The University of Colorado ALARA Program

The University of Colorado maintains a Radioactive Materials license through the Colorado Department of Public Health and Environment (CDPHE).  The ALARA philosophy, or As Low As Reasonably Achievable, is a regulatory requirement for all radiation protection programs.  The University actively works to reduce dose and exposure due to radiation in our radiation safety program.  This reduction in dose and exposure should be accomplished in accordance with ALARA with an emphasis on protecting individuals at the University, including members of the general public.

ALARA Levels

 

	Level I	Level II	Level III
Whole Body Dose:	50 mrem	300 mrem	500 mrem
Skin Dose:	50 mrem	500 mrem	5,000 mrem
Lens of the Eye Dose:	50 mrem	500 mrem	1,500 mrem
Extremity Dose:	50 mrem	500 mrem	5,000 mrem
Individual Organ Dose:	50 mrem	500 mrem	5,000 mrem

Actions taken:

1. Dose/Exposure less than Level I – No action unless deemed necessary by RSO.
2. Dose/Exposure equal to or greater than Level I - Notification of employee and the RSC.  A copy of this notification is maintained in the individual’s dosimetry file.
3. Dose/Exposure equal to or greater than Level II - Notification of employee and the RSC.  A copy of this notification is maintained in the individual’s dosimetry file.  The employee is encouraged to investigate and evaluate techniques for reducing future exposure in their work.  Assistance may be provided by Health Physics.
4. Dose/Exposure equal to or greater than Level III (10% of Annual Limit) - Notification of employee and the RSC.  A copy of this notification is maintained in the individual’s dosimetry file.  An investigation will be performed by the employee and Health Physics.  A written report explaining the exposure will be provided for their dosimetry file and the RSC.

 

	Level I	Level II	Level III
Thyroid (Iodine-125):	60 nCi	120 nCi	500 nCi
Thyroid (Iodine-131):	20 nCi	40 nCi	140 nCi
Urinalysis (Tritium):	10 uCi/liter	28 uCi/liter	50 uCi/liter

Actions taken:

1. Exposure less than Level I – No action unless deemed necessary by Radiation Safety Officer.  A copy of the bioassay report is given to the employee and placed in his/her dosimetry file.  Bioassays will be performed at the following intervals:
•         For Radioiodines -- Within one week of using more than 50 mCi of I-125 or I-131 in a single operation (or within one week of using 10 mCi in a non-contained form).
•         For Tritium -- Within one week of using greater than 100 mCi of tritium in a single operation.  For a continuous experiment using this amount of tritium, bioassays will be performed weekly (on the same day of each week, if possible) until it can be assessed that urine concentrations do not exceed this level in a calendar quarter.  After that, bioassays may be taken monthly (on the same day of each month, if possible) as long as this level is maintained.
2. Exposure equal to or greater than Level I - Notification of employee and the Radiation Safety Committee.  A copy of this notification is maintained in the individual’s dosimetry file.  The employee is encouraged to discuss experimental protocols with Health Physics to seek ways of reducing future exposures.
3. Exposure equal to or greater than Level II - Notification of employee and the Radiation Safety Committee.  A copy of this notification is maintained in the individual’s dosimetry file.  In addition,
•         For Radioiodines --
• An investigation by Health Physics personnel will examine operations involved, including ventilation surveys, to determine the causes of exposure and to evaluate the potential for further exposures.
• If this investigation indicates that further work in the area might result in exposure of the employee to concentrations that are excessive, the employee will be restricted from further exposure until the source of exposure is discovered and corrected.
• Following the investigation, corrective actions that will eliminate or lower the potential for further exposures will be implemented and documented.
• A repeat bioassay will be performed within one week of the previous measurement to confirm the effectiveness of the corrective action and/or to verify internal radioiodines present.
•         For Tritium -- If this level is exceeded in the course of a calendar quarter, a written report shall be sent to  the Director of CDPHE within 30 days of the end of the quarter.  This report will contain the results of all urinalyses for the individual during the calendar quarter, the cause of the excessive concentrations, and the corrective steps taken or planned to prevent recurrence.
4. Exposure equal to or greater than Level III - Notification of employee and the Radiation Safety Committee. A copy of this notification is maintained in the individual’s dosimetry file.  In addition,
•         For Radioiodines --
• The employee will be prevented from any further handling of radioiodine until the thyroid burden is below this limit.
• All investigative steps listed in number 3, above, will be carried out.
• The employee will be sent to an appropriate medical facility for evaluation of therapeutic methods to accelerate removal of the radioiodine from the body.
• Repeat bioassays shall be conducted at one-week intervals until the thyroid burden is below 0.12 uCi of I-125 or 0.04 uCi of I-131.
•         For Tritium -- If this level is exceeded in a single bioassay, a written report shall be sent to the Director of CDPHE within 7 days of the receipt of the bioassay results.
5. If any bioassay shows dose levels exceeding the limits listed in RH 4.52 of the Colorado Rules and Regulations Pertaining to Radiation Control, the notification requirements will be completed, with follow-up written reports to CDPHE within 30 days.

 

 

                 Total Effective Dose Equivalent --
                  IMMEDIATE NOTIFICATION OF CDPHE:  25 rem
                  24-HOUR NOTIFICATION OF CDPHE:  5 rem

                Total Organ Dose Equivalent --
                  IMMEDIATE NOTIFICATION OF CDPHE:  250 rad
                  24-HOUR NOTIFICATION OF CDPHE:  50 rem

 

	Level I	Level II
Tier I source/wipe:	0.001 uCi	0.005 uCi

1. Contamination less than Level I – No action taken unless deemed necessary by RSO.
2. Contamination equal to or greater than Level I - Notification of user and the RSC.  It is recommended that the source be monitored more frequently and possibly removed from circulation,  repaired, or disposed of as radioactive waste.
3. Contamination equal to or greater than Level II - Notification of user, the RSC, and CDPHE (RH 4.58).  The source is removed from use for repair or disposal by Health Physics personnel.

 

	Level I	Level II
dpm/100 cm2	100	1,000

1. Contamination less than Level I – No action taken unless deemed necessary by RSO.
2. Contamination equal to or greater than Level I - Notification of the licensee/lab and RSC.  Immediate clean-up of the area is recommended.  Documentation is maintained by the laboratory involved.
3. Contamination equal to or greater than Level II - Notification of  the licensee/lab and RSC.  Immediate clean-up is required and the area is re-surveyed by Health Physics staff.  Documentation is maintained by the laboratory involved and Health Physics.

 

	Level I	Level II	Level III
dpm/100 cm2 or per ml	100	1,000	10,000

• Contamination less than Level I – No action taken unless deemed necessary by RSO.
• Contamination equal to or greater than Level I - Notification of the licensee/lab and the RSO.
• Contamination equal to or greater than Level II - Notification of  the licensee/lab and the RSO.  Defrosting or clean-up of the freezer is recommended.
• Contamination equal to or greater than Level III - Notification of the licensee/lab and the RSC.  Defrosting or clean-up of the freezer is required and the freezer is re-surveyed by Health Physics personnel.

Actions taken:
1. Contamination/Exposure rate less than Level I on vial or box – No action taken unless  deemed necessary by RSO.  Package is delivered to laboratory.
2. Contamination equal to or greater than Level I on vial - Notification of laboratory and the RSC.  The laboratory is reminded of safe handling practices and has the right to refuse the package. Contamination equal to or greater than Level I on box - An alternate box with appropriate certification and labeling may be used to transport the package, provided the vial is not contaminated.  The contaminated box is disposed of as radioactive waste.
3. Contamination equal to or greater than Level II on vial - Notification of laboratory and the RSC.  The package is not delivered to the laboratory but is instead disposed of at Health Physics as radioactive waste.  Arrangements for replacement are the responsibility of the laboratory involved.
4. Exposure rate equal to or greater than Level II on box - CDPHE is contacted for further instruction before the box is opened by Health Physics staff.

Table of Contents

Appendices List