10-144-220 Me. Code R. § G-C-75

Current through 2024-51, December 18, 2024

Section 144-220-G-C-75 - Release of individuals containing unsealed radioactive material or implants containing radioactive material

A. A licensee may authorize the release from its control of any individual who has been administered unsealed radioactive material or implants containing radioactive material if the total effective dose equivalent to any other individual from exposure to the released individual is not likely to exceed 5 mSv (0.5 rem).¹

B. The licensee shall provide the released individual, or the individual's parent or guardian, with instructions, including written instructions, on actions recommended to maintain doses to other individuals as low as is reasonably achievable if the total effective dose equivalent to any other individual is likely to exceed 1 mSv (0.1 rem). If the total effective dose equivalent to a nursing infant or child could exceed 1 mSv (0.1 rem) assuming there were no interruption of breast-feeding, the instructions must also include:

(1) Guidance on the interruption or discontinuation of breast-feeding; and

(2) Information on the potential consequences, if any, of failure to follow guidance.

C. Release of the individual must be approved by a person listed as an authorized user on the Agency license, and who is approved for the type of radioactive material use for which the patient being released has received.

D. The licensee shall maintain a record of the basis for authorizing the release of an individual in accordance with G.2075.A.

E. The licensee shall maintain a record of instructions provided to a breast-feeding female in accordance with G.2075.B.

F. The licensee shall immediately notify the Agency in accordance with G.3075. A if a patient departs prior to an authorized release.

G. The licensee shall notify the Agency in accordance with G.3075.B

(1) When it is aware that a patient containing radioactive material dies; and

(2) If it is possible that any individual could receive exposures in excess of 5 millisievert (500 mrem) as a result of the deceased's body.

¹ U.S. Nuclear Regulatory Commission Regulatory Guide NUREG-1556, Vol. 9, "Consolidated Guidance About Materials Licenses: Program-Specific Guidance About Medical Licenses," describes methods for calculating doses to other individuals and contains tables of activities not likely to cause doses exceeding 5 mSv (0.5 rem).

10-144 C.M.R. ch. 220, § G-C-75