Current through Register 1531, September 27, 2024
(A)
Licensing Requirements to Produce for Noncommercial Transfer
Positron Emission Tomography (PET) Radioactive Drugs. An
application from a medical facility, educational institution, or Federal
facility to produce Positron Emission Tomography (PET) radioactive drugs for
noncommercial transfer to licensees in its consortium authorized for medical
use under
105 CMR
120.500, or equivalent Nuclear Regulatory
Commission, or Agreement State requirements shall include:
(1) A request for authorization for the
production of PET radionuclides or evidence of an existing license issued under
105 CMR
120.100 or equivalent Nuclear Regulatory
Commission, or Agreement State requirements for a PET radionuclide production
facility within its consortium from which it receives PET
radionuclides.
(2) Evidence that
the applicant is qualified to produce radioactive drugs for medical use by
meeting one of the criteria in 105 CMR 120.128(J)(1)(b).
(3) Identification of individual(s)
authorized to prepare the PET radioactive drugs if the applicant is a pharmacy,
and documentation that each individual meets the requirements of an authorized
nuclear pharmacist as specified in 105 CMR 120.128(J)(2)(b).
(4) Information identified in 105 CMR
120.128(J)(1)(c) on the PET drugs to be noncommercially transferred to members
of its consortium.
(B)
Licensing Requirements to Initially Transfer Source Material to
Persons Generally Licensed under
105 CMR
120.121(A).
(1) An application for a specific license to
initially transfer source material for use under
105 CMR
120.121(A), or equivalent
regulations of the NRC or an Agreement State, will be approved if:
(a) The applicant satisfies the general
requirements specified in
105 CMR
120.125; and
(b) The applicant submits adequate
information on, and the Agency approves the methods to be used for quality
control, labeling, and providing safety instructions to recipients.
(2) Each person licensed under 105
CMR 120.128(B) shall label the immediate container of each quantity of source
material with the type of source material and quantity of material and the
words, "'radioactive material".
(3)
Each person licensed under 105 CMR 120.128(B) shall ensure that the quantities
and concentrations of source material are as labeled and indicated in any
transfer records.
(4) Each person
licensed under 105 CMR 120.128(B) shall provide the information specified in
105 CMR 120.128(B)(4) to each person to whom source material is transferred for
use under
105 CMR
120.121(A) or equivalent
provisions in the NRC or Agreement State regulations. This information must be
transferred before the source material is transferred for the first time in
each calendar year to the particular recipient. The required information
includes:
(a) A copy of
105 CMR
120.121(A) through (C), (F), and
(G) and
105 CMR
120.140, or relevant equivalent regulations
of the NRC or Agreement State.
(b)
Appropriate radiation safety precautions and instructions relating to handling,
use, storage, and disposal of the material.
(5) Each person licensed under 105 CMR
120.128(B) shall report transfers as follows:
(a) File a report with the Agency by an
appropriate method listed in
105 CMR 120.013.
The report shall include the following information:
1. The name, address, and license number of
the person who transferred the source material;
2. For each general licensee under
105 CMR
120.121(A) or equivalent
NRC or Agreement State provisions to whom greater than 50 grams (0.11 lb) of
source material has been transferred in a single calendar quarter, the name and
address of the general licensee to whom source material is distributed; a
responsible agent, by name and/or position and phone number, of the general
licensee to whom the material was sent; and the type, physical form, and
quantity of source material transferred; and
3. The total quantity of each type and
physical form of source material transferred in the reporting period to all
such generally licensed recipients.
(b) File a report with each responsible NRC
or Agreement State agency that identifies all persons, operating under
provisions equivalent to
105 CMR
120.121(A), to whom greater
than 50 grams (0.11 lb) of source material has been transferred within a single
calendar quarter. The report shall include the following information specific
to those transfers made to the NRC or Agreement State being reported to:
1. The name, address, and license number of
the person who transferred the source material; and
2. The name and address of the general
licensee to whom source material was distributed; a responsible agent, by name
and/or position and phone number, of the general licensee to whom the material
was sent; and the type, physical form, and quantity of source material
transferred.
3. The total quantity
of each type and physical form of source material transferred in the reporting
period to all such generally licensed recipients within the NRC's jurisdiction
or the Agreement State.
(c) Submit each report by January
31st of each year covering all transfers for the
previous calendar year. If no transfers were made to persons generally licensed
under
105 CMR
120.121(A) or equivalent
NRC or Agreement State provisions during the current period, a report shall be
submitted to the Agency indicating so. If no transfers have been made to
general licensees within a particular Agreement State during the reporting
period, this information shall be reported to the responsible Agreement State
agency upon request of that agency. If no transfers have been made to NRC
general licensees during the reporting period, this information shall be
reported to the NRC.
(6)
Each person licensed under 105 CMR 120.128(B) shall maintain all information
that supports the reports required by this section concerning each transfer to
a general licensee for a period of one year after the event is included in a
report to the NRC or to an Agreement State agency.
(C)
Requirements for Other
Specific Licenses (Reserved).
(D)
Licensing Requirements to
Manufacture or Initially Transfer Devices Containing Radioactive Material to
Persons Generally Licensed under
105
CMR 120.122(D).
(1) An application for a specific license to
manufacture or distribute devices containing radioactive material, excluding
special nuclear material, to persons generally licensed under
105
CMR 120.122(D) or
equivalent regulations of the U.S. Nuclear Regulatory Commission, an Agreement
State, or a Licensing State will be approved if:
(a) the applicant satisfies the general
requirements of
105 CMR
120.125;
(b) the applicant submits sufficient
information relating to the design, 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:
1. the
device can be safely operated by persons not having training in radiological
protection;
2. under ordinary
conditions of handling, storage, and use of the device, the radioactive
material contained in the device will not be released or inadvertently removed
from the device, and it is unlikely that any person will receive in one year a
dose in excess of 10% of the annual limits specified in
105 CMR
120.211(A), and
3. under accident conditions such as fire and
explosion associated with handling, storage, and use of the device, it is
unlikely that any person would receive an external radiation dose or dose
commitment in excess of the following organ doses:
a. Whole body; head and trunk; active
blood-forming organs; gonads; or lens of eye
........................................... 15 rems (150 mSv)
b. Hands and forearms; feet and ankles;
localized areas of skin averaged over areas no larger than one square
centimeter ............... 200 rems (2 Sv)
c. Other organs .............................
50 rems (500 mSv); and
(c) each device bears a durable, legible,
clearly visible label or labels approved by the Agency, which contain in a
clearly identified and separate statement:
1.
instructions and precautions necessary to assure safe installation, operation,
and servicing of the device; documents such as operating and service manuals
may be identified in the label and used to provide this information;
2. the requirement, or lack of requirement,
for leak testing, or for testing any "on-off" mechanism and indicator,
including the maximum time interval for such testing, and the identification of
radioactive material by isotope, quantity of radioactivity, and date of
determination of the quantity; and
3. the information called for in one of the
following statements, as appropriate, in the same or substantially similar
form:
The receipt, possession, use, and transfer of this device,
Model, Serial No., are subject to a general license or the equivalent and the
regulations of the U.S. Nuclear Regulatory Commission or a State with which the
U.S. Nuclear Regulatory Commission 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. [The model, serial
number, and name of the manufacturer or distributor may be omitted from the
label provided the information is elsewhere specified in labeling affixed to
the device.]
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[Note: Devices licensed under
10
CFR 32.53 prior to January 19, 1975 may bear
labels authorized by the regulations in effect on January 1,
1975.]
(d) each
device having a separable source housing that provides the primary shielding
for the source also bears, on the source housing, a durable label containing
the device model number and serial number, the isotope and quantity, the words,
"Caution-Radioactive Material", the radiation symbol described in
105 CMR 120.237,
and the name of the manufacturer or initial distributor.
(e) each device meeting the criteria of 105
CMR 120 122(D)(3)(m)1., bears a permanent (e.g., embossed,
etched, stamped, or engraved) label affixed to the source housing if separable,
or the device if the source housing is not separable, that includes the words,
"Caution-Radioactive Material", and, if practicable, the radiation symbol
described in
105 CMR
120.237.
(f) the device has been registered in the
Sealed Source and Device Registry.
(2) In the event the applicant desires that
the device be required to be tested at intervals longer than six months, either
for proper operation of the "on-off" mechanism and indicator, if any, or for
leakage of radioactive material or for both, the applicant shall include in the
application sufficient information to demonstrate that such longer interval is
justified by performance characteristics of the device or similar devices and
by design features which have a significant bearing on the probability or
consequences of leakage of radioactive material from the device or failure of
the "on-off" mechanism and indicator. In determining the acceptable interval
for the test for leakage of radioactive material, the Agency will consider
information which includes, but is not limited to:
(a) primary containment or source
capsule;
(b) protection of primary
containment;
(c) method of sealing
containment;
(d) containment
construction materials;
(e) form of
contained radioactive material;
(f)
maximum temperature withstood during prototype tests;
(g) maximum pressure withstood during
prototype tests;
(h) maximum
quantity of contained radioactive material;
(i) radiotoxicity of contained radioactive
material; and
(j) operating
experience with identical devices or similarly designed and constructed
devices.
(3) In the event
the applicant desires that the general licensee under
105
CMR 120.122(D), or under
equivalent regulations of the U.S. Nuclear Regulatory Commission, an Agreement
State, or a Licensing State be authorized to install the device, collect the
sample to be analyzed by a specific licensee for leakage of radioactive
material, service the device, test the "on-off" mechanism and indicator, or
remove the device from installation, the applicant shall include in the
application written instructions to be followed by the general licensee,
estimated calendar quarter doses associated with such activity or activities,
and basis for such estimates. The submitted information shall demonstrate that
performance of such activity or activities by an individual untrained in
radiological protection, in addition to other handling, storage, and use of
devices under the general license, is unlikely to cause that individual to
receive a dose in excess of 10% of the annual limits specified in
105 CMR
120.211(A).
(4) Each person licensed under 105 CMR
120.128(D) to initially transfer devices to generally licensed persons shall:
(a) if a device containing radioactive
material is to be transferred for use under the general license contained in
105
CMR 120.122(D), each person
that is licensed under 105 CMR 120.128(D) shall provide the information
specified in 120.128(D)(4) to each person to whom a device is to be
transferred. This information must be provided before the device may be
transferred. In the case of a transfer through an intermediate person, the
information must also be provided to the intended user prior to initial
transfer to the intermediate person. The required information includes:
1. a copy of the general license contained in
105
CMR 120.122(D); if
105
CMR 120.122(D)(3)(b) through
(d) do not apply to the particular device,
those paragraphs may be omitted;
2.
a copy of
105
CMR 120.122,
120.009(A),
120.281,
and
120.282;
3. a list of the services that can only be
performed by a specific licensee; and,
4. information on acceptable disposal options
including estimated costs of disposal;
(b) if radioactive material is to be
transferred in a device for use under an equivalent general license of the U.S.
Nuclear Regulatory Commission, an Agreement State, or a Licensing State each
person that is licensed under 105 CMR 120.128(D) shall provide the information
specified in 105 CMR 120.128(D)(4)(b) to each person to whom a device is to be
transferred. This information must be provided before the device may be
transferred. In the case of a transfer through an intermediate person, the
information must also be provided to the intended user prior to initial
transfer to the intermediate person. The required information includes:
1. a copy of NRC or Agreement State
regulations equivalent to
105
CMR 120.122(D),
120.009(A),
120.281,
and
120.282.
If a copy of the 105 CMR 120.000 is provided to a prospective general licensee
in lieu of the U.S. Nuclear Regulatory Commission's, Agreement
State's, or Licensing State's regulations, it shall be accompanied by a note
explaining that use of the device is regulated by the U.S. Nuclear Regulatory
Commission, the Agreement State; or Licensing State; if certain paragraphs of
the regulations do not apply to the particular device, those paragraphs may be
omitted;
2. a list of the services
that can only be performed by a specific licensee;
3. information on acceptable disposal options
including estimated costs of disposal; and,
4 the name or title, address, and phone
number of the contact at the U.S. Nuclear Regulatory Commission, the Agreement
State, or Licensing State from which additional information may be
obtained;
(c) an
alternative approach to informing customers may be proposed by the licensee for
approval by the Agency;
(d) each
device that is transferred after February 19, 2002 must meet the labeling
requirements in 105 CMR 120.128(D)(1)(c) through (e);
(e) if a notification of bankruptcy has been
made under
105 CMR
120.131(E) or the license
is to be terminated, each person licensed under 105 CMR 120.128(D) shall
provide, upon request, to the Agency and to any appropriate Agreement State or
NRC, records of final disposition required under 105 CMR
120.128(D)(5)(c).
(5)
Each person licensed under 105 CMR 120.128(D) to initially transfer devices to
generally licensed persons shall comply with the requirements of 105 CMR
120.128(D)(5).
(a) The person shall report to
the Agency all transfers of devices to persons for use under the general
license in
105
CMR 120.122(D) and all
receipts of devices from persons licensed under
105
CMR 120.122(D). The report
must be submitted on a quarterly basis on NRC Form 653 - "Transfers of
Industrial Devices Report" or in a clear and legible report containing all of
the data required by the form.
1. The
required information for transfers to general licensees includes:
a. the identity of each general licensee by
name and mailing address for the location of use; if there is no mailing
address for the location of use, an alternate address for the general licensee
shall be submitted along with information on the actual location of
use;
b. the name, title, and phone
number of the person identified by the general licensee as having knowledge of
and authority to take required actions to ensure compliance with the
appropriate regulations and requirements;
c. the date of transfer;
d. the type, model number, and serial number
of the device transferred; and
e.
the quantity and type of byproduct material contained in the device.
2. If one or more intermediate
persons will temporarily possess the device at the intended place of use before
its possession by the user, the report must include the same information for
both the intended user and each intermediate person, and clearly designate the
intermediate person(s).
3. For
devices received from a
105
CMR 120.122(D) general
licensee, the report must include the identity of the general licensee by name
and address, the type, model number, and serial number of the device received,
the date of receipt, and, in the case of devices not initially transferred by
the reporting licensee, the name of the manufacturer or initial
transferor.
4. If the licensee
makes changes to a device possessed by a
105
CMR 120.122(D) general
licensee, such that the label must be changed to update required information,
the report must identify the general licensee, the device, and the changes to
information on the device label.
5.
The report must cover each calendar quarter, must be filed within 30 days of
the end of the calendar quarter, and must clearly indicate the period covered
by the report.
6. The report must
clearly identify the specific licensee submitting the report and include the
license number of the specific licensee.
7. If no transfers have been made to U.S.
Nuclear Regulatory Commission Licensees during the reporting period, this
information shall be reported to the U.S. Nuclear Regulatory
Commission.
8. If no transfers have
been made to general licensees within a particular State during the reporting
period, this information shall be reported to the responsible State agency upon
request of that agency.
(b) The person shall report all transfers of
devices to persons for use under a general license in the U.S. Nuclear
Regulatory Commission's, an Agreement State's, or a Licensing State's
regulations that are equivalent to
105
CMR 120.122(D) and all
receipts of devices from general licensees in the U.S. Nuclear Regulatory
Commission's, an Agreement State's, or a Licensing State's jurisdiction to the
responsible agency. The report must be submitted on Form 653 - "Transfers of
Industrial Devices Report" or in a clear and legible report containing all of
the data required by the form.
1. The required
information for transfers to general licensees includes:
a. the identity of each general licensee by
name and mailing address for the location of use; if there is no mailing
address for the location of use, an alternate address for the general licensee
shall be submitted along with information on the actual location of
use;
b. the name, title, and phone
number of the person identified by the general licensee as having knowledge of
and authority to take required actions to ensure compliance with the
appropriate regulations and requirements;
c. the date of transfer;
d. the type, model number, and serial number
of the device transferred; and
e.
the quantity and type of byproduct material contained in the device.
2. If one or more intermediate
persons will temporarily possess the device at the intended place of use before
its possession by the user, the report must include the same information for
both the intended user and each intermediate person, and clearly designate the
intermediate person(s).
3. For
devices received from a general licensee, the report must include the identity
of the general licensee by name and address, the type, model number, and serial
number of the device received, the date of receipt, and, in the case of devices
not initially transferred by the reporting licensee, the name of the
manufacturer or initial transferor.
4. If the licensee makes changes to a device
possessed by a general licensee, such that the label must be changed to update
required information, the report must identify the general licensee, the
device, and the changes to information on the device label.
5. The report must cover each calendar
quarter, must be filed within 30 days of the end of the calendar quarter, and
must clearly indicate the period covered by the report.
6. The report must clearly identify the
specific licensee submitting the report and must include the license number of
the specific licensee.
7. If no
transfers have been made to U.S. Nuclear Regulatory Commission Licensees during
the reporting period, this information shall be reported to the U.S. Nuclear
Regulatory Commission.
8. If no
transfers have been made to general licensees within a particular State during
the reporting period, this information shall be reported to the responsible
State agency upon request of that agency.
(c) The person shall maintain all information
concerning transfers and receipts of devices that supports the reports required
by 105 CMR 120.128(D)(5). Records required by 105 CMR 120.128(D)(5)(c) must be
maintained for a period of three years following the date of the recorded
event.
(E)
Special Requirements for the Manufacture, Assembly, or Repair of
Luminous Safety Devices for Use in Aircraft. An application for a
specific license to manufacture, assemble, or repair luminous safety devices
containing tritium or promethium-147 for use in aircraft, for distribution to
persons generally licensed under
105
CMR 120.122(B) will be
approved if:
(1) the applicant satisfies the
general requirements specified in
105 CMR
120.125; and
(2) the applicant satisfies the requirements
of 10 CFR Part 32 §§ 32.53 through 32.56.
(F)
Special Requirements for
License to Manufacture or Initially Transfer Calibration or Reference Sources
Containing Americium-241, or Radium-226 for Distribution to Persons Generally
Licensed under
105
CMR 120.122(G).
An application for a specific license to manufacture or initially transfer
calibration or reference sources containing americium-241, or radium-226, for
distribution to persons generally licensed under
105
CMR 120.122(G), will be
approved if:
(1) the applicant satisfies the
general requirement of
105 CMR
120.125; and
(2) The applicant submits sufficient
information regarding each type of calibration or reference source pertinent to
evaluation of the potential radiation exposure, including:
(a) Chemical and physical form and maximum
quantity of americium-241 or radium-226 in the source;
(b) Details of construction and
design;
(c) Details of the method
of incorporation and binding of the americium-241 or radium-226 in the
source;
(d) Procedures for and
results of prototype testing of sources, which are designed to contain more
than 0.005 microcurie of americium-241 or radium-226, to demonstrate that the
americium-241 or radium-226 contained in each source will not be released or be
removed from the source under normal conditions of use;
(e) Details of quality control procedures to
be followed in manufacture of the source;
(f) Description of labeling to be affixed to
the source or the storage container for the source;
(g) Any additional information, including
experimental studies and tests, required by the Commission to facilitate a
determination of the safety of the source.
(3) Each source will contain no more than 5
microcuries of americium-241 or radium-226.
(4) The Agency determines, with respect to
any type of source containing more than 0.005 microcurie of americium-241 or
radium-226, that:
(a) The method of
incorporation and binding of the americium-241 or radium-226 in the source is
such that the americium-241 will not be released or be removed from the source
under normal conditions of use and handling of the source; and
(b) The source has been subjected to and has
satisfactorily passed the prototype tests prescribed by
10
CFR
32.57(e).
(5) Each person licensed under 105 CMR
120.128(F) shall affix to each source, or storage container for the source, a
label which shall contain sufficient information relative to safe use and
storage of the source and shall include the following statement or a
substantially similar statement which contains the information called for in
the following statement:
The receipt, possession, use, and transfer of this source,
Model ______, Serial No. _______, are subject to a general license or the
equivalent and the regulations of the U.S. Nuclear Regulatory Commission or a
State with which the U.S. Nuclear Regulatory 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 (OR RADIUM-226). DO NOT TOUCH RADIOACTIVE PORTION OF THIS
SOURCE.
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(6)
Each person licensed under 105 CMR 120.128(F) shall perform a dry wipe test
upon each source containing more than 3.7 kilobecquerels (0.1 microcurie) of
americium-241 or radium-226 before transferring the source to a general
licensee under
105
CMR 120.122(G) or under
equivalent regulations of NRC or an Agreement State. This test shall be
performed by wiping the entire radioactive surface of the source with a filter
paper with the application of moderate finger pressure. The radioactivity on
the filter paper shall be measured using methods capable of detecting 0.185
kilobecquerel (0.005 microcurie) of americium-241 or radium-226. If a source
has been shown to be leaking or losing more than 0.185 kilobecquerel (0.005
microcurie) of americium-241 or radium-226 by the methods described in 105 CMR
120.128(F)(6), the source shall be rejected and shall not be transferred to a
general licensee under
105
CMR 120.122(G) or
equivalent regulations of NRC or an Agreement State.
(G)
Requirements for Other
Specific Licenses (Reserved).
(H)
Manufacture and Distribution
of Radioactive Material for Certain In Vitro Clinical or
Laboratory Testing Under General License. An application for a
specific license to manufacture or distribute radioactive material for use
under the general license of
105
CMR 120.122(I) will be
approved if:
(1) the applicant satisfies the
general requirements specified in
105 CMR
120.125.
(2) the radioactive material is to be
prepared for distribution in prepackaged units of:
(a) carbon-14 in units not exceeding ten
microcuries (370 kBq) each.
(b)
cobalt-57 in units not exceeding ten microcuries (370 kBq) each.
(c) hydrogen-3 (tritium) in units not
exceeding 50 microcuries (1.85 MBq) each.
(d) iodine-125 in units not exceeding ten
microcuries (370 kBq) each.
(e)
Mock Iodine-125 in units not exceeding 0.05 microcurie (1.85 kBq) of iodine-129
and 0.005 microcurie (185 Bq) of americium-241 each.
(f) iodine-131 in units not exceeding ten
microcuries (370 kBq) each.
(g)
iron-59 in units not exceeding 20 microcuries (740 kBq) each.
(h) selenium-75 in units not exceeding ten
microcuries (370 kBq) each.
(3) each prepackaged unit bears a durable,
clearly visible label:
(a) identifying the
radioactive contents as to chemical form and radionuclide, and indicating that
the amount of radioactivity does not exceed ten microcuries (370 kBq) of
iodine-125, iodine-131, carbon-14, cobalt-57, or selenium-75; 50 microcuries
(1.85 MBq) of hydrogen-3 (tritium); 20 microcuries (740 kBq) of iron-59; or
Mock Iodine-125 in units not exceeding 0.05 microcurie (1.85 kBq) of iodine-129
and 0.005 microcurie (185 Bq) of americium-241 each; or cobalt-57 in units not
exceeding 0.37 megabecquerel (10 microcuries); and
(b) displaying the radiation caution symbol
described in
105 CMR 120.237(A)
and the words, "CAUTION, RADIOACTIVE
MATERIAL", and "Not for Internal or External Use in Humans or
Animals".
(4) the
following statement or a substantially similar statement which contains the
information called for in the following statement, 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, clinical laboratories or
hospitals and only for in vitro clinical or laboratory tests
not involving internal or external administration of the material, or the
radiation therefrom, to human beings or animals. Its receipt, acquisition,
possession, use, and transfer are subject to the regulations and a general
license of the U.S. Nuclear Regulatory Commission or of a State with which the
U.S. Nuclear Regulatory Commission has entered into an agreement for the
exercise of regulatory authority.
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(5)
the label affixed to the unit, or the leaflet or brochure which accompanies the
package, contains adequate information as to the precautions to be observed in
handling and storing such radioactive material. In the case of the Mock
Iodine-125 reference or calibration source, the information accompanying the
source must also contain directions to the licensee regarding the waste
disposal requirements set out in
105 CMR
120.251.
(I)
Licensing the Manufacture and
Distribution of Ice Detection Devices. An application for a
specific license to manufacture and distribute ice detection devices to persons
generally licensed under
105
CMR 120.122(J) will be
approved if:
(1) the applicant satisfies the
general requirements of
105 CMR
120.125; and
(2) the criteria of 10 CFR Part 32,
§§ 32.61 and 32.62 are met.
(J)
Manufacture, Preparation, or
Transfer for Commercial Distribution of Drugs Containing Radioactive Material
for Medical Use under
105 CMR
120.500.
(1) An application for a specific license to
manufacture, prepare, or transfer for commercial distribution radioactive drugs
containing radioactive material for use by persons authorized pursuant to
105 CMR
120.500 will be approved if:
(a) the applicant satisfies the general
requirements specified in
105 CMR
120.125;
(b) the applicant submits evidence that the
applicant is at least one of the following:
1. registered or licensed with the U.S. Food
and Drug Administration (FDA) as the owner or operator of a drug establishment
that engages in the manufacture, preparation, propagation, compounding, or
processing of a drug under 21 CFR 207.20(a);
2. registered or licensed with a State agency
as a drug manufacturer;
3. licensed
as a pharmacy by a State Board of Pharmacy;
4. operating as a nuclear pharmacy pursuant
to 247 CMR 13.00: Registration Requirements and Minimal Professional
Standards for Nuclear Pharmacies;
5. operating as a nuclear pharmacy within a
Federal medical institution; or
6.
a Positron Emission Tomography (PET) drug production facility registered with a
State agency.
(c) the
applicant submits information on the radionuclide; the chemical and physical
form; the maximum activity per vial, syringe, generator, or other container of
the radioactive drug; and the shielding provided by the packaging to show it is
appropriate for safe handling and storage of the radioactive drugs by medical
use licensees; and
(d) the applicant
commits to the following labeling requirements:
1. a label is affixed to each transport
radiation shield, whether it is constructed of lead, glass, plastic, or other
material of a radioactive drug to be transferred for commercial distribution.
The label must include the radiation symbol and the words "CAUTION, RADIOACTIVE
MATERIAL", the name of the radioactive drug or its abbreviation, and the
quantity of radioactivity at a specified date and time. For radioactive drugs
with a half life greater than 100 days the time may be omitted.
2. a label is affixed to each syringe, vial,
or other container used to hold a radioactive drug to be transferred for
commercial distribution. The label must include the radiation symbol and the
words "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.
(2) A
licensee pursuant to 105 CMR 120.128(J)(1)(b)3. or (b)4. or (b)5.:
(a) may prepare radioactive drugs for medical
use, as defined in
105 CMR 120.502,
provided that the radioactive drug is prepared by either an authorized nuclear
pharmacist, as specified in 105 CMR 120.128(J)(2)(b) and (d), or an individual
under the supervision of an authorized nuclear pharmacist as specified in
105 CMR
120.519.
(b) may allow a pharmacist to work as an
authorized nuclear pharmacist if:
1. this
individual qualifies as an authorized nuclear pharmacist as defined in
105 CMR 120.502;
or
2. this individual meets the
requirements specified in
105 CMR
120.526(B) and
120.529
and the licensee has received an approved license amendment identifying this
individual as an authorized nuclear pharmacist; or
3. this individual is designated as an
authorized nuclear pharmacist in accordance with 105 CMR
120.128(J)(2)(d).
(c) is
permitted to perform the actions authorized in 105 CMR 120.128(J)(2)(a) and (b)
in spite of more restrictive language in license conditions.
(d) may designate a pharmacist, as defined in
105 CMR 120.005, as
an authorized nuclear pharmacist if:
1. The
individual was a nuclear pharmacist preparing only radioactive drugs containing
accelerator-produced radioactive material; and
2. The individual practiced at a pharmacy at
a Government agency or Federally recognized Indian Tribe before November 30,
2007 or at all other pharmacies before August 8, 2009, or an earlier date as
noticed by the NRC.
(e)
shall provide to the Agency:
1. A copy of
each individual's certification by a specialty board whose certification
process has been recognized by the Agency, Nuclear Regulatory Commission or an
Agreement State as specified in
105 CMR
120.526(A); or
2. The Agency, Agreement State or Nuclear
Regulatory Commission license; or
3. The Nuclear Regulatory Commission master
materials licensee permit; or
4.
The permit issued by a licensee or Nuclear Regulatory Commission master
materials permittee of broad scope or the authorization from a commercial
nuclear pharmacy authorized to list its own authorized nuclear pharmacist;
or
5. Documentation that only
accelerator-produced radioactive materials were used in the practice of nuclear
pharmacy at a Government agency or Federally recognized Indian Tribe before
November 30, 2007 or at all other locations of use before August 8, 2009, or an
earlier date as noticed by the NRC; and
6. A copy of the State pharmacy licensure or
registration, no later than 30 days after the date that the licensee allows,
under 105 CMR 120.128(J)(2)(b)1. and 3. of 105 CMR 120.128(J), the individual
to work as an authorized nuclear pharmacist.
(3) A licensee shall possess and use
instrumentation to measure the radioactivity of radioactive drugs. The licensee
shall have procedures for use of the instrumentation. The licensee shall
measure, by direct measurement or by combination of measurements and
calculations, the amount of radioactivity in dosages of alpha-, beta-, or
photon-emitting radioactive drugs prior to transfer for commercial
distribution. In addition, the licensee shall:
(a) perform tests before initial use,
periodically, and following repair, on each instrument for accuracy, linearity,
and geometry dependence, as appropriate for the use of the instrument; and make
adjustments when necessary; and
(b)
check each instrument for constancy and proper operation at the beginning of
each day of use.
(4) A
licensee shall satisfy the labeling requirements in 105 CMR
120.128(J)(1)(d).
(5) Nothing in
105 CMR 120.128(J) relieves the licensee from complying with applicable FDA,
other Federal, and State requirements governing radioactive drugs.
(K)
Manufacture and Distribution of Generators or Reagent Kits for
Preparation of Radiopharmaceuticals Containing Radioactive
Material5. An application for a
specific license to manufacture and distribute generators or reagent kits
containing radioactive material for preparation of radiopharmaceuticals by
persons licensed pursuant to
105 CMR
120.100 for the uses listed in
105
CMR 120.547 will be approved if:
(1) the applicant satisfies the general
requirements specified in
105 CMR
120.125;
(2) the applicant submits evidence that:
(a) the generator or reagent kit is to be
manufactured, labeled and packaged in accordance with the Federal Food, Drug
and Cosmetic Act or the Public Health Service Act, such as a new drug
application (NDA) approved by the Food and Drug Administration (FDA), or a
"Notice of Claimed Investigational Exemption for a New Drug" (IND) that has
been accepted by the FDA; or
(b)
the manufacture and distribution of the generator or reagent kit are not
subject to the Federal Food, Drug and Cosmetic Act and the Public Health
Service Act.
(3) the
applicant submits information on the radionuclide, chemical and physical form,
packaging including maximum activity per package, and shielding provided by the
packaging of the radioactive material contained in the generator or reagent
kit;
(4) the label affixed to the
generator or reagent kit contains information on the radionuclide, quantity,
and date of assay; and
(5) the
label affixed to the generator or reagent kit, or the leaflet or brochure which
accompanies the generator or reagent kit, contains:
(a) adequate information, from a radiation
safety standpoint, on the procedures to be followed and the equipment and
shielding to be used in eluting the generator or processing radioactive
material with the reagent kit; and
(b) a statement that this generator or
reagent kit, as appropriate, is approved for use by persons licensed by the
Agency pursuant to
105
CMR 120.547 or under equivalent licenses of
the U.S. Nuclear Regulatory Commission, an Agreement State, or a Licensing
State. The labels, leaflets, or brochures required by 105 CMR 120.128(K) are in
addition to the labeling required by the Food and Drug Administration (FDA) and
they may be separate from or, with the approval of FDA, may be combined with
the labeling required by FDA.
(L)
Manufacture and Distribution
of Sources or Devices Containing Radioactive Material for Medical
Use. An application for a specific license to manufacture and
distribute sources and devices containing radioactive material to persons
licensed pursuant to
105 CMR
120.500 for use as a calibration,
transmission, or reference source or for the uses listed in
105 CMR
120.559,
120.568,
120.570
and
120.589
will be approved if:
(1) the applicant
satisfies the general requirements in
105 CMR
120.125;
(2) the applicant submits sufficient
information regarding each type of source or device pertinent to an evaluation
of its radiation safety, including:
(a) the
radioactive material contained, its chemical and physical form, and
amount;
(b) details of design and
construction of the source or device;
(c) procedures for, and results of, prototype
tests to demonstrate that the source or device will maintain its integrity
under stresses likely to be encountered in normal use and accidents;
(d) for devices containing radioactive
material, the radiation profile of a prototype device;
(e) details of quality control procedures to
assure that production sources and devices meet the standards of the design and
prototype tests;
(f) procedures and
standards for calibrating sources and devices;
(g) legend and methods for labeling sources
and devices as to their radioactive content; and
(h) instructions for handling and storing the
source or device from the radiation safety standpoint; these instructions are
to be included on a durable label attached to the source or device or attached
to a permanent storage container for the source or device; provided, that
instructions which are too lengthy for such label may be summarized on the
label and printed in detail on a brochure which is referenced on the
label.
(3) the label
affixed to the source or device, or to the permanent storage container for the
source or device, contains information on the radionuclide, quantity, and date
of assay, and a statement that the Agency has approved the distribution of the
(name of source or device) to persons licensed to use radioactive material
identified in
105
CMR 120.535,
120.559,
120.568,
and
120.570
or under equivalent licenses of the U.S. Nuclear Regulatory Commission or an
Agreement State;
(4) the source or
device has been registered in the Sealed Source and Device Registry;
(5) in the event the applicant desires that
the source or device be required to be tested for leakage of radioactive
material at intervals longer than six months, he or she shall include in his or
her application sufficient information to demonstrate that such longer interval
is justified by performance characteristics of the source or device or similar
sources or devices and by design features that have a significant bearing on
the probability or consequences of leakage of radioactive material from the
source; and
(6) in determining the
acceptable interval for test of leakage of radioactive material, the Agency
will consider information that includes, but is not limited to:
(a) primary containment or source
capsule;
(b) protection of primary
containment;
(c) method of sealing
containment;
(d) containment
construction materials;
(e) form of
contained radioactive material;
(f)
maximum temperature withstood during prototype tests;
(g) maximum pressure withstood during
prototype tests;
(h) maximum
quantity of contained radioactive material;
(i) radiotoxicity of contained radioactive
material; and
(j) operating
experience with identical sources or devices or similarly designed and
constructed sources or devices.
(M)
Requirements for License to
Manufacture and Distribute Industrial Products Containing Depleted Uranium for
Mass-volume Applications.
(1) An
application for a specific license to manufacture industrial products and
devices containing depleted uranium for use pursuant to
105 CMR
120.121(E) or equivalent
regulations of the U.S. Nuclear Regulatory Commission or an Agreement State
will be approved if:
(a) the applicant
satisfies the general requirements specified in
105 CMR
120.125;
(b) the applicant submits sufficient
information relating to the design, manufacture, prototype testing, quality
control procedures, labeling or marking, proposed uses, and potential hazards
of the industrial product or device to provide reasonable assurance that
possession, use, or transfer of the depleted uranium in the product or device
is not likely to cause any individual to receive a radiation dose in excess of
10% of the annual limits specified in
105 CMR
120.211(A); and
(c) the applicant submits sufficient
information regarding the industrial product or device and the presence of
depleted uranium for a mass-volume application in the product or device to
provide reasonable assurance that unique benefits will accrue to the public
because of the usefulness of the product or device.
(2) In the case of an industrial product or
device whose unique benefits are questionable, the Agency will approve an
application for a specific license under 105 CMR 120.128(M) only if the product
or device is found to combine a high degree of utility and low probability of
uncontrolled disposal and dispersal of significant quantities of depleted
uranium into the environment.
(3)
The Agency may deny any application for a specific license under 105 CMR
120.128(M) if the end use(s) of the industrial product or device cannot be
reasonably foreseen.
(4) Each
person licensed pursuant to 105 CMR 120.128(M)(1) shall:
(a) maintain the level of quality control
required by the license in the manufacture of the industrial product or device,
and in the installation of the depleted uranium into the product or
device;
(b) label or mark each unit
to:
1. identify the manufacturer of the
product or device and the number of the license under which the product or
device was manufactured, the fact that the product or device contains depleted
uranium, and the quantity of depleted uranium in each product or device;
and
2. state that the receipt,
possession, use, and transfer of the product or device are subject to a general
license or the equivalent and the regulations of the U.S. Nuclear Regulatory
Commission or an Agreement State.
(c) assure that the depleted uranium before
being installed in each product or device has been impressed with the following
legend clearly legible through any plating or other covering: "Depleted
Uranium";
(d)
1. furnish a copy of the general license
contained in
105 CMR
120.121(E) and a copy of
form MRCP 120.100-1 to each person to whom he or she transfers depleted uranium
in a product or device for use pursuant to the general license contained in
105 CMR
120.121(E); or
2. furnish a copy of the general license
contained in the U.S. Nuclear Regulatory Commission's or Agreement State's
regulation equivalent to
105 CMR
120.121(E) and a copy of
the U.S. Nuclear Regulatory Commission's or Agreement State's certificate, or
alternatively, furnish a copy of the general license contained in
105 CMR
120.121(E) and a copy of
form MRCP 120.100-1 to each person to whom he or she transfers depleted uranium
in a product or device for use pursuant to the general license of the U.S.
Nuclear Regulatory Commission or an Agreement State, with a note explaining
that use of the product or device is regulated by the U.S. Nuclear Regulatory
Commission or an Agreement State under requirements substantially the same as
those in
105 CMR
120.121(E).
(e) report to the Agency all transfers of
industrial products or devices to persons for use under the general license in
105 CMR
120.121(E). Such report
shall identify each general licensee by name and address, an individual by name
and/or position who may constitute a point of contact between the Agency and
the general licensee, the type and model number of device transferred, and the
quantity of depleted uranium contained in the product or device. The report
shall be submitted within 30 days after the end of each calendar quarter in
which such a product or device is transferred to the generally licensed person.
If no transfers have been made to persons generally licensed under
105 CMR
120.121(E) during the
reporting period, the report shall so indicate;
(f)
1.
report to the U.S. Nuclear Regulatory Commission all transfers of industrial
products or devices to persons for use under the U.S. Nuclear Regulatory
Commission general license in 10 CFR Part 40, § 40.25;
2. report to the responsible State agency all
transfers of devices manufactured and distributed pursuant to 105 CMR
120.128(M) for use under a general license in that State's regulations
equivalent to
105 CMR
120.121(E);
3. such report shall identify each general
licensee by name and address, an individual by name and/or position who may
constitute a point of contact between the Agency and the general licensee, the
type and model number of the device transferred, and the quantity of depleted
uranium contained in the product or device. The report shall be submitted
within 30 days after the end of each calendar quarter in which such product or
device is transferred to the generally licensed person;
4. if no transfers have been made to U.S.
Nuclear Regulatory Commission licensees during the reporting period, this
information shall be reported to the U.S. Nuclear Regulatory Commission;
and
5. if no transfers have been
made to general licensees within a particular Agreement State during the
reporting period, this information shall be reported to the responsible
Agreement State agency upon the request of that agency.
(g) keep records showing the name, address,
and point of contact for each general licensee to whom he or she transfers
depleted uranium in industrial products or devices for use pursuant to the
general license provided in
105 CMR
120.121(E) or equivalent
regulations of the U.S. Nuclear Regulatory Commission or an Agreement State.
The records shall be maintained for a period of two years and shall show the
date of each transfer, the quantity of depleted uranium in each product or
device transferred, and compliance with the report requirements of
105 CMR
120.100.
(N)
Sealed Source and Device
Registration - Registration of Product Information and Inactivation of
Certificates of Registration of Sealed Sources and Devices.
(1) Any manufacturer or initial distributor
of a sealed source or device containing a sealed source may submit a request to
the Agency for evaluation of radiation safety information about its product and
for its registration.
(2) The
request for review must be sent to the Agency in duplicate by an appropriate
method listed in
105 CMR
120.013.
(3) The request for review of a sealed source
or a device must include sufficient information about the design, manufacture,
prototype testing, quality control program, labeling, proposed uses and leak
testing and, for a device, the request must also include sufficient information
about installation, service and maintenance, operating and safety instructions,
and its potential hazards, to provide reasonable assurance that the radiation
safety properties of the source or device are adequate to protect health and
minimize danger to life and property.
(4) The Agency normally evaluates a sealed
source or a device using radiation safety criteria in accepted industry
standards. If these standards and criteria do not readily apply to a particular
case, the Agency formulates reasonable standards and criteria with the help of
the manufacturer or distributor. The Agency shall use criteria and standards
sufficient to ensure that the radiation safety properties of the device or
sealed source are adequate to protect health and minimize danger to life and
property.
(5) After completing the
evaluation and determining that requirements for registration have been met,
the Agency shall issue a certificate of registration to the person making the
request. The certificate of registration acknowledges the availability of the
submitted information for inclusion in an application for a specific license
proposing use of the product, or concerning use under an exemption from
licensing or general license as applicable for the category of
certificate.
(6) The person
submitting the request for evaluation and registration of safety information
about the product shall manufacture and distribute the product in accordance
with:
(a) The statements and representations,
including quality control program, contained in the request; and
(b) The provisions of the registration
certificate.
(7)
Authority to manufacture or initially distribute a sealed source or device to
specific licensees may be provided in the license without the issuance of a
certificate of registration in the following cases:
(a) Calibration and reference sources
containing no more than:
1. 37 MBq (1 mCi),
for beta and/or gamma emitting radionuclides; or
2. 0.37 MBq (10 µCi), for alpha
emitting radionuclides; or
(b) The intended recipients are qualified by
training and experience and have sufficient facilities and equipment to safely
use and handle the requested quantity of radioactive material in any form in
the case of unregistered sources or, for registered sealed sources contained in
unregistered devices, are qualified by training and experience and have
sufficient facilities and equipment to safely use and handle the requested
quantity of radioactive material in unshielded form, as specified in their
licenses; and
1. The intended recipients are
licensed under
105 CMR
120.127 or comparable provisions of NRC or an
Agreement State;
2. The recipients
are authorized for research and development; or
3. The sources and devices are to be built to
the unique specifications of the particular recipient and contain no more than
740 GBq (20 Ci) of tritium or 7.4 GBq (200 mCi) of any other
radionuclide.
(8) After the certificate is issued, the
Agency may conduct an additional review as it determines is necessary to ensure
compliance with current regulatory standards. In conducting its review, the
Agency will complete its evaluation in accordance with criteria specified in
105 CMR 120.128(N). The Agency may request such additional information as it
considers necessary to conduct its review and the certificate holder shall
provide the information as requested.
(9) A certificate holder who no longer
manufactures or initially transfers any of the sealed source(s) or device(s)
covered by a particular certificate issued by the Agency shall request
inactivation of the registration certificate. Such a request must be made to
the Agency by an appropriate method listed in
105 CMR 120.013
and must normally be made no later than two years after initial distribution of
all of the source(s) or device(s) covered by the certificate has ceased.
However, if the certificate holder determines that an initial transfer was in
fact the last initial transfer more than two years after that transfer, the
certificate holder shall request inactivation of the certificate within 90 days
of this determination and briefly describe the circumstances of the
delay.
(10) If a distribution
license is to be terminated in accordance with
105
CMR 120.132, the licensee shall request
inactivation of its registration certificates associated with that distribution
license before the Agency will terminate the license. Such a request for
inactivation of certificate(s) must indicate that the license is being
terminated and include the associated specific license number.
(11) A specific license to manufacture or
initially transfer a source or device covered only by an inactivated
certificate no longer authorizes the licensee to initially transfer such
sources or devices for use. Servicing of devices must be in accordance with any
conditions in the certificate, including in the case of an inactive
certificate.
5 Although the Agency does not
regulate the manufacture and distribution of reagent kits that do not contain
radioacitve material, it does regulate the use of such reagent kits for the
preparation of radiopharmaceuticals containing radioactive material as part of
its licensing and regulation of the users of radioactive material. Any
manufacturer of reagent kits that do not contain radioactive material who
desires to have his reagent kits approved by the Agency for use by persons
licensed pursuant to
105
CMR 120.547 may submit the pertinent
information specified in 105 CMR
120.128(K).