38 M.R.S. § 1455 Nuclear Facility Decommissioning Cleanup

• Library: Maine Revised Statutes
• Edition: 2023
• Currency: Current through 131st (2023-2024) Legislature Chapter 486
• Year: 2023
• Citation: 38 M.R.S. § 1455

1.Definitions. As used in this section, unless the context otherwise indicates, the following terms have the following meanings.

A. "Average member of the critical group" means a member of the critical group who is subjected to the most likely exposure situation based on prudently conservative exposure assumptions and parameter values within the model calculations. [ 1999, c. 739, § 3 (NEW) .]

B. "Critical group" means the group of individuals reasonably expected to receive the greatest exposure to residual radioactivity for any applicable set of circumstances. [ 1999, c. 739, § 3 (NEW) .]

C. "Nuclear facility owner" means the owner of a nuclear power plant or decommissioned nuclear power plant in the State. [ 1999, c. 739, § 3 (NEW) .]

D. "Total effective dose equivalent" has the same meaning as in 10 Code of Federal Regulations, Section 20.1003, as in effect on January 1, 2000. [ 1999, c. 739, § 3 (NEW) .]

[ 1999, c. 739, § 3 (NEW) .]

2.Radiation dose standard. The site at which the decommissioning of a nuclear power plant has been completed must meet the following standards, as determined by the department:

A. The residual radioactivity distinguishable from background radiation results in a total effective dose equivalent to an average member of the critical group of not more than 10 millirems, or 0.10 millisievert, per year, including that from groundwater sources of drinking water; and [ 1999, c. 739, § 3 (NEW) .]

B. The residual radioactivity distinguishable from background radiation in groundwater sources of drinking water results in a total effective dose equivalent of not more than 4 millirems, or 0.04 millisievert, per year to the average member of the critical group. [ 1999, c. 739, § 3 (NEW) .]

A nuclear facility owner shall demonstrate compliance with this subsection using actual measurements and the analytic methodology approved by the United States Nuclear Regulatory Commission and supplemented by modeling the effects of engineering controls that have been designed to reduce exposure.