reglab/statecodes huggingface dataset:
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0100 - Radiation Dose Limits: Occupational Dose Limits For Adults

Current through Register Vol. 63, No. 7, July 1, 2024
(1) Each licensee
			 or registrant must control the occupational dose to individual adults, except
			 for planned special exposures under OAR 333-120-0150, to the following dose
			 limits:
(a) An annual limit, which is the
			 more limiting of:
(A) The total effective dose
			 equivalent 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).
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0110 - Compliance with Requirements for Summation of External and Internal Doses

Current through Register Vol. 63, No. 7, July 1, 2024
(1) If the licensee
			 is required to monitor under OAR
			 333-120-0210(1)
			 and (2), the licensee must demonstrate
			 compliance with the dose limits by summing external and internal doses. If the
			 licensee is required to monitor only under OAR
			 333-120-0210(1)
 
			 or only under
			 333-120-0210(2),
			 then summation is not required to demonstrate compliance with the dose limits.
			 The licensee may demonstrate compliance with the requirements for summation of
			 external and internal doses by meeting one of the conditions specified in
			 section (2) of this rule and the conditions in sections (3) and (4) of this
			 rule.
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.
(2) Intake by Inhalation. If the only intake
			 of radionuclides is by inhalation, the total effective dose equivalent limit is
			 not exceeded if the sum of the deep-dose equivalent divided by the total
			 effective dose equivalent limit, and one of the following, does not exceed
			 unity:
(a) The sum of the fractions of the
			 inhalation ALI for each radionuclide; or
(b) The total number of derived air
			 concentration-hours (DAC-hours) for all radionuclides divided by 2,000;
			 or
(c) The sum of the calculated
			 committed effective dose equivalents to all significantly irradiated organs or
			 tissues (T) calculated from bioassay data using appropriate biological models
			 and expressed as a fraction of the annual limit.
NOTE:
An organ or tissue is deemed to be
				significantly irradiated if, for that organ or tissue, the product of the
				weighting factors, WT, and the committed dose equivalent, HT,50, per unit
				intake is greater than ten percent of the maximum weighted value of HT50 (i.e.
				WTHT50) per unit intake for any organ or tissue.
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0120 - Determination of External Dose from Airborne Radioactive Material

Current through Register Vol. 63, No. 7, July 1, 2024
Licensees must, 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 ( 10 CFR, Part 20, Appendix B, Footnotes 1 and 2 to 20.1001 to
				20.2401).
NOTE:
Airborne radioactivity measurements and DAC
				values should not be used as the primary means to assess the deep-dose
				equivalent when the airborne radioactive material includes radionuclides other
				than noble gases or if the cloud of airborne radioactive material is not
				relatively uniform. The determination of the deep-dose equivalent to an
				individual should be based upon measurements using instruments or individual
				monitoring devices.
Stat. Auth.: ORS 453.635
Stats. Implemented: ORS 453.605 -
				  453.807
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0130 - Determination of Internal Exposure

Current through Register Vol. 63, No. 7, July 1, 2024
(1)
			 For purposes of assessing dose used to determine compliance with occupational
			 dose equivalent limits, the licensee must, when required under OAR
			 333-120-0210,
			 take suitable and timely measurements of:
(a)
			 Concentrations of radioactive materials in air in work areas; or
(b) Quantities of radionuclides in the body;
			 or
(c) Quantities of radionuclides
			 excreted from the body; or
(d)
			 Combinations of these measurements.
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0150 - Planned Special Exposures

Current through Register Vol. 63, No. 7, July 1, 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 OAR
				333-120-0100 provided that each of the following conditions is satisfied:
(1) The licensee or registrant authorizes a
			 planned special exposure only in an exceptional situation when alternatives
			 that might avoid the higher exposure are unavailable or impractical.
(2) The licensee or registrant (and employer
			 if the employer is not the licensee or registrant) specifically authorizes the
			 planned special exposure, in writing, before the exposure occurs.
(3) Before a planned special exposure, the
			 licensee or registrant ensures that the individuals involved are:
(a) Informed of the purpose of the planned
			 operation;
(b) Informed of the
			 estimated doses and associated potential risks and specific radiation levels or
			 other conditions that might be involved in performing the task; and
(c) Instructed in the measures to be taken to
			 keep the dose ALARA considering other risks that may be present.
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0160 - Occupational Dose Limits for Minors

Current through Register Vol. 63, No. 7, July 1, 2024
The annual occupational dose limits for minors are 10 percent
				of the annual dose limits specified for adult workers in OAR
				333-120-0100.
Stat. Auth.: ORS 453.635
Stats. Implemented: ORS 453.605 -
				  453.807
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0170 - Dose to an Embryo/Fetus

Current through Register Vol. 63, No. 7, July 1, 2024
(1) The
			 licensee or registrant must ensure that the dose equivalent to an embryo/fetus
			 during the entire pregnancy, due to occupational exposure of a declared
			 pregnant woman does not exceed five mSv (0.5 rem). Records must be kept in
			 accordance with OAR
			 333-120-0650.
NOTE:
A woman is not a declared pregnant woman
				unless she says so in writing without being coerced. Unless a woman, who also
				is a radiation worker, has declared her pregnancy as required, she is to be
				treated as any other radiation worker. Pursuant to Title VII of the Civil
				Rights Act of 1964, as amended, no employer may restrict a fertile female's job
				because of concern for the health of the fetus that a woman might conceive. The
				court held that sex-specific fetal-protection policies are forbidden.
				Additionally, a female worker legally can declare pregnancy if she does not yet
				have documented medical proof. The document, "Instruction Concerning Prenatal
				Radiation Exposure," discusses declared pregnancy. It is available from Public
				Health Division, Radiation Protection Services Suite 640, 800 N.E. Oregon St.,
				Portland, OR 97232, phone (971) 673-0490.
(2) The licensee or registrant must make
			 efforts to avoid substantial variation above a uniform monthly exposure rate to
			 a declared pregnant woman so as to satisfy the limit in section (1) of this
			 rule.
(3) The dose equivalent to an
			 embryo/fetus must be taken as the sum of:
(a)
			 The deep-dose equivalent to the declared pregnant woman; and
(b) The dose equivalent to the embryo/fetus
			 from radionuclides in the embryo/fetus and radionuclides in the declared
			 pregnant woman, If the dose equivalent to the embryo/fetus is found to have
			 exceeded 0.5 rem (5 mSv), or is within 0.05 rem (0.5 mSv) of this dose, by the
			 time the woman declares the pregnancy to the licensee, the licensee shall be
			 deemed to be in compliance with subsection (3)(a) of this rule if the
			 additional dose equivalent to the embryo/fetus does not exceed 0.05 rem (0.5
			 mSv) during the remainder of the pregnancy.
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0180 - Dose Limits for Individual Members of the Public

Current through Register Vol. 63, No. 7, July 1, 2024
(1) Each licensee or registrant must conduct
			 operations so that:
(a) The total effective
			 dose equivalent to individual members of the public from the licensed or
			 registered operation does not exceed one mSv (0.1 rem) in a year, exclusive of
			 the dose contributions from background, from any medical administration the
			 individual has received, from exposure to individuals administered radioactive
			 material and released in accordance with OAR
			 333-116-0260,
			 from voluntary participation in medical research programs, and the licensee's
			 disposal of radioactive material into sanitary sewerage in accordance with OAR
			 333-120-0520;
			 and
(b) The dose in any
			 unrestricted area from external sources, exclusive of the dose contributions
			 from patients administered radioactive material and released in accordance with
			 OAR
			 333-116-0260,
			 does not exceed 0.02 mSv (0.002 rem) in any one hour.
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0190 - Compliance with Dose Limits for Individual Members of the Public

Current through Register Vol. 63, No. 7, July 1, 2024
(1) The licensee or
			 registrant must make or cause to be made, as appropriate, 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 OAR
			 333-120-0180.
(2) A licensee or registrant must show
			 compliance with the annual dose limit in OAR
			 333-120-0180  by:
(a) Demonstrating by measurement or
			 calculation that the total effective dose equivalent to the individual likely
			 to receive the highest dose from the licensed or registered operation does not
			 exceed the annual dose limit; or
(b) 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  10 CFR Part 20
			  Table 2 of
Appendix B
to 20.1001 to 20.2401; 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.
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0200 - Surveys and Monitoring: General

Current through Register Vol. 63, No. 7, July 1, 2024
(1) Each licensee or registrant must make or
			 cause to be made, surveys that:
(a) Are
			 necessary for the licensee or registrant to comply with the rules in this
			 division; and
(b) Are reasonable
			 under the circumstances to evaluate:
(A) The
			 magnitude and extent of radiation levels; and
(B) The concentrations or quantities of
			 radioactive material; and
(C) The
			 potential radiological hazards that could be
			 present.
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0210 - Surveys and Monitoring: Conditions Requiring Individual Monitoring of External and Internal Occupational Dose

Current through Register Vol. 63, No. 7, July 1, 2024
Each licensee or registrant must monitor exposures to radiation
				and radioactive material at levels sufficient to demonstrate compliance with
				the occupational dose limits of this division. As a minimum:
(1) Each licensee or registrant must monitor
			 occupational exposure to radiation and must supply and require the use of
			 individual monitoring devices by:
(a) Adults
			 likely to receive, in one year from sources external to the body, a dose in
			 excess of 10 percent of the limits in OAR 333-120-0100(1);
(b) Minors likely to receive, in one year
			 from sources external to the body, a dose in excess of 10 percent of any of the
			 applicable limits in OAR 333-120-0160  or 333-120-0170;
(c) Declared pregnant women likely to receive
			 during the entire pregnancy, from radiation sources external to the body, a
			 deep dose equivalent in excess of one mSv (0.1 rem). An individual monitoring
			 device used for the dose to an embryo/fetus of a declared pregnant woman,
			 pursuant to OAR 333-120-0170(1), must be located under the protective apron at
			 the waist; and
(d) Individuals
			 entering a high or very high radiation area.
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0215 - Location of Individual Monitoring Devices

Current through Register Vol. 63, No. 7, July 1, 2024
Each licensee or registrant must ensure that individuals who
				are required to monitor occupational doses in accordance with OAR
				333-120-0210(1)  wear individual monitoring devices as
				follows:
(1) An individual monitoring
			 device used for monitoring the dose to the whole body must be worn at the
			 unshielded location of the whole body likely to receive the highest exposure.
			 When a protective apron is worn, the location of the individual monitoring
			 device is typically at the neck (collar);
(2) An individual monitoring device used for
			 monitoring the dose to an embryo/fetus of a declared pregnant woman, pursuant
			 to OAR
			 333-120-0170(1),
			 must be located at the waist under any protective apron being worn by the
			 woman;
(3) An individual monitoring
			 device used for monitoring the lens dose equivalent, to demonstrate compliance
			 with OAR
			 333-120-0100(1)(b)(A),
			 must be located at the neck (collar), outside any protective apron being worn
			 by the monitored individual, or at an unshielded location closer to the
			 eye;
(4) An individual monitoring
			 device used for monitoring the dose to the extremities, to demonstrate
			 compliance with OAR
			 333-120-0100(1)(b)(B),
			 must be worn on the extremity likely to receive the highest exposure. Each
			 individual monitoring device must be oriented to measure the highest dose to
			 the extremity being monitored.
Stat. Auth.: ORS 453.635
Stats. Implemented: ORS 453.605 -
				  453.807
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0220 - Control of Access to High Radiation Areas

Current through Register Vol. 63, No. 7, July 1, 2024
(1) The licensee or registrant must ensure
			 that each entrance or access point to a high radiation area has one or more of
			 the following features:
(a) A control device
			 that, upon entry into the area, causes the level of radiation to be reduced
			 below that level at which an individual might receive a deep-dose equivalent of
			 one mSv (0.1 rem) in one hour at 30 centimeters from the radiation source or
			 from any surface that the radiation penetrates;
(b) A control device that energizes a
			 conspicuous visible or audible alarm signal so that the individual entering the
			 high radiation area and the supervisor of the activity are made aware of the
			 entry; or
(c) Entryways that are
			 locked, except during periods when access to the areas is required, with
			 positive control over each individual entry.
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0230 - Control of Access to Very High Radiation Areas

Current through Register Vol. 63, No. 7, July 1, 2024
(1) In addition to the requirements in OAR
			 333-120-0220,
			 the licensee or registrant must institute additional measures to ensure that an
			 individual is not able to gain unauthorized or inadvertent access to areas in
			 which radiation levels could be encountered at five gray (500 rad) or more in
			 one hour at one meter from a radiation source or any surface through which the
			 radiation penetrates.
(2) The
			 licensee or registrant is not required to control entrance or access to rooms
			 or other areas containing sources of radiation capable of producing a very high
			 radiation area as described in OAR
			 333-120-0220  if the licensee or registrant has met all the specific requirements for access
			 and control specified in OAR chapter 333, division 105 (industrial
			 radiography), division 106 (X-rays in the healing arts), division 109 (particle
			 accelerators), and division 123 (therapeutic radiation machines).
Stat. Auth.: ORS 453.635
Stats. Implemented: ORS 453.605 -
				  453.807
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0240 - Control of Access to Very High Radiation Areas - Irradiators

Current through Register Vol. 63, No. 7, July 1, 2024
This rule applies to licensees or registrants with sources of
				radiation in non-self-shielded irradiators. It 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.
(1) Each
			 area in which there may exist radiation levels in excess of five gray (500 rad)
			 in one hour at one meter from a sealed radioactive source that is used to
			 irradiate materials must meet the following requirements.
(a) Each entrance or access point must be
			 equipped with entry control devices which:
(A) Function automatically to prevent any
			 individual from inadvertently entering the area when very high radiation levels
			 exist; 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 sealed source, to be reduced below
			 that at which it would be possible for an individual to receive a deep-dose
			 equivalent in excess of one mSv (0.1 rem) in one hour; and
(C) Prevent operation of the source if the
			 source would produce radiation levels in the area that could result in a
			 deep-dose equivalent to an individual in excess of one mSv (0.1 rem) in one
			 hour.
NOTE:
This rule applies to radiation from
				accelerators, and byproduct, source, NARM, or special nuclear radioactive
				materials that are used in sealed sources in non-self-shielded irradiators.
				This rule does not apply to radioactive or X-ray sources that are used in
				teletherapy or medical accelerators, in radiography, or in completely
				self-shielded irradiators in which the source is both stored and operated
				within the same shielding radiation barrier and, in the designed configuration
				of the irradiator, is always physically inaccessible to any individual and
				cannot create high levels of radiation in an area that is accessible to any
				individual. This rule also does not apply to sources from which the radiation
				is incidental to some other use.
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0250 - Security of Stored Material

Current through Register Vol. 63, No. 7, July 1, 2024
(1)
			 The licensee must secure from unauthorized removal or access licensed materials
			 that are stored in controlled or unrestricted areas.
(2) The registrant must secure registered
			 radiation machines from unauthorized removal.
(3) The registrant must use devices or
			 administrative procedures to prevent unauthorized use of registered radiation
			 machines.
Stat. Auth.: ORS 453.635
Stats. Implemented: ORS 453.605 -
				  453.807
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0260 - Control of Material Not in Storage

Current through Register Vol. 63, No. 7, July 1, 2024
The licensee must control and maintain constant surveillance of
				licensed material that is in a controlled or unrestricted area and that is not
				in storage.
Stat. Auth.: ORS 453.635
Stats. Implemented: ORS 453.605 -
				  453.807
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0300 - Use of Process or Other Engineering Controls

Current through Register Vol. 63, No. 7, July 1, 2024
The licensee must use, to the extent practicable, process or
				other engineering controls (e.g., containment or ventilation) to control the
				concentrations of radioactive material in air.
Stat. Auth.: ORS 453.635
Stats. Implemented: ORS 453.605 -
				  453.807
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0310 - Use of Other Controls

Current through Register Vol. 63, No. 7, July 1, 2024
(1) When
			 it is not practicable 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 must, consistent with
			 maintaining the total effective dose equivalent ALARA, increase monitoring and
			 limit intakes by one or more of the following means:
(a) Control of access;
(b) Limitations of exposure times;
(c) Use of respiratory protection equipment;
			 or
(d) Other controls.
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0330 - Further Restrictions on the Use of Respiratory Protection Equipment

Current through Register Vol. 63, No. 7, July 1, 2024
The Authority may impose restrictions in addition to those in
				OAR
				333-120-0310 and
				333-120-0320,
				and
10 CFR
,
Part 20
,
Appendix A
to
				20.1001 to 20.2401 to:
(1) Ensure that
			 the respiratory protection program of the licensee is adequate to limit
			 exposures of individuals to airborne radioactive materials; and
(2) Limit the extent to which a licensee may
			 use respiratory protection equipment instead of process or other engineering
			 controls.
Stat. Auth.: ORS 453.635
Stats. Implemented: ORS 453.605 -
				  453.807
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0340 - Application for Use of Higher Assigned Protection factors

Current through Register Vol. 63, No. 7, July 1, 2024
The licensee shall obtain authorization from the Authority
				before using assigned protection factors in excess of those specified in  10 CFR
				Part 20, Appendix A. The Authority may authorize a licensee to use higher
				assigned protection factors on receipt of an application that:
(1) Describes the situation for which a need
			 exists for higher protection factors; and
(2) Demonstrates that the respiratory
			 protection equipment provides these higher protection factors under the
			 proposed conditions of use.
Stat. Auth: ORS 453.635
Stats. Implemented: ORS
				  453.635
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0400 - Caution Signs

Current through Register Vol. 63, No. 7, July 1, 2024
(1) Standard
			 radiation symbol: Unless otherwise authorized by the Authority, the symbol
			 prescribed by this division must use the colors magenta, purple, or black on
			 yellow background. The symbol prescribed by this division is the three-bladed
			 design: [Symbol not included. See ED. NOTE.]
(a) Cross-hatched area is to be magenta, or
			 purple, or black; and
(b) The
			 background is to be yellow.
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0410 - Posting Requirements

Current through Register Vol. 63, No. 7, July 1, 2024
(1) Posting
			 of radiation areas: The licensee or registrant must post each radiation area
			 with a conspicuous sign or signs bearing the radiation symbol and the words
			 "Caution, Radiation Area."
(2)
			 Posting of high radiation areas: The licensee or registrant must post each high
			 radiation area with a conspicuous sign or signs bearing the radiation symbol
			 and the words "Caution, High Radiation Area" or "Danger, High Radiation
			 Area."
(3) Posting of very high
			 radiation areas: The licensee or registrant must post each very high radiation
			 area with a conspicuous sign or signs bearing the radiation symbol and words
			 "Grave Danger, Very High Radiation Area."
(4) Posting of airborne radioactivity areas:
			 The licensee must post each airborne radioactivity area with a conspicuous sign
			 or signs bearing the radiation symbol and the words "Caution, Airborne
			 Radioactivity Area" or "Danger, Airborne Radioactivity Area."
(5) Posting of areas or rooms in which
			 licensed material is used or stored: The licensee must post each area or room
			 in which there is used or stored an amount of licensed material exceeding ten
			 times the quantity of such material specified in  10 CFR, Part 20, Appendix C to
			 20.1001 to 20.2401 with a conspicuous sign or signs bearing the radiation
			 symbol and the words "Caution, Radioactive Material(s)" or "Danger, Radioactive
			 Material(s)."
Publications: Publications referenced are available from the
				  agency.
Stat. Auth.: ORS 453.635
Stats. Implemented: ORS 453.605 -
				  453.807
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0420 - Exceptions to Posting Requirements

Current through Register Vol. 63, No. 7, July 1, 2024
(1) A licensee is not required to post
			 caution signs in areas or rooms containing radioactive materials for periods of
			 less than eight hours, if all of the following conditions are met:
(a) The materials are constantly attended
			 during these periods by an individual who takes the precautions necessary to
			 prevent the exposure of individuals to radiation or radioactive materials in
			 excess of the limits established in this division; and
(b) The area or room is subject to the
			 licensee's control.
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0430 - Labeling Containers

Current through Register Vol. 63, No. 7, July 1, 2024
(1) The
			 licensee must ensure that each container of licensed material bears a durable,
			 clearly visible label bearing the radiation symbol and the words "CAUTION,
			 RADIOACTIVE MATERIAL" or "DANGER, RADIOACTIVE MATERIAL." The label must also
			 provide sufficient information (such as the radionuclide(s) present, an
			 estimate of the quantity of radioactivity, the date for which the activity is
			 estimated, radiation levels, kinds of materials, and mass enrichment) to permit
			 individuals handling or using the containers, or working in the vicinity of the
			 containers, to take precautions to avoid or minimize exposures.
(2) Each licensee must, prior to removal or
			 disposal of empty uncontaminated containers to unrestricted areas, remove or
			 deface the radioactive material label or otherwise clearly indicate that the
			 container no longer contains radioactive materials.
(3) Each registrant must ensure that each
			 radiation machine is labeled in a conspicuous manner which cautions individuals
			 that radiation is produced when it is energized.
Stat. Auth.: ORS 453.635
Stats. Implemented: ORS 453.605 -
				  453.807
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0440 - Exemptions to Labeling Requirements

Current through Register Vol. 63, No. 7, July 1, 2024
A licensee is not required to label:
(1) Containers holding licensed material in
			 quantities less than the quantities listed in  10 CFR, Part 20, Appendix C to
			 20.1001 to 20.2401; or
(2)
			 Containers holding licensed material in concentrations less than those
			 specified in  10 CFR, Part 20, Table 3 of Appendix B to 20.1001 to 20.2401;
			 or
(3) Containers attended by an
			 individual who takes the precautions necessary to prevent the exposure of
			 individuals in excess of the limits established by this division; or
(4) Containers when they are in transport and
			 packaged and labeled in accordance with the regulations of the U.S. Department
			 of Transportation (49 CFR); or
NOTE:
Labeling of packages containing radioactive
				materials is required by the U.S. Department of Transportation (DOT) if the
				amount and type of radioactive material exceeds the limits for an excepted
				quantity or article as defined and limited by DOT regulations  49 CFR 173.403 (m) and (w) and 173.421-173.424.
(5) Containers that are accessible only to
			 individuals authorized to handle or use them, or to work in the vicinity of the
			 containers, if the contents are identified to these individuals by a readily
			 available written record (examples of containers of this type are containers in
			 locations such as water-filled canals, storage vaults, or hot cells). The
			 record must be retained as long as the containers are in use for the purpose
			 indicated on the records; or
(6)
			 Installed manufacturing or process equipment, such as reactor components,
			 piping, and tanks.
Stat. Auth.: ORS 453.635
Stats. Implemented: ORS 453.605 -
				  453.807
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0450 - Precautionary Procedures: Procedures for Receiving and Opening Packages

Current through Register Vol. 63, No. 7, July 1, 2024
(1) Each licensee
			 who expects to receive a package containing quantities of radioactive material
			 in excess of a Type A quantity, as defined in
			 49 CFR
			 173.435 Table of A1 and A2 Values for
			 Radionuclides, must make arrangements to receive:
(a) The package when the carrier offers it
			 for delivery; or
(b) Notification
			 of the arrival of the package at the carrier's terminal and to take possession
			 of the package expeditiously.
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0460 - Testing for Leakage or Contamination of Sealed Sources

Current through Register Vol. 63, No. 7, July 1, 2024
(1) The licensee in
			 possession of any sealed source must assure that:
(a) Each sealed source, except as specified
			 in section (2) of this rule is tested for leakage or contamination and the test
			 results are received before the sealed source is put into use unless the
			 licensee has a certificate from the transferor indicating that the sealed
			 source was tested within six months before transfer to the licensee;
			 and
(b) 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
			 Authority, an Agreement State, a Licensing State, or the U.S. Nuclear
			 Regulatory Commission; and
(c) 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 Authority, an Agreement State, a Licensing State, or
			 the U.S. Nuclear Regulatory Commission; and
(d) 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 must assure that the sealed source is tested for leakage or
			 contamination before further use; and
(e) Tests for leakage for all sealed sources,
			 except brachytherapy sources manufactured to contain radium-226, must be
			 capable of detecting the presence of 185 Bq (0.005 uCi) of radioactive material
			 on a test sample. Test samples must 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; and
(f) The test
			 for leakage for brachytherapy sources manufactured to contain radium-226 must
			 be capable of detecting an absolute leakage rate of 37 Bq (0.001 uCi) 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; and
(g) Tests for
			 contamination from radium-226 daughters must be taken on the interior surface
			 of brachytherapy source storage containers and must be capable of detecting the
			 presence of 185 Bq (0.005 uCi) of a radium daughter which has a half-life
			 greater than four days.
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0500 - General Requirements

Current through Register Vol. 63, No. 7, July 1, 2024
(1) A
			 licensee must dispose of licensed radioactive material only:
(a) By transfer to an authorized recipient as
			 provided in OAR
			 333-102-0330;
			 or
(b) By decay in storage;
			 or
(c) By release in effluents
			 within the limits in OAR
			 333-120-0520;
			 or
(d) As authorized under OAR
			 333-120-0520,
			 333-120-0530,
			 333-120-0540  and
			 333-120-0545.
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0510 - Method for Obtaining Approval of Proposed Disposal Procedures

Current through Register Vol. 63, No. 7, July 1, 2024
A licensee or applicant for a license may apply to the
				Authority for approval of proposed procedures, not otherwise authorized in the
				rules of this division, to dispose of licensed material generated in the
				licensee's activities. Each application must include:
(1) A description of the waste containing
			 licensed material to be disposed of, including the physical and chemical
			 properties important to risk evaluation, and the proposed manner and conditions
			 of waste disposal; and
(2) An
			 analysis and evaluation of pertinent information on the nature of the
			 environment; and
(3) The nature and
			 location of other potentially affected licensed and unlicensed facilities;
			 and
(4) Analyses and procedures to
			 ensure that doses are maintained ALARA and within the dose limits in this
			 division.
Stat. Auth.: ORS 453.635
Stats. Implemented: ORS 453.605 -
				  453.807
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0520 - Disposal by Release into Sanitary Sewerage

Current through Register Vol. 63, No. 7, July 1, 2024
(1) A licensee may discharge licensed
			 material into sanitary sewerage if each of the following conditions is
			 satisfied:
(a) The material is readily
			 soluble (or is readily dispersible biological material) in water; and
(b) The quantity of licensed or other
			 radioactive material that the licensee releases into the sewer in one month
			 divided by the average monthly volume of water released into the sewer by the
			 licensee does not exceed the concentration listed in  10 CFR Part 20  Table 3 of
			 Appendix B to 20.1001 to 20.2401; and
(c) If more than one radionuclide is
			 released, the following conditions also must be satisfied:
(A) The licensee must determine the fraction
			 of the limit in  10 CFR Part 20  Table 3 of Appendix B to 20.1001 to 20.2401
			 represented by discharges into sanitary sewerage by dividing the actual monthly
			 average concentration of each radionuclide released by the licensee into the
			 sewer by the concentration of that radionuclide listed in  10 CFR Part 20  Table
			 3 of Appendix B to 20.1001 to 20.2401; and
(B) The sum of the fractions for each
			 radionuclide required by paragraph (1)(c)(A) of this rule does not exceed
			 unity; and
(d) The total
			 quantity of licensed and other radioactive material that the licensee releases
			 into the sanitary sewerage system in a year does not exceed 185 GBq (5 Curies)
			 of hydrogen-3, 37 GBq (1 Curie) of carbon-14, and 37 GBq (1 Curie) of all other
			 radioactive materials combined.
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0530 - Treatment of Disposal by Incineration

Current through Register Vol. 63, No. 7, July 1, 2024
A licensee may treat or dispose of licensed material by
				incineration only in the amounts and forms specified in OAR
				333-120-0540 or as specifically approved by the Authority pursuant to OAR
				333-120-0510.
Stat. Auth.: ORS 453.635
Stats. Implemented: ORS 453.605 -
				  453.807
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0540 - Disposal of Specific Wastes

Current through Register Vol. 63, No. 7, July 1, 2024
(1) A
			 licensee may dispose of the following licensed material as if it were not
			 radioactive:
(a)1.85 kBq (0.05 uCi), or less,
			 of hydrogen-3 or carbon-14 per gram of medium used for liquid scintillation
			 counting; and
(b)1.85 kBq (0.05
			 uCi), or less, of hydrogen-3 or carbon-14 per gram of animal tissue, averaged
			 over the weight of the entire animal.
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0545 - Disposal of Certain Byproduct Material

Current through Register Vol. 63, No. 7, July 1, 2024
(1) Licensed material as defined in
			 subsections (c) and (d) of the definition of byproduct material outlined in OAR
			 333-120-0015(14)
 
			 may be disposed of in accordance with   10 CFR Part 61   even though it is not
			 defined as low-level radioactive waste. Therefore, any licensed byproduct
			 material being disposed of at a facility or transferred for ultimate disposal
			 at a facility licensed under 10 CFR Part 61 of this chapter must meet the
			 requirements of OAR
			 333-120-0550.
(2) A licensee may dispose of byproduct
			 material as defined in sections (c) and (d) of the definition of byproduct
			 material outlined in OAR
			 333-120-0015(14)
 
			 at a disposal facility authorized in accordance with any federal or state solid
			 or hazardous waste laws including the Solid Waste Disposal Act as authorized
			 under the Energy Policy Act of 2005.
Stat. Auth.: ORS 453.635
Stats. Implemented: ORS 453.605 -
				  453.807
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0550 - Transfer for Disposal and Manifests

Current through Register Vol. 63, No. 7, July 1, 2024
(1) The requirements of this rule and  10 CFR
			 Part 20  Appendix G to 20.1001 to 20.2401 are designed to control transfers of
			 low-level radioactive waste intended for disposal at a land disposal facility
			 (as defined in  10 CFR Part 61), establish a manifest tracking system, and
			 supplement existing requirements concerning transfers and recordkeeping for
			 those wastes.
(2) Each shipment of
			 radioactive waste intended for disposal at a licensed land disposal facility
			 must be accompanied by a shipment manifest as specified in  10 CFR Part 20
			  section I of Appendix G to 20.1001 to 20.2401.
(3) Each shipment manifest must include a
			 certification by the waste generator as specified in   10 CFR Part 20   section II
			 of Appendix G to 20.1001 to 20.2401.
(4) Each person involved in the transfer for
			 disposal and disposal of waste, including the waste generator, waste collector,
			 waste processor, and disposal facility operator, must comply with the
			 requirements specified in 10 CFR Part 20 section III of Appendix G to 20.1001
			 to 20.2401.
(5) Any licensee
			 shipping byproduct material defined in subsections (c) and (d) of the
			 definition of byproduct material outlined in OAR
			 333-120-0015(14)
 
			 intended for ultimate disposal at a land disposal facility licensed under  10
			 CFR Part 61  must document the information required on the Nuclear Regulatory
			 Commission's Uniform Low-Level Radioactive Waste Manifest and transfer this
			 recorded manifest information to the intended consignee in accordance with  10
			 CFR Part 20, Appendix G
Appendices referenced are available from the
				  agency.
Stat. Auth.: ORS 453.635
Stats. Implemented: ORS 453.605 -
				  453.807
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0560 - Compliance with Environmental and Health Protection Regulations

Current through Register Vol. 63, No. 7, July 1, 2024
Nothing in chapter 333 divisions 100 through 123 relieves the
				licensee or registrant from complying with other applicable Federal, State, and
				local regulations or rules governing any other toxic or hazardous properties of
				materials that may be disposed of under division 333-120.
Stat. Auth.: ORS 453.635
Stats. Implemented: ORS 453.605 -
				  453.807
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0600 - General Provisions

Current through Register Vol. 63, No. 7, July 1, 2024
(1) Each
			 licensee must use the SI units becquerel, gray, sievert and coulomb per
			 kilogram, or the special units curie, rad, rem, including multiples and
			 subdivisions, and must clearly indicate the units of all quantities on records
			 required by this division.
(2) The
			 licensee must make a clear distinction among the quantities entered on the
			 records required by this division (e.g. total effective dose equivalent,
			 shallow-dose equivalent, lens dose equivalent, deep-dose equivalent, committed
			 effective dose equivalent).
Stat. Auth.: ORS 453.635
Stats. Implemented: ORS 453.605 -
				  453.807
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0610 - Records of Radiation Protection Programs

Current through Register Vol. 63, No. 7, July 1, 2024
(1) Each licensee must maintain records of
			 the radiation protection program, including:
(a) The provisions of the program;
			 and
(b) Audits and other reviews of
			 program content and implementation.
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0620 - Records of Surveys and Leak Tests

Current through Register Vol. 63, No. 7, July 1, 2024
(1) Each licensee or registrant must maintain
			 records showing the results of surveys, sealed source leak tests, and
			 calibrations required by OAR
			 333-120-0200,
			 333-120-0450(2)
 
			 and
			 333-120-0460.
			 The licensee or registrant must retain these records in accordance with
			 333-100-0057.
(2) The licensee or registrant must retain
			 each of the following records until the Authority terminates each pertinent
			 license or registration requiring the record:
(a) Records of the results of surveys to
			 determine the dose from external sources and used, in the absence of or in
			 combination with individual monitoring data, in the assessment of individual
			 dose equivalents. This includes records of survey results to determine the dose
			 from external sources and used, in the absence of or in combination with
			 individual monitoring data, in the assessment of individual dose equivalents
			 required under the standards for protection against radiation in effect prior
			 to January 1, 1994; and
(b) Records
			 of the results of measurements and calculations used to determine individual
			 intakes of radioactive material and used in the assessment for internal dose.
			 This includes records documenting the results of measurements and calculations
			 used to determine individual intakes of radioactive material and used in the
			 assessment of internal dose required under the standards for protection against
			 radiation in effect prior to January 1, 1994; and
(c) Records showing the results of air
			 sampling, surveys, and bioassays required pursuant to OAR
			 333-120-0320(1)(c)(A)
			 and (B). This includes records documenting
			 the results of air sampling, surveys, and bioassays required under the
			 standards for protection against radiation in effect prior to January 1, 1994;
			 and
(d) Records of the results of
			 measurements and calculations used to evaluate the release of radioactive
			 effluents to the environment. This includes records documenting the results of
			 measurements and calculations used to evaluate the release of radioactive
			 effluents to the environment required under the standards for protection
			 against radiation in effect prior to January 1, 1994.
Oregon Administrative Rules › Chapter 333 - OREGON HEALTH AUTHORITY, PUBLIC HEALTH DIVISION › Division 120 - STANDARDS FOR PROTECTION AGAINST RADIATION › Section 333-120-0630 - Determination of Prior Occupational Dose

Current through Register Vol. 63, No. 7, July 1, 2024
(1) For each individual likely to receive, in
			 a year, an occupational dose requiring monitoring pursuant to OAR
			 333-120-0210,
			 the licensee or registrant must:
(a)
			 Determine the occupational radiation dose received during the current year;
			 and
(b) Attempt to obtain the
			 records of lifetime cumulative occupational radiation dose.