Oregon Administrative Rules › Chapter 345 - DEPARTMENT OF ENERGY, ENERGY FACILITY SITING COUNCIL › Division 1 - GENERAL PROVISIONS › Section 345-001-0010 - Definitions

Current through Register Vol. 63, No. 7, July 1, 2024
In this chapter, unless the context requires otherwise or a
				term is specifically defined within a division or a rule, terms have the
				meaning provided in ORS
				469.300 and the following
				definitions:
(1) "Analysis area" means
			 the area or areas specifically described in the project order issued under OAR
			 345-015-0160(1), containing resources that the proposed facility may
			 significantly affect. The analysis area is the area for which the applicant
			 must describe the proposed facility's impacts in the application for a site
			 certificate. A proposed facility might have different analysis areas for
			 different types of resources. For the purpose of submitting an application for
			 a site certificate in an expedited review granted under 345-015-0300  or
			 345-015-0310, the analysis areas are the study areas defined in this rule,
			 subject to modification in the project order.
(2) "Applicant" as defined in ORS
			 469.300 or, if an application
			 has not been submitted, a person who has submitted, or intends to submit, a
			 notice of intent or a request for expedited review.
(3) "Background radiation" means the direct
			 radiation (gamma) and concentrations of potential radionuclide contaminants in
			 construction materials and the environment in the vicinity of the plant not
			 associated with the nuclear operation and retirement of the facility.
			 Background must be determined as follows:
(a)
			 For direct radiation, the results of any background measurements taken prior to
			 operation of the facility must be provided and 6 to 10 measurements must be
			 taken in areas in the vicinity of the site with materials and/or geological
			 formations representative of the site that have not been affected by the
			 operation and retirement of the facility. Background must be calculated at the
			 average and at the 95% confidence level.
(b) Environmental samples must be taken for
			 soil, sediment, water, and other materials present at the facility site that
			 could have been affected by facility operations and retirement. Measurements
			 for these samples must be calculated at the average and 95% confidence levels,
			 based on 6 to 10 measurements. Background environmental samples must be taken
			 at locations on site or in the immediate vicinity of the site which are
			 unaffected by plant operations. Background must be calculated at the average
			 and 95% confidence levels, based on 6 to 10 measurements at each
			 location.
(c) For construction
			 material such as concrete, asphalt, block, brick and other materials used to
			 construct the buildings and systems at the site, representative samples of
			 materials unaffected by site operations must be selected and surveyed. Six to
			 ten samples of each material must be taken to determine the level of naturally
			 occurring and artificially induced concentrations of naturally occurring
			 radioactivity present. Measurements must include direct radiation (beta-gamma
			 and alpha), wipes and qualitative and quantitative laboratory analyses.
			 Concentrations of fission and activation products from historical fallout must
			 be characterized as well.
(d) All
			 measurements must be made using appropriate instruments, properly calibrated,
			 and in sufficient number to determine compliance with
			 requirements.