 3 X 10-4 | |
Te 131m | ------- | 6 X 10-4 | |
Te 132 | ------- | 3 X 10-4 | |
Terbium (65) -- | Tb 160 | ------- | 4 X 10-4 |
Thallium (81) -- | Tl 200 | ------- | 4 X 10-3 |
Tl 201 | ------- | 3 X 10-3 | |
Tl 202 | ------- | 1 X 10-3 | |
Tl 204 | ------- | 1 X 10-3 | |
Thulium (69) -- | Tm 170 | ------- | 5 X 10-4 |
Tm 171 | ------- | 5 X 10-3 | |
Tin (50) ----- | Sn 113 | ------- | 9 X 10-4 |
Sn 125 | ------- | 2 X 10-4 |
Tungsten | |||
(Wolfram)(74)-- | W 181 | -------- | 4 X 10-3 |
W 187 | -------- | 7 X 10-4 | |
Vanadium (23) - | V 48 | 3 X 10-4 | |
Xenon (54) --- | Xe 131m | 4 X 10-6 | ------ |
Xe 133 | 3 X 10-6 | ------ | |
Xe 135 | 1 X 10-6 | ||
Ytterbium (80) - | Yb 175 | -------- | 1 X 10-3 |
Yttrium (30) --- | Y 90 | -------- | 2 X 10-4 |
Y 91m | -------- | 3 X 10-2 | |
Y 91 | -------- | 3 X 10-4 | |
Y 92 | 6 X 10-4 | ||
-4 | |||
______ | -3 | ||
----- | -4 | ||
-2 | |||
-4 | |||
Zr 97 | -------- | 2 X 10-4 | |
Beta and/or gamma | emitting | ||
radioactive material | not | ||
listed above with ha | lf- | ||
life less than 3 years | -- | 1 X 10-10 | 1 X 10-6 |
NOTE 1: Many radioisotopes disintegrate into isotopes which are also radioactive. In expressing the concentrations in Schedule C, the activity stated is that of the parent isotope and takes into account the daughters.
NOTE 2: For purposes of RH-301. where there is involved a combination of isotopes, the limit for the combination should be derived as follows: Determine for each isotope in the product the ratio between the concentration present in the product and the exempt concentration established in Schedule C for the specific isotope when not in combination. The sum of such ratios may not exceed "1" (i.e. unity).
Example:
Radioactive Material | Column I Curies | Column II Curies |
Antimony-122 | 1 | 0.01 |
Antimony-124 | 1 | 0.01 |
Antimony-125 | 1 | 0.01 |
Arsenic-73 | 10 | 0.1 |
Arsenic-74 | 1 | 0.01 |
Arsenic-76 | 1 | 0.01 |
Arsenic-77 | 10 | 0.1 |
Barium-131 | 10 | 0.1 |
Barium-140 | 1 | 0.01 |
Beryllium-7 | 10 | 0.1 |
Bismuth-210 | 0.1 | 0.001 |
Bromine-82 | 10 | 0.1 |
Cadmium-109 | 1 | 0.01 |
Cadmium-115m | 1 | 0.01 |
Cadmium-115 | 10 | 0.1 |
Calcium-45 | 1 | 0.01 |
Calcium-47 | 10 | 0.1 |
Carbon-14 | 100 | 1. |
Cerium-141 | 10 | 0.1 |
Cerium-143 | 10 | 0.1 |
Cerium-144 | 0.1 | 0.001 |
Cesium-131 | 100 | 1. |
Cesium-134m | 100 | 1. |
Cesium-134 | 0.1 | 0.001 |
Cesium-135 | 1 | 0.01 |
Cesium-136 | 10 | 0.1 |
Cesium-137 | 0.1 | 0.001 |
Chlorine-36 | 1 | 0.01 |
Chlorine-38 | 100 | 1. |
Chronmium-51 | 100 | 1. |
Cobalt-57 | 10 | 0.1 |
Cobalt-58m | 100 | 1. |
Cobalt-58 | 1 | 0.01 |
Cobalt-60 | 0.1 | 0.001 |
Copper-64 | 10 | 0.1 |
Dysprosium-165 | 100 | 1. |
Dysprosium-166 | 10 | 0.1 |
Erbium-169 | 10 | 0.1 |
Erbium-171 | 10 | 0.1 |
Europium-152 9.2 h | 10 | 0.1 |
Europium-152 13 y | 0.1 | 0.001 |
Europium-154 | 0.1 | 0.001 |
Europium-155 | 1 | 0.01 |
Fluorine-18 | 100 | 1. |
Gadolinium-153 | 1 | 0.01 |
Gadolinium-159 | 10 | 0.1 |
Gallium-72 | 10 | 0.1 |
Germanium-71 | 100 | 1. |
Gold-198 | 10 | 0.1 |
Gold-199 | 10 | 0.1 |
Hafnium-181 | 1 | 0.01 |
Holmium-166 | 10 | 0.1 |
Hydrogen-3 | 100 | 1. |
Indium-113m | 100 | 1. |
Indium-114m | 1 | 0.01 |
Indium-115m | 100 | 1. |
Indium-115 | 1 | 0.01 |
Iodine-125 | 0.1 | 0.001 |
Iodine-126 | 0.1 | 0.001 |
Iodine-129 | 0.1 | 0.001 |
Iodine-131 | 0.1 | 0.001 |
Iodine-132 | 10 | 0.1 |
Iodine-133 | 1 | 0.01 |
Iodine-134 | 10 | 0.1 |
Iodine-135 | 1 | 0.01 |
Iridium-192 | 1 | 0.01 |
Iridium-194 | 10 | 0.1 |
Iron-55 | 10 | 0.1 |
Iron-59 | 1 | 0.01 |
Krypton-85 | 100 | 1. |
Krypton-87 | 10 | 0.1 |
Lanthanum-140 | 1 | 0.01 |
Lutetium-177 | 10 | 0.1 |
Manganese-52 | 1 | 0.01 |
Manganese-54 | 1 | 0.01 |
Manganese-56 | 10 | 0.1 |
Mercury-197m | 10 | 0.1 |
Mercuty-197 | 10 | 0.1 |
Mercury-203 | 1 | 0.01 |
Molybdenum-99 | 10 | 0.1 |
Neodymium-147 | 10 | 0.1 |
Neodymium-149 | 10 | 0.1 |
Nickel-59 | 10 | 0.1 |
Nickel-63 | 1 | 0.01 |
Nickel-65 | 10 | 0.1 |
Niobium-93m | 1 | 0.01 |
Niobium-95 | 1 | 0.01 |
Niobium-97 | 100 | 1. |
Osmium-185 | 1 | 0.01 |
Osmium-191m | 100 | 1. |
Osmium-191 | 10 | 0.1 |
Osmium-193 | 10 | 0.1 |
Palladium-103 | 10 | 0.1 |
Palladium-109 | 10 | 0.1 |
Phosphorus-32 | 1 | 0.01 |
Platinum-191 | 10 | 0.1 |
Platinum-193m | 100 | 1. |
Platinum-193 | 10 | 0.1 |
Platinum-197m | 100 | 1. |
Platinum-197 | 10 | 0.1 |
Polonium-210 | 0.01 | 0.0001 |
Potassium-42 | 1 | 0.01 |
Praseodymium-142 | 10 | 0.1 |
Praseodymium-143 | 10 | 0.1 |
Promethium-147 | 1 | 0.01 |
Promethium-149 | 10 | 0.1 |
Radium-226 | 0.01 | 0.0001 |
Rhenium-186 | 10 | 0.1 |
Rhenium-188 | 10 | 0.1 |
Rhodium-103m | 1,000 | 10. |
Rhodium-105 | 10 | 0.1 |
Rubidium-86 | 1 | 0.01 |
Rubidium-87 | 1 | 0.01 |
Ruthenium-97 | 100 | 1. |
Ruthenium-103 | 1 | 0.01 |
Ruthenium-105 | 10 | 0.1 |
Ruthenium-106 | 0.1 | 0.001 |
Samarium-151 | 1 | 0.01 |
Samarium-153 | 10 | 0.1 |
Scandium-46 | 1 | 0.01 |
Scandium-47 | 10 | 0.1 |
Scandium-48 | 1 | 0.01 |
Selenium-75 | 1 | 0.01 |
Silicon-31 | 10 | 0.1 |
Silver-105 | 1 | 0.01 |
Silver-110m | 0.1 | 0.001 |
Silver-111 | 10 | 0.1 |
Sodium-22 | 0.1 | 0.001 |
Sodium-24 | 1 | 0.01 |
Strontium-85m | 1,000 | 10. |
Strontium-85 | 1 | 0.01 |
Strontium-89 | 1 | 0.01 |
Strontium-90 | 0.01 | 0.0001 |
Strontium-91 | 10 | 0.1 |
Strontium-92 | 10 | 0.1 |
Sulfur-35 | 10 | 0.1 |
Tantalum-182 | 1 | 0.01 |
Technetium-96 | 10 | 0.1 |
Technetium-97m | 10 | 0.1 |
Technetium-97 | 10 | 0.1 |
Technetium-99m | 100 | 1. |
Technetium-99 | 1 | 0.01 |
Tellurium-125m | 1 | 0.01 |
Tellurium-127m | 1 | 0.01 |
Tellurium-127 | 10 | 0.1 |
Tellurium-129m | 1 | 0.01 |
Tellurium-129 | 100 | 1. |
Tellurium-131m | 10 | 0.1 |
Tellurium-132 | 1 | 0.01 |
Terbium-160 | 1 | 0.01 |
Thallium-200 | 10 | 0.1 |
Thallium-201 | 10 | 0.1 |
Thallium-202 | 10 | 0.1 |
Tallium-204 | 1 | 0.01 |
Thulium-170 | 1 | 0.01 |
Thulium-171 | 1 | 0.01 |
Tin-113 | 1 | 0.01 |
Tin-125 | 1 | 0.01 |
Tungsten-181 | 1 | 0.01 |
Tungsten-185 | 1 | 0.01 |
Tungsten-187 | 10 | 0.1 |
Vanadium-48 | 1 | 0.01 |
Xenon-131m | 1,000 | 10. |
Xenon-133 | 100 | 1. |
Xenon-135 | 100 | 1. |
Ytterbium-175 | 10 | 0.1 |
Yttrium-90 | 1 | 0.01 |
Yttrium-91 | 1 | 0.01 |
Yttrium-92 | 10 | 0.1 |
Yttrium-93 | 1 | 0.01 |
Zinc-65 | 1 | 0.01 |
Zinc-69m | 10 | 0.1 |
Zinc-69 | 100 | 1. |
Zirconium-93 | 1 | 0.01 |
Zirconium-95 | 1 | 0.01 |
Zirconium-97 | 1 | 0.01 |
Any radioactive material other | ||
than alpha emitting radioactive | ||
material, source material | ||
or special nuclear material | ||
not listed above | 0.1 | 0.001 |
Radioactive Material 15/16/ | Release Fraction | Quantity (Curies) |
Actinium-228 | 0.001 | 4,000 |
Americium-241 | .001 | 2 |
Americium-242 | .001 | 2 |
Americium-243 | .001 | 2 |
Antimony-124 | .01 | 4,000 |
Antimony-126 | .01 | 6,000 |
Barium-133 | .01 | 10,000 |
Barium-140 | .01 | 30,000 |
Bismuth-207 | .01 | 5,000 |
Bismuth-210 | .01 | 600 |
Cadmium-109 | .01 | 1,000 |
Cadmium-113 | .01 | 80 |
Calcium-45 | .01 | 20,000 |
Californium-252 | .001 | 9 (20 mg) |
Carbon-14 (Non CO) | .01 | 50,000 |
Cerium-141 | .01 | 10,000 |
Cerium-144 | .01 | 300 |
Cesium-134 | .01 | 2,000 |
Cesium-137 | .01 | 3,000 |
Chlorine-36 | .5 | 100 |
Chromium-51 | .01 | 300,000 |
Cobalt-60 | .001 | 5,000 |
Copper-64 | .01 | 200,000 |
Curium-242 | .001 | 60 |
Curium-243 | .001 | 3 |
Curium-244 | .001 | 4 |
Curium-245 | .001 | 2 |
Europium-152 | .01 | 500 |
Europium-154 | .01 | 400 |
Europium-155 | .01 | 3,000 |
Gadolinium-153 | .01 | 5,000 |
Germanium-68 | .01 | 2,000 |
Gold-198 | .01 | 30,000 |
Hafnium-172 | .01 | 400 |
Hafnium-181 | .01 | 7,000 |
Holmium-166m | .01 | 100 |
Hydrogen-3 | .5 | 20,000 |
Iodine-125 | .5 | 10 |
Iodine-131 | .5 | 10 |
Indium-114m | .01 | 1,000 |
Iridium-192 | 0.001 | 40,000 |
Iron-55 | .01 | 40,000 |
Iron-59 | .01 | 7,000 |
Krypton-85 | 1.0 | 6,000,000 |
Lead-210 | .01 | 8 |
Maganese-56 | .01 | 60,000 |
Mercury-203 | .01 | 10,000 |
Molybdenum-99 | .01 | 30,000 |
Neptunium-237 | .001 | 2 |
Nickel-63 | .01 | 20,000 |
Niobium-94 | .01 | 300 |
Phosphors-32 | .5 | 100 |
Phosphorus-33 | .5 | 1,000 |
Polonium-210 | .01 | 10 |
Potassium-42 | .01 | 9,000 |
Promethium-145 | .01 | 4,000 |
Promethium-147 | .01 | 4,000 |
Ruthenium-106 | .01 | 200 |
Samarium-151 | .01 | 4,000 |
Scandium-46 | .01 | 3,000 |
Selenium-75 | .01 | 10,000 |
Silver-110m | .01 | 9,000 |
Sodium-24 | .01 | 10,000 |
Strontium-89 | .01 | 3,000 |
Strontium-90 | .01 | 90 |
Sulfur-35 | .5 | 900 |
Technetium-99 | .01 | 10,000 |
Technetium-99m | .01 | 400,000 |
Tellurium-127m | .01 | 5,000 |
Tellurium-129m | .01 | 5,000 |
Terbium-160 | .01 | 4,000 |
Thulium-170 | .01 | 4,000 |
Tin-113 | .01 | 10,000 |
Tin-123 | .01 | 3,000 |
Tin-126 | .01 | 1,000 |
Titanium-44 | .01 | 100 |
Vanadium-48 | .01 | 7,000 |
Xenon-133 | 1.0 | 900,000 |
Yttrium-91 | .01 | 2,000 |
Zinc-6 | .01 | 5,000 |
Zirconium-93 | .01 | 400 |
Zirconium-95 | .01 | 5,000 |
Any other beta-gamma emitter | .01 | 10,000 |
Mixed fission products | .01 | 1,000 |
Mixed corrosion products | .01 | 10,000 |
Contaminated equipment, beta-gamma Irradiated material, any form other than solid noncombustible | .001 .01 | 10,000 1,000 |
Irradiated material, solid noncombustible Mixed radioactive waste, beta-gamma Packaged mixed waste, beta-gamma | .001 .01 .001 | 10,000 1,000 10,000 |
Any other alpha emitter | .001 | 2 |
Contaminated equipment, ALPHA | .0001 | 20 |
Packaged waste, alpha 16/ | .0001 | 20 |
Combinations of radioactive materials listed above 15/ | -- | -- |
APPENDIX A:
Criteria Relating to Use of Financial Tests
and Parent Company Guarantees for Providing Reasonable
Assurance of Funds for Decommissioning
An applicant or licensee may provide reasonable assurance of the availability of funds for decommissioning based on obtaining a parent company guarantee that funds will be available for decommissioning costs and on a demonstration that the parent company passes a financial test. This appendix established criteria for passing the financial test and for obtaining the parent company guarantee.
The terms of a parent company guarantee which an applicant or licensee obtains must provide that:
APPENDIX B: Criteria Relating to Use of Financial Tests
and Self Guarantees for Providing Reasonable
Assurance of Funds for Decommissioning
An applicant or licensee may provide reasonable assurance of the availability of funds for decommissioning based on furnishing its own guarantee that funds will be available for decommissioning costs and on a demonstration that the company passes a financial test of Section Il of Appendix B. The terms of the self-guarantee are in Section III of Appendix B. This Appendix establishes criteria for passing the financial test for the self-guarantee and establishes the terms for a self-guarantee.
Appendix B, the licensee must send notice to the Department of its intent to establish alternate financial assurance as specified in the Department's Regulations within 120 days of such notice.
The terms of a self-guarantee which an applicant or licensee obtains must provide that:
APPENDIX C: Criteria Relating to Use of Financial Tests and Self Guarantees for Providing Reasonable Assurance of Funds for Decommissioning by Commercial Companies That Have no Outstanding Rated Bonds
An applicant or licensee may provide reasonable assurance of the availability of funds for decommissioning based on furnishing its own guarantee that funds will be available for decommissioning costs and on a demonstration that the company passes a financial test of Section II of APPENDIX C. The terms of the self-guarantee are in Section III of APPENDIX C. This Appendix establishes criteria for passing the financial test for the self-guarantee and establishes the terms for a self-guarantee.
times the total current decommissioning cost estimate (or the current amount required if certification is used), whichever is greater, for all decommissioning activities for which the company is responsible as self-guaranteeing licensee and as parent-guarantor.
The terms of a self-guarantee which an applicant or licensee furnishes must provide that:
APPENDIX D: Criteria Relating to Use of Financial Tests and Self Guarantees for Providing Reasonable Assurance of Funds for Decommissioning by Nonprofit Colleges, Universities, and Hospitals
An applicant or licensee may provide reasonable assurance of the availability of funds for decommissioning based on furnishing its own guarantee that funds will be available for decommissioning costs and on a demonstration that the applicant or licensee passes a financial test of Section II of APPENDIX D. The terms of the self-guarantee are in Section III of APPENDIX D. This Appendix establishes criteria for passing the financial test for the self-guarantee and establishes the terms for a self-guarantee.
The terms of a self-guarantee which an applicant or licensee furnishes must provide that:
FOOTNOTES FOR SECTION 2
1/ Attention is directed to the fact that regulation by the State of source material, byproduct material and special nuclear material in quantities not sufficient to form a critical mass is subject to the provisions of the agreement between the State and the U.S. Nuclear Regulatory Commission and to 10 CFR Part 150 of the Commission's regulations.
2/ The requirements specified in Subdivision B and C of this Subparagraph need not be met by counterweights manufactured prior to December 31, 1969; provided that such counterweights are impressed with the legend, "CAUTION - RADIOACTIVE MATERIAL - URANIUM," as previously required by these Regulations.
3/ Authority to transfer possession or control by the manufacturer, processor or producer of any equipment, device, commodity or other product containing source or byproduct material whose subsequent possession, use, transfer and disposal by all other persons are exempted from regulatory requirements may be obtained only from the U.S. Nuclear Regulatory Commission, Washington, D.C. 20555.
4/ For purposes of this Subparagraph, "electron tubes" include spark gap tubes, power tubes, gas tubes including glow lamps, receiving tubes, microwaves tubes, indicator tubes, pick-up tubes, radiation detection tubes and any other completely sealed tube that is designed to conduct or control electrical currents.
5/ Authority to transfer possession or control by the manufacturer, processor or producer of any equipment, device, commodity or other product containing byproduct material whose subsequent possession, use, transfer and disposal by all other persons are exempted from regulatory requirements may be obtained only from the U.S. Nuclear Regulatory Commission, Washington, D.C. 20555.
6/ Attention is directed particularly to the provisions of Section 3 of these
Regulations which relate to the labeling of containers.
7/ Any notification of incidents referred to in those requirements shall be filed with or made to the Department.
8/ The New Drug provisions of the Federal Food, Drug and Cosmetic Act also govern the availability and use of any specific diagnostic drugs in interstate commerce.
9/ The model, serial number and name of manufacturer or distributor may be omitted from this label provided they are elsewhere specified in labeling affixed to the device.
10/ Deleted. Deleted when RH-405.m. was deleted.
11/ Authority to transfer possession or control by the manufacturer, processor or producer of any equipment, device, commodity or other product containing source or byproduct material whose subsequent possession, use, transfer and disposal by all other persons are exempted from regulatory requirements may be obtained only from the U.S. Nuclear Regulatory Commission, Washington, D.C. 20555.
12/ Values are given in Column 1 only for those materials normally used in gases.
13/ Ci/gm for solids.
14/ These reporting requirements do not supersede or release licensee of complying with the requirements under the Emergency Planning and Community Right-to-Know Act of 1986, Title III, Pubic Law 99-499 or other state or federal reporting requirements.
15/ For combinations of radioactive materials, consideration of the need an emergency plan is required if the sum of the ratios of the quantity of for each radioactive material authorized to the quantity listed for that material in Schedule F exceeds one.
16/ Waste packaged in Type B containers does not require an emergency plan.
(FOOTNOTES APPEAR AT THE END OF THIS SECTION)
.
cartridge, or canister that removes specific air contaminants by passing ambient air through the air-purifying element.
v Controlled area - An area, outside of a restricted area but inside the site boundary, access to which can be limited by the licensee for any reason.
independent establishment, corporation wholly or partly owned by the United States of America, which is an instrumentality of the United States, or any board, bureau, division, service, office, officer, authority, administration, or other establishment in the executive branch of the Government.
groundwater, and other media at a site resulting from activities under the licensee's control. This includes radioactivity from all licensed and unlicensed sources used by the licensee, but, excludes background radiation. It also includes radioactive materials remaining at the site as a result of routine or accidental releases of radioactive material at the site even if those burials were made in accordance with the provision of Section 3. Part E. Waste Disposal.
Note: At very high doses received at high dose rates, units of absorbed dose (e.g., rads and grays) are appropriate, rather than units of dose equivalent (e.g., rems and sieverts).
ORGAN DOSE WEIGHTING FACTORS
Organ or Tissue | w T |
Gonads | 0.25 |
Breast | 0.15 |
Red bone marrow | 0.12 |
Lung | 0.12 |
Thyroid | 0.03 |
Bone surfaces | 0.03 |
Remainder | 0.30a |
Whole Body | 1.00b |
a 0.30 results from 0.06 for each of 5 "remainder" organs (excluding the skin and the lens of the eye) that receive the highest doses.
b For the purpose of weighting the external whole body dose (for adding it to the internal dose), a single weighting factor, wT = 1.0, has been specified. The use of other weighting factors for external exposure will be approved on a case-by-case basis until such time as specific guidance is issued.
As used in this Part, the units of radiation dose are:
TABLE RH-1102 #1
QUALITY FACTORS AND ABSORBED DOSE EQUIVALENCIES
TYPE OF RADIATION Factor | Quality (Q) | Absorbed Dose Equal to a Unit Dose Equivalenta |
X-, gamma, or beta radiation | 1 | 1 |
Alpha particles, multiple-charged particles, fission fragments and heavy particles of unknown charge | 20 | 0.05 |
Neutrons of unknown energy | 10 | 0.1 |
High-energy protons | 10 | 0.1 |
a Absorbed dose in rad equal to 1 rem or the absorbed dose in gray equal to 1 sievert.
TABLE RH-1102 #2
MEAN QUALITY FACTORS, Q, AND FLUENCE PER UNIT DOSE EQUIVALENT FOR MONOENERGETIC NEUTRONS
Neutron Energy (MeV) | Quality Factora (Q) | Fluence per Unit Dose Equivalentb (neutrons cm-2 rem-1) | |
(thermal) | 2.5 x 10-8 1 x 10-7 1 x 10-6 1 x 10-5 1 x 10-4 1 x 10-3 1 x 10-2 1 x 10-1 | 2 2 2 2 2 2 2.5 7.5 | 980 x 106 980 x 106 810 x 106 810 x 106 840 x 106 980 x 106 1010 x 106 170 x 106 |
5 x 10-1 | 11 | 39 x 106 | |
1 | 11 | 27 x 106 | |
2.5 | 9 | 29 x 106 | |
5 | 8 | 23 x 106 | |
7 | 7 | 24 x 106 | |
10 | 6.5 | 24 x 106 | |
14 | 7.5 | 17 x 106 | |
20 | 8 | 16 x 106 | |
40 | 7 | 14 x 106 | |
60 | 5.5 | 16 x 106 | |
1 x 102 | 4 | 20 x 106 | |
2 x 102 | 3.5 | 19 x 106 | |
3 x 102 | 3.5 | 16 x 106 | |
4 x 102 | 3.5 | 14 x 106 |
a Value of quality factor (Q) at the point where the dose equivalent is maximum in a 30 cm diameter cylinder tissue-equivalent phantom.
b Monoenergetic neutrons incident normally on a 30 cm diameter cylinder tissue-equivalent phantom.
For the purposes of this Part, activity is expressed in the special unit of curies (Ci) or in the SI unit of becquerels (Bq), or their multiples, or disintegrations (transformations) per unit of time.
Except as specifically authorized by the Department in writing, no interpretation of the meaning of the Regulations in this Part by an officer or employee of the Department other than a written interpretation by the Department Director or designee will be recognized to be binding upon the Department.
NOTE: 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.
NOTE: The intake through intact skin has been included in the calculation of DAC for Hydrogen-3 and does not need to be further evaluated.
Licensees shall, when determining the dose from airborne radioactive material, include the contribution to the deep-dose equivalent, eye dose equivalent, and shallow-dose equivalent from external exposure to the radioactive cloud (See Appendix G to RH-1000. through RH-2110., footnotes 1 and 2).
NOTE: Airborne radioactivity measurements and DAC values should 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 should be based upon measurements using instruments or individual monitoring devices.
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 5 rems (0.05 Sv) for radionuclides that have their ALIs or DACs based on the committed effective dose equivalent.
In this case, 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 must also demonstrate that the limits in RH-1200.a.1.i. and ii. are met.
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 RH-1201. provided that each of the following conditions is satisfied:
The annual occupational dose limits for minors are ten (10%) percent of the annual dose limits specified for adult workers in RH-1200.
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 require a licensee to make available to the individual appropriate bioassay services and to furnish a copy of the reports of such services to the Department.
NUCLIDE1 | AVERAGE2,3,6 | MAXIMUM2,4,6 | REMOVABLE2,3,5,6 |
U-nat, U-235, U-238, and associated decay products except Ra-226, Th-230, Ac-227, and Pa-231 | 5,000 dpm alpha/ 100 cm2 | 15,000 dpm alpha/ 100 cm2 | 1,000 dpm alpha/ 100 cm2 |
Transuranics, Ra-226 Ra-228, Th-230, Th-228, Pa-231, Ac-227, I-129 | 100 dpm/ 100 cm2 | 300 dpm/ 100 cm2 | 20 dpm/ 100 cm2 |
Th-nat, Th-232, Sr-90, Ra-223, Ra-224, U-232, I-125, I-126, I-131, I-133 | 1,000 dpm/ 100 cm2 | 3,000 dpm/ 100 cm2 | 200 dpm/ 100 cm2 |
Beta-gamma emitters (nuclides with decay modes other than alpha emission or spontaneous fission) except Sr-90 and others noted above. | 5,000 dpm beta, gamma/ 100 cm2 | 15,000 dpm, beta, gamma/ 100 cm2 | 1,000 dpm beta gamma/ 100 cm2 |
FOOTNOTES FOR TABLE RH-1213.b.: ACCEPTABLE SURFACE CONTAMINATION LEVELS
1 Where surface contamination by both alpha and beta-gamma emitting nuclides exists, the limits established for alpha and beta-gamma emitting nuclides should apply independently.
2 As used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background efficiency, and geometric factors associated with the instrumentation.
3 Measurements of average contamination level should not be averaged over more than one square meter. For objects of less surface area, the average should be derived for each object.
4 The maximum contamination level applies to an area of not more than 100 cm2.
5 The amount of removable radioactive material per 100 cm2 of surface area should be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped.
6 The average and maximum radiation levels associated with surface contamination resulting from beta-gamma emitters should not exceed 0.2 mrad/hr at one (1) cm and 1.0 mrad/hr at 1 cm, respectively, measured through not more than seven (7) milligrams per square centimeter of total absorber.
A site will be considered acceptable for unrestricted use if the residual radioactivity that is distinguishable from background radiation results in a TEDE to an average member of the critical group that does not exceed 25 mrem (0.25 mSv) per year, including that from groundwater sources of drinking water, and the residual radioactivity has been reduced to levels that are as low as reasonably achievable (ALARA). Determination of the levels which are ALARA must take into account consideration of any detriments, such as deaths from transportation accidents, expected to potentially result from decontamination and waste disposal.
A site will be considered acceptable for license termination under restricted conditions if:
Termination Plan (LTP) to the Department indicating the licensee's intent to decommission in accordance with RH-410.d. and specifying that the licensee intends to decommission by restricting use of the site. The licensee shall document in the LTP or decommissioning plan how the advice of individuals and institutions in the community who may be affected by the decommissioning has been sought and incorporated, as appropriate, following analysis of that advice.
from residual radioactivity distinguishable from background to the average member of the critical group will not exceed 25 mrem (0.25 mSv) TEDE per year;
Upon the receipt of an LTP or decommissioning plan from the licensee, or a proposal by the licensee for release of a site pursuant to RH-1217. or RH-1218., or whenever the Department deems such notice to be in the public interest, the Department shall:
Applicants for licenses, other than renewals, shall describe in the application how facility design and procedures for operation will minimize, to the extent practicable, contamination of the facility and the environment, facilitate eventual decommissioning, and minimize, to the extent practicable, the generation of radioactive waste.
Each portable gauge licensee shall use a minimum of two (2) 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.
Each licensee or registrant shall monitor exposures to radiation and radioactive material at levels sufficient to demonstrate compliance with the occupational dose limits this Part. As a minimum: of
NOTE: All of the occupational doses in RH-1200. continues to be applicable to the declared pregnant worker as long as the embryo/fetus dose limit is not exceeded.
CAUTIONDANGER
or RADIATION AREARADIATION AREA
CAUTIONDANGER
or HIGH RADIATION AREAHIGH RADIATION AREA
Very high radiation areas. In addition to the requirements in RH-1311., the licensee or registrant shall institute additional measures to ensure that an individual is not able to gain unauthorized or inadvertent access to areas in which radiation levels could be encountered at 500 rads (5 grays) or more in one (1) hour at one (1) meter from a radiation source or any surface through which the radiation penetrates.
GRAVE DANGER, VERY HIGH RADIATION AREA
CAUTIONDANGER
or AIRBORNE RADIOACTIVITY AREA AIRBORNE RADIOACTIVITY AREA
repair, testing, and quality assurance of respiratory protection equipment;
Control Section Chief at least thirty (30) days before the date that respiratory protection equipment is first used under the provisions of RH-1303.f.5.A.
The Department may impose restrictions in addition to those in RH-1303.f.4. and RH-1303.f.5. and Appendix E to RH-1000. through RH-2110. to:
CAUTIONDANGER
or
RADIOACTIVE MATERIALRADIOACTIVE MATERIAL
CAUTIONDANGER
or
RADIOACTIVE MATERIALRADIOACTIVE MATERIAL
It shall also provide sufficient information3/ to permit individuals handling or using the containers or working in the vicinity thereof, to take precautions to avoid or minimize exposures.
CAUTIONDANGER
or
RADIOACTIVE MATERIALRADIOACTIVE MATERIAL
It shall also provide sufficient information3/ to permit individuals handling or using the containers or working in the vicinity thereof, to take precautions to avoid or minimize exposures.
Instructions required for individuals working in or frequenting any portion of a restricted area are specified in Part N of this Section.
* Labeled with a Radioactive White I, Yellow II, or Yellow III label as specified in U.S. Department of Transportation regulations, 49 CFR 172.403 and 172.436-440.
The licensee shall control and maintain constant surveillance of licensed material that is in a controlled or unrestricted area and that is not in storage.
A licensee or applicant for a license may apply to the Department for approval of proposed procedures, not otherwise authorized in the Regulations in this Section, to dispose of licensed material generated in the licensee's activities. Each application shall include:
Paragraph a.3.i. of this Section does not exceed unity; and
No licensee shall dispose of radioactive material by burial in soil unless specific approval has been granted by the Department.
A licensee may treat or dispose of licensed material by incineration only in the amounts and forms specified in RH-1405. or as specifically approved by the Department pursuant to RH-1401.
Nothing in this Subpart 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 of under this Part E.
Form Z or equivalent until the Department terminates each pertinent license requiring this record. The licensee or registrant shall retain records used in preparing Department Form Z for three (3) years after the record is made.
Each licensee or registrant shall report promptly by telephone and confirm promptly by letter to the Department of Health and Human Services, Radiation Control Section, P. O. Box 1437, Mail Slot H-30, Little Rock, Arkansas 72203-1437, the theft or loss as soon as such theft or loss becomes known to the licensee or registrant of:
All licensees or registrants shall make reports to the Department at 1-800-633 -1735.
Section shall, within 30 days after making the telephone report, make a written report setting forth the following information:
Department or shall permit the Agency to perform, such reasonable tests as the Department deems appropriate or necessary including, but not limited to, tests of:
each licensee or registrant shall submit a written report within 30 days after learning of any of the following occurrences:
Each specific licensee shall, no less than thirty (30) days before vacating or relinquishing possession or control of premises which may have been contaminated with radioactive material as a result of the activities, notify the Department in writing of intent to vacate. When deemed necessary by the Department, the licensee shall decontaminate the premises in such a manner as the Department may specify.
TABLE RH-1509.a.2.
Radionuclide | Quantity of Radionuclidea in Curies |
Cesium-137 | 1 |
Cobalt-60 | 1 |
Gold-198 | 100 |
Iodine-131 | 1 |
Iridium-192 | 10 |
Krypton-85 | 1,000 |
Promethium-147 | 10 |
Technetium-99m | 1,000 |
a The Department may require as a license condition, or by rule, Regulation, or order pursuant to RH-2002., reports from licensees who are licensed to use radionuclides not on this list, in quantities sufficient to cause comparable radiation levels.
shall have the following records available at the temporary jobsite for inspection by the Department:
This Part establishes requirements, for which a registrant (or licensee) is responsible, for use of x-ray equipment by or under the supervision of an individual authorized by and licensed in accordance with state statutes to engage in the healing arts or veterinary medicine. The provisions of this Part are in addition to and not in substitution for, other applicable provisions of these Regulations.
where:
s = Estimated standard deviation of the population.
X = Mean value of observations in sample.
Xi = ith observation in sample.
n = Number of observations in sample.
limiting device attached.
Percent line-voltage regulation - 100(Vn-V1)/V1
where
Vn = No-load line potential and V1 = Load line potential.
*formerly NBS (National Bureau of Standards)
Regulations shall not be operated for diagnostic or therapeutic purposes.
TABLE I
Design Operating Range (Kilovolts peak) | Measured Potential (Kilovolts peak) | Half-value Layer (Millimeters of aluminum) |
--- Below 50 --- | 30 | 0.3 |
40 | 0.4 | |
49 | 0.5 | |
--- 50 to 70 --- | 50 | 1.2 |
60 | 1.3 | |
70 | 1.5 | |
--- Above 70 --- | 71 | 2.1 |
80 | 2.3 | |
90 | 2.5 | |
100 | 2.7 | |
110 | 3.0 | |
120 | 3.2 | |
130 | 3.5 | |
140 | 3.8 | |
150 | 4.1 |
TABLE II
Filtration Required vs. Operating Voltage | |
Operating Voltage (kVp) | Total Filtration (inherent plus added) (millimeters aluminum equivalent) |
Below 50 | 0.5 millimeters |
50 to 70 | 1.5 millimeters |
Above 70 | 2.5 millimeters |
All fluoroscopic x-ray systems shall meet the following requirements:
February 25, 1978, if the angle between the plane of the image receptor and beam axis is variable, means shall be provided to indicate when the axis of the x-ray beam is perpendicular to the plane of the image receptor, and compliance shall be determined with the beam axis indicated to be perpendicular to the plane of the image receptor.
shall include in a log for Department review the estimated patient radiation exposure received per procedure. Estimated adult skin doses that exceed 300 rad and estimated skin doses for children (under the age of 18) that exceed 100 rad must be reviewed by the facility's radiation safety committee.
The review must document the reason why an estimated skin dose exceeded 300 rad for adults or 100 rad for children, and the reason must be documented in the committee's minutes. If a facility does not have a radiation safety committee, the facility must provide the Department, within thirty (30) days of the event, documentation stating why the patient's estimated dose exceeded 300 rad for adults or 100 rad for children.
This shall be considered met if a positive beam-limiting device meeting manufacturer's specifications have been properly used or if evidence of collimation is shown on at least three sides or three corners of the film (for example, projections from the shutters of the collimator, cone cutting at the corners, or borders at the film's edge.)
With a timer setting of 0.5 seconds or less, the average exposure period (T) shall be greater than or equal to five (5) times the maximum exposure period (Tmax) minus the minimum exposure period (Tmin) when four timer tests are performed: T > 5 (Tmax - Tmin)
For systems having independent selection of exposure time settings, the average ratios (X1) of exposure to the indicated timer setting, in units of C kg-1s-1 (mR/ s), obtained at any two clinically used timer settings shall not differ by more than 0.10 times their sum. This is written as:
(X1 - X2) [LESS THAN] 0.1 (X1 + X2)
where X1 and X2 are the average C kg-1s-1 (mR/s) values.
All mobile or portable radiographic systems shall be provided with means to limit the source-to-skin distance to equal to or greater than thirty (30) centimeters except for veterinary systems.
When all technique factors are held constant, including control panel selections associated with automatic exposure control systems, the coefficient of variation of exposure for both manual and automatic exposure control systems shall not exceed 0.05. This requirement applies to clinically used techniques.
Radiation emitted from the x-ray tube when the system is fully charged and the exposure switch or timer is not activated shall not exceed a rate of two (2) milliroentgens (0.516 µC/kg) per hour at five (5) centimeters from any accessible surface of the diagnostic source assembly, with the beam-limiting device fully open.
Deviation of measured technique factors from indicated values of kVp and exposure time shall not exceed the limits specified for that system by its manufacturer. In the absence of manufacturer's specifications, the deviation shall not exceed ten (10) percent of the indicated value for kVp and twenty (20%) percent for time mA/mAs linearity.
X1 - X2 [LESS THAN] 0.10 (X1 + X2)
where X1 and X2 are the average values obtained at each of two (2) consecutive tube current settings, or at two settings differing by no more than a factor of two (2) where the tube current selection is continuous.
(or C kg-1mAs-1), obtained at any two consecutive mAs selector settings shall not differ by more than 0.10 times their sum:
X1 - X2 [LESS THAN] 0.10 (X1 + X2)
where X1 and X2 are the average values obtained at any two (2) consecutive mAs selector settings, or at two (2) settings differing by no more than a factor of two (2) where the mAs selector provides continuous selection.
Determination of compliance shall be based on ten (10) exposures taken within a time period of one (1) hour, at each of the two (2) settings. These two (2) settings may include any two focal spot sizes except where one is equal to or less than 0.45 millimeters and the other is greater than 0.45 millimeters. For purposes of this requirement, focal spot size is the nominal focal spot size specified by the x-ray tube manufacturer.
Diagnostic x-ray systems incorporating one or more certified component(s) shall be required to comply with the following additional requirement(s) which relate to that certified component(s).
systems equipped with Positive Beam Limitation (PBL).
If PBL is being used, the following requirements shall be met:
For systems having independent selection of exposure time settings, the average ratios (X1) of exposure to the indicated timer setting, in units of C kg-1s-1 (mR/s), obtained at any two clinically used timer settings shall not differ by more than 0.10 times their sum. This is written as:
(X1 - X2) [LESS THAN] 0.1 (X1 + X2) where X1 and X2 are the average values.
For equipment installed before January 1, 2006, there must exist a means to allow the operator to be at least six (6) feet (1.8 meters) from the tube housing assembly while making exposure.
The following requirements apply when the equipment is operated on a power supply as specified by the manufacturer for any fixed x-ray tube potential within the range of 40 percent to 100 percent of the maximum rated:
(X1 - X2) [LESS THAN] 0.1 (X1 + X2) where X1 and X2
are the average values obtained at each of two (2) consecutive tube current settings, or at two settings differing by no more than a factor of two (2) where the tube current selection is continuous.
(X1 - X2) [LESS THAN] 0.1 (X1 + X2) where X1 and X2
are the average values obtained at any two (2) mAs selector settings, or at two (2) settings differing by no more than a factor of two (2) where the mAs selector provides continuous selection.
Deviation of technique factors from indicated values for kVp and exposure time (if time is independently selectable) shall not exceed the limits specified for that system by its manufacturer. In the absence of manufacturer's specifications the deviation shall not exceed ten (10%) percent.
NOTE: In many cases structural materials of ordinary walls suffice as a protective barrier without addition of special shielding material.
above 150 kVp.
due to leakage radiation, including x-rays, electrons and neutrons, at any point in a circular plane of two (2) meters radius centered on a perpendicular to the central axis of the beam at the normal treatment distance and outside the maximum useful beam, shall not exceed 0.1 percent of the maximum dose in rads (grays) of the un-attenuated useful beam measured at the point of intersection of the central axis of the beam and the plane surface.
Measurements excluding those for neutrons shall be averaged over an area up to but not exceeding 100 square centimeters at the positions specified. Measurements of the portion of the leakage radiation dose contributed by neutrons shall be averaged over an area up to but not exceeding 200 square centimeters.
TABLE III
Maximum Energy of Electron Beam in MeV | X-ray Absorbed Dose as a Fraction of Maximum Absorbed Dose |
1 | 0.03 |
15 | 0.05 |
35 | 0.10 |
50 | 0.20 |
TABLE IV
Maximum Photon Energy in MeV | Absorbed Dose at the Surface as a Fraction of the Maximum Absorbed Dose |
1 | 0.80 |
2 | 0.70 |
5 | 0.60 |
15 | 0.50 |
35 | 0.40 |
50 | 0.20 |
For new equipment, a system shall be provided from whose readings the absorbed dose rate at a reference point in the treatment volume can be calculated.12/ In addition:
The licensee shall determine, or obtain from the manufacturer, the location with reference to an accessible point on the radiation head of:
Spot checks shall be performed on systems subject to RH-1608. during full calibrations and thereafter at intervals not to exceed one (1) month.
NOTE: Spot checks shall include absorbed dose
measurements at a minimum of two (2) depths in a phantom at intervals not to exceed one (1) month. Such spot checks shall meet the following requirements:
All wall, ceiling, and floor areas shall be equivalent or provided with applicable protective barriers. Stationary, mobile or portable x-ray systems shall be provided with either a two (2) meter (6.5 feet) high protective barrier for operator protections during exposures, or shall be provided with means to allow the operator to be at least 2.7 meters (9 feet) from the tube housing assembly during exposures if the equipment has been installed or relocated after January 1, 2006.
For equipment installed before January 1, 2006, there must exist a means to allow the operator to be at least six (6) feet (1.8 meters) from the tube housing assembly during exposures.
Radiologic Technologist.
All reasonable efforts must be made to obtain any of the beneficiary's previous mammogram records, including original images and films, copies of written reports prepared by interpreting physicians, and other relevant information pertinent to previous mammograms that might be available from others, for comparison with current mammogram records. All reporting and record keeping must meet the requirements of the Food and Drug Administration (FDA) 21 CFR Part 900.12(c).
approved phantom.
Schedule A
INFORMATION TO BE SUBMITTED BY PERSONS
PROPOSING TO CONDUCT HEALING ARTS SCREENING
Persons requesting that the Agency approve a healing arts screening program shall submit the following information and evaluation:
This Part provides special requirements for analytical x-ray equipment. The requirements of this Part are in addition to, and not in substitution for applicable requirements in other parts of these Regulations.
BEAM", or words having a similar intent, on the x-ray source housing; and.
On open-beam configurations installed after January 1, 1979, each port on the radiation source housing shall be equipped with a shutter that cannot be opened unless a collimator or a coupling has been connected to the port.
Each radiation source housing shall be subject to the following requirements:
Each x-ray generator shall be supplied with a protective cabinet which limits leakage radiation measured at a distance of five (5) centimeters from its surface such that it is not capable of producing a dose in excess of 0.25 millirem in one hour.
ray equipment shall be conspicuously posted with a sign or signs bearing the radiation symbol and the words:
"CAUTION - X-RAY EQUIPMENT," or words having a similar intent.
Normal operating procedures shall be written and available to all analytical x-ray equipment workers. No person shall be permitted to operate analytical x-ray equipment in any manner other than that specified in the procedures unless such person has obtained written approval of the radiation safety officer.
No person shall bypass a safety device unless such person has obtained the approval of the Radiation Safety Officer. When a safety device has been bypassed, a readily discernible sign bearing the words
"SAFETY DEVICE NOT WORKING,"
or words having a similar intent, shall be placed on the radiation source housing.
Except as specified in RH-1612.b. no operation involving removal of covers, shielding materials or tube housings or modifications to shutters, collimators or beam stops shall be performed without ascertaining that the tube is off and will remain off until safe conditions have been restored. The main switch, rather than interlocks, shall be used for routine shutdown in preparation for repairs.
This definition assumes that the dose profile is centered around z = 0 and that, for a multiple tomogram system, the scan increment between adjacent scans is nT.
CTNx = of the material of interest. CTNw = of water.
k (ux - Uw) CTN = |j,w
Where: k = A constant, a normal value of 1,000 when the Houndsfield scale of CTN is used;
Linear attenuation coefficient of the material of interest;
|j,w = Linear attenuation coefficient of water.
Where: CS = Linear attenuation coefficient of the material of interest.
|j,w = Linear attenuation coefficient of water. s = Standard deviation of the CTN of picture elements in a specified area of the CT image.
conditions of operation to be used during a scan or a scan sequence shall be indicated prior to the initiation of a scan or a scan sequence. On equipment having all or some of these conditions of operation at fixed values, this requirement may be met by permanent markings. Indication of CT conditions of operation shall be visible from any position from which scan initiation is possible.
dosimetry phantom for the minimum, maximum, and midrange values of the nominal tomographic section thickness used by the registrant shall be measurable. Where less than three (3) nominal tomographic thick nesses can be selected, the dose profile determination shall be performed for each available nominal tomographic section thickness;
(For the purpose of determining the CTDI, the manufacturer's statement as to the nominal tomographic section thickness for that particular system may be utilized.)
Each licensee shall maintain a copy of its license, license conditions, documents incorporated by reference, and amendments to each of these items until superseded by new documents approved by the Department or until the Department terminates the license.
Each licensee or registrant shall maintain records of the calibrations of its radiation survey instruments that are required in RH-1801.e. and retain each record for three (3) years after it is made.
Each licensee shall maintain records of leak test results for sealed sources and for devices containing depleted uranium (DU). The results must be stated in units of microcuries (bequerels). The licensee shall retain each record for three (3) years after it is made or until the source in storage is removed.
Each licensee or registrant shall maintain records of alarm system and entrance control device tests required under RH-1801.j. and retain each record for three (3) years after it is made.
Each licensee or registrant shall maintain the following records (of training and certification) for three (3) years after the record is made:
Each licensee or registrant shall maintain a copy of current operating and emergency procedures until the Department terminates the license or registration. Superseded material must be retained for three (3) years after the change is made.
Each licensee or registrant shall maintain the following exposure records specified in RH-1802.f.
Each licensee or registrant shall maintain a record of each exposure device survey conducted before the device is placed in storage as specified in RH-1803.c.3. if that survey is the last one performed in the workday. Each record must be maintained for three (3) years after it is made.
Each record required by RH-1800.d. must be legible throughout the specified retention period. The record may be the original or a reproduced copy or a microform provided that the copy or microform is authenticated by authorized personnel and that the microform is capable of reproducing a clear copy throughout the required retention period. The record may also be stored in electronic media with the capability for producing legible, accurate, and complete records during the required retention period. Records, such as letters, drawings, and specifications, must include all pertinent information, such as stamps, initials, and signatures. The licensee or registrant shall maintain adequate safeguards against tampering with and loss of records.
meters and operability checks of pocket dosimeters and/or electronic personal dosimeters as required by RH-1800.d.11.
RH-750, a copy of the Agreement State or Nuclear Regulatory Commission license authorizing the use of licensed materials.
This publication has been approved for incorporation by Radiation Control. This publication may be purchased from the American National Standards Institute, Inc., 1430 Broadway, New York, New York 10018 Telephone (212) 642-4900.
A copy of the document is available for inspection in the office of Arkansas Department of Health and Human Services, Division of Health, Radiation Control, 5800 West 10th Street, Suite 100, Little Rock, Arkansas 72204.
Engineering analysis may be submitted by an applicant or licensee to demonstrate the applicability of previously performed testing on similar individual radiography equipment components. Upon review, the Department may find this an acceptable alternative to actual testing of the component pursuant to the above referenced standard.
the following requirements apply to radiographic exposure devices, source assemblies, and associated equipment that allow the source to be moved out of the device for radiographic operation or to source changers.
changers.
The maximum exposure rate limit for storage containers and source changers are 200 millirem (2 millisieverts) per hour at any exterior surface, and ten (10) millirem (0.1 millisieverts) per hour at one (1) meter from any exterior surface with the sealed source in the shielded position.
Should such testing reveal the presence of 0.005 microcurie (185 Bq) or more of removable DU contamination, the exposure device must be removed from use until an evaluation of the wear on the S-tube has been made. Should the evaluation reveal that the S-tube is worn through, the device may not be used again. DU shielded devices do not have to be tested for DU contamination while in storage and not in use. Before using or transferring such a device however, the device must be tested for DU contamination if the interval of storage exceeds twelve (12) months. A record of the DU leak test must be made in accordance with RH-1800.d.
which shall be kept available for inspection by the Department, showing for each source of radiation the following information:
and storage containers, associated equipment, source changers, and survey instruments.
The facility may continue to be used during this seven (7) day period, provided the licensee or registrant implements the continuous surveillance requirements or RH-1803.a. and uses an alarming ratemeter, Test records for entrance controls and audible and visual alarm must be maintained in accordance with RH-1800.d.8.
and under other Sections, each licensee or registrant shall provide a written report to the Arkansas Department of Health & Human Services, Radiation Control, P.O. Box 1437 Mail Slot H-30, Little Rock, Arkansas 72203-1437 within thirty (30) days of the occurrence of any of the following incidents involving radiographic equipment:
"CAUTION" * RADIOACTIVE MATERIAL NOTIFY CIVIL AUTHORITIES (or "NAME OF COMPANY")
* or "DANGER"
"STANDARDS FOR PROTECTION AGAINST RADIATION" including its Part N: "NOTICES, INSTRUCTIONS AND REPORTS TO WORKERS: INSPECTIONS"
and in applicable Department of Transportation (DOT) as referenced in the Nuclear Regulatory Commission's (NRC) 10 CFR Part 71, in the Department license(s) under which the radiographer will perform industrial radiography, the licensee's or registrant's operating and emergency procedures;
"STANDARDS FOR PROTECTION AGAINST RADIATION" including its Part N: "NOTICES, INSTRUCTIONS AND REPORTS TO WORKERS: INSPECTIONS"
and in applicable Department of Transportation (DOT) as referenced in the Nuclear Regulatory Commission's (NRC) 10 CFR Part 71, in the Department license(s) under which the radiographer will perform industrial radiography, the licensee's or registrant's operating and emergency procedures;
The Department may confiscate any radiographer's certification card should there be serious health and safety violations relating to the Regulations, license conditions, and/or licensee Operating and Emergency Procedures. The radiographer will be restricted from conducting radiographic operations within the State of Arkansas.
The Radiation Safety Officer (RSO) shall ensure that radiation safety activities are being performed in accordance with approved procedures and regulatory requirements in the daily operation of the licensee's or registrant's program.
For cabinet x-ray systems designed to admit humans there shall also be provided:
CAUTION: X-RAYS PRODUCED WHEN ENERGIZED
CAUTION: DO NOT INSERT ANY PART OF THE BODY WHEN SYSTEM IS ENERGIZED X-RAY HAZARD
APPENDIX IRC RADIOGRAPHIC CERTIFICATION
"DANGER (or CAUTION) RADIOACTIVE MATERIAL."
"CAUTION (or DANGER), RADIOACTIVE MATERIAL, NOTIFY CIVIL AUTHORITIES
OR ________________________ IF FOUND.
(Name of Company)
reveals the presence of 0.005 microcurie (185 Bq) or more of removable radioactive material, the licensee shall remove the sealed source from service immediately and have it decontaminated, repaired, or disposed of by a Department, U.S. Nuclear Regulatory Commission, or an Agreement State licensee that is authorized to perform these functions. The licensee shall check the equipment associated with the leaking source for radioactive contamination and, if contaminated, have it decontaminated or disposed of by a Department, U.S. Nuclear Regulatory Commission, or an Agreement State licensee that is authorized to perform these functions.
days of receiving the test results. The report must describe the equipment involved in the leak, the test results, any contamination which resulted from the leaking source, and the corrective actions taken up to the time the report is made.
The following sealed sources are exempt from the periodic leak requirements set out in RH-1935.a. through RH-1935.d.:
Each licensee shall conduct a quarterly physical inventory to account for all radioactive material received and possessed under the license. The licensee shall retain records of the inventory for three (3) years from the date of the inventory for inspection by the Department. The inventory must indicate the quantity and type of radioactive material, the location of the radioactive material, the date of the inventory, and the name of the individual conducting the inventory.
"NOTIFY CIVIL AUTHORITIES OR ________________________ (or
Company Name) IF FOUND" (fill in Company Name).
Regulations;
and personnel;
Example of Plaque for Identifying Wells Containing Sealed Sources Containing Radioactive Material Abandoned Downhole
The size of the plaque should be convenient for use on active or inactive wells, e.g., a 7-inch square. Letter size of the word "CAUTION" should be approximately twice the letter size of the rest of the information, e.g., 1/2-inch and 1/4-inch letter size, respectively.
APPENDIX A
CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND
(See notes at end of Appendix)
Element (atomic number) | Isotope16/ | Table I _________________ | Table II _______________ | ||
Column 1 Column 2 | Column 1 | Column 2 | |||
Air (µ Ci/ml) | Water (µ Ci/ml) | Air (µ Ci/ml) | Water (µ Ci/ml) | ||
Actinium (89) | Ac-227 S | 2 X 10-12 | 6 X 10-5 | 8 X 10-14 | 2 X 10-6 |
I | 3 X 10-11 | 9 X 10-3 | 9 X 10-13 | 3 X 10-4 | |
Ac-228 S | 8 X 10-8 | 3 X 10-3 | 3 X 10-9 | 9 X 10-5 | |
I | 2 X 10-8 | 3 X 10-3 | 6 X 10-10 | 9 X 10-5 | |
Americium(95) | Am-241 S | 6 X 10-12 | 1 X 10-4 | 2 X 10-13 | 4 X 10-6 |
I | 1 X 10-10 | 8 X 10-4 | 4 X 10-12 | 3 X 10-5 | |
Am-242m S | 6 X 10-12 | 1 X 10-4 | 2 X 10-13 | 4 X 10-6 | |
I | 3 X 10-10 | 3 X 10-3 | 9 X 10-12 | 9 X 10-5 | |
Am-242 S | 4 X 10-8 | 4 X 10-3 | 1 X 10-9 | 1 X 10-4 | |
I | 5 X 10-8 | 4 X 10-3 | 2 X 10-9 | 1 X 10-4 | |
Am-243 S | 6 X 10-12 | 1 X 10-4 | 2 X 10-13 | 4 X 10-6 | |
I | 1 X 10-10 | 8 X 10-4 | 4 X 10-12 | 3 X 10-5 | |
Am-244 S | 4 X 10-6 | 1 X 10-1 | 1 X 10-7 | 5 X 10-3 | |
I | 2 X 10-5 | 1 X 10-1 | 8 X 10-7 | 5 X 10-3 | |
Antimony (51) | Sb-122 S | 2 X 10-7 | 8 X 10-4 | 6 X 10-9 | 3 X 10-5 |
I | 1 X 10-7 | 8 X 10-4 | 5 X 10-9 | 3 X 10-5 | |
Sb-124 S | 2 X 10-7 | 7 X 10-4 | 5 X 10-9 | 2 X 10-5 | |
I | 2 X 10-8 | 7 X 10-4 | 7 X 10-10 | 2 X 10-5 | |
Sb-125 S | 5 X 10-7 | 3 X 10-3 | 2 X 10-8 | 1 X 10-4 | |
I | 3 X 10-8 | 3 X 10-10 | 9 X 10-3 | 1 X 10-4 | |
Argon (18) | A-37 Sub17/ | 6 X 10-3 | ---- | 1 X 10-4 | ---- |
A-41 Sub | 2 X 10-6 | ---- | 4 X 10-8 | ---- | |
Arsenic (33) | As-73 S | 2 X 10-6 | 1 X 10-2 | 7 X 10-8 | 5 X 10-4 |
I | 4 X 10-7 | 1 X 10-2 | 1 X 10-8 | 5 X 10-4 | |
As-74 S | 3 X 10-7 | 2 X 10-3 | 1 X 10-8 | 5 X 10-5 | |
I | 1 X 10-7 | 2 X 10-3 | 4 X 10-9 | 5 X 10-5 | |
As-76 S | 1 X 10-7 | 6 X 10-4 | 4 X 10-9 | 2 X 10-5 | |
I | 1 X 10-7 | 6 X 10-4 | 3 X 10-9 | 2 X 10-5 | |
As-77 S | 5 X 10-7 | 2 X 10-3 | 2 X 10-8 | 8 X 10-5 | |
I | 4 X 10-7 | 2 X 10-3 | 1 X 10-8 | 8 X 10-5 | |
Astatine 85) | At-211 S | 7 X 10-9 | 5 X 10-5 | 2 X 10-10 | 2 X 10-6 |
I | 3 X 10-8 | 2 X 10-3 | 1 X 10-9 | 7 X 10-5 | |
Barium (56) | Ba-131 S | 1 X 10-6 | 5 X 10-3 | 4 X 10-8 | 2 X 10-4 |
I | 4 X 10-7 | 5 X 10-3 | 1 X 10-8 | 2 X 10-4 | |
Ba-140 S | 1 X 10-7 | 8 X 10-4 | 4 X 10-9 | 3 X 10-5 | |
I | 4 X 10-8 | 7 X 10-4 | 1 X 10-9 | 2 X 10-5 | |
Berkelium (97) | Bk-249 S | 9 X 10-10 | 2 X 10-2 | 3 X 10-11 | 6 X 10-4 |
I | 1 X 10-7 | 2 X 10-2 | 4 X 10-9 | 6 X 10-4 | |
Bk-250 S | 1 X 10-7 | 6 X 10-3 | 5 X 10-9 | 2 X 10-4 | |
I | 1 X 10-6 | 6 X 10-3 | 4 X 10-8 | 2 X 10-4 | |
Beryllium (4) | Be-7 S | 6 X 10-6 | 5 X 10-2 | 2 X 10-7 | 2 X 10-3 |
I | 1 X 10-6 | 5 X 10-2 | 4 X 10-8 | 2 X 10-3 | |
Bismuth (83) | Bi-206 S | 2 X 10-7 | 1 X 10-3 | 6 X 10-9 | 4 X 10-5 |
I | 1 X 10-7 | 1 X 10-3 | 5 X 10-9 | 4 X 10-5 | |
Bi-207 S | 2 X 10-7 | 2 X 10-3 | 6 X 10-9 | 6 X 10-5 | |
I | 1 X 10-8 | 2 X 10-3 | 5 X 10-10 | 6 X 10-5 | |
Bi-210 S | 6 X 10-9 | 1 X 10-3 | 2 X 10-10 | 4 X 10-5 | |
I | 6 X 10-9 | 1 X 10-3 | 2 X 10-10 | 4 X 10-5 | |
Bi-212 S | 1 X 10-7 | 1 X 10-2 | 3 X 10-9 | 4 X 10-4 | |
I | 2 X 10-7 | 1 X 10-2 | 7 X 10-9 | 4 X 10-4 | |
Bromine (35) | Br-82 S | 1 X 10-6 | 8 X 10-3 | 4 X 10-8 | 3 X 10-4 |
I | 2 X 10-7 | 1 X 10-3 | 6 X 10-9 | 4 X 10-5 | |
Cadmium (48) | Cd-109 S | 5 X 10-8 | 5 X 10-3 | 2 X 10-9 | 2 X 10-4 |
I | 7 X 10-8 | 5 X 10-3 | 3 X 10-9 | 2 X 10-4 | |
Cd-115mS | 4 X 10-8 | 7 X 10-4 | 1 X 10-9 | 3 X 10-5 | |
I | 4 X 10-8 | 7 X 10-4 | 1 X 10-9 | 3 X 10-5 | |
Cd-115 S | 2 X 10-7 | 1 X 10-3 | 8 X 10-9 | 3 X 10-5 | |
I | 2 X 10-7 | 1 X 10-3 | 6 X 10-9 | 4 X 10-5 | |
Calcium (20) | Ca-45 S | 3 X 10-8 | 3 X 10-4 | 1 X 10-9 | 9 X 10-6 |
I | 1 X 10-7 | 5 X 10-3 | 4 X 10-9 | 2 X 10-4 | |
Ca-47 S | 2 X 10-7 | 1 X 10-3 | 6 X 10-9 | 5 X 10-5 | |
I | 2 X 10-7 | 1 X 10-3 | 6 X 10-9 | 3 X 10-5 | |
Californium (98 | ) Cf-249 S | 2 X 10-12 | 1 X 10-4 | 5 X 10-14 | 4 X 10-6 |
I | 1 X 10-10 | 7 X 10-4 | 3 X 10-12 | 2 X 10-5 | |
C | f-250 S | 5 X 10-12 | 4 X 10-4 | 2 X 10-13 | 1 X 10-5 |
I | 1 X 10-10 | 7 X 10-4 | 3 X 10-12 | 3 X 10-5 | |
Cf-251 S | 2 X 10-12 | 1 X 10-4 | 6 X 10-14 | 4 X 10-6 | |
I | 1 X 10-10 | 8 X 10-4 | 3 X 10-12 | 3 X 10-5 | |
Cf-252 S | 6 X 10-12 | 2 X 10-4 | 2 X 10-13 | 7 X 10-6 | |
I | 3 X 10-11 | 2 X 10-4 | 1 X 10-12 | 7 X 10-6 | |
Cf-253 S | 8 X 10-10 | 4 X 10-3 | 3 X 10-1 | 1 X 10-4 | |
I | 8 X 10-10 | 4 X 10-3 | 3 X 10-11 | 1 X 10-4 | |
Cf-254 S | 5 X 10-12 | 4 X 10-6 | 2 X 10-13 | 1 X 10-7 | |
I | 5 X 10-12 | 4 X 10-6 | 2 X 10-13 | 1 X 10-7 |
Carbon (6) | C-14 S | 4 X 10-6 | 2X10-2 | 1X10-7 | 8 X 10-4 |
(C02) Sub17/ | 5 X 10-5 | ------ | 1 X 10-6 | ------ | |
Cenum (58) | Ce-141 S | 4 X 10-7 | 3 X 10-3 | 2 X 10-8 | 9X10-5 |
I | 2 X 10-7 | 3 X 10-3 | 5 X 10-9 | 9X10-5 | |
Ce-143 S | 3 X 10-7 | 1 X 10-3 | 9 X 10-9 | 4X10-5 | |
I | 2 X 10-7 | 1 X 10-3 | 7 X 10-9 | 4X10-5 | |
Ce-144 S | 1 X 10-8 | 3 X 10-4 | 3 X 10-10 | 1 X 10-5 | |
I | 6 X 10-9 | 3 X 10-4 | 2 X 10-10 | 1 X 10-5 | |
Cesium (55) | Cs-131 S | 1 X 10-5 | 7X10-2 | 4 X 10-7 | 2X10-3 |
I | 3 X 10-6 | 3 X 10-2 | 1 X 10-7 | 9X10-4 | |
Cs-134mS | 4 X 10-5 | 2X10-1 | 1 X 10-6 | 6X10-3 | |
I | 6 X 10-6 | 3 X 10-2 | 2 X 10-7 | 1 X 10-3 | |
Cs-134 S | 4 X 10-8 | 3 X 10-4 | 1 X 10-10 | 9X10-6 | |
I | 1 X 10-8 | 1 X 10-3 | 4 X 10-10 | 4X10-5 | |
Cs-135 S | 5 X 10-7 | 3 X 10-3 | 2 X 10-8 | 1 X 10-4 | |
I | 9 X 10-8 | 7X10-3 | 3 X 10-9 | 2X10-4 | |
Cs-136 S | 4 X 10-7 | 2X10-3 | 1 X 10-8 | 9X10-5 | |
I | 2 X 10-7 | 2X10-3 | 6 X 10-9 | 6X10-5 | |
Cs-137 S | 6 X 10-8 | 4X10-4 | 2 X 10-9 | 2X10-5 | |
I | 1 X 10-8 | 1 X 10-3 | 5 X 10-10 | 4X10-5 | |
Chlorine (17) | Cl-36 S | 4 X 10-7 | 2X10-3 | 1 X 10-8 | 8 X 10-5 |
I | 2 X 10-8 | 2X10-3 | 8 X 10-10 | 6X10-5 | |
Cl-38 S | 3 X 10-6 | 1 X 10-2 | 9 X 10-8 | 4X10-4 | |
I | 2 X 10-6 | 1 X 10-2 | 7 X 10-8 | 4X10-4 | |
Chromium (24) | Cr-51 S | 1 X 10-5 | 5 X 10-2 | 4 X 10-7 | 2X10-3 |
I | 2 X 10-6 | 5 X 10-2 | 8 X 10-8 | 2X10-3 | |
Cobalt (27) | Co-57 S | 3 X 10-6 | 2X10-2 | 1 X 10-7 | 5 X 10-4 |
I | 2 X 10-7 | 1 X 10-2 | 6 X 10-9 | 4X10-4 | |
Co-58m S | 2 X 10-5 | 8 X 10-2 | 6 X 10-7 | 3 X 10-3 | |
I | 9 X 10-6 | 6X10-2 | 3 X 10-7 | 2X10-3 | |
Co-58 S | 8 X 10-7 | 4X10-3 | 3 X 10-8 | 1 X 10-4 | |
I | 5 X 10-8 | 3 X 10-3 | 2 X 10-9 | 9X10-5 | |
Co-60 S | 3 X 10-7 | 1 X 10-3 | 1 X 10-8 | 5 X 10-5 | |
I | 9 X 10-9 | 1 X 10-3 | 3 X 10-10 | 3 X 10-5 | |
Copper (29) | Cu-64 S | 2 X 10-6 | 1 X 10-2 | 7 X 10-8 | 3 X 10-4 |
I | 1 X 10-6 | 6X10-3 | 4 X 10-8 | 2X10-4 |
Curium (96) | Cm-242 S | 1 X 10-10 | 7 X 10-4 | 4 X 10-12 | 2 X 10-5 |
I | 2 X 10-10 | 7 X 10-4 | 6 X 10-12 | 2 X 10-5 | |
Cm-243 S | 6 X 10-12 | 1 X 10-4 | 2 X 10-13 | 5 X 10-6 | |
I | 1 X 10-10 | 7 X 10-4 | 3 X 10-12 | 2 X 10-5 | |
Cm-244 S | 9 X 10-12 | 2 X 10-4 | 3 X 10-13 | 7 X 10-6 | |
I | 1 X 10-10 | 8 X 10-4 | 3 X 10-12 | 3 X 10-5 | |
Cm-245 S | 5 X 10-12 | 1 X 10-4 | 2 X 10-13 | 4 X 10-6 | |
I | 1 X 10-10 | 8 X 10-4 | 4 X 10-12 | 3 X 10-5 | |
Cm-246 S | 5 X 10-12 | 1 X 10-4 | 2 X 10-13 | 4 X 10-6 | |
I | 1 X 10-10 | 8 X 10-4 | 4 X 10-12 | 3 X 10-5 | |
Cm-247 S | 5 X 10-12 | 1 X 10-4 | 2 X 10-13 | 4 X 10-6 | |
I | 1 X 10-10 | 6 X 10-4 | 4 X 10-12 | 2 X 10-5 | |
Cm-248 S | 6 X 10-13 | 1 X 10-5 | 2 X 10-14 | 4 X 10-7 | |
I | 1 X 10-11 | 4 X 10-5 | 4 X 10-13 | 1 X 10-6 | |
Cm-249 S | 1 X 10-5 | 6 X 10-2 | 4 X 10-7 | 2 X 10-3 | |
I | 1 X 10-5 | 6 X 10-2 | 4 X 10-7 | 2 X 10-3 | |
Dysprosium ( | 66)Dy-165 S | 3 X 10-6 | 1 X 10-2 | 9 X 10-8 | 4 X 10-4 |
I | 2 X 10-6 | 1 X 10-2 | 7 X 10-8 | 4 X 10-4 | |
Dy-165 S | 2 X 10-7 | 1 X 10-3 | 8 X 10-9 | 4 X 10-5 | |
I | 2 X 10-7 | 1 X 10-3 | 7 X 10-9 | 4 X 10-5 | |
Einsteinium ( | 99)Es-253 S | 8 X 10-10 | 7 X 10-4 | 3 X 10-11 | 2 X 10-5 |
I | 6 X 10-10 | 7 x 10-4 | 2 X 10-11 | 2 X 10-5 | |
Es-254mS | 5 X 10-9 | 5 X 10-4 | 2 X 10-10 | 2 X 10-5 | |
I | 6 X 10-9 | 5 X 10-4 | 2 X 10-10 | 2 X 10-5 | |
Es-254 S | 2 X 10-11 | 4 X 10-4 | 6 X 10-13 | 1 X 10-5 | |
I | 1 X 10-10 | 4 X 10-4 | 4 X 10-12 | 1 X 10-5 | |
Es-255 S | 5 X 10-10 | 8 X 10-4 | 2 X 10-11 | 3 X 10-5 | |
I | 4 X 10-10 | 8 X 10-4 | 1 X 10-11 | 3 X 10-5 | |
Erbium (68) | Er-169 S | 6 X 10-7 | 3 X 10-3 | 2 X 10-8 | 9 X 10-5 |
I | 4 X 10-7 | 3 X 10-3 | 1 X 10-8 | 9 X 10-5 | |
Er-171 S | 7 X 10-7 | 3 X 10-3 | 2 X 10-8 | 1 X 10-4 | |
I | 6 X 10-7 | 3 X 10-3 | 2 X 10-8 | 1 X 10-4 | |
Europium (63 | ) Eu-152 S | 4 X 10-7 | 2 X 10-3 | 1 X 10-8 | 6 X 10-5 |
(T/2= | |||||
9.2 hrs)I | 3 X 10-7 | 2 X 10-3 | 1 X 10-8 | 6 X 10-5 | |
Eu-152 S (T/2= | 1 X 10-8 | 2 X 10-3 | 4 X 10-10 | 8 X 10-5 | |
13 yrs) I | 2 X 10-8 | 2 X 10-3 | 6 X 10-10 | 8 X 10-5 | |
Eu-154 S | 4 X 10-9 | 6 X 10-4 | 1 X 10-10 | 2 X 10-5 | |
I | 7 X 10-9 | 6 X 10-4 | 2 X 10-10 | 2 X 10-5 |
Europium (6 | 3) Eu-155 S | 9 X 10-8 | 6 X 10-3 | 3 X 10-9 | 2 X 10-4 |
I | 7 X 10-8 | 6 X 10-3 | 3 X 10-9 | 2 X 10-4 | |
Fermium (10 | 0) Fm-254 S | 6 X 10-8 | 4 X 10-3 | 2 X 10-9 | 1 X 10-4 |
I | 7 X 10-8 | 4 X 10-3 | 2 X 10-9 | 1 X 10-4 | |
Fm-255 S | 2 X 10-8 | 1 X 10-3 | 6 X 10-10 | 3 X 10-5 | |
I | 1 X 10-8 | 1 X 10-3 | 4 X 10-10 | 3 X 10-5 | |
Fm-256 S | 3 X 10-9 | 3 X 10-5 | 1 X 10-10 | 9 X 10-7 | |
I | 2 X 10-9 | 3 X 10-5 | 6 X 10-11 | 9 X 10-7 | |
Fluorine (9) | F-18 S | 5 X 10-6 | 2 X 10-2 | 2 X 10-7 | 8 X 10-4 |
I | 3 X 10-6 | 1 X 10-2 | 9 X 10-8 | 5 X 10-4 | |
Gadolinium | (64)Gd-153 S | 2 X 10-7 | 6 X 10-3 | 8 X 10-9 | 2 X 10-4 |
I | 9 X 10-8 | 6 X 10-3 | 3 X 10-9 | 2 X 10-4 | |
Gd-159 S | 5 X 10-7 | 2 X 10-3 | 2 X 10-8 | 8 X 10-5 | |
I | 4 X 10-7 | 2 X 10-3 | 1 X 10-8 | 8 X 10-5 | |
Gallium (31) | Ga-72 S | 2 X 10-7 | 1 X 10-3 | 8 X 10-9 | 4 X 10-5 |
I | 2 X 10-7 | 1 X 10-3 | 6 X 10-9 | 4 X 10-5 | |
Germanium | (32) Ge-68 S | 4 X 10-6 | 2 X10-2 | 1 X 10-7 | 8 X 10-4 |
I | 1 X 10-8 | --- | 5 X 10-10 | -- | |
Ge-71 S | 1 X 10-5 | 5 X 10-2 | 4 X 10-7 | 2 X 10-3 | |
I | 6 X 10-6 | 5 X 10-2 | 2 X 10-7 | 2 X 10-3 | |
Gold (79) | Au-195* S | 8 X 10-6 | 4 X 10-2 | 3 X 10-7 | 1 X 10-3 |
I | 6 X 10-8 | 6 X 10-3 | 2 X 10-9 | 2 X 10-4 | |
Gold (79) | Au-196 S | 1 X 10-6 | 5 X 10-3 | 4 X 10-8 | 2 X 10-4 |
I | 6 X 10-7 | 4 X 10-3 | 2 X 10-8 | 1 X 10-4 | |
Au-198 S | 3 X 10-7 | 2 X 10-3 | 1 X 10-8 | 5 X 10-5 | |
I | 2 X 10-7 | 1 X 10-3 | 8 X 10-9 | 5 X 10-5 | |
Au-199 S | 1 X 10-6 | 5 X 10-3 | 4 X 10-8 | 2 X 10-4 | |
I | 8 X 10-7 | 4 X 10-3 | 3 X 10-8 | 2 X 10-4 | |
Hafnium (72 | ) Hf-181 S | 4 X 10-8 | 2 X 10-3 | 1 X 10-9 | 7 X 10-5 |
I | 7 X 10-8 | 2 X 10-3 | 3 X 10-9 | 7 X 10-5 | |
Holmium (6 | 7) Ho-166 S | 2 X 10-7 | 9 X 10-4 | 7 X 10-9 | 3 X 10-5 |
I | 2 X 10-7 | 9 X 10-4 | 6 X 10-9 | 3 X 10-5 | |
Hydrogen (1 | ) H-3 S | 5 X 10-6 | 1 X 10-1 | 2 X 10-7 | 3 X 10-3 |
I | 5 X 10-6 | 1 X 10-1 | 2 X 10-7 | 3 X 10-3 | |
Sub17/ | 2 X 10-3 | --- | 4 X 10-5 | -- |
number) | Isotope16/ | (µ Ci/ml) (µ Ci/ml) | (µ Ci/ml) | (µ Ci/ml) | |
Indium (49) | In-113m S | 8 X 10-6 | 4 X 10-2 | 3 X 10-7 | 1 X 10-3 |
I | 7 X 10-6 | 4 X 10-2 | 2 X 10-7 | 1 X 10-3 | |
In-114m S | 1 X 10-7 | 5 X 10-4 | 4 X 10-9 | 2 X 10-5 | |
I | 2 X 10-8 | 5 X 10-4 | 7 X 10-10 | 2 X 10-5 | |
Indium (49) | In-115m S | 2 X 10-6 | 1 X 10-2 | 8 X 10-8 | 4 X 10-4 |
I | 2 X 10-6 | 1 X 10-2 | 6 X 10-8 | 4 X 10-4 | |
In-115 S | 2 X 10-7 | 3 X 10-3 | 9 X 10-9 | 9 X 10-5 | |
I | 3 X 10-8 | 3 X 10-3 | 1 X 10-9 | 9 X 10-5 | |
Iodine (53) | I-125 S | 5 X 10-9 | 4 X 10-5 | 8 X 10-11 | 2 X 10-7 |
I | 2 X 10-7 | 6 X 10-3 | 6 X 10-9 | 2 X 10-4 | |
I-126 S | 8 X 10-9 | 5 x 10-5 | 9 X 10-11 | 3 X 10-7 | |
I | 3 X 10-7 | 3 X 10-3 | 1 X 10-8 | 9 X 10-5 | |
I-129 S | 2 X 10-9 | 1 X 10-5 | 2 X 10-11 | 6 X 10-8 | |
I | 7 X 10-8 | 6 X 10-3 | 2 X 10-9 | 2 X 10-4 | |
I-131 S | 9 X 10-9 | 6 X 10-5 | 1 X 10-10 | 3 X 10-7 | |
I | 3 X 10-7 | 2 X 10-3 | 1 X 10-8 | 6 X 10-5 | |
I-132 S | 2 X 10-7 | 2 X 10-3 | 3 X 10-9 | 8 X 10-6 | |
I | 9 X 10-7 | 5 X 10-3 | 3 X 10-8 | 2 X 10-4 | |
I-133 S | 3 X 10-8 | 2 X 10 | 4 X 10-10 | 1 X 10-6 | |
I | 2 X 10-7 | 1 X 10-3 | 7 X 10-9 | 4 X 10-5 | |
I-134 S | 5 X 10-7 | 4 X 10-3 | 6 X 10-9 | 2 X 10-5 | |
I | 3 X 10-6 | 2 X 10-2 | 1 X 10-7 | 6 X 10-4 | |
I-135 S | 1 X 10-7 | 7 X 10-4 | 1 X 10-9 | 4 X 10-6 | |
I | 4 X 10-7 | 2 X 10-3 | 1 X 10-8 | 7 X 10-5 | |
Iridium (77) | Ir-190 S | 1 X 10-6 | 6 X 10-3 | 4 X 10-8 | 2 X 10-4 |
I | 4 X 10-7 | 5 X 10-3 | 1 X 10-8 | 2 X 10-4 | |
Ir-192 S | 1 X 10-7 | 1 X 10-3 | 4 X 10-9 | 4 X 10-5 | |
I | 3 X 10-8 | 1 X 10-3 | 9 X 10-10 | 4 X 10-5 | |
Ir-194 S | 2 X 10-7 | 1 X 10-3 | 8 X 10-9 | 3 X 10-5 | |
I | 2 X 10-7 | 9 X 10-4 | 5 X 10-9 | 3 X 10-5 | |
Iron (26) | Fe-55 S | 9 X 10-7 | 2 X 10-2 | 3 X 10-8 | 8 X 10-4 |
I | 1 X 10-6 | 7 X 10-2 | 3 X 10-8 | 2 X 10-3 | |
Fe-59 S | 1 X 10-7 | 2 X 10-3 | 5 X 10-9 | 6 X 10-5 | |
I | 5 X 10-8 | 2 X 10-3 | 2 X 10-9 | 5 X 10-5 | |
Krypton (36) | Kr-85m Sub17 | / 6 X 10-6 | --- | 1 X 10-7 | --- |
Kr-85 Sub | 1 X 10-5 | --- | 3 X 10-7 | --- | |
Kr-87 Sub | 1 X 10-6 | --- | 2 X 10-8 | --- | |
Kr-88 Sub | 1 X 10-6 | --- | 2 X 10-8 | --- | |
Lanthanum (57) | La-140 S | 2 X 10-7 | 7 X 10-4 | 5 X 10-9 | 2 X 10-5 |
I | 1 X 10-7 | 7 X 10-4 | 4 X 10-9 | 2 X 10-5 | |
Lead (82) | Pb-203 S | 3 X 10-6 | 1 X 10-2 | 9 X 10-8 | 4 X 10-4 |
I | 2 X 10-6 | 1 X 10-2 | 6 X 10-8 | 4 X 10-4 | |
Pb-210 S | 1 X 10-10 | 4 X 10-6 | 4 X 10-12 | 1 X 10-7 | |
I | 2 X 10-10 | 5 X 10-3 | 8 X 10-12 | 2 X 10-4 | |
Pb-212 S | 2 X 10-8 | 6 X 10-4 | 6 X 10-10 | 2 X 10-5 | |
I | 2 X 10-8 | 5 X 10-4 | 7 X 10-10 | 2 X 10-5 | |
Lutetium (71) | Lu-177 S | 6 X 10-7 | 3 X 10-3 | 2 X 10-8 | 1 X 10-4 |
I | 5 X 10-7 | 3 X 10-3 | 2 X 10-8 | 1 X 10-4 | |
Manganese (25) | Mn-52 S | 2 X 10-7 | 1 X 10-3 | 7 X 10-9 | 3 X 10-5 |
I | 1 X 10-7 | 9 X 10-4 | 5 X 10-9 | 3 X 10-5 | |
Mn-54 S | 4 X 10-7 | 4 X 10-3 | 1 X 10-8 | 1 X 10-4 | |
I | 4 X 10-8 | 3 X 10-3 | 1 X 10-9 | 1 X 10-4 | |
Mn-56 S | 8 X 10-7 | 4 X 10-3 | 3 X 10-8 | 1 X 10-4 | |
I | 5 X 10-7 | 3 X 10-3 | 2 X 10-8 | 1 X 10-4 | |
Mercury (80) | Hg-197mS | 7 X 10-7 | 6 X 10-3 | 3 X 10-8 | 2 X 10-4 |
I | 8 X 10-7 | 5 X 10-3 | 3 X 10-8 | 2 X 10-4 | |
Hg-197 S | 1 X 10-6 | 9 X 10-3 | 4 X 10-8 | 3 X 10-4 | |
I | 3 X 10-6 | 1 X 10-2 | 9 X 10-8 | 5 X 10-4 | |
Hg-203 S | 7 X 10-8 | 5 X 10-4 | 2 X 10-9 | 2 X 10-5 | |
I | 1 X 10-7 | 3 X 10-3 | 4 X 10-9 | 1 X 10-4 | |
Molybdenum (4 | 2)Mo-99 S | 7 X 10-7 | 5 X 10-3 | 3 X 10-8 | 2 X 10-4 |
I | 2 X 10-7 | 1 X 10-3 | 7 X 10-9 | 4 X 10-5 | |
Neodymium (60 | )Nd-144 S | 8 X 10-11 | 2 X 10-3 | 3 X 10-12 | 7 X 10-5 |
I | 3 X 10-10 | 2 X 10-3 | 1 X 10-11 | 8 X 10-5 | |
Nd-147 S | 4 X 10-7 | 2 X 10-3 | 1 X 10-8 | 6 X 10-5 | |
I | 2 X 10-7 | 2 X 10-3 | 8 X 10-9 | 6 X 10-5 | |
Nd-149 S | 2 X 10-6 | 8 X 10-3 | 6 X 10-8 | 3 X 10-4 | |
I | 1 X 10-6 | 8 X 10-3 | 5 X 10-8 | 3 X 10-4 | |
Neptunium (93) | Np-237 S | 4 X 10-12 | 9 X 10-5 | 1 X 10-13 | 3 X 10-6 |
I | 1 X 10-10 | 9 X 10-4 | 4 X 10-12 | 3 X 10-5 | |
Np-239 S | 8 X 10-7 | 4 X 10-3 | 3 X 10-8 | 1 X 10-4 | |
I | 7 X 10-7 | 4 X 10-3 | 2 X 10-8 | 1 X 10-4 |
Nickel (28) | Ni-59 S | 5 X 10-7 | 6 X 10-3 | 2 X 10-8 | 2 X 10-4 |
I | 8 X 10-7 | 6 X 10-2 | 3 X 10-8 | 2 X 10-4 | |
Ni-63 S | 6 X 10-8 | 8 X 10-4 | 2 X 10-9 | 3 X 10-5 | |
I | 3 X 10-7 | 2 X 10-2 | 1 X 10-8 | 7 X 10-4 | |
Ni-65 S | 9 X 10-7 | 4 X 10-3 | 3 X 10-8 | 1 X 10-4 | |
I | 5 X 10-7 | 3 X 10-3 | 2 X 10-8 | 1 X 10-4 | |
Niobium (41) | Nb-93m S | 1 X 10-7 | 1 X 10-2 | 4 X 10-9 | 4 X 10-4 |
I | 2 X 10-7 | 1 X 10-2 | 5 X 10-9 | 4 X 10-4 | |
Nb-95 S | 5 X 10-7 | 3 X 10-3 | 2 X 10-8 | 1 X 10-4 | |
I | 1 X 10-7 | 3 X 10-3 | 3 X 10-9 | 1 X 10-4 | |
Nb-97 S | 6 X 10-6 | 3 X 10-2 | 2 X 10-7 | 9 X 10-4 | |
I | 5 X 10-6 | 3 X 10-2 | 2 X 10-7 | 9 X 10-4 | |
Osmium (76) | Os-185 S | 5 X 10-7 | 2 X 10-3 | 2 X 10-8 | 7 X 10-5 |
I | 5 X 10-8 | 2 X 10-3 | 2 X 10-9 | 7 X 10-5 | |
Os-191mS | 2 X 10-5 | 7 X 10-2 | 6 X 10-7 | 3 X 10-3 | |
I | 9 X 10-6 | 7 X 10-2 | 3 X 10-7 | 2 X 10-3 | |
Os-191 S | 1 X 10-6 | 5 X 10-3 | 4 X 10-8 | 2 X 10-4 | |
I | 4 X 10-7 | 5 X 10-3 | 1 X 10-8 | 2 X 10-4 | |
Os-193 S | 4 X 10-7 | 2 X 10-3 | 1 X 10-8 | 6 X 10-5 | |
I | 3 X 10-7 | 2 X 10-3 | 9 X 10-9 | 5 X 10-5 | |
Palladium (46 | ) Pd-103 S | 1 X 10-6 | 1 X 10-2 | 5 X 10-8 | 3 X 10-4 |
I | 7 X 10-7 | 8 X 10-3 | 3 X 10-8 | 3 X 10-4 | |
Pd-109 S | 6 X 10-7 | 3 X 10-3 | 2 X 10-8 | 9 X 10-5 | |
I | 4 X 10-7 | 2 X 10-3 | 1 X 10-8 | 7 X 10-5 | |
Phosphorus (1 | 5 P-32 S | 7 X 10-8 | 5 X 10-4 | 2 X 10-9 | 2 X 10-5 |
I | 8 X 10-8 | 7 X 10-4 | 3 X 10-9 | 2 X 10-5 | |
Platinum (78) | Pt-191 S | 8 X 10-7 | 4 X 10-3 | 3 X 10-8 | 1 X 10-4 |
I | 6 X 10-7 | 3 X 10-3 | 2 X 10-8 | 1 X 10-4 | |
Pt-193mS | 7 X 10-6 | 3 X 10-2 | 2 X 10-8 | 1 X 10-3 | |
I | 5 X 10-7 | 3 X 10-2 | 2 X 10-7 | 1 X 10-3 | |
Pt-193 S | 1 X 10-6 | 3 X 10-2 | 4 X 10-8 | 9 X 10-4 | |
I | 3 X 10-7 | 5 X 10-2 | 1 X 10-8 | 2 X 10-3 | |
Pt-197mS | 6 X 10-6 | 3 X 10-2 | 2 X 10-7 | 1 X 10-3 | |
I | 5 X 10-6 | 3 X 10-2 | 2 X 10-7 | 9 X 10-4 | |
Pt-197 S | 8 X 10-7 | 4 X 10-3 | 3 X 10-8 | 1 X 10-4 | |
I | 6 X 10-7 | 3 X 10-3 | 2 X 10-8 | 1 X 10-4 |
Plutonium (94) | Pu-238 S | 2 X 10-12 | 1 X 10-4 | 7 X 10-14 | 5 X 10-6 |
I | 3 X 10-11 | 8 X 10-4 | 1 X 10-12 | 3 X 10-5 | |
Pu-239 S | 2 X 10-12 | 1 X 10-4 | 6 X 10-14 | 5 X 10-6 | |
I | 4 X 10-11 | 8 X 10-4 | 1 X 10-12 | 3 X 10-5 | |
Pu-240 S | 2 X 10-12 | 1 X 10-4 | 6 X 10-14 | 5 X 10-6 | |
I | 4 X 10-11 | 8 X 10-4 | 1 X 10-12 | 3 X 10-5 | |
Pu-241 S | 9 X 10-11 | 7 X 10-3 | 3 X 10-12 | 2 X 10-4 | |
I | 4 X 10-8 | 4 X 10-2 | 1 X 10-9 | 1 X 10-3 | |
Pu-242 S | 2 X 10-12 | 1 X 10-4 | 6 X 10-14 | 5 X 10-6 | |
I | 4 X 10-11 | 9 X 10-4 | 1 X 10-12 | 3 X 10-5 | |
Pu-243 S | 2 X 10-6 | 1 X 10-2 | 6 X 10-8 | 3 X 10-4 | |
I | 2 X 10-6 | 1 X 10-2 | 8 X 10-8 | 3 X 10-4 | |
Pu-244 S | 2 X 10-12 | 1 X 10-4 | 6 X 10-14 | 4 X 10-6 | |
I | 3 X 10-11 | 3 X 10-4 | 1 X 10-12 | 1 X 10-5 | |
Polonium (84) | Po-210 S | 5 X 10-10 | 2 X 10-5 | 2 X 10-11 | 7 X 10-7 |
I | 2 X 10-10 | 8 X 10-4 | 7 X 10-12 | 3 X 10-5 | |
Potassium (19) | K-42 S | 2 X 10-6 | 9 X 10-3 | 7 X 10-8 | 3 X 10-4 |
I | 1 X 10-7 | 6 X 10-4 | 4 X 10-9 | 2 X 10-5 | |
Praseodymium | (59) Pr-142 S | 2 X 10-7 | 9 X 10-4 | 7 X 10-9 | 3 X 10-5 |
I | 2 X 10-7 | 9 X 10-4 | 5 X 10-9 | 3 X 10-5 | |
Pr-143 S | 3 X 10-7 | 1 X 10-3 | 1 X 10-8 | 5 X 10-5 | |
I | 2 X 10-7 | 1 X 10-3 | 6 X 10-9 | 5 X 10-5 | |
Promethium (6 | 1) Pm-147 S | 6 X 10-8 | 6 X 10-3 | 2 X 10-9 | 2 X 10-4 |
I | 1 X 10-7 | 6 X 10-3 | 3 X 10-9 | 2 X 10-4 | |
Pm-149 S | 3 X 10-7 | 1 X 10-3 | 1 X 10-8 | 4 X 10-5 | |
I | 2 X 10-7 | 1 X 10-3 | 8 X 10-9 | 4 X 10-5 | |
Protoactinium ( | 91) Pa-230 S | 2 X 10-9 | 7 X 10-3 | 6 X 10-11 | 2 X 10-4 |
I | 8 X 10-10 | 7 X 10-3 | 3 X 10-11 | 2 X 10-4 | |
Pa-231 S | 1 X 10-12 | 3 X 10-5 | 4 X 10-14 | 9 X 10-7 | |
I | 1 X 10-10 | 8 X 10-4 | 4 X 10-12 | 2 X 10-5 | |
Pa-233 S | 6 X 10-7 | 4 X 10-3 | 2 X 10-8 | 1 X 10-4 | |
I | 2 X 10-7 | 3 X 10-3 | 6 X 10-9 | 1 X 10-4 | |
Radium (88) | Ra-233 S | 2 X 10-9 | 2 X 10-5 | 6 X 10-11 | 7 X 10-7 |
I | 2 X 10-10 | 1 X 10-4 | 8 X 10-12 | 4 X 10-6 | |
Ra-224 S | 5 X 10-9 | 7 X 10-5 | 2 X 10-10 | 2 X 10-6 | |
I | 7 X 10-10 | 2 X 10-4 | 2 X 10-11 | 5 X 10-6 |
Radium (88) | Ra-226 S | 3 X 10-11 | 4 X 10-7 | 3 X 10-12 | 3 X 10-8 |
I | 5 X 10-11 | 9 X 10-4 | 2 X 10-12 | 3 X 10-5 | |
Ra-228 S | 7 X 10-11 | 8 X 10-7 | 2 X 10-12 | 3 X 10-8 | |
I | 4 X 10-11 | 7 X 10-4 | 1 X 10-12 | 3 X 10-5 | |
Radon (86) | Rn-220 S | 3 X 10-7 | ------ | 1 X 10-8 | ------ |
------ | ------ | ------ | ------ | ------ | |
Rn-22218/ S | 3 X 10-8 | ------ | 3 X 10-9 | ------ | |
Rhenium (75) | Re-183 S | 3 X 10-6 | 2 X 10-2 | 9 X 10-8 | 6 X 10-4 |
I | 2 X 10-7 | 8 X 10-3 | 5 X 10-9 | 3 X 10-4 | |
Re-186 S | 6 X 10-7 | 3 X 10-3 | 2 X 10-8 | 9 X 10-5 | |
I | 2 X 10-7 | 1 X 10-3 | 8 X 10-9 | 5 X 10-5 | |
Re-187 S | 9X 10-6 | 7 X 10-2 | 3 X 10-7 | 3 X 10-3 | |
I | 5 X 10-7 | 4 X 10-2 | 2 X 10-8 | 2 X 10-3 | |
Re-188 S | 4 X 10-7 | 2 X 10-3 | 1 X 10-8 | 6 X 10-5 | |
I | 2 X 10-7 | 9 X 10-4 | 6 X 10-9 | 3 X 10-5 | |
Rhodium (45) | Rh-103m S | 8X 10-5 | 4 X 10-1 | 3 X 10-6 | 1 X 10-2 |
I | 6X 10-5 | 3 X 10-1 | 2 X 10-6 | 1 X 10-2 | |
Rh-105 S | 8 X 10-7 | 4 X 10-3 | 3 X 10-8 | 1 X 10-4 | |
I | 5 X 10-7 | 3 X 10-3 | 2 X 10-8 | 1 X 10-4 | |
Rubidium (37) | Rb-86 S | 3 X 10-7 | 2 X 10-3 | 1 X 10-8 | 7 X 10-5 |
I | 7 X 10-3 | 7 X lO-4 | 2 X 10-9 | 2 X 10-5 | |
Rb-87 S | 5 X 10-7 | 3 X 10-3 | 2 X 10-8 | 1 X 10-4 | |
I | 7 X 10-8 | 5 X 10-3 | 2 X 10-9 | 2 X 10-4 | |
Ruthenium (44) | Ru-97 S | 2 X 10-6 | 1 X 10-2 | 8 X 10-8 | 4 X 10-4 |
I | 2 X 10-6 | 1 X 10-2 | 6 X 10-8 | 3 X 10-4 | |
Ru-103 S | 5 X 10-7 | 2 X 10-3 | 2 X 10-8 | 8 X 10-5 | |
I | 8 X 10-8 | 2 X 10-3 | 3 X 10-9 | 8 X 10-5 | |
Ru-105 S | 7 X 10-7 | 3 X 10-3 | 2 X 10-8 | 1 X 10-4 | |
I | 5 X 10-7 | 3 X 10-3 | 2 X 10-8 | 1 X 10-4 | |
Ru-106 S | 8 X 10-8 | 4 X 10-4 | 3 X 10-9 | 1 X 10-5 | |
I | 6 X 10-9 | 3 X 10-4 | 2 X 10-10 | 1 X 10-5 | |
Rhenium (75) | Sm-147 S | 7 X 10-11 | 2 X 10-3 | 2 X 10-12 | 6 X 10-5 |
I | 3 X 10-10 | 2 X 10-3 | 9 X 10-12 | 7 X 10-5 | |
Sm-151 S | 6 X 10-8 | 1 X 10-2 | 2 X 10-9 | 4 X 10-4 | |
I | 1 X 10-7 | 1 X 10-2 | 5 X 10-9 | 4 X 10-4 | |
Sm-153 S | 5 X 10-7 | 2 X 10-3 | 2 X 10-8 | 8 X 10-5 | |
I | 4 X 10-7 | 2 X 10-3 | 1 X 10-8 | 8 X 10-5 |
Scandium (21) | Sc-46 S | 2 X 10-7 | 1 X 10-3 | 8 X 10-9 | 4 X 10-5 |
I | 2 X 10-8 | 1 X 10-10 | 8 X 10-10 | 4 X 10-5 | |
Sc-47 S | 6 X 10-7 | 3 X 10-3 | 2 X 10-8 | 9 X 10-5 | |
I | 5 X 10-7 | 3 X 10-3 | 2 X 10-8 | 9 X 10-5 | |
Sc-48 S | 2 X 10-7 | 8 X 10-4 | 6 X 10-9 | 3 X 10-5 | |
I | 1 X 10-7 | 8 X 10-4 | 5 X 10-9 | 3 X 10-5 | |
Selenium (34) | Se-75 S | 1 X 10-6 | 9 X 10-3 | 4 X 10-8 | 3 X 10-4 |
I | 1 X 10-7 | 8 X 10-3 | 4 X 10-9 | 3 X 10-4 | |
Silicon (14) | Si-31 S | 6 X 10-6 | 3 X 10-2 | 2 X 10-7 | 9 X 10-4 |
I | 1 X 10-6 | 6 X 10-3 | 3 X 10-8 | 2 X 10-4 | |
Silver (47) | Ag-105 S | 6 X 10-7 | 3 X 10-3 | 2 X 10-8 | 1 X 10-4 |
I | 8 X 10-8 | 3 X 10-3 | 3 X 10-9 | 1 X 10-4 | |
Ag-110m S | 2 X 10-7 | 9 X 10-4 | 7 X 10-9 | 3 X 10-5 | |
I | 1 X 10-8 | 9 X 10-4 | 3 X 10-10 | 3 X 10-5 | |
Ag-111 S | 3 X 10-7 | 1 X 10-3 | 1 X 10-8 | 4 X 10-5 | |
I | 2 X 10-7 | 1 X 10-3 | 8 X 10-9 | 4 X 10-5 | |
Sodium (11) | Na-22 S | 2 X 10-7 | 1 X 10-3 | 6 X 10-9 | 4 X 10-5 |
I | 9 X 10-9 | 9 X 10-4 | 3 X 10-10 | 3 X 10-5 | |
Na-24 S | 1 X 10-6 | 6 X 10-3 | 4 X 10-8 | 2 X 10-4 | |
I | 1 X 10-7 | 8 X 10-4 | 5 X 10-9 | 3 X 10-5 | |
Strontium (38) | Sr-85m S | 4 X 10-5 | 2 X 10-1 | 1 X 10-6 | 7 X 10-3 |
I | 3 X 10-5 | 2 X 10-1 | 1 X 10-6 | 7 X 10-3 | |
Sr-85 S | 2 X 10-7 | 3 X 10-3 | 8 X 10-9 | 1 X 10-4 | |
I | 1 X 10-7 | 5 X 10-3 | 4 X 10-9 | 2 X 10-4 | |
Sr-89 S | 3 X 10-8 | 3 X 10-4 | 3 X 10-10 | 3 X 10-6 | |
I | 4 X 10-8 | 8 X 10-4 | 1 X 10-9 | 3 X 10-5 | |
Sr-90 S | 1 X 10-9 | 1 X 10-5 | 3 X 10-11 | 3 X 10-7 | |
I | 5 X 10-9 | 1 X 10-3 | 2 X 10-10 | 4 X 10-5 | |
Sr-91 S | 4 X 10-7 | 2 X 10-3 | 2 X 10-8 | 7 X 10-5 | |
I | 3 X 10-7 | 1 X 10-3 | 9 X 10-9 | 5 X 10-5 | |
Sr-92 S | 4 X 10-7 | 2 X 10-3 | 2 X 10-8 | 7 X 10-5 | |
I | 3 X 10-7 | 2 X 10-3 | 1 X 10-8 | 6 X 10-5 | |
Sulfur (16) | S-35 S | 3 X 10-7 | 2 X 10-3 | 9 X 10-9 | 6 X 10-5 |
I | 3 X 10-7 | 8 X 10-3 | 9 X 10-9 | 3 X 10-4 | |
Tantalum (73) | Ta-182 S | 4 X 10-8 | 1 X 10-3 | 1 X 10-9 | 4 X 10-5 |
I | 2 X 10-8 | 1 X 10-3 | 7 X 10-10 | 4 X 10-5 |
Technetium (43 | )Tc-96m S | 8 X 10-5 | 4 X 10-1 | 3 X 10-6 | 1 X 10-2 |
I | 3 X 10-5 | 3 X 10-1 | 1 X 10-6 | 1 X 10-2 | |
Tc-96 S | 6 X 10-7 | 3 X 10-3 | 2 X 10-8 | 1 X 10-4 | |
I | 2 X 10-7 | 1 X 10-3 | 8 X 10-9 | 5 X 10-5 | |
Tc-97m S | 2 X 10-6 | 1 X 10-2 | 8 X 10-8 | 4 X 10-4 | |
I | 2 X 10-7 | 5 X 10-3 | 5 X 10-9 | 2 X 10-4 | |
Tc-97 S | 1 X 10-5 | 5 X 10-2 | 4 X 10-7 | 2 X 10-3 | |
I | 3 X 10-7 | 2 X 10-2 | 1 X 10-8 | 8 X 10-4 | |
Tc-99m S | 4 X 10-5 | 2 X 10-1 | 1 X 10-6 | 6 X 10-3 | |
I | 1 X 10-5 | 8 X 10-2 | 5 X 10-7 | 3 X 10-3 | |
Tc-99 S | 2 X 10-6 | 1 X 10-2 | 7 X 10-8 | 3 X 10-4 | |
I | 6 X 10-8 | 5 X 10-3 | 2 X 10-9 | 2 X 10-4 | |
Tellurium (52) | Te-125m S | 4 X 10-7 | 5 X 10-3 | 1 X 10-8 | 2 X 10-4 |
I | 1 X 10-7 | 3 X 10-3 | 4 X 10-9 | 1 X 10-4 | |
Te-127m S | 1 X 10-7 | 2 X 10-3 | 5 X 10-9 | 6 X 10-5 | |
I | 4 X 10-8 | 2 X 10-3 | 1 X 10-9 | 5 X 10-5 | |
Te-127 S | 2 X 10-6 | 8 X 10-3 | 6 X 10-8 | 3 X 10-4 | |
I | 9 X 10-7 | 5 X 10-3 | 3 X 10-8 | 2 X 10-4 | |
Te-129m S | 8 X 10-8 | 1 X 10-3 | 3 X 10-9 | 3 X 10-5 | |
I | 3 X 10-8 | 6 X 10-4 | 1 X 10-9 | 2 X 10-5 | |
Te-129 S | 5 X 10-6 | 2 X 10-2 | 2 X 10-7 | 8 X 10-4 | |
I | 4 X 10-6 | 2 X 10-2 | 1 X 10-7 | 8 X 10-4 | |
Te-131m S | 4 X 10-7 | 2 X 10-3 | 1 X 10-8 | 6 X 10-5 | |
I | 2 X 10-7 | 1 X 10-3 | 6 X 10-9 | 4 X 10-5 | |
Te-132 S | 2 X 10-7 | 9 X 10-4 | 7 X 10-9 | 3 X 10-5 | |
I | 1 X 10-7 | 6 X 10-4 | 4 X 10-9 | 2 X 10-5 | |
Terbium (65) | Tb-160 S | 1 X 10-7 | 1 X 10-3 | 3 X 10-9 | 4 X 10-5 |
I | 3 X 10-8 | 1 X 10-3 | 1 X 10-9 | 4 X 10-5 | |
Thallium (81) | Tl-200 S | 3 X 10-6 | 1 X 10-2 | 9 X 10-8 | 4 X 10-4 |
I | 1 X 10-6 | 7 X 10-3 | 4 X 10-8 | 2 X 10-4 | |
Tl-201 S | 2 X 10-6 | 9 X 10-3 | 7 X 10-8 | 3 X 10-4 | |
I | 9 X 10-7 | 5 X 10-3 | 3 X 10-8 | 2 X 10-4 | |
Tl-202 S | 8 X 10-7 | 4 X 10-3 | 3 X 10-8 | 1 X 10-4 | |
I | 2 X 10-7 | 2 X 10-3 | 8 X 10-9 | 7 X 10-5 | |
Tl-204 S | 6 X 10-7 | 3 X 10-3 | 2 X 10-8 | 1 X 10-4 | |
I | 3 X 10-8 | 2 X 10-3 | 9 X 10-10 | 6 X 10-5 | |
Thorium (90) | Th-227 S | 3 X 10-10 | 5 X 10-4 | 1 X 10-11 | 2 X 10-5 |
I | 2 X 10-10 | 5 X 10-4 | 6 X 10-12 | 2 X 10-5 | |
Th-228 S | 9 X 10-12 | 2 X 10-4 | 3 X 10-13 | 7 X 10-6 | |
I | 6 X 10-12 | 4 X 10-4 | 2 X 10-13 | 1 X 10-5 |
Thorium (90) | Th-2 | 30 S 2 | X 10-12 5 X 10-5 | 8 | X 10-14 2 X 10-6 |
I | 1 X 10-11 | 9 X 10-4 | 3 X 10-13 | 3 X 10-5 | |
Th-231 S | 1 X 10-6 | 7 X 10-3 | 5 X 10-8 | 2 X 10-4 | |
I | 1 X 10-6 | 7 X 10-3 | 4 X 10-8 | 2 X 10-4 | |
Th-232 S | 3 X 10-11 | 5 X 10-5 | 1 X 10-12 | 2 X 10-6 | |
I Th- | 3 X 10-11 | 1 X 10-3 | 1 X 10-12 | 4 X 10-5 | |
natural S | 6 X 10-11 | 6 X 10-5 | 2 X 10-12 | 2 X 10-6 | |
I | 6 X 10-11 | 6 X 10-4 | 2 X 10-12 | 2 X 10-5 | |
Thorium (90) | Th-234 S | 6 X 10-8 | 5 X 10-4 | 2 X 10-9 | 2 X 10-5 |
I | 3 X 10-8 | 5 X 10-4 | 1 X 10-9 | 2 X 10-5 | |
Thulium (69) | Tm-170 S | 4 X 10-8 | 1 X 10-3 | 1 X 10-9 | 5 X 10-5 |
I | 3 X 10-8 | 1 X 10-3 | 1 X 10-9 | 5 X 10-5 | |
Tm-171 S | 1 X 10-7 | 1 X 10-2 | 4 X 10-9 | 5 X 10-4 | |
I | 2 X 10-7 | 1 X 10-2 | 8 X 10-9 | 5 X 10-4 | |
Tin (50) | Sn-113 S | 4 X 10-7 | 2 X 10-3 | 1 X 10-8 | 9 X 10-5 |
I | 5 X 10-8 | 2 X 10-3 | 2 X 10-9 | 8 X 10-5 | |
Sn-125 S | 1 X 10-7 | 5 X 10-4 | 4 X 10-9 | 2 X 10-5 | |
I | 8 X 10-8 | 5 X 10-4 | 3 X 10-9 | 2 X 10-5 | |
Tungsten (74) | W-181 S | 2 X 10-6 | 1 X 10-2 | 8 X 10-8 | 4 X 10-4 |
I | 1 X 10-7 | 1 X 10-2 | 4 X 10-9 | 3 X 10-4 | |
W-185 S | 8 X 10-7 | 4 X 10-3 | 3 X 10-8 | 1 X 10-4 | |
I | 1 X 10-7 | 3 X 10-3 | 4 X 10-9 | 1 X 10-4 | |
W-187 S | 4 X 10-7 | 2 X 10-3 | 2 X 10-8 | 7 X 10-5 | |
I | 3 X 10-7 | 2 X 10-3 | 1 X 10-8 | 6 X 10-5 | |
Uranium (92) | U-230 S | 3 X 10-10 | 1 X 10-4 | 1 X 10-11 | 5 X 10-6 |
I | 1 X 10-10 | 1 X 10-4 | 4 X 10-12 | 5 X 10-6 | |
U-232 S | 1 X 10-10 | 8 X 10-4 | 3 X 10-12 | 3 X 10-5 | |
I | 3 X 10-11 | 8 X 10-4 | 9 X 10-13 | 3 X 10-5 | |
U-233 S | 5 X 10-10 | 9 X 10-4 | 2 X 10-11 | 3 X 10-5 | |
I | 1 X 10-10 | 9 X 10-4 | 4 X 10-12 | 3 X 10-5 | |
U-234 S19/ | 6 X 10-10 | 9 X 10-4 | 2 X 10-11 | 3 X 10-5 | |
I | 1 X 10-10 | 9 X 10-4 | 4 X 10-12 | 3 X 10-5 | |
U-235 S19/ | 5 X 10-10 | 8 X 10-4 | 2 X 10-11 | 3 X 10-5 | |
I | 1 X 10-10 | 8 X 10-4 | 4 X 10-12 | 3 X 10-5 | |
U-236 S | 6 X 10-10 | 1 X 10-3 | 4 X 10-12 | 3 X 10-5 | |
I | 1 X 10-10 | 1 X 10-3 | 4 X 10-12 | 3 X 10-5 | |
U-238 S19/ | 7 X 10-11 | 1 X 10-3 | 3 X 10-12 | 4 X 10-5 |
Uranium (92) | I | 1 X 10-10 | 1 X 10-3 | 5 X 10-12 | 4 X 10-5 |
U-240 S | 2 X 10-7 | 1 X 10-3 | 8 X 10-9 | 3 X 10-5 | |
I | 2 X 10-7 | 1 X 10-3 | 6 X 10-9 | 3 X 10-5 | |
natural S19/ | 1 X 10-10 | 1 X 10-3 | 5 X 10-12 | 3 X 10-5 | |
I | 1 X 10-10 | 1 X 10-3 | 5 X 10-12 | 3 X 10-5 | |
Vanadium (23 | ) V-48 S | 2 X 10-7 | 9 X 10-4 | 6 X 10-9 | 3 X 10-5 |
I | 6 X 10-8 | 8 X 10-4 | 2 X 10-9 | 3 X 10-5 | |
Xenon (54) | Xe-131m Sub17 | / 2 X 10-5 | --- | 4 X 10-7 | --- |
Xe-131 Sub | 1 X 10-5 | --- | 3 X 10-7 | --- | |
Xe-133 Sub | 1 X 10-5 | --- | 3 X 10-7 | --- | |
Xe-135 Sub | 4 X 10-6 | --- | 1 X 10-7 | --- | |
Ytterbium(70) | Yb-175 S | 7 X 10-7 | 3 X 10-3 | 2 X 10-8 | 1 X 10-4 |
I | 6 X 10-7 | 3 X 10-3 | 2 X 10-8 | 1 X 10-4 | |
Yttrium (39) | Y-88* S | 3 X 10-7 | 2 X 10-3 | 6 X 10-9 | 7 X 10-5 |
I | 5 X 10-8 | 3 X 10-3 | 2 X 10-9 | 9 X 10-5 | |
Y-90 S | 1 X 10-7 | 6 X 10-4 | 4 X 10-9 | 2 X 10-5 | |
I | 1 X 10-7 | 6 X 10-4 | 3 X 10-9 | 2 X 10-5 | |
Y-91m S | 2 X 10-5 | 1 X 10-1 | 8 X 10-7 | 3 X 10-3 | |
I | 2 X 10-5 | 1 X 10-1 | 6 X 10-7 | 3 X 10-3 | |
Y-91 S | 4 X 10-8 | 8 X 10-4 | 1 X 10-9 | 3 X 10-5 | |
I | 3 X 10-8 | 8 X 10-4 | 1 X 10-9 | 3 X 10-5 | |
Y-92 S | 4 X 10-7 | 2 X 10-3 | 1 X 10-8 | 6 X 10-5 | |
I | 3 X 10-7 | 2 X 10-3 | 1 X 10-8 | 6 X 10-5 | |
Y-93 S | 2 X 10-7 | 8 X 10-4 | 6 X 10-9 | 3 X 10-5 | |
I | 1 X 10-7 | 8 X 10-4 | 5 X 10-9 | 3 X 10-5 | |
Zinc (30) | Zn-65 S | 1 X 10-7 | 3 X 10-3 | 4 X 10-9 | 1 X 10-4 |
I | 6 X 10-8 | 5 X 10-3 | 2 X 10-9 | 2 X 10-4 | |
Zn-69m S | 4 X 10-7 | 2 X 10-3 | 1 X 10-8 | 7 X 10-5 | |
I | 3 X 10-7 | 2 X 10-3 | 1 X 10-8 | 6 X 10-5 | |
Zn-69 S | 7 X 10-6 | 5 X 10-2 | 2 X 10-7 | 2 X 10-3 | |
I | 9 X 10-6 | 5 X 10-2 | 3 X 10-7 | 2 X 10-3 | |
Zirconium (40 | ) Zr-93 S | 1 X 10-7 | 2 X 10-2 | 4 X 10-9 | 8 X 10-4 |
I | 3 X 10-7 | 2 X 10-2 | 1 X 10-8 | 8 X 10-4 | |
Zr-95 S | 1 X 10-7 | 2 X 10-3 | 4 X 10-9 | 6 X 10-5 | |
I | 3 X 10-8 | 2 X 10-3 | 1 X 10-9 | 6 X 10-5 | |
Zr-97 S | 1 X 10-7 | 5 X 10-4 | 4 X 10-9 | 2 X 10-5 | |
I | 9 X 10-8 | 5 X 10-4 | 3 X 10-9 | 2 X 10-5 |
Any single radio-nuclide not listed above with decay mode other than alpha emission or spontaneous fission and with radioactive half-life less than 2 hours. | Sub17/ | 1 X 10-6 | ---- | 3 X 10-8 | ---- |
Any single radio-nuclide not listed above with decay mode other than | 3 X 10-9 | 9 X 10-5 | 1 X 10-10 | 3 X 10-6 | |
alpha emission or spontaneous fission and with radioactive half-life greater than 2 hours. | |||||
Any single radio-nuclide not listed above, which decays by alpha emission o spontaneous fission. | r | 6 X 10-13 | 4 X 10-7 | 2 X 10-14 | 3 X 10-8 |
* The values for Ge-98, Au-195 and Y-88 have been calculated using the committed dose equivalent values of ICRP Publication 30 for the controlling organ.
CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND
(See notes at end of Appendix) Footnotes continued:
Maximum Time Between Collection Total alpha and Measurement(hours)18a/ disintegrations | Alpha-Emitting Daughter Activity Collected Per Milliliter of Air | |
Microcuries/ml | per minute per ml | |
0.5 | 7.2 X 10-8 | 0.16 |
1.0 | 4.5 X 10-8 | 0.10 |
2.0 | 1.3 X 10-8 | 0.028 |
3.0 | 0.3 X 10-8 | 0.0072 |
NOTE:In any case where there is a mixture in air or water of more
than one radionuclide, the limiting values for purposes of this Appendix should be determined as follows.
Example: If radionuclides a, b and c are present in concentrations Ca,
Cb and Cc, and if the applicable MPC's are MPCa, MPCb and MPCc respectively, then the concentrations shall be limited so that the following relationship exists:
APPENDIX A
CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND
(See notes at end of Appendix)
Table I _________________ | Table II ________________ | ||||
Element (atomic number) Isot | ope16/ | Column 1 Air (µ Ci/ml) | Column 2 Water (µ Ci/ml) | Column 1 Air (µ Ci/ml) | Column 2 Water (µ Ci/ml) |
If it is known that Sr-90, I-125, I-126, I-129, I-131, I-133 (Table II only), Pb-210, Po-210, At-211, Ra-223, Ra-224, Ra-226, Ac-227, Ra-228, Th-230, Pa-231, Th-232, Th-nat, Cm-248, Cf-254 and Fm-256 are not present | ----- | 9 X 10-5 | ----- | 3 X 10-6 | |
APPENDIX A
CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND
(See notes at end of Appendix)
Table I ___________________ | Table II _________________ | |||
Element (atomic number) Isotope16/ | Column 1 Air (µ Ci/ml) | Column 2 Water (µ Ci/ml) | Column 1 Air (µ Ci/ml) | Column 2 Water (µ Ci/ml) |
If it is known that Sr-90, I-125, I-126, I-129, I-131, (I-133, Table II only), Pb-210, Po-210, Ra-223, Ra-226, Ra-228, Pa-231, Th-nat, Cm-248, Cf-254 and Fm-256 are not present | ----- | 6 X 10-5 | --- | -- 2 X 10-6 |
If it is known that Sr-90, I-129, (I-125, I-126, I-131, Table II only), Pb-210, Ra-226, Ra-228, Cm-248 and Cf-254 are not present | ----- | 2 X 10-5 | -- | -- 6 X 10-7 |
If it is known that (I-129, Table II only), Ra-226 and Ra-228 are not present | ----- | 3 X 10-6 | --- | -- 1 X 10-7 |
If it is known that alpha-emitters and Sr-90, I-129, Pb-210, Ac-227, Ra-228, Pa-230, Pu-241 and Bk-249 are not present | 3 X 10-9 | ----- | 1 X | 10-10 ---- |
If it is known that alpha-emitters and Pb-210, Ac-227, Ra-228 and Pu-241 are not present | 3 X 10-10 | ----- | 1 X | 10-11 ---- |
If it is known that alpha-emitters and Ac-227 are not present | 3 X 10-11 | ----- | 1 X | 10-12 ---- |
If it is known that Ac-227, Th-230, Pa-231, Pu-238, Pu-239, Pu-240, Pu-242, Pu-244, Cm-248, Cf-249 and Cf-251 are not present | 3 X 10-12 | ----- | 1 X 10-13 | ----- |
and
Material | Microcuries | Material | Microcuries |
Americium 241 | 0.01 | Germanium 71 | 100 |
Antimony 122 | 100 | Gold 195 | 10 |
Antimony 124 | 10 | Gold 198 | 100 |
Antimony 125 | 10 | Gold 199 | 100 |
Arsenic 73 | 100 | Hafnium 181 | 10 |
Arsenic 74 | 10 | Holmium 166 | 100 |
Arsenic 76 | 10 | Hydrogen 3 | 1,000 |
Arsenic 77 | 100 | Indium 111 | 100 |
Barium 131 | 10 | Indium 113m | 100 |
Barium 133 | 10 | Indium 114m | 10 |
Barium 140 | 10 | Indium 115m | 100 |
Bismuth 210 | 1 | Indium 115 | 10 |
Bromine 82 | 10 | Iodine 123 | 100 |
Cadmium 109 | 10 | Iodine 125 | 1 |
Cadmium 115m | 10 | Iodine 126 | 1 |
Cadmium 115 | 100 | Iodine 129 | 0.1 |
Calcium 45 | 10 | Iodine 131 | 1 |
Calcium 47 | 10 | Iodine 132 | 10 |
Carbon 14 | 100 | Iodine 133 | 1 |
Cerium 141 | 100 | Iodine 134 | 10 |
Cerium 143 | 100 | Iodine 135 | 10 |
Cerium 144 | 1 | Iridium 192 | 10 |
Cesium 129 | 100 | Iridium 194 | 100 |
Cesium 131 | 1,000 | Iron 54 | 10 |
Cesium 134m | 100 | Iron 55 | 100 |
Cesium 134 | 1 | Iron 59 | 10 |
Cesium 135 | 10 | Krypton 85 | 100 |
Cesium 136 | 10 | Krypton 87 | 10 |
Cesium 137 | 10 | Lanthanum 140 | 10 |
Chlorine 36 | 10 | Lutetium 177 | 100 |
Chlorine 38 | 10 | Manganese 52 | 10 |
Chromium 51 | 1,000 | Manganese 54 | 10 |
Cobalt 57 | 100 | Manganese 56 | 10 |
Cobalt 58m | 10 | Mercury 197m | 100 |
Cobalt 58 | 10 | Mercury 197 | 100 |
Cobalt 60 | 1 | Mercury 203 | 10 |
Copper 64 | 100 | Molybdenum 99 | 100 |
Dysprosium 165 | 10 | Neodymium 147 | 100 |
Dysprosium 166 | 100 | Neodymium 149 | 100 |
Erbium 169 | 100 | Nickel 59 | 100 |
Erbium 171 | 100 | Nickel 63 | 10 |
Europium 152 9.2h | 100 | Nickel 65 | 100 |
Europium 152 13yr | 1 | Niobium 93m | 10 |
Europium 154 | 1 | Niobium 95 | 10 |
Europium 155 | 10 | Niobium 97 | 10 |
Fluorine 18 | 1,000 | Osmium 185 | 100 |
Gadolinium 153 | 10 | Osmium 191m | 100 |
Gadolinium 159 | 100 | Osmium 191 | 100 |
Gallium 67 | 100 | Osmium 193 | 100 |
Gallium 72 | 10 | Palladium 103 | 100 |
Germanium 68 | 10 | Palladium 109 | 100 |
Phosphorus 32 | 10 |
Platinum 191 | 100 |
Platinum 193m | 100 |
Platinum 193 | 100 |
Platinum 197m | 100 |
Platinum 197 | 100 |
Plutonium 239 | 0.01 |
Polonium 210 | 0.1 |
Potassium 42 | 10 |
Potassium 43 | 10 |
Praseodymium 142 | 100 |
Praseodymium 143 | 100 |
Promethium 147 | 10 |
Promethium 149 | 10 |
Radium 226 | 0.01 |
Rhenium 186 | 100 |
Rhenium 188 | 100 |
Rhodium 103m | 100 |
Rhodium 105 | 100 |
Rubidium 81 | 10 |
Rubidium 86 | 10 |
Rubidium 87 | 10 |
Ruthenium 97 | 100 |
Ruthenium 103 | 10 |
Ruthenium 105 | 10 |
Ruthenium 106 | 1 |
Samarium 151 | 10 |
Samarium 153 | 100 |
Scandium 46 | 10 |
Scandium 47 | 100 |
Scandium 48 | 10 |
Selenium 75 | 10 |
Silicon 31 | 100 |
Silver 105 | 10 |
Silver 110m | 1 |
Silver 111 | 100 |
Sodium 22 | 1 |
Sodium 24 | 10 |
Strontium 85 | 10 |
Strontium 89 | 1 |
Strontium 90 | 0.1 |
Strontium 91 | 10 |
Strontium 92 | 10 |
Sulfur 35 | 100 |
Tantalum 182 | 10 |
Technetium 96 | 100 |
Technetium 97m | 100 |
Technetium 97 | 100 |
Technetium 99m | 100 |
Technetium 99 | 10 |
Tellurium 125m | 10 |
Tellurium 127m | 10 |
Tellurium 127 | 100 |
Tellurium 129m | 10 |
Tellurium 129 | 100 |
Tellurium 131m | 10 |
Tellurium 132 | 10 |
Terbium 160 | 10 |
Thallium 200 | 100 |
Thallium 201 | 100 |
Thallium 202 | 100 |
Thallium 204 | 10 |
Thorium (natural)20/ | 100 |
Thulium 170 | 10 |
Thulium 171 | 10 |
Tin 113 | 10 |
Tin 125 | 10 |
Tungsten 181 | 10 |
Tungsten 185 | 10 |
Tungsten 187 | 100 |
Uranium | 100 |
(natural)21/ | |
Uranium 233 | 0.01 |
Uranium 234- | |
Uranium 235 | 0 .01 |
Vanadium 48 | 10 |
Xenon 131m | 1,000 |
Xenon 133 | 100 |
Xenon 135 | 100 |
Ytterbium 175 | 100 |
Yttrium 87 | 10 |
Yttrium 88 | 10 |
Yttrium 90 | 10 |
Yttrium 91 | 10 |
Yttrium 92 | 100 |
Yttrium 93 | 100 |
Zinc 65 | 10 |
Zinc 69m | 100 |
Zinc 69 | 1,000 |
Zirconium 93 | 10 |
Zirconium 95 | 10 |
Zirconium 97 | 10 |
Any alpha emitting radionuclide not listed above or mixtures of alpha emitters of unknown composition | 0.01 |
Any radionuclide other than alpha emitting radionuclide, not listed above or mixtures of beta emitters of unknown composition | 0.1 |
Note: For purposes of RH-1303 and RH-1403, where there is involved a combination of isotopes in known amounts, the limit for the combination should be derived as follows: Determine, for each isotope in the combination, the ratio between the quantity present in the combination and the limit otherwise established for the specific isotope when not in combination. The sum of such ratios for all the isotopes in the combination may not exceed "1" (i.e., "unity"). Example: For purposes of RH-1403, if a particular batch contains 20,000 µ Ci of Au198 and 50,000 µ Ci of C14, it may also include not more than 300 µ Ci of I131. This limit was determined as follows:
The denominator in each of the above ratios was obtained by multiplying the figure in the Table by 1,000 as provided in RH-1403.
where r is the gamma-ray constant, corresponding to the dose in R/h at 1 meter per Ci; the number 9 results from the choice of 1 rem/h at a distance of 3 meter as the reference dose-equivalent rate.
for Z [LESS THAN] 55-A1 = 1000 Ci for Z > 55-A1 = 200 Ci where Z is the atomic number of the nuclide.
A1 = 1000 A3
where A3 is the value listed in Table A-3.
A1 is taken to be 2 Ci and the value of A2 is taken to be 0.002 Ci. However, if the atomic number of the radionuclide is known to be less than 82, the value of A1 is taken to be 10 Ci and the value of A2 is taken to be 0.4 Ci.
A1 = 10 Ci A2 = 0.4 Ci
A1 (R1, R2, .... Rn) is the value of A1 or A2 as appropriate for the nuclide R1, R2, .... Rn.
TABLE C-1 A1 AND A2 VALUES FOR RADIONUCLIDES
(See footnotes at end of Table)
Symbol of radionuclide | Element and Atomic Number | A1(Ci) | A2(Ci) | Specific activity (Ci/g) |
Ac-227 | Actinium (89) | 1000 | 0.003 | 7.2 x 10 |
Ac-228 | 10 | 4 | 2.2 x 106 | |
Ag-105 | Silver (47) | 40 | 40 | 3.1 x 104 |
Ag-110m | 7 | 7 | 4.7 x 103 | |
Ag-111 | 100 | 20 | 1.6 x 105 | |
Am-241 | Americium (95) | 8 | 0.008 | 3.2 |
Am-243 | 8 | 0.008 | 1.9 x 10-1 | |
Ar-37 (compressed or | ||||
uncompressed)* | Argon (18) | 1000 | 1000 | 1.0 x 105 |
Ar-41 (uncompressed)* | 20 | 20 | 4.3 x 107 | |
Ar-41 (compressed)* | 1 | 1 | 4.3 x 107 | |
As-73 | Arsenic (33) | 1000 | 400 | 2.4 x 104 |
As-74 | 20 | 20 | 1.0 x 105 | |
As-76 | 10 | 10 | 1.6 x 106 | |
As-77 | 300 | 20 | 1.1 x 106 | |
At-211 | Astatine (85) | 200 | 7 | 2.1 x 106 |
Au-193 | Gold (79) | 200 | 200 | 9.3 x 105 |
Au-196 | 30 | 30 | 1.2 x 105 | |
Au-198 | 40 | 20 | 2.5 x 105 | |
Au-199 | 200 | 25 | 2.1 x 105 | |
Ba-131 | Barium (56) | 40 | 40 | 8.7 x 104 |
Ba-133 | 40 | 10 | 4.0 x 102 | |
Ba-140 | 20 | 20 | 7.3 x 104 | |
Be-7 | Beryllium (4) | 300 | 300 | 3.5 x 105 |
Bi-206 | Bismuth (83) | 5 | 5 | 9.9 x 104 |
Bi-207 | 10 | 25 | 2.2 x 102 | |
Bi-210 (RaE) | 100 | 4 | 1.2 x 105 | |
Bi-212 | 6 | 6 | 1.5 x 107 | |
Bk-249 | Berkelium (97) | 1000 | 1 | 1.8 x 103 |
Br-77 | Bromine (35) | 70 | 25 | 7.1 x 105 |
Br-82 | 6 | 6 | 1.1 x 106 | |
C-11 | Carbon (6) | 20 | 20 | 8.4 x 108 |
C-14 | 1000 | 60 | 4.6 | |
Ca-45 | Calcium (20) | 1000 | 25 | 1.9 x 104 |
Ca-47 | 20 | 20 | 5.9 x 105 | |
Cd-109 | Cadmium (48) | 1000 | 70 | 2.6 x 103 |
Cd-115m | 30 | 30 | 2.6 x 104 | |
Cd-115 | 80 | 20 | 5.1 x 105 | |
Ce-139 | Cerium (58) | 100 | 100 | 6.5 x 103 |
Ce-141 | 300 | 25 | 2.8 x 104 | |
Ce-143 | 60 | 20 | 6.6 x 105 | |
Ce-144 | 10 | 7 | 3.2 x 103 | |
Cf-249 | Californium (98) | 2 | 0.002 | 3.1 |
Cf-250 | 7 | 0.007 | 1.3 x 102 | |
m = metastable state |
Cf-252 Cl-36 | Chlorine (17) | 2 300 | 0.009 10 | 6.5 x 102 3.2 x 10-2 |
Cl-38 | 10 | 10 | 1.3 x 108 | |
Cm-242 | Curium (96) | 200 | 0.2 | 3.3 x 103 |
Cm-243 | 9 | 0.009 | 4.2 x 10 | |
Cm-244 | 10 | 0.01 | 8.2 x 10 | |
Cm-245 | 6 | 0.006 | 1.0 x 10-1 | |
Cm-246 | 6 | 0.006 | 3.6 x 10-1 | |
Co-56 | Cobalt (27) | 5 | 5 | 3.0 x 104 |
Co-57 | 90 | 90 | 8.5 x 103 | |
Co-58m | 1000 | 1000 | 5.9 x 106 | |
Co-58 | 20 | 20 | 3.1 x 104 | |
Co-60 | 7 | 7 | 1.1 x 103 | |
Cr-51 | Chromium (24) | 600 | 600 | 9.2 x 104 |
Cs-129 | Cesium (55) | 40 | 40 | 7.6 x 105 |
Ca-131 | 1000 | 1000 | 1.0 x 105 | |
Ca-134m | 1000 | 10 | 7.4 x 106 | |
Cs-134 | 10 | 10 | 1.2 x 103 | |
Cs-135 | 1000 | 25 | 8.8 x 10-4 | |
Cs-136 | 7 | 7 | 7.4 x 104 | |
Ca-137 | 30 | 10 | 9.8 x 10 | |
Cu-64 | Copper (29) | 80 | 25 | 3.8 x 106 |
Cu-67 | 200 | 25 | 7.9 x 105 | |
Dy-165 | Dysprosium (66) | 100 | 20 | 8.2 x 106 |
Dy-166 | 1000 | 200 | 2.3 x 105 | |
Er-169 | Erbium (68) | 1000 | 25 | 8.2 x 104 |
Er-171 | 50 | 20 | 2.4 x 106 | |
Eu-152m | Europium (63) | 30 | 30 | 2.2 x 106 |
Eu-152 | 20 | 10 | 1.9 x 102 | |
Eu-154 | 10 | 5 | 1.5 x 102 | |
Eu-155 | 400 | 60 | 1.4 x 103 | |
F-18 | Fluorine (9) | 20 | 20 | 9.3 x 107 |
Fe-52 | Iron (26) | 5 | 5 | 7.3 x 106 |
Fe-55 | 1000 | 1000 | 2.2 x 103 | |
Fe-59 | 10 | 10 | 4.9 x 104 | |
Ga-67 | Gallium (31) | 100 | 100 | 6.0 x 105 |
Ga-68 | 20 | 20 | 4.0 x 107 | |
Ga-72 | 7 | 7 | 3.1 x 106 | |
Gd-153 | Gadolinium (64) | 200 | 100 | 3.6 x 103 |
Gd-159 | 300 | 20 | 1.1 x 106 | |
Ge-68 | Germanium (32) | 20 | 10 | 7.0 x 103 |
Ge-71 | 1000 | 1000 | 1.6 x 105 | |
m = metastable state |
H-3 | Hydrogen (1) see T-Tritium | |||
Hf-181 | Hafnium (72) | 30 | 25 | 1.6 x 104 |
Hg-197m | Mercury (80) | 200 | 200 | 6.6 x 105 |
Hg-197 | 200 | 200 | 2.5 x 105 | |
Hg-203 | 80 | 25 | 1.4 x 104 | |
Ho-166 | Holmium (67) | 30 | 30 | 6.9 x 105 |
I-123 | Iodine (53) | 50 | 50 | 1.9 x 106 |
I-125 | 1000 | 70 | 1.7 x 104 | |
I-126 | 40 | 10 | 7.8 x 104 | |
I-129 | 1000 | 2 | 1.6 x 10-4 | |
I-131 | 40 | 10 | 1.2 x 105 | |
I-132 | 7 | 7 | 1.1 x 107 | |
I-133 | 30 | 10 | 1.1 x 106 | |
I-134 | 8 | 8 | 2.7 x 107 | |
I-135 | 10 | 10 | 3.5 x 106 | |
In-111 | Indium (49) | 30 | 25 | 4.2 x 105 |
In-113m | 60 | 60 | 1.6 x 107 | |
In-114m | 30 | 20 | 2.3 x 104 | |
In-115m | 100 | 20 | 6.1 x 106 | |
Ir-190 | Iridium (77) | 10 | 10 | 6.2 x 104 |
Ir-192 | 20 | 10 | 9.1 x 103 | |
Ir-194 | 10 | 10 | 8.5 x 105 | |
K-42 | Potassium (19) | 10 | 10 | 6.0 x 106 |
K-43 | 20 | 10 | 3.3 x 106 | |
Kr-85m | ||||
(uncompressed)* | Krypton (36) | 100 | 100 | 8.4 x 106 |
Kr-85m (compressed | )* | 3 | 3 | 8.4 x 106 |
Kr-85 (uncompresse | d)* | 1000 | 1000 | 4.0 x 102 |
Kr-85 (compressed) | * | 5 | 5 | 4.0 x 102 |
Kr-87 (uncompresse | d)* | 20 | 20 | 2.8 x 107 |
Kr-87 (compressed) | * | 0.6 | 0.6 | 2.8 x 107 |
La-140 | Lanthanum (57) | 30 | 30 | 5.6 x 105 |
LSA: Low specific | activity material - see | Footnote | ||
Lu-177 | Lutetium (71) | 300 | 25 | 1.1 x 105 |
MFP: Mixed fission | products | 10 | 0.4 | |
Mg-28 | Magnesium (12) | 6 | 6 | 5.2 x 106 |
Mn-52 | Manganese (25) | 5 | 5 | 4.4 x 105 |
Mn-54 | 20 | 20 | 8.3 x 103 | |
Mn-56 | 5 | 5 | 2.2 x 107 | |
Mo-99 | Molybdenum (42) | 100 | 20 | 4.7 x 105 |
m = metastable state
N-13 Na-22 | Nitrogen (7) Sodium (11) | 20 8 | 10 8 | 1.5 x 109 6.3 x 103 |
Na-24 | 5 | 5 | 8.7 x 106 | |
Nb-93m | Niobium (41) | 1000 | 200 | 1.1 x 103 |
Nb-95 | 20 | 20 | 3.9 x 104 | |
Nb-97 | 20 | 20 | 2.6 x 107 | |
Nd-147 | Neodymium (60) | 100 | 20 | 8.0 x 104 |
Nd-149 | 30 | 20 | 1.1 x 107 | |
Ni-59 | Nickel (28) | 1000 | 900 | 8.1 x 10-2 |
Ni-63 | 1000 | 100 | 4.6 x 10 | |
Ni-65 | 10 | 10 | 1.9 x 107 | |
Np-237 | Neptunium (93) | 5 | 0.005 | 6.9 x 10-4 |
Np-239 | 200 | 25 | 2.3 x 105 | |
Os-185 | Osmium (76) | 20 | 20 | 7.3 x 103 |
Os-191 | 600 | 200 | 4.6 x 104 | |
Os-191m | 200 | 200 | 1.2 x 106 | |
Os-193 | 100 | 20 | 5.3 x 105 | |
P-32 | Phosphorus (15) | 30 | 30 | 2.9 x 105 |
Pa-230 | Protactinium (91) | 20 | 0.8 | 3.2 x 104 |
Pa-231 | 2 | 0.002 | 4.5 x 10-2 | |
Pa-233 | 100 | 100 | 2.1 x 104 | |
Pb-201 | Lead (82) | 20 | 20 | 1.7 x 106 |
Pb-210 | 100 | 0.2 | 8.8 x 10 | |
Pb-212 | 6 | 5 | 1.4 x 104 | |
Pd-103 | Palladium (46) | 1000 | 700 | 7.5 x 104 |
Pd-109 | 100 | 20 | 2.1 x 104 | |
Pm-147 | Promethium (61) | 1000 | 25 | 9.4 x 102 |
Pm-149 | 100 | 20 | 4.2 x 105 | |
Po-210 | Polonium (84) | 200 | 0.2 | 4.5 x 103 |
Pr-142 | Praseodymium (59) | 10 | 10 | 1.2 x 104 |
Pr-143 | 300 | 20 | 6.6 x 104 | |
Pt-191 | Platinum (78) | 100 | 100 | 2.3 x 105 |
Pt-193m | 200 | 200 | 2.0 x 105 | |
Pt-197m | 300 | 20 | 1.2 x 107 | |
Pt-197 | 300 | 20 | 8.8 x 105 | |
Pu-238 | Plutonium (94) | 3 | 0.003 | 1.7 x 10 |
Pu-239 | 2 | 0.002 | 6.2 x 10-2 | |
Pu-240 | 2 | 0.002 | 2.3 x 10-1 | |
Pu-241 | 1000 | 0.1 | 1.1 x 102 | |
Pu-242 | 3 | 0.003 | 3.9 x 10-3 | |
Ra-223 | Radium (88) | 50 | 0.2 | 5.0 x 104 |
Ra-224 | 6 | 0.5 | 1.6 x 106 | |
Ra-226 | 10 | 0.05 | 1.0 | |
Ra-228 | 10 | 0.05 | 2.3 x 102 |
m = metastable state
Rb-81 | Rubidium (37) | 30 | 25 | 8.2 x 104 |
Rb-86 | 30 | 30 | 8.1 x 104 | |
Rb-87 | "-" | "-" | 6.6 x 10-8 | |
Rb (natural) | "-" | "-" | 1.8 x 10-8 | |
Re-186 | Rhenium (75) | 100 | 20 | 1.9 x 105 |
Re-187 | "-" | "-" | 3.8 x 10-8 | |
Re-188 | 10 | 10 | 1.0 x 104 | |
Re (natural) | "-" | "-" | 2.4 x 10-8 | |
Rh-103m | Rhodium (45) | 1000 | 1000 | 3.2 x 107 |
Rh-105 | 200 | 25 | 8.2 x 105 | |
Rn-222 | Radon (86) | 10 | 2 | 1.5 x 105 |
Ru-97 | Ruthenium (44) | 80 | 80 | 5.5 x 105 |
Ru-103 | 30 | 25 | 3.2 x 104 | |
Ru-105 | 20 | 20 | 6.6 x 104 | |
Ru-106 | 10 | 7 | 3.4 x 103 | |
S-35 | Sulfur (16) | 1000 | 60 | 4.3 x 104 |
Sb-122 | Antimony (51) | 30 | 30 | 3.9 x 105 |
Sb-124 | 5 | 5 | 1.8 x 104 | |
Sb-125 | 40 | 25 | 1.4 x 103 | |
Sc-46 | Scandium (21) | 8 | 8 | 3.4 x 104 |
Sc-47 | 200 | 20 | 8.2 x 105 | |
Sc-48 | 5 | 5 | 1.5 x 106 | |
Se-75 | Selenium (34) | 40 | 40 | 1.4 x 104 |
Si-31 | Silicon (14) | 100 | 20 | 3.9 x 107 |
Sm-147 | Samarium (62) | "-" | "-" | 2.0 x 10-8 |
Sm-151 | 1000 | 90 | 2.6 x 10 | |
Sm-153 | 300 | 20 | 4.4 x 105 | |
Sn-113 | Tin (50) | 60 | 60 | 1.0 x 104 |
Sn-119m | 100 | 100 | 4.4 x 103 | |
Sn-125 | 10 | 10 | 1.1 x 105 | |
Sr-85m | Strontium (38) | 80 | 80 | 3.2 x 107 |
Sr-85 | 30 | 30 | 2.4 x 104 | |
Sr-87m | 50 | 50 | 1.2 x 107 | |
Sr-89 | 100 | 10 | 2.9 x 104 | |
Sr-90 | 10 | 0.4 | 1.5 x 102 | |
Sr-91 | 10 | 10 | 3.6 x 106 | |
Sr-92 | 10 | 10 | 1.3 x 107 | |
T (uncompressed)* | Tritium (1) | 1000 | 1000 | 9.7 x 103 |
T (compressed)* | 1000 | 1000 | 9.7 x 103 | |
T (activated luminou | s paint) | 1000 | 1000 | 9.7 x 103 |
T (absorbed on solid | carrier) | 1000 | 1000 | 9.7 x 103 |
T (tritiated water) | 1000 | 1000 | 9.7 x 103 |
m = metastable state "-" = Unlimited
T (other forms) | 20 | 20 | 9.7 x 103 | |
Ta-182 | Tantalum (73) | 20 | 20 | 6.2 x 103 |
Tb-160 | Terbium (65) | 20 | 10 | 1.1 x 104 |
Tc-96m | Technetium (43) | 1000 | 1000 | 3.8 x 107 |
Tc-96 | 6 | 6 | 3.2 x 105 | |
Tc-97m | 1000 | 200 | 1.5 x 104 | |
Tc-97 | 1000 | 400 | 1.4 x 10-3 | |
Tc-99m | 100 | 100 | 5.2 x 106 | |
Tc-99 | 1000 | 25 | 1.7 x 10-2 | |
Te-125m | Tellurium (52) | 1000 | 100 | 1.8 x 104 |
Te-127m | 300 | 20 | 4.0 x 10 | |
Te-127 | 300 | 20 | 2.6 x 106 | |
Te-129m | 30 | 10 | 2.5 x 104 | |
Te-129 | 100 | 20 | 2.0 x 107 | |
Te-131m | 10 | 10 | 8.0 x 105 | |
Te-132 | 7 | 7 | 3.1 x 105 | |
Th-227 | Thorium (90) | 200 | 0.2 | 3.2 x 104 |
Th-228 | 6 | 0.008 | 8.3 x 102 | |
Th-230 | 3 | 0.003 | 1.9 x 10-2 | |
Th-231 | 1000 | 25 | 5.3 x 105 | |
Th-232 | "-" | "" | 1.1 x 10-7 | |
Th-234 | 10 | 10 | 2.3 x 104 | |
Th (natural) | "-" | "-" | 2.2 x 10-7 | |
Th (irradiated)** | ||||
Tl-200 | Thallium (81) | 20 | 20 | 5.8 x 105 |
Tl-201 | 200 | 200 | 2.2 x 105 | |
Tl-202 | 40 | 40 | 5.4 x 104 | |
Tl-204 | 300 | 10 | 4.3 x 102 | |
Tm-170 | Thulium (69) | 300 | 10 | 6.0 x 103 |
Tm-171 | 1000 | 100 | 1.1 x 103 | |
U-230 | Uranium (92) | 100 | 0.1 | 2.7 x 104 |
U-232 | 30 | 0.03 | 2.1 x 10 | |
U-233 | 100 | 0.1 | 9.5 x 10-3 | |
U-234 | 100 | 0.1 | 6.2 x 10-3 | |
U-235 | 100 | 0.2 | 2.1 x 10-6 | |
U-236 | 200 | 0.2 | 6.2 x 10-5 | |
U-238 | "-" | "-" | 3.3 x 10-7 | |
U (natural) | "-" | "-" | (SEE TABLE C-4) |
m = metastable state "-" = Unlimited
U (enriched) | ||||
20% | "-" | "-" | (SEE TABLE C-4) | |
20% or greater | 100 | 0.1 | (SEE TABLE C-4) | |
U (depleted) | "-" | "-" | (SEE TABLE C-4) | |
U (irradiated)*** | ||||
V-48 | Vanadium (23) | 6 | 6 | 1.7 x 105 |
W-181 | Tungsten (74) | 200 | 100 | 5.0 x 103 |
W-185 | 1000 | 25 | 9.7 x 10-3 | |
W-187 | 40 | 20 | 7.0 x 105 | |
Xe-127 (uncompress | ed)* Xenon (54) | 70 | 70 | 2.8 x 104 |
Xe-127 (compressed | )* | 5 | 5 | 2.8 x 104 |
Xe-131m (compresse | d)* | 10 | 10 | 1.0 x 105 |
Xe-131m (uncompres | sed)* | 100 | 100 | 1.0 x 105 |
Xe-133 (uncompress | ed)* | 1000 | 1000 | 1.9 x 105 |
Xe-133 (compressed | )* | 5 | 5 | 1.9 x 105 |
Xe-135 (uncompress | ed)* | 70 | 70 | 2.5 x 105 |
Xe-135 (compressed | )* | 2 | 2 | 2.5 x 105 |
Y-87 | Yttrium (39) | 20 | 20 | 4.5 x 10 |
Y-90 | 10 | 10 | 2.5 x 105 | |
Y-91m | 30 | 30 | 4.1 x 107 | |
Y-91 | 30 | 30 | 2.5 x 104 | |
Y-92 | 10 | 10 | 9.5 x 106 | |
Y-93 | 10 | 10 | 3.2 x 106 | |
Yb-169 | Ytterbium (70) | 80 | 80 | 2.3 x 105 |
Yb-175 | 400 | 25 | 1.8 x 105 | |
Zn-65 | Zinc (30) | 30 | 30 | 8.0 x 103 |
Zn-69m | 40 | 20 | 3.3 x 106 | |
Zn-69 | 300 | 20 | 5.3 x 107 | |
Zr-93 | Zirconium (40) | 1000 | 200 | 3.5 x 10-3 |
Zr-95 | 20 | 20 | 2.1 x 104 | |
Zr-97 | 20 | 20 | 2.0 x 106 |
m = metastable state "-" = Unlimited
TABLE C-1 A1 AND A2 VALUES FOR RADIONUCLIDES
FOOTNOTES
* For the purpose of Table C-1, compressed gas means a gas at a pressure which exceeds the ambient atmospheric pressure at the location where the containment system was closed.
** The values of A1 and A2 must be calculated in accordance with the procedure specified in Appendix C, Paragraph b, taking into account the activity of the fission products and of the Uranium-233 in addition to that of the Thorium.
*** The values of A1 and A2 must be calculated with the procedure specified in Appendix C, Paragraph b, taking into account the activity of the fission products and Plutonium isotopes in addition to that of the Uranium.
Low specific activity material means any of the following:
quantity in Appendix C is not more than 0.05 curie;
TABLE C-2 RELATIONSHIP BETWEEN A1 AND Emax FOR BETA EMITTERS
Emax(MeV) | A1(Ci) |
[LESS THAN] 0.5 | 1000 |
0.5 - [LESS THAN] 1.0 | 300 |
1.0 - [LESS THAN] 1.5 | 100 |
1.5 - [LESS THAN] 2.0 | 30 |
* 2.0 | 10 |
TABLE C-3
RELATIONSHIP BETWEEN A3 AND THE ATOMIC NUMBER
OF THE RADIONUCLIDE
A3 | |||
Atomic Number | Half-life less than 1000 days | Half-life 1000 days to 106 years | Half-life greater than 106 years |
1 to 81 | 3 Ci | .05 Ci | 3 Ci |
82 and above | .002 Ci | .002 Ci | 3 Ci |
TABLE C-4. ACTIVITY-MASS RELATIONSHIPS FOR URANIUM/THORIUM
Thorium and Uranium enrichment* wt % U-234 present | Specific activity | |
Ci/g | g/Ci | |
0.45 | 5.0 x 10-7 | 2.0 x 106 |
0.72 (natural) | 7.06 x 10-7 | 1.42 x 106 |
1.0 | 7.6 x 10-7 | 1.3 x 106 |
1.5 | 1.0 x 10-6 | 1.0 x 106 |
5.0 | 2.7 x 10-6 | 3.7 x 105 |
10.0 | 4.8 x 10-6 | 2.1 x 105 |
20.0 | 1.0 x 10-5 | 1.0 x 105 |
35.0 | 2.0 x 10-5 | 5.0 x 104 |
50.0 | 2.5 x 10-5 | 4.0 x 104 |
90.0 | 5.8 x 10-5 | 1.7 x 104 |
93.0 | 7.0 x 10-5 | 1.4 x 104 |
95.0 | 9.1 x 10-5 | 1.1 x 104 |
Natural Thorium | 2.2 x 10-7 | 4.6 x 106 |
* The figures for Uranium include representative values for the activity of the Uranium-234 which is concentrated during the enrichment process. The activity for Thorium includes the equilibrium concentration of Thorium-228.
Appendix E to RH-1000 through RH-2110 Assigned Protection Factors for Respiratorsa
RESPIRATOR TYPE | OPERATING MODE | ASSIGNED PROTECTION FACTOR |
I. Air Purifying Respirators [Particulate bonly]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 respirator | 1000 |
Helmet/hood | Powered air-purifying respirator | 1000 |
Facepiece, loose-fitting | Powered air-purifying respirator | 25 |
II. Atmosphere supplying respirators [particulate, gases and vapors f] | ||
1. AIR-LINE RESPIRATORS | ||
Facepiece, half | Demand | 10 |
Facepiece, half | Continuous flow | 50 |
Facepiece, half | Pressure demand | 50 |
Facepiece, full | Demand | 100 |
Facepiece, full | Continuous flow | 1000 |
Facepiece, full | Pressure demand | 1000 |
Helmet/hood | Continuous flow | 1000 |
Facepiece, loose-fitting | Continuous flow | 25 |
Suit | Continuous flow | (g) |
2. SELF-CONTAINED BREATHING APPARATUS (SCBA) | ||
Facepiece, full | Demand | 100h |
Facepiece, full | Pressure demand | 10,000i |
Facepiece, full | Demand, re-circulating | 100h |
Facepiece, full | Positive pressure recirculating | 10,000 i |
III. Combination Respirators: | ||
Any combination of air-purifying and atmosphere-supplying respirators | (1) Assigned protection factor for type and mode of operation as listed above |
FOOTNOTES TO APPENDIX E
a These assigned protection factors apply only in a respiratory protection program that meets the requirement of this Part. 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 such circumstances must also comply with Department of Labor regulations. Radioactive contaminants for which the concentration values in RH-2792., Appendix G to RH-1000. Through RH-2100., Table 1, Column 3 are based on internal dose due to inhalation may, in addition, present external exposure hazards at higher concentrations. Under these circumstances, limitation on occupancy may have to be governed by external dose limits.
b Air purifying respirators with APF [LESS THAN]100 must be equipped with particulate filters that are at least 95 percent efficient. Air purifying respirators with APF = 100 must be equipped with particulate filters that are at least 99 percent efficient. Air purifying respirators with APFs > 100 must be equipped with particulate filters that are at least 99.97 percent efficient.
c The licensee may apply to the Department for the use of an APF greater than one (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 pre-use seal check on this type of device. All other respiratory protection program requirements listed in RH-1303(f). apply. An assigned protection factor has not been assigned for these devices. However, an APF equal to ten (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 Appendix 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 requirement 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 one-third of the intake occurs by absorption through the skin so that an overall protection factor of three (3) 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., RH-1303.(f))
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 limitation 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.
APPENDIX J
REQUIREMENTS FOR LOW-LEVEL WASTE TRANSFER FOR
DISPOSAL AT LAND DISPOSAL FACILITIES AND MANIFESTS
The shipment manifest shall contain the name, address, and telephone number of the person generating the waste. The manifest shall also include the name, address, and telephone number or the name and EPA hazardous waste identification number of the person transporting the waste to the land disposal facility. The manifest must also indicate as completely as practicable: a physical description of the waste, the volume, radionuclide identity and quantity, the total radioactivity, and the principal chemical form. The solidification agent must be specified. Waste containing more than 0.1% chelating agents by weight must be identified and the weight percentage of the chelating agent estimated. Wastes classified as Class A, Class B, or Class C in RH-407. must be clearly identified as such in the manifest. The total quantity of the radionuclides H-3, C-14, Tc-99, and I-129 must be shown. The manifest required by this Paragraph may be shipping papers used to meet Department of Transportation or Environmental Protection Agency regulations or requirements of the receiver, provided all the required information is included. Copies of manifests required by this Section may be legible carbon copies or legible photocopies.
The waste generator shall include in the shipment manifest a certification that the transported materials are properly classified, described, packaged, marked, and labeled and are in proper condition for transportation according to the applicable regulations of the Department of Transportation and the Department. An authorized representative of the waste generator shall sign and date the manifest.
This Part establishes requirements for notices, instructions and reports by licensees or registrants to individuals engaged in work under a license or registration; and options available to such individuals in connection with Department inspection of licensees or registrants to ascertain compliance with the provisions of the Act and the regulations, orders and licenses issued thereunder regarding radiological working conditions. The Regulations in this Part apply to all persons who receive, possess, use, own or transfer sources of radiation licensed by or registered with the Department pursuant to these Regulations in Section 1 and Section 2.
"This report is furnished to you under the provisions of Arkansas Department of Health Regulations entitled 'Standards for Protection Against Radiation.' You should preserve this report for further reference."
that an inspection is not warranted because there are no reasonable grounds to believe that a violation exists or has occurred, the Department shall notify the complainant in writing of such determination.
Arkansas Department of Health and Human Services
STANDARDS FOR PROTECTION AGAINST RADIATION
The Arkansas Department of Health and Human Services (ADHHS) has adopted regulations with standards to protect you from hazards associated with radioactive materials and radiation emitting machines which are licensed or registered by ADHHS. In particular, the following information is available for your review:
Section 3 : Standards for Protection Against Radiation
Part N: Notice, Instructions, and Reports to Workers. Any other documents your employer must provide.
These may be found at the following location:
YOUR EMPLOYER'S RESPONSIBILITY
Your employer is required to:
YOUR RESPONSIBILITY AS A WORKER
You should:
and the emergency procedures which apply to your work.
REPORTS ON YOUR RADIATION EXPOSURE HISTORY
INSPECTIONS:All licensed or registered activities are subject to inspection by the ADHHS.
INQUIRIES
Direct all inquiries on matters outlined above to: ADHHS, Division of Health, Radiation Control Section, P.O. Box 1437, Mail Slot H-30, Little Rock, AR 72203-1437; (501) 661-2301 Emergencies only (800) 633-1735
POSTING REQUIREMENT: Copies of this notice must be posted in every establishment where employees are engaged in activities licensed or registered by the ADHHS. Posting must permit employees working in or frequenting any portion of a restricted area to observe a coy on the way to or from their place of employment.
FOOTNOTES FOR SECTION 3
1/ 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, HT50, per unit intake is greater than ten (10%) percent of the maximum weighted value of HT50 (i.e., WTH50,T) per unit intake for any organ or tissue. HT50 was H50
2/ This Section applies to radiation from byproduct, source, or special nuclear materials that are used in sealed sources in non-self-shielded irradiators. This Section does not apply to radioactive sources that are used in teletherapy, in radiography, or in completely self-shielded irradiators in which the source is both stored and operated within the same shielding radiation barrier and, in the designed configuration of the create high levels of radiation in an area that is accessible to any individual. This Section also does not apply to sources from which the radiation is incidental to some other use or to nuclear reactor-generated radiation.
3/ As appropriate, the information will include radiation levels, kinds of material, estimate of activity, date for which activity is estimated, etc.
4/ Labeling of packages containing radioactive materials is required by the
Department of Transportation (DOT) if the amount and type of radioactive material exceeds the limits for an excepted quantity or article as defined and limited by DOT regulations 49 CFR 173.403(m) and (w) and 173.421-424.
5/ For example, containers in locations such as water-filled canals, storage vaults, or hot cells.
6/ Licensees are not required to reevaluate the separate external dose equivalents and internal committed dose equivalents or intakes of radionuclides assessed under RH-102. through RH-1308. Further, occupational exposure histories obtained and recorded on Department Form Z 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.
7/ Assessments of dose equivalent and records made using units in effect before the licensee's adoption of this Part need not be changed.
8/ A previous RH-407. permitted burial of small quantities of licensed materials in soil before January 28, 1981, without specific Department authorization.
9/ With respect to the limit for the embryo/fetus (RH-1027), the identifiers should be those of the declared pregnant woman.
10/ If, because of the patient's condition, a delay in order to provide a written revision to an existing written directive would jeopardize the patient's health, an oral revision to an existing written directive will be acceptable, provided that the oral revision is documented immediately in the patient's record and a revised written directive is signed by the authorized user within 48 hours of the oral revision.
Also, a written revision to an existing written directive may be made for any diagnostic or therapeutic procedure provided that the revision is dated and signed by an authorized user prior to the administration of the radiopharmaceutical dosage, the brachytherapy dose, the gamma stereotactic radiosurgery dose, the teletherapy dose, or the next teletherapy fractional dose. If, because of the emergent nature of the patient's condition, a delay in order to provide a written directive would jeopardize the patient's health, an oral directive will be acceptable, provided that the information contained in the oral directive is documented immediately in the patient's record and a written directive is prepared within 24 hours of the oral directive.
11/ The nominal chemical composition of type 1100 aluminum alloy is 99.00 percent (99%) minimum aluminum, 0.12 percent copper.
12/ The radiation detectors specified in RH-1608.b.6. may form part of this system.
13/ The calibration protocol published by the AAPM is accepted as an established protocol. Other protocols which are equivalent will be accepted, but the user should submit that protocol to the Department for concurrence that the protocol is equivalent.
14/ An example of a suggested plaque is shown in this Part.
15/ Appropriate warnings may include:
16/ Soluble (S); Insoluble (I)
17/ "Sub" means that values given are for submersion in a semi-spherical infinite cloud of airborne material.
18/ For purposes of these Regulations, it may be assumed that the daughter activity concentrations in the following table are equivalent to an air concentration of 10-7 microcuries of Radon-222 per milliliter of air in equilibrium with the daughters RaA, RaB, RaC and RaC'.
18a/ The duration of sample collection and the duration of measurement should be sufficiently short compared to the time between collection and measurement, as not to have a statistically significant effect upon the results.
19/ For soluble mixtures of U-238, U-234 and U-235 in air, chemical toxicity may be the limiting factor. If the percent by weight (enrichment) of U-235 is less than 5, the concentration value for a 40-hour workweek, Table I, is 0.2 milligrams Uranium per cubic meter or air average. For any enrichment, the product of the average of concentration and time of exposure during a 40-hour workweek shall not exceed 8 X 10-3 SA µCi-hr/ml, where SA is the specific activity of the Uranium inhaled. The concentration value for Table II is 0.007 milligrams Uranium per cubic meter of air. The specific activity for natural Uranium is 6.77 X 10-7 curies per gram U. The specific activity for other mixtures of U-238, U-235 and U-234, if not known, shall be:
SA = 3.6 X 10-7 curies/gram U U-depleted
SA = [0.4 + 0.38 (enrichment) + 0.0034 (enrichment)2] X 10-6 > 0.72
where enrichment is the percentage by weight of U-235, expressed as percent.
20/ Based on alpha disintegration rate of Th-232, Th-230, and their daughter products.
21/ Based on alpha disintegration rate of U-238, U-234, and U-235.
(FOOTNOTES APPEAR AT THE END OF THIS SECTION)
The following terms are as defined for the purpose of this Section. To ensure compatibility with international transportation standards, all limits in this part are given in terms of dual units: The International System of Units (SI) followed or preceded by U.S. standard or customary units. The U.S. customary units are not exact equivalents, but rounded to a convenient value, providing a functionally equivalent unit. For the purpose of this part, either unit may be used.
These values are either listed in RH-2700., Table C-1 or may be derived in accordance with the procedure prescribed in RH-2700., Appendix C.
uranium-233, uranium-235, or any combination of the radionuclides. Unirradiated natural uranium and depleted uranium that has been irradiated in thermal reactors only are not included in this definition.
Commonwealth of Puerto Rico, the Virgin Islands, Guam, American Samoa, and the Commonwealth of the Northern Mariana Islands.
Type A quantity.
Requirement for License.
Except as authorized in a general license or a specific license issued by the Department, or as exempted in this part, no licensee may:
Each licensee shall maintain for one (1) year a record of the name of the individual contacted.
B(U) or B(M) in the NRC Certificate of Compliance, may be used under the general license of RH-3302. with the following additional limitations:
Except as specified in RH-3306.f.2. for encapsulated plutonium beryllium sources, this general license applies only when a package is labeled with a transport index not less than the number given by the following equation, where the package contains 'x' grams of uranium-235, 'y' grams of uranium-233, and 'z' grams of the fissile radionuclides of plutonium:
Minimum Transport Index = (0.25x + 0.33y + 0.4z)
where X and Y are the mass defined in the table following RH-3307.d.2.
PERMISSIBLE MASS LIMITS FOR SHIPMENTS OF FISSILE MATERIAL | ||
Fissile mate- | Fissile mate- | |
rial mass (g) | rial mass (g) | |
mixed with | mixed with | |
substances | substances | |
Fissile material | having a hy- | having a hy- |
drogen density | drogen density | |
less than or | greater than | |
equal to water | water | |
Uranium-235 (X) | 500 | 290 |
Other fissile material | (Y) 300 | 180 |
Prior to each shipment of licensed material, the licensee shall ensure that the package with its contents satisfies the applicable requirements of this Section and the license. The licensee shall determine that:
The level of non-fixed (removable) radioactive contamination on the external surfaces of each package offered for shipment is as low as reasonably achievable. The level of non-fixed (removable) radioactive contamination may be determined by wiping an area of 300 square centimeters of the surface concerned with an absorbent material, using moderate pressure, and measuring the activity on the wiping material. Sufficient measurements must be taken in the most appropriate locations to yield a representative assessment of the non-fixed contamination levels. Except as provided in RH-3401.h.2., the amount of radioactivity measured on any single wiping material, when averaged over the surface wiped, must not exceed the limits given in Table 3 below at any time during transport. Other methods of assessment of equal or greater efficiency may be used. When other methods are used, the detection efficiency of the method used must be taken into account and in no case may the removable contamination on the external surfaces of the package exceed ten (10) times the limits listed in Table 3.
radiation levels external to the package may exceed the limits specified in RH-3401.h.1. but shall not exceed any of the following:
Table 3
Removable External Radioactive Contamination Wipe Limits
Maximum Permissible Limits Contaminant | uCi/cm2* | dpm/cm2 |
Beta-gamma emitting radionuclides; all radionuclides with half-lives less than ten days; natural uranium; natural thorium; uranium-235; uranium-238; thorium-232; thorium-228 and thorium-230 when contained in ores or physical concentrates | 10-5 | 22 |
All other alpha emitting radionuclides | 10-6 | 2.2 |
NOTE (*) == to convert microcuries (µCi) to SI units of megabecquerels, multiply the values by 37. | ||
Notwithstanding the provisions of any general licenses and notwithstanding any exemptions stated directly in this Section or included indirectly by citation of the U.S. Department of Transportation (DOT) regulations, as may be applicable, the licensee shall assure that plutonium in any form is not transported by air, or delivered to a carrier for air transport, unless:
The licensee shall report to the Department within thirty (30) days:
FOOTNOTES FOR SECTION 4
1/Any notification of incidents referred to in those requirements shall be filed with or made to, the Department.
2/For the purpose of this Section, "nuclear waste" means any large quantity of source, byproduct, or special nuclear material required to be in Type B packaging while transported to, through or across State boundaries to a disposal site, or to a collection point for transport to a disposal site.
Research and Development, as used in this Regulation, does not include the external administration of radiation to human beings.
Sources of Ionizing Radiation of the State Board of Health, Standards for Protection Against Radiation.
Radiation Control,
Arkansas Department of Health & Human Services,
P.O. Box 1437, Mail Slot H-30,
Little Rock, Arkansas 72203-1437.
The application shall set forth all applicable information called for by the form.
instrumentation tests and smear results shall be kept current and on file at each accelerator facility.
TABLE III
Maximum Energy of Electron Beam in MeV | X-ray Absorbed Dose as a Fraction of Maximum Absorbed Dose |
1 | 0.03 |
15 | 0.05 |
35 | 0.10 |
50 | 0.20 |
TABLE IV
Maximum Photon Energy in MeV | Absorbed Dose at the Surface as a Fraction of the Maximum Absorbed Dose |
1 | 0.80 |
2 | 0.70 |
5 | 0.60 |
15 | 0.50 |
35 | 0.40 |
50 | 0.20 |
All therapy systems shall be provided with radiation detectors in the radiation head.
It shall be possible to terminate irradiation and equipment movements or go from an interruption condition to termination condition, at any time from the operator's position at the treatment control panel.
Equipment capable of both x-ray therapy and electron therapy shall meet the following requirements:
Equipment capable of generating radiation beams of different energies shall meet the following requirements:
Equipment capable of both stationary beam therapy and moving beam therapy shall meet the following requirements:
For new equipment, a system shall be provided from whose readings the absorbed dose rate at a reference point in the treatment volume can be calculated. In addition:
The licensee shall determine, or obtain from the manufacturer, the location with reference to an accessible point on the radiation head of:
Capabilities shall be provided so that all radiation safety interlocks can be checked. When pre-selection of any of the operating conditions requires action in the treatment room and/or at the treatment control panel, selection at one location shall not give a display at the other location until the requisite selected operations in both locations have been completed.
In addition to Section 3, the following design requirements shall apply:
A licensee shall install in each treatment room a permanent radiation monitor capable of continuously monitoring beam status.
Spot checks shall be performed on systems subject to Part F during full calibrations and thereafter at intervals not to exceed one (1) month.
NOTE: Spot checks shall include absorbed dose measurements at a minimum of two (2) depths in a phantom at intervals not to exceed one (1) month. Such spot checks shall meet the following requirements:
Each licensee or applicant subject to RH-5500 shall develop, implement, and maintain a quality management program to provide high confidence that radiation will be administered as directed by the authorized user.
If because of the patient's condition, a delay in the order to provide a written revision to an existing written directive would jeopardize the patient's health, an oral revision to an existing written directive will be acceptable, provided that the oral revision is documented as soon as possible in writing in the patient's record and a revised written directive is signed by an authorized user within 48 hours of the oral revision
A licensee shall retain a record of misadministrations reported in accordance with RH-5512. for three (3) years. The record must contain the following:
The Department may, upon application therefore, or upon its own initiative, grant such exemptions or exceptions from the requirements of this Regulation as it determines are authorized by law and will not result in undue hazard to public health and safety or property.
The Department may, by rule, regulation or order, impose upon any licensee such requirements in addition to those established in these Regulations as it deems appropriate or necessary to minimize danger to public health and safety or property.
Department or shall permit the Department to perform, such reasonable tests as the Department deems appropriate or necessary including, but not limited to, tests of:
Impounding.
The Regulations in this Section address the introduction of NORM into products in which neither the NORM nor the radiation emitted from the NORM is considered to be beneficial to the products. The manufacture and distribution of products containing NORM in which the NORM and/or its associated radiation(s) is considered to be a beneficial attribute are licensed under the provisions of Section 2. This Section also addresses waste management and disposal standards.
Suggested State Regulation for Control of Radiation relating to, and an effective program for, the regulatory control of NORM and which has been granted final designation by the Conference of Radiation Control Program Directors, Inc.
Department to a specific facility of a NORM general licensee having more than one site possessing radioactive material exceeding the exemption criteria specified in RH-6005.
NORM RSO approved by the Department as being qualified to oversee radiation protection of workers after attending at least forty (40) hours of classroom training in NORM-related health physics and six (6) months documented on-the-job training with a Department-approved qualified third party Radiation Safety Officer.
Department as being qualified to oversee radiation protection of workers after attending at least forty (40) hours of classroom training in NORM-related health physics and six (6) months documented on-the-the job training with a Department-approved qualified third party Radiation Safety Officer.
hours of classroom training and three (3) months documented on-the-job training in NORM-related surveying techniques and health physics approved by the State as being qualified to perform NORM confirmatory and release surveys at NORM job sites.
handling, interim storage and disposal, of NORM.
The materials contain or are contaminated at concentrations less than 5 picocuries per gram of Radium-226 and/or Radium-228, 0.05% by weight of Uranium or Thorium, or 150 picocuries per gram of any other NORM radionuclide, provided that these concentrations are not exceeded at any time.
A general license is hereby issued to mine, extract, receive,
possess, own, use, process, and dispose of NORM not exempted in RH-6005. without regard to quantity. This general license does not authorize the manufacturing or distribution of products containing NORM in concentrations greater than those specified in RH-6005.a nor the disposal of wastes from other entities. Persons subject to the general license shall notify the Department by filing the Notification of a NORM Facility Form with the Department. The Notification of NORM Facility Form is available from the Department.
NOTE: The Department recommends a general licensee under RH-6010.a.1. conduct or arrange to have conducted a confirmatory survey to determine the extent and magnitude of the NORM contamination at the general licensee's facility.
The transfer of NORM not exempt from these Regulations from one general licensee to another general licensee may be authorized by the Department if:
Environmental Protection Agency for disposal of such wastes;
If the designated facility or receiving licensee is located outside the State of Arkansas, the generating or originating licensee must report the irregularities to the Department.
"I hereby declare that the contents of this consignment are fully and accurately described above by proper shipping name and are classified, packed, marked and labeled, and are in all respects in proper condition for transport according to applicable international and national government regulations."
NORM is accompanied by sufficient copies of a manifest properly prepared, with each copy signed and dated by the licensee and each previous transporter in accordance with these Regulations.
A Worker Protection Plan must be submitted to the Department which includes, but may not be limited to, the following items:
The use of a respirator appropriate for radioactive particulates shall be worn or engineering controls should be utilized to prevent the potential airborne contaminates.
months on-the-job training.
An applicant for a license under RH-6022.b. shall demonstrate that the product is designed and will be manufactured so that:
Part of Body | Column I* Dose in Rem | Column II* Dose in Rem |
Whole body; head and trunk; active blood-forming organs; gonads, or lens of eye | 0.005 | 0.5 |
Hands and forearms; feet and ankles; localized area of skin averaged over areas no larger than 1 square centimeter | 0.075 | 7.5 |
Other organs | 0.015 | 1.5 |
* Dose limit is the dose above background from the product
Each person licensed under RH-6022.c. shall:
If a licensee does not submit an application for license renewal under RH-6028. the licensee shall on or before the expiration date specified in the license:
following the expiration date specified in the license, shall:
Applications for amendment of a license shall be filed in accordance with RH-6021. and shall specify the respects in which the licensee desires the license to be amended and the grounds for such amendment.
In considering an application by a licensee to renew or amend the license, the Department will apply the criteria set for in RH-6022.
Each specific licensee shall, no less than thirty (30) days before vacating or relinquishing possession or control of premises which may have been contaminated with Naturally Occurring Radioactive Material as a result of the activities, notify the Department in writing of intent to vacate. When deemed necessary by the Department, the licensee shall decontaminate the premises in such a manner as the Department may specify.
APPENDIX A, SECTION 7
ACCEPTABLE SURFACE CONTAMINATION LEVELS FOR NORM
NUCLIDEa | AVERAGEbcf | MAXIMUMbdf | REMOVABLEbcef |
U-nat, U-235, & U-238 and associated products. (including Po-210) except Ra-226, Th-230, AC-227, and Pa-231 | 5,000 dpm alpha/100 cm2 | 15,000 dpm alpha/100 cm2 | 1,000 dpm alpha/100 cm2 |
Ra-226, Ra-228, Th-230, Th-228, Pa-231, Ac-227 | 100 dpm/ 100 cm2 | 300 dpm/ 100 cm2 | 20 dpm/ 100 cm2 |
Th-nat, Th-232, Ra-223, Ra-224, U-232 | 1,000 d pm/ 100 cm2 | 3,000 dpm/ 100 cm2 | 200 dpm/ 100 cm2 |
Beta-gamma emitters (nuclides with decay modes other than alpha emission or spontaneous fission, including Pb-2l0), except others noted above. | 5,000 dpm beta,gamma/ 100 cm2 | 15,000 dpm, beta gamma/ 100 cm2 | 1,000 dpm beta,gamma/ 100 cm2 |
a Where surface contamination by both alpha and beta-gamma emitting nuclides exists, the limits established for alpha and beta-gamma emitting nuclides should apply independently.
b As used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, and geometric factors associated with the instrumentation.
c Measurements of average contamination level should not be averaged over more than one square meter. For objects of less surface area, the average should be derived for each object.
d The maximum contamination level applies to an area of not more than 100
cm2.
e The amount of removable radioactive material per 100 cm2 of surface area should be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped.
f The average and maximum radiation levels associated with surface contamination resulting from beta-gamrna emitters should not exceed 0.2 mrad/hr at one (1) cm and 1.0 mrad/hr at one (1) cm, respectively, measured through not more than seven (7) milligrams per square centimeter of total absorber.
Underwater irradiators do not have radiation rooms.
Except as specifically authorized by the Department in writing, no interpretation of the meaning of the Regulations in this Section by any officer or employee of the Department, other than a written interpretation by the Department, will be recognized to be binding upon the Department.
A person, as defined in RH-1100.bc. of these Regulations, shall file an application for a specific license authorizing the use of radioactive material or radiation producing machines in well logging in accordance with RH-403. and RH-404.
The Department will approve an application for a specific license for the use of licensed material in an irradiator if the applicant meets the requirements contained in this Section.
including the frequency of the checks required by RH-7061.
The applicant may not begin construction of a new irradiator prior to the submission to the Department of both an application for a license for the irradiator and the fee required. As used in this Section, the term "construction" includes the construction of any portion of the permanent irradiator structure on the site but does not include: Engineering and design work, purchase of a site, site surveys or soil testing, site preparations, site excavation, construction of warehouse or auxiliary structures, and other similar tasks. Any activities undertaken prior to the issuance of a license are entirely at the risk of the applicant and having no bearing on the issuance of a license with respect to the requirements of the Atomic Energy Act of 1954, as amended, and rules, regulations, and orders issued under the Act.
In either case, the licensee shall have a method to safely store the sources during repairs of the pool.
If the product to be irradiated moves on a product conveyor system, the source rack and the mechanism that moves the rack must be protected by a barrier or guides to prevent products and product carriers from hitting or touching the rack or mechanism.
Irradiators whose construction begins after July 1, 1993, must meet the design requirements of this Section.
If the irradiator will use more than 2 x 1017 becquerels (5 million curies) of activity, the licensee shall evaluate the effects of heating of the shielding walls by the irradiator sources.
These requirements must be met for irradiators whose construction begins after July 1, 1993. The requirements must be met prior to loading sources.
Department approval only if all of the following conditions are met:
If the licensee uses a radiation monitor on a pool water circulating system, the detection of above normal radiation levels must activate an alarm. The alarm set-point must be set as low as practical, but high enough to avoid false alarms. The licensee may reset the alarm set point to a higher level if necessary to operate the pool water purification system to clean up contamination in the pool if specifically provided for in written emergency procedures.
The licensee shall maintain the following records at the irradiator for the periods specified.
Regulations, the licensee shall report the following events if not reported under other parts of the Department Regulations:
Sources of radiation shall be subject to impounding pursuant to Section 5 of these Regulations.
This Section establishes additional requirements and provisions for the specific use of radionuclides in the healing arts. These requirements and provisions provide for the protection of the public healthy and safety. The requirements and provisions of this Section are in addition to, and not in substitution for, others in these regulations. The requirements and provisions of these regulations apply to applicants and licensees subject to this Section unless specifically exempted.
Each record required by Section 9 must be legible throughout the retention period specified by each Department regulation. The record may be the original, a reproduced copy, or a microform provided that the copy or microform is authenticated by authorized personnel and the microform is capable of producing a clear copy throughout the required retention period. The record may also be stored in electronic media with the capability of reproducing legible, accurate, and complete records during the required retention period. Records such as letters, drawings, and specifications must include all pertinent information such as stamps, initials, and signatures. The licensee shall maintain adequate safeguards against tampering with and loss of records.
Nothing in this Section relieves the licensee from complying with applicable U.S. Food and Drug Administration, other Federal, and State requirements governing radioactive drugs or devices.
A licensee may conduct research involving human subjects using radioactive material provided:
A licensee shall apply for and must receive a license amendment:
A licensee possessing a Type A specific license of broad scope for medical use is exempt from:
The Department may, upon application of any interested person or upon its own initiative, grant such exemptions form the regulations in Section 9 as it determines are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest.
embedded, activated, or sealed sources are utilized to deliver a radiation dose at a distance of up to a few centimeters, by surface, intracavitary, intraluminal or interstitial application.
If, because of the emergent nature of the patient's condition, a delay in order to provide a written directive would jeopardize the patient's health, an oral directive will be acceptable, provided that the information contained in the oral directive is documented as soon as possible in writing in the patient's record and a written directive is prepared within 48 hours of the oral directive.
If, because of the patient's condition, a delay in order to provide a written revision to an existing written directive would jeopardize the patient's health, an oral revision to an existing written directive will be acceptable, provided that the oral revision is documented as soon as possible in the patient's record and a revised written directive is signed by the authorized user within 48 hours of the oral revision.
For medical use, a licensee may only use:
Except as provided in RH-8318., the licensee shall require an individual fulfilling the responsibilities of the Radiation Safety Officer (RSO) as provided in RH-8300. to be an individual who:
The licensee shall require the authorized medical physicist to be an individual who:
The licensee shall require the authorized nuclear pharmacist to be a pharmacist who:
The training and experience specified in Section 9 must have been obtained within the seven (7) years preceding the date of application or the individual must have had related continuing education and experience since the required training and experience was completed.
Each licensee shall establish written quality control procedures for all diagnostic equipment used for radionuclide studies. As a minimum, quality control procedures and frequencies shall be those recommended by equipment manufacturers or procedures, which have been approved by the Department. The licensee shall conduct quality control procedures in accordance with written procedures.
Specific Requirements For The Use of Sources For Brachytherapy
Any person authorized by RH-8005. for medical use of radioactive material may receive, possess, and use the following radioactive material for check, calibration and reference use:
Each syringe and vial that contains a radioactive drug shall be labeled to identify the radioactive drug. Each syringe shield and vial shield shall also be labeled unless the label on the syringe or vial is visible when shielded.
A licensee shall require each individual preparing or handling a vial that contains a radioactive drug to keep the vial in a vial radiation shield.
Specific Requirements for the Use of Radioactive Material for Uptake, Dilution, or Excretion Studies
A licensee may use any unsealed radioactive material, in quantities that do not require a written directive, for a diagnostic use involving measurements of uptake, dilution, or excretion that is:
A licensee authorized to use radioactive material for uptake, dilution, and excretion studies shall possess a portable radiation detection survey instrument capable of detecting dose rates over the range of one (1) microsievert (0.1 mrem) per hour to 500 microsieverts (50 mrems) per hour. The instrument shall be operable and calibrated in accordance with RH-8402.
Except as provided in RH-8318., the licensee shall require an authorized user of unsealed radioactive material for the uses authorized under RH-8500. to be a physician who:
Specific Requirements or the Use of Unsealed Radioactive Material-Written Directive Not Required
A licensee may use, for imaging and localization studies, any radioactive material prepared for medical use, in quantities that do not require a written directive as described in RH-8307. that is:
A licensee authorized to use radioactive material for imaging and localization studies shall possess a portable radiation detection survey instrument capable of detecting dose rates over the range of one (1) microsievert (0.1 mrem) per hour to 500 microsieverts (50 mrems) per hour, and a portable radiation measurement survey instrument capable of measuring dose rates over the range of ten (10) microsieverts (1 mrem) per hour to ten (10) millisieverts (1000 mrems) per hour. The instruments shall be operable and calibrated in accordance with RH-8402.
Except as provided in RH-8318., the licensee shall require an authorized user of unsealed radioactive material for the uses authorized under RH-8530. to be a physician who:
Specific Requirements for the Use of Unsealed Radioactive Material-Written Directive Required
A licensee may use any unsealed radioactive material for diagnostic or therapeutic medical use for which a written directive is required that has been:
In addition to the requirements of RH-2803. of these regulations:
A licensee authorized to use radioactive material for which a written directive is required shall possess a portable radiation detection survey instrument capable of detecting dose rates over the range of one (1) microsievert (0.1 mrem) per hour to 500 microsieverts (50 mrems) per hour, and a portable radiation measurement survey instrument capable of measuring dose rates over the range of ten (10) microsieverts (1 mrem) per hour to ten (10) millisieverts (1000 mrems) per hour. The instruments shall be operable and calibrated in accordance with RH-8402.
Except as provided by RH-8318, the licensee shall require an authorized user of radioactive material for the uses authorized under RH-8550. to be a physician who:
Except as provided in RH-8318., the licensee shall require an authorized user for the oral administration of sodium iodide I-131 in quantities less than or equal to 1.22 gigabecquerels (33 millicuries), for which a written directive is required, to be a physician who:
Except as provided in RH-8318., the licensee shall require an authorized user for the oral administration of sodium iodide I-131 in quantities greater than 1.22 gigabecquerels (33 millicuries), to be a physician who:
Manual Brachytherapy
A licensee shall use only brachytherapy sources for therapeutic medical uses:
In addition to the requirements of RH-2303. of these regulations:
The licensee shall perform acceptance testing on the treatment planning system in accordance with published protocols accepted by nationally recognized bodies. At a minimum, the acceptance testing must include, as applicable, verification of:
A licensee authorized to use manual brachytherapy sources shall possess a portable radiation detection survey instrument capable of detecting dose rates over the range of one (1) microsievert (0.1 mrem) per hour to 500 microsieverts (50 mrems) per hour, and a portable radiation measurement survey instrument capable of measuring dose rates over the range of ten (10) microsieverts (1 mrem) per hour to ten (10) millisieverts (1000 mrems) per hour. The instruments shall be operable and calibrated in accordance with RH-8402.
Except as provided in RH-8318., the licensee shall require an authorized user of a manual brachytherapy source for the uses authorized under RH-8600. to be a physician who:
Except as provided in RH-8318, the licensee shall require an authorized user of a strontium-90 source for ophthalmic uses authorized under RH-8600. to be a physician who:
Sealed Sources For Diagnosis
A licensee shall use only sealed sources for diagnostic medical uses:
Except as provided in RH-8318., the licensee shall require the authorized user of a diagnostic sealed source for use in a device authorized under RH-8620. to be a physician, dentist, or podiatrist who:
Photon Emitting Remote Afterloader Units, Teletherapy Units, And Gamma Stereotactic
Radiosurgery Units
A licensee shall use sealed sources in photon emitting remote afterloader units, teletherapy units, or gamma stereotactic radiosurgery units for therapeutic medical uses:
years; 18 to 30 months after that calibration, the system must have been intercompared with another dosimetry system that was calibrated within the past 24 months by NIST or by a calibration laboratory accredited by the AAPM. The results of the inter-comparison must have indicated that the calibration factor of the licensee's system had not changed by more than two (2%) percent. The licensee may not use the intercomparison result to change the calibration factor. When intercomparing dosimetry systems to be used for calibrating sealed sources for therapeutic units. The licensee shall use a comparable unit with beam attenuators or collimators, as applicable, and sources of the same radionuclide as the source used at the licensee's facility.
The licensee shall perform acceptance testing on the treatment planning system in accordance with published protocols accepted by nationally recognized bodies. At a minimum, the acceptance testing must include, as applicable, verification of:
A licensee authorized to use radioactive material in remote afterloader units, teletherapy units, and gamma stereotactic radiosurgery units shall possess a portable radiation detection survey instrument capable of detecting dose rates over the range of one (1) microsievert (0.1 mrem) per hour to 500 microsieverts (50 mrems) per hour, and a portable radiation measurement survey instrument capable of measuring dose rates over the range of ten (10) microsieverts (1 mrem) per hour to ten (10) millisieverts (1000 mrems) per hour. The instruments shall be operable and calibrated in accordance with RH-8402.
Except as provided in RH-8318., the licensee shall require an authorized user of a sealed source for a use authorized under RH-8630. to be a physician who:
The licensee shall require an authorized user of a sealed source for a use authorized under RH-8630. to be a physician who has met the training and experience requirements outlined in 10 CFR Part 35 Subpart J 35.960.
Other Medical Uses of Radioactive Material or Radiation from Radioactive Material
A licensee may use radioactive material or a radiation source approved for medical use that is not specifically addressed in Section 9 if:
Records
A licensee shall retain a record of each radiation protection program change made in accordance with RH-8301.a. for five (5) years. The record must include a copy of the old and new procedures; the effective date of the change; and the signature of the licensee management that reviewed and approved the change.
A licensee shall retain a copy of each written directive as required by RH-8307. for three (3) years.
A licensee shall retain a record of misadministrations reported in accordance with RH-8800. for three (3) years. The record must contain the licensee's name; names of the individuals involved; the social security number or other identification number if one has been assigned, of the individual who is the subject of the misadministration; a brief description of the event; why it occurred; the effect, if any, on the individual; the actions, if any, taken, or planned, to prevent recurrence; and, whether the licensee notified the individual (or the individual's responsible relative or guardian) and, if not, whether such failure to notify was based on guidance from the referring physician.
A licensee shall retain a record of a dose to an embryo/fetus or a nursing child reported in accordance with RH-8801 for three (3) years. The record must contain the licensee's name; names of all the individuals involved; social security number or other identification number if one has been assigned to the pregnant individual or nursing child who is the subject of the event; a brief description of the event; why it occurred; the effect, if any, on the embryo/fetus or nursing child; the actions, if any, taken, or planned, to prevent recurrence; and whether the licensee notified the pregnant individual or mother (or the mother's or child's responsible relative or guardian) and, if not, whether such failure to notify was based on guidance from the referring physician.
A licensee shall maintain a record of instrument calibrations required by RH-8401. for three (3) years. The records must include the model and serial number of the instrument, the date of the calibration, the results of the calibration, and the name of the individual who performed the calibration.
A licensee shall maintain a record of survey instrument calibrations required by RH-8402. for three (3) years. The record must include the model and serial number of the instrument, the date of the calibration, the results of the calibration, and the name of the individual who performed the calibration.
A licensee shall maintain a record of dosage determinations required by RH-8403. for three (3) years. The record must contain the radioactive drug; the patient's or human research subject's name, or identification number if one has been assigned; prescribed dosage; the determined dosage, or a notation that the total activity is less than 1.1 megabecquerel (30 |J,Ci); the date and time of the dosage determination; and the name of the individual who determined the dosage.
A licensee shall retain a record of the quarterly physical inventory of sealed sources and brachytherapy sources required by RH-8405.e. for three (3) years. The inventory record must contain the model number of each source, and serial number if one has been assigned, the identity of each source radionuclide and its nominal activity, the location of each source, and the name of the individual who performed the inventory.
A licensee shall retain a record of each survey required by RH-8408. for three (3) years. The record must include the date of the survey, the results of the survey, the instrument used to make the survey, and the name of the individual who performed the survey.
A licensee shall maintain records of the disposal of licensed materials, as required by RH-8410., for three (3) years. The record must include the date of the disposal, the survey instrument used, the background radiation level, the radiation level measured at the surface of each waste container, and the name of the individual who performed the survey.
A licensee shall maintain a record of the radionuclide contaminant concentration tests required by RH-8531. for three (3) years. The record must include, for each measured elution of radionuclide used to prepare a radioactive drug, the ratio of the measures expressed as kilobecquerel of contaminant per megabecquerel of desired radionuclide (microcuries/millicuries), or microgram of contaminant per megabecquerel of desired radionuclide (microgram/millicuries), the time and date of the measurement, and the name of the individual who made the measurement.
A licensee shall maintain a record of safety instructions and training required by RH-8551., RH-8603., and RH-8633. for three (3) years. The record must include a list of the topics covered, the date of the instruction or training, the name(s) of the attendee(s), and the name(s) of the individual(s) who provided the instruction.
A licensee shall maintain a record of the surveys required by RH-8601. and RH-8631. for three (3) years. Each record must include the date and results of the survey, the survey instrument used, and the name of the individual who made the survey.
A licensee shall maintain a record of the calibrations on brachytherapy sources required by RH-8605. for three (3) years after the last use of the source. The record must include the date of the calibration; the manufacturer's name, model number, and serial number for the source and the instruments used to calibrate the source; the source output or activity; source positioning accuracy within applicators; and the signature of the authorized medical physicist.
A licensee shall maintain a record of the of the activity of a strontium-90 source required by RH-8605. for the life of the source. The record must include the date and initial activity of the source as determined under RH-8605., and for each decay calculation, the date, the source activity and the signature of the authorized medical physicist.
A licensee shall retain a record of the installation, maintenance, adjustment, and repair of remote afterloader units, teletherapy units, and gamma stereotactic radiosurgery units as required by RH-8632. for three (3) years. For each installation, maintenance, adjustment, and repair, the record must include the date description of the service, and name(s) of the individual(s) who performed the work.
Reports
To meet the requirements of this paragraph, the notification of the individual who is the subject of the misadministration may be made instead to that individual's responsible relative or guardian. If a verbal notification is made, the licensee shall inform the individual, or appropriate responsible relative or guardian, that a written description of the event can be obtained for the licensee upon request. The licensee shall provide such a written description if requested.
To meet the requirements of this paragraph, the notification may be made to the mother's or child's responsible relative or guardian instead of the mother, when appropriate. If a verbal notification is made, the licensee shall inform the mother, or the mother's or child's responsible relative or guardian, that a written description of the event can be obtained from the licensee upon request. The licensee shall provide such a written description if requested.
A licensee shall file a report with the Department within five (5) days if a leakage test required by RH-8405. reveals the presence of 185 Becquerel (0.005 |j,Ci) or more of removable contamination. The written report must include the model number and serial number if assigned, of the leaking source; the radionuclide and its estimated activity; the results of the test; the date of the test; and the action taken.
SEVERABILITY
If any provision of these Rules and Regulations, or the application thereof to any person or circumstance, is held invalid, such invalidity shall not affect other provisions or applications of these Rules and Regulations which can give effect without the invalid provisions or applications. To this end, the provisions hereto are declared to be severable.
REPEAL
All Regulations and parts of Regulations in conflict herewith are hereby repealed.
007.14.12 Ark. Code R. 001