10 C.F.R. Subpart B—Site Suitability Determination, Methods, and Criteria
Title 10 - Energy
(a) The scope of this subpart includes the following for both the preclosure and postclosure periods: (1) The bases for the suitability determination for the Yucca Mountain site as a location for a geologic repository; (2) The suitability evaluation methods for applying the site suitability criteria to a geologic repository at the Yucca Mountain site; and (3) The site suitability criteria that DOE will apply in accordance with section 113(b)(1)(A)(iv) of the NWPA. (b) DOE will seek NRC concurrence on any future revisions to this subpart. DOE will evaluate whether the Yucca Mountain site is suitable for the location of a geologic repository on the basis of the preclosure and postclosure determinations described in §§963.12 and 963.15. If DOE's evaluation of the Yucca Mountain site for the location of a geologic repository under §§963.12 and 963.15 shows that the geologic repository is likely to meet the applicable radiation protection standards for the preclosure and postclosure periods, then DOE may determine that the site is a suitable location for the development of such a repository. DOE will apply the method and criteria described in §§963.13 and 963.14 to evaluate the suitability of the Yucca Mountain site for the preclosure period. If DOE finds that the results of the preclosure safety evaluation conducted under §963.13 show that the Yucca Mountain site is likely to meet the applicable radiation protection standard, DOE may determine the site suitable for the preclosure period. (a) DOE will evaluate preclosure suitability using a preclosure safety evaluation method. DOE will evaluate the performance of the geologic repository at the Yucca Mountain site using the method described in paragraph (b) of this section and the criteria in §963.14. DOE will consider the performance of the system in terms of the criteria to evaluate whether the geologic repository is likely to comply with the applicable radiation protection standard. (b) The preclosure safety evaluation method, using preliminary engineering specifications, will assess the adequacy of the repository facilities to perform their intended functions and prevent or mitigate the effects of postulated Category 1 and 2 event sequences. The preclosure safety evaluation will consider: (1) A preliminary description of the site characteristics, the surface facilities and the underground operating facilities; (2) A preliminary description of the design bases for the operating facilities and a preliminary description of any associated limits on operation; (3) A preliminary description of potential hazards, event sequences, and their consequences; and (4) A preliminary description of the structures, systems, components, equipment, and operator actions intended to mitigate or prevent accidents. DOE will evaluate preclosure suitability using the following criteria: (a) Ability to contain radioactive material and to limit releases of radioactive materials; (b) Ability to implement control and emergency systems to limit exposure to radiation; (c) Ability to maintain a system and components that perform their intended safety functions; and (d) Ability to preserve the option to retrieve wastes during the preclosure period. DOE will apply the method and criteria described in §§963.16 and 963.17 to evaluate the suitability of the Yucca Mountain site for the postclosure period. If DOE finds that the results of the total system performance assessments conducted under §963.16 show that the Yucca Mountain site is likely to meet the applicable radiation protection standard, DOE may determine the site suitable for the postclosure period. (a) DOE will evaluate postclosure suitability using the total system performance assessment method. DOE will conduct a total system performance assessment to evaluate the ability of the geologic repository to meet the applicable radiation protection standard under the following circumstances: (1) DOE will conduct a total system performance assessment to evaluate the ability of the Yucca Mountain disposal system to limit radiological doses and radionuclide concentrations in the case where there is no human intrusion into the repository. DOE will model the performance of the Yucca Mountain disposal system using the method described in paragraph (b) of this section and the criteria in §963.17. DOE will consider the performance of the system in terms of the criteria to evaluate whether the Yucca Mountain disposal system is likely to comply with the applicable radiation protection standard. (2) DOE will conduct a separate total system performance assessment to evaluate the ability of the Yucca Mountain disposal system to limit radiological doses in the case where there is a human intrusion as specified by 10 CFR 63.322. DOE will model the performance of the Yucca Mountain disposal system using the method described in paragraph (b) of this section and the criteria in §963.17. If required by applicable NRC regulations regarding a human intrusion standard, §63.321, DOE will consider the performance of the system in terms of the criteria to evaluate whether the Yucca Mountain disposal system is likely to comply with the applicable radiation protection standard. (b) In conducting a total system performance assessment under this section, DOE will: (1) Include data related to the suitability criteria in §963.17; (2) Account for uncertainties and variabilities in parameter values and provide the technical basis for parameter ranges, probability distributions, and bounding values; (3) Consider alternative models of features and processes that are consistent with available data and current scientific understanding, and evaluate the effects that alternative models would have on the estimated performance of the Yucca Mountain disposal system ; (4) Consider only events that have at least one chance in 10,000 of occurring over 10,000 years; (5) Provide the technical basis for either inclusion or exclusion of specific features, events, and processes of the geologic setting, including appropriate details as to magnitude and timing regarding any exclusions that would significantly change the dose to the reasonably maximally exposed individual; (6) Provide the technical basis for either inclusion or exclusion of degradation, deterioration, or alteration processes of engineered barriers, including those processes that would adversely affect natural barriers, (such as degradation of concrete liners affecting the pH of ground water or precipitation of minerals due to heat changing hydrologic processes), including appropriate details as to magnitude and timing regarding any exclusions that would significantly change the dose to the reasonably maximally exposed individual; (7) Provide the technical basis for models used in the total system performance assessment such as comparisons made with outputs of detailed process-level models and/or empirical observations (for example, laboratory testing, field investigations, and natural analogs); (8) Identify natural features of the geologic setting and design features of the engineered barrier system important to isolating radioactive waste; (9) Describe the capability of the natural and engineered barriers important to isolating radioactive waste, taking into account uncertainties in characterizing and modeling such barriers; (10) Provide the technical basis for the description of the capability of the natural and engineered barriers important to isolating radioactive waste; (11) Use the reference biosphere and reasonably maximally exposed individual assumptions specified in applicable NRC regulations; and (12) Conduct appropriate sensitivity studies. (a) DOE will evaluate the postclosure suitability of a geologic repository at the Yucca Mountain site through suitability criteria that reflect both the processes and the models used to simulate those processes that are important to the total system performance of the geologic repository. The applicable criteria are: (1) Site characteristics, which include: (i) Geologic properties of the site—for example, stratigraphy, rock type and physical properties, and structural characteristics; (ii) Hydrologic properties of the site—for example, porosity, permeability,moisture content, saturation, and potentiometric characteristics; (iii) Geophysical properties of the site—for example, densities, velocities and water contents, as measured or deduced from geophysical logs; and (iv) Geochemical properties of the site—for example, precipitation, dissolution characteristics, and sorption properties of mineral and rock surfaces. (2) Unsaturated zone flow characteristics, which include: (i) Climate—for example, precipitation and postulated future climatic conditions; (ii) Infiltration—for example, precipitation entering the mountain in excess of water returned to the atmosphere by evaporation and plant transpiration; (iii) Unsaturated zone flux—for example, water movement through the pore spaces, or flowing along fractures or through perched water zones above the repository; (iv) Seepage—for example, water dripping into the underground repository openings from the surrounding rock. (3) Near field environment characteristics, which include: (i) Thermal hydrology—for example, effects of heat from the waste on water flow through the site, and the temperature and humidity at the engineered barriers. (ii) Near field geochemical environment—for example, the chemical reactions and products resulting from water contacting the waste and the engineered barrier materials. (4) Engineered barrier system degradation characteristics, which include: (i) Engineered barrier system component performance—for example, drip shields, backfill, coatings, or chemical modifications, and (ii) Waste package degradation—for example, the corrosion of the waste package materials within the near-field environment. (5) Waste form degradation characteristics, which include: (i) Cladding degradation—for example, corrosion or break-down of the cladding on the spent fuel pellets; (ii) Waste form dissolution—for example, the ability of individual radionuclides to dissolve in water penetrating breached waste packages. (6) Engineered barrier system degradation, flow, and transport characteristics, which include: (i) Colloid formation and stability—for example, the formation of colloidal particles and the ability of radionuclides to adhere to these particles as they may migrate through the remaining barriers; and (ii) Engineered barrier transport—for example, the movement of radionuclides dissolved in water or adhering to colloidal particles to be transported through the remaining engineered barriers and in the underlying unsaturated zone. (7) Unsaturated zone flow and transport characteristics, which include: (i) Unsaturated zone transport—for example, the movement of water with dissolved radionuclides or colloidal particles through the unsaturated zone underlying the repository, including retardation mechanisms such as sorption on rock or mineral surfaces; (ii) Thermal hydrology—for example, effects of heat from the waste on water flow through the site. (8) Saturated zone flow and transport characteristics, which include: (i) Saturated zone transport—for example, the movement of water with dissolved radionuclides or colloidal particles through the saturated zone underlying and beyond the repository, including retardation mechanisms such as sorption on rock or mineral surfaces; and (ii) Dilution—for example, diffusion of radionuclides into pore spaces, dispersion of radionuclides along flow paths, and mixing with non-contaminated ground water. (9) Biosphere characteristics, which include: (i) Reference biosphere and reasonably maximally exposed individual—for example, biosphere water pathways, location and behavior of reasonably maximally exposed individual; and (ii) Biosphere transport and uptake—for example, the consumption of ground or surface waters through direct extraction or agriculture, including mixing with non-contaminated waters and exposure to contaminated agricultural products. (b) DOE will evaluate the postclosure suitability of the Yucca Mountain disposal system using criteria that consider disruptive processes and events important to the total system performance of the geologic repository. The applicable criteria related to disruptive processes and events include: (1) Volcanism—for example, the probability and potential consequences of a volcanic eruption intersecting the repository; (2) Seismic events—for example, the probability and potential consequences of an earthquake on the underground facilities or hydrologic system; and (3) Nuclear criticality—for example, the probability and potential consequences of a self-sustaining nuclear reaction as a result of chemical or physical processes affecting the waste either in or after release from breached waste packages.
Title 10: Energy
PART 963—YUCCA MOUNTAIN SITE SUITABILITY GUIDELINES
Subpart B—Site Suitability Determination, Methods, and Criteria
§ 963.10 Scope.
§ 963.11 Suitability determination.
§ 963.12 Preclosure suitability determination.
§ 963.13 Preclosure suitability evaluation method.
§ 963.14 Preclosure suitability criteria.
§ 963.15 Postclosure suitability determination.
§ 963.16 Postclosure suitability evaluation method.
§ 963.17 Postclosure suitability criteria.
