reglab/statecodes huggingface dataset:
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part C - LICENSING OF RADIOACTIVE MATERIAL › SPECIFIC LICENSES › Section 144-220-C-22 - Modification, revocation and termination of specific license

Current through 2024-29, July 17, 2024
A. The terms and conditions of all licenses
					 shall be subject to amendment, revision, or modification or the license may be
					 suspended or revoked by reason of amendments to the Act, or by reason of rules,
					 regulations and orders issued by the Agency.
B. Any license may be revoked, suspended or
					 modified, in whole or in part, for any material false statement in the
					 application or any statement of fact required under provisions of the Act, or
					 because of conditions revealed by such application or statement of fact or any
					 report, record, or inspection or other means which would warrant the Agency to
					 refuse to grant a license on an original application, or for violation of, or
					 failure to observe any of the terms and conditions of the Act, or of the
					 license, or of any rule, regulation, or order of the Agency.
C. Except in cases of willfulness or those in
					 which the public health, interest or safety requires otherwise, no license
					 shall be modified, suspended, or revoked unless, prior to the institution of
					 proceedings therefore, facts of conduct which may warrant such action shall
					 have been called to the attention of the licensee in writing and the licensee
					 shall have been accorded an opportunity to demonstrate or achieve compliance
					 with all lawful requirements.
D.
					 The Agency may terminate a specific license upon request submitted by the
					 licensee to the Agency in writing.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part C - LICENSING OF RADIOACTIVE MATERIAL › SPECIFIC LICENSES › Section 144-220-C-23 - Deliberate misconduct

Current through 2024-29, July 17, 2024
A. Any licensee,
					 certificate of registration holder, applicant for a license or certificate of
					 registration, employee of a licensee, certificate of registration holder or
					 applicant; or any contractor (including a supplier or consultant),
					 subcontractor, employee of a contractor or subcontractor of any licensee or
					 certificate of registration holder or applicant for a license or certificate of
					 registration, who knowingly provides to any licensee, applicant, certificate
					 holder, contractor, or subcontractor, any components, equipment, materials, or
					 other goods or services that relate to a licensee's, certificate holder's or
					 applicant's activities in this Part, may not:
(1) Engage in deliberate misconduct that
					 causes or would have caused, if not detected, a licensee, certificate of
					 registration holder, or applicant to be in violation of any rule, regulation,
					 or order; or any term, condition, or limitation of any license issued by the
					 Agency; or
(2) Deliberately submit
					 to the Agency, a licensee, certificate of registration holder, an applicant, or
					 a licensee's, certificate holder's or applicant's, contractor or subcontractor,
					 information that the person submitting the information knows to be incomplete
					 or inaccurate in some respect material to the Agency.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part C - LICENSING OF RADIOACTIVE MATERIAL › RECIPROCITY › Section 144-220-C-25 - Records

Current through 2024-29, July 17, 2024
A. Each person who receives radioactive
					 material pursuant to a license issued pursuant to this Part and Parts E, G, I,
					 M, N and Q of this rule shall keep records showing the receipt, transfer, and
					 disposal of the byproduct material as follows:
(1) The licensee shall retain each record of
					 receipt of radioactive material as long as the material is possessed and for
					 three years following transfer or disposal of the material.
(2) The licensee who transferred the material
					 shall retain each record of transfer of source or byproduct material until the
					 Agency terminates each license that authorizes the activity that is subject to
					 the recordkeeping requirement.
(3)
					 The licensee who disposed of the material shall retain each record of disposal
					 of radioactive material until the Agency terminates each license that
					 authorizes disposal of the material.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part C - LICENSING OF RADIOACTIVE MATERIAL › Schedule D - QUANTITIES OF RADIOACTIVE MATERIALS REQUIRING CONSIDERATION OF THE NEED FOR AN EMERGENCY PLAN FOR RESPONDING TO A RELEASE

Current through 2024-29, July 17, 2024
Radioactive
								Material
Release Fraction
Quantity
								(curies)
Radioactive
								Material
Release Fraction
Quantity
								(curies)
Actinium-228
0.001
4,000
Krypton-85
1
6,000,000
Americium-241
0.001
2
Lead-210
0.01
8
Americium-242
0.001
2
Manganese-56
0.01
60,000
Americium-243
0.001
2
Mercury-203
0.01
10,000
Antimony-124
0.01
4,000
Molybdenum-99
0.01
30,000
Antimony-126
0.01
6,000
Neptunium-237
0.001
2
Barium-133
0.01
10,000
Nickel-63
0.01
20,000
Barium-140
0.01
30,000
Niobium-94
0.01
300
Bismuth-207
0.01
5,000
Phosphorus-32
0.5
100
Bismuth-210
0.01
600
Phosphorus-33
0.5
1,000
Cadmium-109
0.01
1,000
Polonium-210
0.01
10
Cadmium-113
0.01
80
Potassium-42
0.01
9,000
Calcium-45
0.01
20,000
Promethium-145
0.01
4,000
Californium-252
0.001
9 (20 mg)
Promethium-147
0.01
4,000
Carbon-14 (NonCO2)
0.01
50,000
Radium-226
0.001
100
Cerium-141
0.01
10,000
Ruthenium-106
0.01
200
Cerium-144
0.01
300
Samarium-151
0.01
4,000
Cesium-134
0.01
2,000
Scandium-46
0.01
3,000
Cesium-137
0.01
3,000
Selenium-75
0.01
10,000
Chlorine-36
0.5
100
Silver-110m
0.01
1,000
Chromium-51
0.01
300,000
Sodium-22
0.01
9,000
Cobalt-60
0.001
5,000
Sodium-24
0.01
10,000
Copper-64
0.01
200,000
Strontium-89
0.01
3,000
Curium-242
0.001
60
Strontium-90
0.01
90
Curium-243
0.001
3
Sulphur-35
0.5
900
Curium-244
0.001
4
Technetium-99
0.01
10,000
Curium-245
0.001
2
Technetium-99m
0.01
400,000
Europium-152
0.01
500
Tellurium-127m
0.01
5,000
Europium-154
0.01
400
Tellurium-129m
0.01
5,000
Europium-155
0.01
3,000
Terbium-160
0.01
4,000
Gadolinium-153
0.01
5,000
Thulium-170
0.01
4,000
Germanium-68
0.01
2,000
Tin-113
0.01
10,000
Gold-198
0.01
30,000
Tin-123
0.01
3,000
Hafnium-172
0.01
400
Tin-126
0.01
1,000
Hafnium-181
0.01
7,000
Titanium-44
0.01
100
Holmium-166m
0.01
100
Vanadium-48
0.01
7,000
Hydrogen-3
0.5
20,000
Xenon-133
1
900,000
Indium-114m
0.01
1,000
Yttrium-91
0.01
2,000
Iodine-125
0.5
10
Zinc-65
0.01
5,000
Iodine-131
0.5
10
Zirconium-93
0.01
400
Iridium-192
0.001
40,000
Zirconium-95
0.01
5,000
Iron-55
0.01
40,000
Iron-59
0.01
7,000
Any other beta-gamma emitter
0.01
10,000
Irradiated material, solid noncombustible
0.001
10,000
Mixed fission products
0.01
1,000
Mixed radioactive waste, beta-gamma
0.01
1,000
Mixed corrosion products
0.01
10,000
Packaged mixed waste, beta-gamma
0.001
10,000
Contaminated equipment beta-gamma
0.001
10,000
Any other alpha emitter
0.001
2
Contaminated equipment alpha
0.0001
20
Irradiated material, any form other than solid
								noncombustible
0.01
1,000
Packaged waste, alpha
0.0001
20
Combinations of radioactive materials listed
								above
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part C - LICENSING OF RADIOACTIVE MATERIAL › Appendix 144-220-C-B - NATURALLY OCCURRING OR ACCELERATOR PRODUCED RADIOACTIVE MATERIAL (NARM)

Current through 2024-29, July 17, 2024
Examples of naturally occurring radioactive materials.
					 (Naturally occurring radioactive material is any material of natural origin
					 that emits radiation spontaneously, excluding uranium, thorium, and the
					 tailings produced in their extraction)
Hydrogen-3
Indium-115
Lead-210
Beryllium-7
Lanthanum-138
Lead-212
Beryllium-10
Cerium-142
Bismuth-210
Carbon-14
Neodymium-144
Bismuth-212
Sodium-22
Samarium-147
Polonium-210
Silicon-32
Samarium-148
Radon-220
Phosphorus-32
Samarium-149
Radon-222
Phosphorus-33
Gadolinium-152
Radium-224
Sulfur-35
Hafnium-174
Radium-226
Chlorine-36
Lutetium-176
Radium-228
Chlorine-39
Rhenium-187
Actinium-227
Potassium-40
Platinum-190
Actinium-228
Vanadium-50
Platinum-192
Protoactinium-231
Rubidium-87
Lead-204
Examples of accelerator-produced radioactive materials.
					 (Accelerator- produced radioactive material is any material made radioactive
					 (emits radiation spontaneously) by a particle accelerator)
Carbon-11
Zinc-62
Iodine-124
Nitrogen-13
Gallium-66
Iodine-125*
Oxygen-15
Gallium--67
Iodine-126
Fluorine-18
Germanium-68
Xenon-127
Sodium-22
Arsenic -73
Cesium-131
Magnesium-28
Selenium-73
Promethium-145
Aluminum-28
Bromine-77
Dysprosium-157
Phosphorus-33
Krypton-77
Osmium-190
Argon-37
Krypton-81
Iridium-190
Potassium-43
Rubidium-81
Iridium-190ml
Scandium-49
Rubidium-82
Platinum-193m
Manganese-52
Rubidium-84
Gold -195
Iron-52
Strontium-82
Mercury-197
Cobalt-57
Strontium-87m
Thallium-199
Cobalt-58
Yttrium-87
Thallium-201
Copper-62
Technetium-97m
Lead-203
Copper-67
Indium-111
Bismuth-204
Zinc-62
Iodine-123
* Excludes Iodine-125 as radioactive material, which
					 requires licensing by either the U.S. Nuclear Regulatory Commission or an
					 Agreement State.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart A - GENERAL PROVISIONS › Section 144-220-D-A-1001 - Purpose

Current through 2024-29, July 17, 2024
A. Part D establishes standards for
					 protection against ionizing radiation resulting from activities conducted
					 pursuant to licenses or registrations issued by the Agency. This rule is issued
					 pursuant to 22 M.R.S., Ch. 160, the Radiation Protection Act.
B. The requirements of Part D are designed to
					 control the receipt, possession, use, transfer, and disposal of sources of
					 radiation by any licensee or registrant so the total dose to an individual,
					 including doses resulting from all sources of radiation other than background
					 radiation, does not exceed the standards for protection against radiation
					 prescribed in Part D. However, nothing in Part D shall be construed as limiting
					 actions that may be necessary to protect health and safety.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart A - GENERAL PROVISIONS › Section 144-220-D-A-1002 - Scope

Current through 2024-29, July 17, 2024
Except as specifically provided in other Parts of this
						rule, Part D applies to persons licensed or registered by the Agency to
						receive, possess, use, transfer, or dispose of sources of radiation. The limits
						in Part D do not apply to doses due to background radiation, to exposure of
						patients to radiation for the purpose of medical diagnosis or therapy, to
						exposure from individuals administered radioactive material and released in
						accordance with Part G, or to voluntary participation in medical research
						programs.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart A - GENERAL PROVISIONS › Section 144-220-D-A-1003 - Definitions. (See Part A)

Current through 2024-29, July 17, 2024
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart A - GENERAL PROVISIONS › Section 144-220-D-A-1004 - Units of radiation dose (See Part A)

Current through 2024-29, July 17, 2024
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart A - GENERAL PROVISIONS › Section 144-220-D-A-1005 - Units of radioactivity (See Part A)

Current through 2024-29, July 17, 2024
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart A - GENERAL PROVISIONS › Section 144-220-D-A-1008 - Implementation

Current through 2024-29, July 17, 2024
A. (Reserved)
B. (Reserved)
C. Any existing license or registration
					 condition that is more restrictive than Part D remains in force until there is
					 an amendment or renewal of the license or registration.
D. If a license or registration condition
					 exempts a licensee or registrant from a provision of Part D in effect on or
					 before January 1, 1994, it also exempts the licensee or registrant from the
					 corresponding provision of Part D.
E. If a license or registration condition
					 cites provisions of Part D in effect prior to January 1, 1994, which do not
					 correspond to any provisions of Part D, the license or registration condition
					 remains in force until there is an amendment or renewal of the license or
					 registration that modifies or removes this condition.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart B - RADIATION PROTECTION PROGRAMS › Section 144-220-D-B-1101 - Radiation protection programs

Current through 2024-29, July 17, 2024
A. Each
					 licensee or registrant shall develop, document, and implement a radiation
					 protection program sufficient to ensure compliance with the provisions of Part
					 D. See D.2102 for record keeping requirements relating to these
					 programs.
B. The licensee or
					 registrant shall use, to the extent practical, procedures and engineering
					 controls based upon sound radiation protection principles to achieve
					 occupational doses and public doses that are as low as is reasonably achievable
					 (ALARA).
C. The licensee or
					 registrant shall periodically (at least annually), review the radiation
					 protection program content and implementation.
D. To implement the ALARA requirements of
					 D.1101.B and notwithstanding the requirements in D.1301, a constraint on air
					 emissions of radioactive material to the environment, excluding Radon-222 and
					 its daughters, shall be established by licensees other than those subject to 10
					 CFR Part 50.34a of the USNRC regulations, such that the individual member of
					 the public likely to receive the highest dose will not be expected to receive a
					 total effective dose equivalent in excess of 0.1mSv (10 mrem) per year from
					 these emissions. If a licensee subject to this requirement exceeds this dose
					 constraint, the licensee shall report the exceedance as provided in D.2203 and
					 promptly take appropriate corrective action to ensure against
					 recurrence.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart C - OCCUPATIONAL DOSE LIMITS › Section 144-220-D-C-1201 - Occupational dose limits for adults

Current through 2024-29, July 17, 2024
A. The
					 licensee or registrant shall control the occupational dose to individual
					 adults, except for planned special exposures pursuant to D.1206, to the
					 following dose limits:
(1) An annual limit,
					 which is the more limiting of:
(a) The total
					 effective dose equivalent (TEDE) being equal to 0.05 Sv (5 rem); or
(b) The sum of the deep-dose equivalent and
					 the committed dose equivalent to any individual organ or tissue other than the
					 lens of the eye being equal to 0.5 Sv (50 rem).
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart C - OCCUPATIONAL DOSE LIMITS › Section 144-220-D-C-1202 - Compliance with requirements for summation of external and internal doses

Current through 2024-29, July 17, 2024
A. If the licensee or registrant is required
					 to monitor pursuant to both D.1502.A and B, the licensee or registrant shall
					 demonstrate compliance with the dose limits by summing external and internal
					 doses. If the licensee or registrant is required to monitor only pursuant to
					 D.1502.A or only pursuant to D.1502.B, then summation is not required to
					 demonstrate compliance with the dose limits. The licensee or registrant may
					 demonstrate compliance with the requirements for summation of external and
					 internal doses by meeting one of the conditions specified in paragraph B of
					 this Section and the conditions in paragraphs C and D of this Section. 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.
B. Intake by inhalation. If the only intake
					 of radionuclides is by inhalation, the total effective dose equivalent (TEDE)
					 limit is not exceeded if the sum of the deep-dose equivalent divided by the
					 total effective dose equivalent limit, and one of the following, does not
					 exceed unity:
(1) The sum of the fractions of
					 the inhalation ALI for each radionuclide, or
(2) The total number of derived air
					 concentration-hours (DAC-hours) for all radionuclides divided by 2,000,
					 or
(3) The sum of the calculated
					 committed effective dose equivalents to all significantly irradiated organs or
					 tissues (T) calculated from bioassay data using appropriate biological models
					 and expressed as a fraction of the annual limit. For purposes of this
					 requirement, an organ or tissue is deemed to be significantly irradiated if,
					 for that organ or tissue, the product of the weighting factors,
					 WT, and the committed dose equivalent,
					 HT,50, per unit intake is greater than 10 percent of the
					 maximum weighted value of HT,50 that is,
					 WTHT,50, unit intake for any
					 organ or tissue.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart C - OCCUPATIONAL DOSE LIMITS › Section 144-220-D-C-1203 - Determination of external dose from airborne radioactive material

Current through 2024-29, July 17, 2024
A. Licensees or registrants shall, when
					 determining the dose from airborne radioactive material, include the
					 contribution to the deep-dose-equivalent, lens-dose equivalent, and
					 shallow-dose equivalent from external exposure to the radioactive cloud. See
					 Appendix B, footnotes 1 and 2.
B.
					 Airborne radioactivity measurements and DAC values shall not be used as the
					 primary means to assess the deep-dose equivalent when the airborne radioactive
					 material includes radionuclides other than noble gases or if the cloud of
					 airborne radioactive material is not relatively uniform. The determination of
					 the deep-dose equivalent to an individual shall be based upon measurements
					 using instruments or individual monitoring devices.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart C - OCCUPATIONAL DOSE LIMITS › Section 144-220-D-C-1204 - Determination of internal exposure

Current through 2024-29, July 17, 2024
A. For purposes
					 of assessing dose used to determine compliance with occupational dose
					 equivalent limits, the licensee or registrant shall, when required pursuant to
					 D.1502, take suitable and timely measurements of:
(1) Concentrations of radioactive materials
					 in air in work areas; or
(2)
					 Quantities of radionuclides in the body; or
(3) Quantities of radionuclides excreted from
					 the body; or
(4) Combinations of
					 these measurements.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart C - OCCUPATIONAL DOSE LIMITS › Section 144-220-D-C-1206 - Planned special exposures

Current through 2024-29, July 17, 2024
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 D.1201 provided that each of the
						following conditions is satisfied:
A.
					 The licensee or registrant authorizes a planned special exposure only in an
					 exceptional situation when alternatives that might avoid the dose estimated to
					 result from the planned special exposure are unavailable or
					 impractical.
B. The licensee or
					 registrant, and employer if the employer is not the licensee or registrant,
					 specifically authorizes the planned special exposure, in writing, before the
					 exposure occurs.
C. Before a
					 planned special exposure, the licensee or registrant ensures that each
					 individual involved is:
(1) Informed of the
					 purpose of the planned operation; and
(2) Informed of the estimated doses and
					 associated potential risks and specific radiation levels or other conditions
					 that might be involved in performing the task; and
(3) Instructed in the measures to be taken to
					 keep the dose ALARA considering other risks that may be present.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart C - OCCUPATIONAL DOSE LIMITS › Section 144-220-D-C-1207 - Occupational dose limits for minors

Current through 2024-29, July 17, 2024
The annual occupational dose limits for minors are 10
						percent of the annual occupational dose limits specified for adult workers in
						D.1201.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart C - OCCUPATIONAL DOSE LIMITS › Section 144-220-D-C-1208 - Dose equivalent to an embryo/fetus

Current through 2024-29, July 17, 2024
A. The
					 licensee or registrant shall ensure that the dose equivalent to an embryo/fetus
					 during the entire pregnancy, due to occupational exposure of a declared
					 pregnant woman, does not exceed 5 mSv (0.5 rem). See D.2106 for record keeping
					 requirements.
B. The licensee or
					 registrant shall make efforts to avoid substantial
					 variation1 above a uniform monthly exposure rate to
					 a declared pregnant woman so as to satisfy the limit in D.1208.A.
C. The dose equivalent to an embryo/fetus
					 shall be taken as the sum of:
(1) The
					 deep-dose equivalent to the declared pregnant woman; and
(2) The dose equivalent to the embryo/fetus
					 from radionuclides in the embryo/fetus and radionuclides in the declared
					 pregnant woman.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart D - RADIATION DOSE LIMITS FOR INDIVIDUAL MEMBERS OF THE PUBLIC › Section 144-220-D-D-1301 - Dose limits for individual members of the public

Current through 2024-29, July 17, 2024
A. Each licensee or registrant shall conduct
					 operations so that:
(1) The Total effective
					 dose equivalent to individual members of the public from the licensed or
					 registered operation does not exceed 1 mSv (0.1 rem) in a year, exclusive of
					 the dose contribution from background radiation, from any medical
					 administration the individual has received, from exposure to individuals
					 administered radioactive material and released in accordance with Part G, from
					 voluntary participation in medical research programs, and from the licensee's
					 or registrant's disposal of radioactive material into sanitary sewerage in
					 accordance with D.20032, and
(2) The dose in any unrestricted area from
					 external sources, exclusive of the dose contributions from patients
					 administered radioactive material and released in accordance with Part G, does
					 not exceed 0.02 mSv (0.002 rem) in any one hour.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart D - RADIATION DOSE LIMITS FOR INDIVIDUAL MEMBERS OF THE PUBLIC › Section 144-220-D-D-1302 - Compliance with dose Limits for individual members of the public

Current through 2024-29, July 17, 2024
A. The licensee or registrant shall make or
					 cause to be made surveys of radiation levels in unrestricted and controlled
					 areas and radioactive materials in effluents released to unrestricted and
					 controlled areas to demonstrate compliance with the dose limits for individual
					 members of the public in D.1301.
B.
					 A licensee or registrant shall show compliance with the annual dose limit in
					 D.1301 by: D.1302. B(1)
(1) Demonstrating by
					 measurement or calculation that the total effective dose equivalent to the
					 individual likely to receive the highest dose from the licensed or registered
					 operation does not exceed the annual dose limit; or
(2) Demonstrating that:
(a) The annual average concentrations of
					 radioactive material released in gaseous and liquid effluents at the boundary
					 of the unrestricted area do not exceed the values specified in Table II of
					 Appendix B; and
(b) If an
					 individual were continually present in an unrestricted area, the dose from
					 external sources would not exceed 0.02 mSv (0.002 rem) in an hour and 0.5 mSv
					 (0.05 rem) in a year.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart D - RADIATION DOSE LIMITS FOR INDIVIDUAL MEMBERS OF THE PUBLIC › Section 144-220-D-D-1310 - Testing for leakage or contamination of sealed sources

Current through 2024-29, July 17, 2024
A. The licensee or registrant in possession
					 of any sealed source shall assure that:
(1)
					 Each sealed source, except as specified in D.1310.B, is tested for leakage or
					 contamination and the test results are received before the sealed source is put
					 into use unless the licensee or registrant has a certificate from the
					 transferor indicating that the sealed source was tested within six months
					 before transfer to the licensee or registrant.
(2) Each sealed source that is not designed
					 to emit alpha particles is tested for leakage or contamination at intervals not
					 to exceed six months or at alternative intervals approved by the Agency, after
					 evaluation of information specified by C.11.K(4) and (5) of this rule, an
					 Agreement State or the Nuclear Regulatory Commission.
(3) Each sealed source that is designed to
					 emit alpha particles is tested for leakage or contamination at intervals not to
					 exceed three months or at alternative intervals approved by the Agency, after
					 evaluation of information specified by C.11.K(4) and (5) of this rule, an
					 Agreement State or the Nuclear Regulatory Commission.
(4) For each sealed source that is required
					 to be tested for leakage or contamination, at any other time there is reason to
					 suspect that the sealed source might have been damaged or might be leaking, the
					 licensee or registrant shall assure that the sealed source is tested for
					 leakage or contamination before further use.
(5) Tests for leakage for all sealed sources,
					 except brachytherapy sources manufactured to contain radium, shall be capable
					 of detecting the presence of 185 Bq (0.005 µCi) of radioactive material
					 on a test sample. Test samples shall be taken from the sealed source or from
					 the surfaces of the container in which the sealed source is stored or mounted
					 on which one might expect contamination to accumulate. For a sealed source
					 contained in a device, test samples are obtained when the source is in the
					 "off" position.
(6) The test for
					 leakage for brachytherapy sources manufactured to contain radium shall be
					 capable of detecting an absolute leakage rate of 37 Bq (0.001 µCi) of
					 radon-222 in a 24 hour period when the collection efficiency for radon-222 and
					 its daughters has been determined with respect to collection method, volume and
					 time.
(7) Tests for contamination
					 from radium daughters shall be taken on the interior surface of brachytherapy
					 source storage containers and shall be capable of detecting the presence of 185
					 Bq (0.005 µCi) of a radium daughter which has a half-life greater than
					 four days.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart E - RADIOLOGICAL CRITERIA FOR LICENSE TERMINATION › Section 144-220-D-E-1401 - General provisions and scope

Current through 2024-29, July 17, 2024
The criteria in this subpart apply to the decommissioning
						of facilities licensed under Parts C, E, G, K, and N of this rule.
A. The criteria in this subpart do not apply
					 to sites which have been decommissioned prior to the effective date of this
					 rule.
B. After a site has been
					 decommissioned and the license terminated in accordance with the criteria in
					 this subpart, the Agency will require additional cleanup only if, based on new
					 information, it determines that the criteria of this subpart were not met and
					 residual radioactivity remaining at the site could result in significant threat
					 to public health and safety.
C.
					 When calculating total effective dose equivalent to the average member of the
					 critical group, the licensee shall determine the peak annual TEDE dose expected
					 within the first 1000 years after decommissioning.
D. Specific time limits for the completing
					 the decommissioning process.
(1) Licensees
					 shall complete decommissioning of the site or separate building or outdoor area
					 as soon as practicable, but not later than 24 months following the initiation
					 of decommissioning.
(2) When
					 decommissioning involves the entire site, the licensee shall request license
					 termination as soon as practicable but not later than 24 months following the
					 initiation of decommissioning.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart E - RADIOLOGICAL CRITERIA FOR LICENSE TERMINATION › Section 144-220-D-E-1402 - Radiological criteria for unrestricted use

Current through 2024-29, July 17, 2024
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 shall not
						exceed 10 mrem (0.10 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.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart E - RADIOLOGICAL CRITERIA FOR LICENSE TERMINATION › Section 144-220-D-E-1403 - Criteria for license termination under restricted conditions

Current through 2024-29, July 17, 2024
A site will be considered acceptable for license
						termination under restricted conditions if:
A. The licensee can demonstrate that further
					 reductions in residual radioactivity necessary to comply with the provisions of
					 D.1402. would result in net public or environmental harm or were not being made
					 because the residual levels associated with restricted conditions are 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;
B. The licensee has made
					 provisions for legally enforceable institutional controls that provide
					 reasonable assurance that the total effective dose equivalent from residual
					 radioactivity distinguishable from background to the average member of the
					 critical group will not exceed 10 mrem (0.10 mSv) per year;
C. The licensee has provided sufficient
					 financial assurance to enable an independent third party, including a
					 governmental custodian of a site, to assume and carry out responsibilities for
					 any necessary control and maintenance of the site. Acceptable financial
					 assurance mechanisms are:
(1) Funds placed
					 into a trust segregated from the licensee's assets and outside the licensee's
					 administrative control, and in which the adequacy of the trust funds is to be
					 assessed based on an assumed one percent real rate of return on investment;
(2) A statement of intent in the
					 case of State, or local Government licensees, as described in Part C.8.F;
					 or
(3) When a governmental entity
					 is assuming custody and ownership of a site, an arrangement that is deemed
					 acceptable by such governmental entity;
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart E - RADIOLOGICAL CRITERIA FOR LICENSE TERMINATION › Section 144-220-D-E-1404 - Alternate criteria for license termination

Current through 2024-29, July 17, 2024
A. The Agency may terminate a license using
					 alternate criteria greater than the dose criterion of parts D.1402, D.1403.B,
					 and D.1403.D, if the licensee:
(1) Provides
					 assurance that public health and safety would continue to be protected, and
					 that it is unlikely that the dose from all man-made sources combined, other
					 than medical, would be more than the 1 mSv/y (100 mrem/y) limit, by submitting
					 an analysis of possible sources of exposure;
(2) Has employed to the extent practical
					 restrictions on the site use according to the provisions of D.1403 in
					 minimizing exposures at the site; and
(3) Reduces doses to ALARA levels, taking
					 into consideration any detriments such as traffic accidents expected to
					 potentially result from decontamination and waste disposal.
(4) Has submitted a decommissioning plan or
					 license termination plan to the Agency indicating the licensee's intent to
					 decommission in accordance with Parts C, D, and E., and specifying that the
					 licensee proposes to decommission by use of alternate criteria. The licensee
					 shall document in the decommissioning plan or LTP how the advice of individuals
					 and institutions in the community who may be affected by the decommissioning
					 has been sought and addressed, as appropriate, following analysis of that
					 advice. In seeking such advice, the license shall provide for:
(a) Participation by representatives of a
					 broad cross section of community interests who may be affected by the
					 decommissioning;
(b) An opportunity
					 for a comprehensive, collective discussion on the issues by the participants
					 represented; and
(c) A publicly
					 available summary of the results of all such discussions, including a
					 description of the individual viewpoints of the participants on the issues and
					 the extent of agreement and disagreement among the participants on the
					 issues.
(5) Has provided
					 sufficient financial assurance in the form of a trust fund to enable an
					 independent third party, including a governmental custodian of a site, to
					 assume and carry out responsibilities for any necessary control and maintenance
					 of the site.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart F - SURVEYS AND MONITORING › Section 144-220-D-F-1501 - General

Current through 2024-29, July 17, 2024
A. Each licensee shall make, or cause to be
					 made, surveys of areas, including the subsurface, that:
(1) Are necessary for the licensee or
					 registrant to comply with Part D; and
(2) Are necessary under the circumstances to
					 evaluate:
(a) The magnitude of radiation
					 levels; and
(b) Concentrations or
					 quantities of residual radioactivity; and
(c) The potential radiological hazards of the
					 radiation levels and residual radioactivity detected.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart F - SURVEYS AND MONITORING › Section 144-220-D-F-1502 - Conditions requiring individual monitoring of external and internal occupational dose

Current through 2024-29, July 17, 2024
Each licensee or registrant shall monitor exposures from
						sources of radiation at levels sufficient to demonstrate compliance with the
						occupational dose limits of Part D. As a minimum:
A. Each licensee or registrant shall monitor
					 occupational exposure to radiation from licensed and unlicensed radiation
					 sources under the control of the licensee and shall supply and require the use
					 of individual monitoring devices by:
(1)
					 Adults likely to receive, in one year from sources external to the body, a dose
					 in excess of 10 percent of the limits in D.1201.A; and
(2) Minors likely to receive, in one year
					 from sources external to the body, a deep-dose equivalent in excess of 1 mSv
					 (0.1 rem), a lens dose equivalent in excess of 1.5 mSv (0.15 rem), or a shallow
					 dose equivalent to the skin or to the extremities in excess of 5 mSv (0.5 rem;
					 and
(3) Declared pregnant women
					 likely to receive during the entire pregnancy from sources external to the
					 body, a deep-dose equivalent in excess of 1 mSv (0.1 rem; and
(4) Individuals entering a high or very high
					 radiation area.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart G - CONTROL OF EXPOSURE FROM EXTERNAL SOURCES IN RESTRICTED AREAS › Section 144-220-D-G-1601 - Control of access to high radiation areas

Current through 2024-29, July 17, 2024
A. The licensee or registrant shall ensure
					 that each entrance or access point to a high radiation area has one or more of
					 the following features:
(1) A control device
					 that, upon entry into the area, causes the level of radiation to be reduced
					 below that level at which an individual might receive a deep-dose equivalent of
					 1 mSv (0.1 rem) in one hour at 30 centimeters from the source of radiation or
					 from any surface that the radiation penetrates; or
(2) A control device that energizes a
					 conspicuous visible or audible alarm signal so that the individual entering the
					 high radiation area and the supervisor of the activity are made aware of the
					 entry; or
(3) Entryways that are
					 locked, except during periods when access to the areas is required, with
					 positive control over each individual entry.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart G - CONTROL OF EXPOSURE FROM EXTERNAL SOURCES IN RESTRICTED AREAS › Section 144-220-D-G-1602 - Control of access to very high radiation areas

Current through 2024-29, July 17, 2024
A. In addition to the requirements in D.1601,
					 the licensee or registrant shall institute 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 5 Gy (500 rad) or more in one
					 hour at 1 meter from a source of radiation or any surface through which the
					 radiation penetrates. This requirement does not apply to rooms or areas in
					 which diagnostic x-ray systems are the only source of radiation, or to
					 non-self-shielded irradiators.
B.
					 The registrant is not required to control entrance or access to rooms or other
					 areas containing sources of radiation capable of producing a very high
					 radiation area as described in D.1602.A if the registrant has met all the
					 specific requirements for access and control specified in other applicable
					 Parts of this rule, such as, Part E for industrial radiography, Part F for
					 x-rays in the healing arts, and Part I for particle accelerators.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart G - CONTROL OF EXPOSURE FROM EXTERNAL SOURCES IN RESTRICTED AREAS › Section 144-220-D-G-1603 - Control of access to very high radiation areas - irradiators

Current through 2024-29, July 17, 2024
A. Section D.1603 applies to licensees or
					 registrants with sources of radiation in non-self-shielded irradiators. Section
					 D.1603 does not apply to sources of radiation that are used in teletherapy, in
					 industrial radiography, or in completely self-shielded irradiators in which the
					 source of radiation is both stored and operated within the same shielding
					 radiation barrier and, in the designed configuration of the irradiator, is
					 always physically inaccessible to any individual and cannot create high levels
					 of radiation in an area that is accessible to any individual.
B. Each area in which there may exist
					 radiation levels in excess of 5 Gy (500 rad) in one hour at 1 meter from a
					 source of radiation that is used to irradiate materials shall meet the
					 following requirements:
(1) Each entrance or
					 access point shall be equipped with entry control devices which:
(a) Function automatically to prevent any
					 individual from inadvertently entering a very high radiation area;
					 and
(b) Permit deliberate entry
					 into the area only after a control device is actuated that causes the radiation
					 level within the area, from the source of radiation, to be reduced below that
					 at which it would be possible for an individual to receive a deep-dose
					 equivalent in excess of 1 mSv (0.1 rem) in one hour; and
(c) Prevent operation of the source of
					 radiation if it would produce radiation levels in the area that could result in
					 a deep-dose equivalent to an individual in excess of 1 mSv (0.1 rem) in one
					 hour.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart H - RESPIRATORY PROTECTION AND CONTROLS TO RESTRICT INTERNAL EXPOSURE IN RESTRICTED AREAS › Section 144-220-D-H-1701 - Use of process or other engineering controls

Current through 2024-29, July 17, 2024
The licensee or registrant shall use, to the extent
						practicable, process or other engineering controls, such as, containment,
						decontamination or ventilation, to control the concentrations of radioactive
						material in air.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart H - RESPIRATORY PROTECTION AND CONTROLS TO RESTRICT INTERNAL EXPOSURE IN RESTRICTED AREAS › Section 144-220-D-H-1702 - Use of other controls

Current through 2024-29, July 17, 2024
A. When it is not
					 practical to apply process or other engineering controls to control the
					 concentrations of radioactive material in air to values below those that define
					 an airborne radioactivity area, the licensee or registrant shall, consistent
					 with maintaining the total effective dose equivalent ALARA, increase monitoring
					 and limit intakes by one or more of the following means:
(1) Control of access; or
(2) Limitation of exposure times;
					 or
(3) Use of respiratory
					 protection equipment; or
(4) Other
					 controls.
Code of Maine Rules › 10 - DEPARTMENT OF HEALTH AND HUMAN SERVICES › 144 - DEPARTMENT OF HEALTH AND HUMAN SERVICES - GENERAL › Chapter 220 - Rules Relating to Radiation Protection › Part D - STANDARDS FOR PROTECTION AGAINST RADIATION › Subpart H - RESPIRATORY PROTECTION AND CONTROLS TO RESTRICT INTERNAL EXPOSURE IN RESTRICTED AREAS › Section 144-220-D-H-1704 - Further restrictions on the use of respiratory protection equipment

Current through 2024-29, July 17, 2024
The Agency may impose restrictions in addition to the
						provisions of D.1702 and D.1703, and Appendix A of this Part, in order
						to:
A. Ensure that the respiratory
					 protection program of the licensee is adequate to limit doses to individuals
					 from intakes of radioactive materials consistent with maintaining total
					 effective dose equivalent ALARA; and
B. Limit the extent to which a licensee may
					 use respiratory protection equipment instead of process or other engineering
					 controls.