42 U.S.C. § 10263

Current through P.L. 118-106 (published on www.congress.gov on 10/04/2024)
Section 10263 - Functions

The Board shall evaluate the technical and scientific validity of activities undertaken by the Secretary after December 22, 1987, including-

(1) site characterization activities; and
(2) activities relating to the packaging or transportation of high-level radioactive waste or spent nuclear fuel.

42 U.S.C. § 10263

Pub. L. 97-425, title V, §503, as added Pub. L. 100-202, §101(d) [title III], Dec. 22, 1987, 101 Stat. 1329-104, 1329-121; Pub. L. 100-203, title V, §5051, Dec. 22, 1987, 101 Stat. 1330-249.

EDITORIAL NOTES

CODIFICATION Pub. L. 100-202 and Pub. L. 100-203 added identical sections.

Secretary
The term "Secretary" means the Secretary of Energy.
high-level radioactive waste
The term "high-level radioactive waste" means-(A) the highly radioactive material resulting from the reprocessing of spent nuclear fuel, including liquid waste produced directly in reprocessing and any solid material derived from such liquid waste that contains fission products in sufficient concentrations; and(B) other highly radioactive material that the Commission, consistent with existing law, determines by rule requires permanent isolation.
site characterization
The term "site characterization" means-(A) siting research activities with respect to a test and evaluation facility at a candidate site; and(B) activities, whether in the laboratory or in the field, undertaken to establish the geologic condition and the ranges of the parameters of a candidate site relevant to the location of a repository, including borings, surface excavations, excavations of exploratory shafts, limited subsurface lateral excavations and borings, and in situ testing needed to evaluate the suitability of a candidate site for the location of a repository, but not including preliminary borings and geophysical testing needed to assess whether site characterization should be undertaken.
spent nuclear fuel
The term "spent nuclear fuel" means fuel that has been withdrawn from a nuclear reactor following irradiation, the constituent elements of which have not been separated by reprocessing.