ML19029A617

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Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 11 - Radioactive Waste Management
ML19029A617
Person / Time
Site: Clinch River
Issue date: 01/18/2019
From: James Shea
Tennessee Valley Authority
To:
Office of New Reactors
Fetter A
References
TVACLINCHRIVERESP, TVACLINCHRIVERESP.SUBMISSION.5, CRN.PART02, CRN.PART02.2
Download: ML19029A617 (27)
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Text

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report CHAPTER 11 TABLE OF CONTENTS Section Title Page CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT ................................................... 11.2-1 11.2.3 Liquid Radioactive Releases ....................................................... 11.2-1 11.2.3.1 Exposure Pathways .................................................. 11.2-1 11.2.3.2 Liquid Pathway Doses .............................................. 11.2-2 11.2.4 References ................................................................................. 11.2-3 11.3.3 Gaseous Radioactive Releases .................................................. 11.3-1 11.3.3.1 Exposure Pathways .................................................. 11.3-1 11.3.3.2 Gaseous Pathway Doses ......................................... 11.3-2 11.3.4 References ................................................................................. 11.3-2 11-i Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report CHAPTER 11 LIST OF TABLES Number Title 11.2-1 Liquid Effluent Dose Calculation Parameters 11.2-2 Total Projected Population Distribution within 50 Miles of the Clinch River Nuclear Site in 2067 11.2-3 Milk, Meat, and Vegetable and Fruit Production in Tennessee within 50 Miles of the Clinch River Nuclear Site 11.2-4 Projected Liquid Radioactive Effluent Concentrations in Watts Bar Reservoir 11.2-5 Radioactive Liquid Effluent Doses per Reactor for the Maximally Exposed Individual 11.2-6 Radioactive Liquid Effluent Doses for the Site for the Maximally Exposed Individual 11.2-7 Comparison of Doses to the Maximally Exposed Individual from Liquid and Gaseous Radioactive Effluents with 10 CFR 50, Appendix I, Criteria 11.2-8 Comparison of Doses to the Maximally Exposed Individual from All Sources with 40 CFR 190 Criteria 11.2-9 Collective Doses per Reactor to the Population within 50 Miles of the Clinch River Nuclear Site from Liquid and Gaseous Effluents 11.3-1 Gaseous Effluent Dose Calculation Parameters 11.3-2 Atmospheric Dispersion and Ground Deposition Factors by Location 11.3-3 Projected Gaseous Radioactive Effluent Concentrations at the Site Exclusion Area Boundary 11.3-4 Gaseous Radioactive Effluent Doses per Reactor for the Maximally Exposed Individual 11.3-5 Gaseous Radioactive Effluent Doses for the Site for the Maximally Exposed Individual 11-ii Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT 11.2.3 Liquid Radioactive Releases This section describes the radiological impacts of liquid radioactive waste effluents from normal plant operation at the CRN Site on members of the public. Subsection 11.2.3.1 describes the exposure pathways by which radiation and radioactive effluents can be transmitted from the proposed nuclear units to individuals living near the site. Subsection 11.2.3.2 provides an estimate of the maximum doses to the public and evaluates the impacts of these doses by comparing them to applicable regulatory limits.

11.2.3.1 Exposure Pathways Small quantities of radioactive liquids would be discharged to the Clinch River arm of the Watts Bar Reservoir, from the discharge structure at Clinch River Mile 15.5 shown in Figure 1.2-2, during normal operation of the nuclear units at the CRN Site. The impact of these releases on individuals and the general population in the vicinity of the site is evaluated by considering the major exposure pathways from the release point to the receptors of interest. The major exposure pathways are those that could yield the highest radiological doses for a given receptor. The relative importance of an exposure pathway is based on the type and amount of radioactivity released, the environmental transport mechanism, and the consumption or usage factors at the receptor.

The source term for the liquid radioactive waste effluents from normal plant operations at the CRN Site is provided in Table 2.0-6. As compliance is evaluated on a per-unit basis in some cases (i.e., 10 CFR 50, Appendix I) and on a per-site basis in others (i.e., 10 CFR 20, Appendix B, and 40 CFR 190), a determination of the source term with releases from one unit and for the site (all units) was required. In both cases, the source term for the surrogate plant is a composite of the four small modular reactor (SMR) technologies being considered. The source term associated with the release from one unit is a composite developed by selecting a representative activity for each of the radionuclides from the information for the four SMR technologies, consistent with the guidance provided in NEI 10-01 (Reference 11.2-4). The source term associated with the site was determined by selecting a representative per-radionuclide site activity of those calculated for each of the SMR technologies (determined by multiplying the per-radionuclide activity for a specific SMR unit by the maximum number of units being considered for that SMR technology). In some cases, based upon the maturity of the source term and the amount of conservatism, a lower activity for certain radionuclides was used. An evaluation was performed to ensure that the adjusted source terms utilized to evaluate the dose consequences are conservative compared to source terms for large light water reactors (scaled to a comparable power output) and are considered to be reasonable for use.

The exposure pathways considered and the analytical methods used to estimate doses to the maximally exposed individual (MEI) and to the general population surrounding the CRN Site are based on Regulatory Guide (RG) 1.109. The MEI is defined as a member of the general public at an assumed location that results in the maximum possible calculated dose. The MEI approach supports comparisons with established dose criteria for the public.

The NRC-endorsed LADTAP II computer program (Reference 11.2-1) is used to calculate liquid radioactive waste effluent doses, with parameters specific to the Clinch River arm of the Watts Bar Reservoir and downstream locations. LADTAP II implements the radiological exposure models described in RG 1.109 for radioactivity in liquid effluents, as well as exposure models for boating and swimming, as described in Reference 11.2-1.

11.2-1 Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report The following exposure pathways are considered in LADTAP II in calculating doses to the MEI and the general population:

internal exposure from ingestion of aquatic foods internal exposure from ingestion of drinking water internal exposure from ingestion of meat or milk from livestock consuming water and pasture feed from farms irrigated by contaminated water internal exposure from ingestion of vegetables and fruits from farms irrigated by contaminated water external exposure to shoreline sediments external exposure from boating and swimming Population doses for the CRN Site are calculated for the year 2067, 40 years from the projected commencement of commercial operation of the last of potentially multiple units at the site. At that time, the affected population within 50 miles of the site (permanent and transient) is projected to be at its maximum during the period of plant operation. The total projected population (permanent and transient) for the year 2067 within 50 miles of the CRN site is provided in Table 11.2-2 and was calculated using the methodology presented in Subsection 2.1.3.

11.2.3.2 Liquid Pathway Doses Based on the design inputs and assumptions shown in Table 11.2-1, the LADTAP II computer program is used to calculate doses to the MEI and the general population from the following activities:

ingesting fish and invertebrates caught in Watts Bar Reservoir ingesting water from Watts Bar Reservoir ingesting meat, milk and vegetables irrigated by water from Watts Bar Reservoir using the shoreline of Watts Bar Reservoir boating and swimming in Watts Bar Reservoir As shown in Table 11.2-4, the projected CRN Site liquid radioactive effluent concentrations in the Clinch River arm of the Watts Bar Reservoir are within the effluent concentration limits (ECLs) of 10 CFR 20, Appendix B, Table 2, Column 2.

The projected annual doses to the MEI from liquid radioactive effluents from each reactor and for the site are shown in Tables 11.2-5 and 11.2-6, respectively.

The projected total annual doses per reactor from both liquid and gaseous radioactive effluents are within the design objectives of 10 CFR 50, Appendix I, as shown in Table 11.2-7.

The projected total site doses due to liquid and gaseous radioactive effluents and direct radiation are within the environmental standards of 40 CFR 190, as shown in Table 11.2-8.

11.2-2 Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Because 40 CFR 190 is more restrictive than 10 CFR 20.1301, compliance with the limits of 40 CFR 190 demonstrates compliance with the 0.1 rem (100 mrem) limit of 10 CFR 20.1301.

Projected annual collective doses to the population within 50 miles of the CRN Site are shown in Table 11.2-9.

11.2.4 References 11.2-1. NUREG/CR-4013, LADTAP II Technical Reference and User Guide, U.S. Nuclear Regulatory Commission, 1986.

11.2-2. NCRP Report No. 160, Ionizing Radiation Exposure of the Population of the United States, National Council on Radiation Protection and Measurements, 2009.

11.2-3. Westinghouse Electric Corporation, Westinghouse AP1000 Design Control Document, Non-Proprietary, Revision 19, June 13, 2011.

11.2-4. NEI 10-01, Industry Guidance for Developing a Plant Parameter Envelope in Support of an Early Site Permit, Revision 1, May 2012.

11.2-3 Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 11.2-1 (Sheet 1 of 2)

Liquid Effluent Dose Calculation Parameters Parameter Value Basis/Comment Water Type Freshwater Clinch River arm of the Watts Bar Reservoir is fresh water.

3/s This mean annual flow rate conservatively bounds flow data collected Reactor Effluent 4000 ft Discharge Rate over a period of 47 years for Clinch River arm of the Watts Bar Reservoir.

Radionuclide Release Table 2.0-6 Values are shown per reactor and for all reactors on site.

Rates Population Within 50 2,658,157 Table 11.2-2 shows the total projected population distribution (permanent Miles and transient) within 50 miles of the Clinch River Nuclear (CRN) Site by sector and distance in 2067. Food production rates and population consumption and usage rates in 2067 are estimated using the ratio of 2067 to 2010 population.

Impoundment None This model does not apply to the river discharge scenario.

Reconcentration Model Shore-Width Factor 0.2 This is the appropriate value for a river (RG 1.109, Table A-2).

Dilution Factor for 1 No dilution is assumed beyond full mixing in the river flow rate.

Receptors Transit Time to Receptors 0 It is conservatively assumed that there is no decay beyond the distribution times built into LADTAP II.

Usage and Consumption Annual usage and consumption rates for the average individual and the Rates by Age Group MEI are taken from Tables E-4 and E-5, respectively, of RG 1.109. Times spent boating and swimming are assumed to be identical to that spent on shoreline activities. LADTAP II utilizes the maximum rates in calculating individual doses and the average rates in calculating population doses.

Sport Fishing Harvest 1.87 x 106 These are projected values for 2067. It is assumed that the Watts Bar kg/yr Reservoir is the source of 50 percent of the fish and invertebrate Commercial Fishing 5.93 x 106 consumption by the population within 50 miles of the CRN Site. This is a Harvest kg/yr conservative assumption because only the part of the river downstream from CRN Site is affected by liquid effluents, there are other bodies of Sport Invertebrate 2.71 x 105 water in the region, and some fish and invertebrate food is likely imported Harvest kg/yr from outside the region. It is further assumed that for every individual who Commercial Invertebrate 8.61 x 105 catches fish or invertebrates for sport, there are four individuals that Harvest kg/yr consume the catch, reflecting a typical family of four for the purpose of calculating population doses.

Population Supplied by 2.49 x 105 This is the projected value for 2067.

Drinking Water Population Shoreline, 3.40 x 107 This is the projected value for 2067. Times spent swimming and boating Swimming, and Boating hr/yr are assumed to be identical to that spent on shoreline activities.

Usage Irrigation Rate 110 L/m2 This corresponds to a rate of 1 inch/week, which bounds the actual rate per month within 50 miles of the CRN Site.

Vegetable Production Table 11.2-3 The table shows the values for 2067. Vegetable production rates within 50 miles of the CRN Site are assumed to be equal to the state-wide production rates for Tennessee, multiplied by the fraction of the harvested land area within Tennessee that falls within 50 miles of the site, as shown in Table 11.2-3. Furthermore, production rates for leafy vegetables are assumed to be the same as for non-leafy vegetables.

11.2-4 Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 11.2-1 (Sheet 2 of 2)

Liquid Effluent Dose Calculation Parameters Parameter Value Basis/Comment Milk and Meat Production Table 11.2-3 Milk and meat production rates within 50 miles of the CRN Site are assumed to be equal to the state-wide production rates for Tennessee, multiplied by the respective fractions of the milk and meat animals within Tennessee that reside within 50 miles of the site, as shown in Table 11.2-3.

11.2-5 Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 11.2-2 Total Projected Population Distribution within 50 Miles of the Clinch River Nuclear Site in 2067 Distance (Miles)

Direction 0-1 1-2 2-3 3-4 4-5 5 - 10 10 - 20 20 - 30 30 - 40 40 - 50 S 13 29 38 150 213 2,446 14,716 24,197 19,100 10,242 SSW 14 31 41 150 147 1,242 5,357 26,006 49,143 21,631 SW 13 51 69 132 265 965 3,895 5,502 12,679 44,254 WSW 16 68 172 151 373 7,989 4,829 7,185 7,015 9,876 W 18 107 161 183 742 18,819 15,343 5,587 52,483 12,930 WNW 21 89 248 87 220 5,303 6,069 8,407 11,606 13,108 NW 20 25 50 14 84 1,771 7,498 4,907 3,914 24,543 NNW 0 1 0 0 156 2,077 8,465 840 11,546 35,117 N 0 0 0 0 110 2,850 2,594 570 5,499 12,272 NNE 0 0 0 0 0 8,678 10,509 12,234 35,396 11,082 NE 5 0 0 0 0 1,555 51,540 30,575 25,463 12,290 ENE 8 9 1 0 0 1,670 104,860 711,355 81,037 31,999 E 8 14 130 57 116 9,101 130,456 207,087 67,225 108,807 ESE 6 39 112 203 475 12,098 26,220 229,719 32,360 14,583 SE 8 42 85 307 357 22,492 11,132 21,153 4,038 10,641 SSE 7 59 67 234 396 3,916 35,921 17,961 2,693 707 Total 157 564 1,174 1,668 3,654 102,972 439,404 1,313,285 421,197 374,082 Grand Total = 2,658,157 Notes:

Total projected population within 50 miles of the Clinch River Nuclear Site in 2067 (2,658,157) is an increase of 54% as compared to the total population in 2010 (1,723,327).

11.2-6 Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 11.2-3 Milk, Meat, and Vegetable and Fruit Production in Tennessee within 50 Miles of the Clinch River Nuclear Site Production in Percent of Production Production within 50 Miles of the CRN Site Tennessee in Tennessee within 50 (kg/yr)

Food (kg/yr) Miles of CRN Site Present 2067 Irrigation 2067 Milk 4.30 x 108 28.81% 1.24 x 108 1.91 x 108 3.08 x 104 Red Meat 3.06 x 108 12.75% 3.91 x 107 - -

8 14.39% 6.65 x 107 - -

Broilers 4.62 x 10 Meat (Total) - - 1.06 x 108 1.63 x 108 2.62 x 104 Vegetables and 8.79%

5.17 x 109 4.54 x 108 7.00 x 108 1.13 x 105 Fruits (% Harvested Land)

Column 1 2 3 4 5 Notes:

Entries in Column 2 assume that the fraction of the land area of counties outside Tennessee within 50 miles of the Clinch River Nuclear (CRN) Site is negligible, pursuant to Table 11.2-2.

Entries in Column 3 are obtained by multiplying the values in Column 1 by those in Column 2.

Entries in Column 4 are obtained by multiplying the values in Column 3 by a population ratio of 1.54, from the footnote of Table 11.2-2.

Entries in Column 5 show production using irrigated water and are obtained by multiplying Column 4 by 2.41%, the percentage of state irrigation occurring within 50 miles of the CRN site, and by 0.67%, the percentage of irrigation occurring with water from Watts Bar Reservoir.

Dashes (-) = No Value 11.2-7 Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 11.2-4 (Sheet 1 of 3)

Projected Liquid Radioactive Effluent Concentrations in Watts Bar Reservoir Release Concentration (Ci/mL)

Nuclide (Ci/yr) River ECL Fraction of ECL H-3 8.85 x 102 2.48 x 10-7 1 x 10-3 2.5 x 10-4 C-14 9.83 x 10-3 2.75 x 10-12 3x 10-5 9.2 x 10-8 Na-24 8.40 x 10-3 2.35 x 10-12 5 x 10-5 4.7 x 10-8 P-32 3.03 x 10-4 8.48 x 10-14 9 x 10-6 9.4 x 10-9 Cr-51 1.28 x 10-1 3.59 x 10-11 5 x 10-4 7.2 x 10-8 Mn-54 6.53 x 10-2 1.83 x 10-11 3x 10-5 6.1 x 10-7 Mn-56 1.09 x 10-3 3.05 x 10-13 7 x 10-5 4.4 x 10-9 Fe-55 4.87 x 10-2 1.36 x 10-11 1 x 10-4 1.4 x 10-7 Fe-59 1.19 x 10-2 3.33 x 10-12 1 x 10-5 3.3 x 10-7 Co-58 5.51 x 10-2 1.54 x 10-11 2x 10-5 7.7 x 10-7 Co-60 8.21 x 10-3 2.30 x 10-12 3 x 10-6 7.7 x 10-7 Ni-63 1.84 x 10-1 5.14 x 10-11 1 x 10-4 5.1 x 10-7 Cu-64 6.72 x 10-3 1.88 x 10-12 2 x 10-4 9.4 x 10-9 Zn-65 2.11 x 10-2 5.91 x 10-12 5x 10-6 1.2 x 10-6 Br-82 7.48 x 10-6 2.09 x 10-15 4 x 10-5 5.2 x 10-11 Br-83 1.41 x 10-5 3.94 x 10-15 9 x 10-4 4.4 x 10-12 Br-84 1.01 x 10-3 2.82 x 10-13 4 x 10-4 7.0 x 10-10 Br-85 9.68 x 10-9 2.71 x 10-18 - -

-5 Rb-86 7.48 x 10 2.09 x 10-14 7x 10-6 3.0 x 10-9 Rb-88 1.49 x 10-2 4.18 x 10-12 4 x 10-4 1.0 x 10-8 Rb-89 6.18 x 10-4 1.73 x 10-13 9 x 10-4 1.9 x 10-10 Sr-89 1.67 x 10-4 4.69 x 10-14 8x 10-6 5.9 x 10-9 Sr-90 1.43 x 10-5 4.00 x 10-15 5 x 10-7 8.0 x 10-9 Sr-91 6.67 x 10-4 1.87 x 10-13 2 x 10-5 9.3 x 10-9 Sr-92 2.36 x 10-4 6.61 x 10-14 4 x 10-5 1.7 x 10-9 Y-90 1.86 x 10-6 5.21 x 10-16 7x 10-6 7.4 x 10-11 Y-91 1.25 x 10-4 3.51 x 10-14 8 x 10-6 4.4 x 10-9 Y-91m 2.67 x 10-5 7.47 x 10-15 2 x 10-3 3.7 x 10-12 Y-92 9.01 x 10-4 2.52 x 10-13 4 x 10-5 6.3 x 10-9 Y-93 7.25 x 10-4 2.03 x 10-13 2x 10-5 1.0 x 10-8 Zr-95 2.20 x 10-3 6.15 x 10-13 2 x 10-5 3.1 x 10-8 Zr-97 4.40 x 10-7 1.23 x 10-16 9 x 10-6 1.4 x 10-11 Nb-95 1.07 x 10-3 2.99 x 10-13 3 x 10-5 1.0 x 10-8 Mo-99 4.52 x 10-2 1.27 x 10-11 2x 10-5 6.3 x 10-7 Tc-99m 2.27 x 10-2 6.35 x 10-12 1 x 10-3 6.3 x 10-9 Tc-99 1.76 x 10-8 4.93 x 10-18 6 x 10-5 8.2 x 10-14 Ru-103 2.63 x 10-3 7.36 x 10-13 3 x 10-5 2.5 x 10-8 Ru-105 7.04 x 10-8 1.97 x 10-17 7x 10-5 2.8 x 10-13 11.2-8 Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 11.2-4 (Sheet 2 of 3)

Projected Liquid Radioactive Effluent Concentrations in Watts Bar Reservoir Release Concentration (Ci/mL)

Nuclide (Ci/yr) River ECL Fraction of ECL Ru-106 3.92 x 10-2 1.10 x 10-11 3x 10-6 3.7 x 10-6 Rh-103m 4.37 x 10-6 1.22 x 10-15 6 x 10-3 2.0 x 10-13 Rh-105 4.27 x 10-7 1.19 x 10-16 5x 10-5 2.4 x 10-12 Rh-106 3.74 x 10-7 1.05 x 10-16 1.0 x 10-8 1.0 x 10-8 Ag-110m 2.66 x 10-2 7.46 x 10-12 6 x 10-6 1.2 x 10-6 Ag-110 3.48 x 10-8 9.73 x 10-18 - -

-4 6.42 x 10-14 7x 10-6 9.2 x 10-9 Sb-124 2.29 x 10 Sb-125 7.92 x 10-9 2.22 x 10-18 3 x 10-5 7.4 x 10-14 Sb-127 4.40 x 10-8 1.23 x 10-17 1 x 10-5 1.2 x 10-12 Sb-129 1.76 x 10-8 4.93 x 10-18 4 x 10-5 1.2 x 10-13 Te-127m 5.72 x 10-6 1.60 x 10-15 9x 10-6 1.8 x 10-10 Te-127 1.28 x 10-5 3.57 x 10-15 1 x 10-4 3.6 x 10-11 Te-129m 6.90 x 10-2 1.93 x 10-11 7 x 10-6 2.8 x 10-6 Te-129 1.65 x 10-4 4.62 x 10-14 4 x 10-4 1.2 x 10-10 Te-131m 1.98 x 10-3 5.54 x 10-13 8x 10-6 6.9 x 10-8 Te-131 4.05 x 10-5 1.13 x 10-14 8 x 10-5 1.4 x 10-10 Te-132 1.32 x 10-1 3.70 x 10-11 9 x 10-6 4.1 x 10-6 Te-134 1.06 x 10-6 2.96 x 10-16 3 x 10-4 9.9 x 10-13 I-129 5.04 x 10-9 1.41 x 10-18 2x 10-7 7.1 x 10-12 I-130 1.85 x 10-5 5.17 x 10-15 2 x 10-5 2.6 x 10-10 I-131 1.66 x 10-1 4.64 x 10-11 1 x 10-6 4.6 x 10-5 I-132 1.32 x 10-1 3.70 x 10-11 1 x 10-4 3.7 x 10-7 I-133 2.76 x 10-1 7.73 x 10-11 7x 10-6 1.1 x 10-5 I-134 3.91 x 10-2 1.10 x 10-11 4 x 10-4 2.7 x 10-8 I-135 1.64 x 10-1 4.60 x 10-11 3 x 10-5 1.5 x 10-6 Cs-134 3.44 x 10-2 9.64 x 10-12 9 x 10-7 1.1 x 10-5 Cs-136 1.17 x 10-2 3.28 x 10-12 6x 10-6 5.5 x 10-7 Cs-137 4.24 x 10-2 1.19 x 10-11 1 x 10-6 1.2 x 10-5 Cs-138 1.42 x 10-2 3.96 x 10-12 4 x 10-4 9.9 x 10-9 Ba-137m 2.07 x 10-3 5.79 x 10-13 - -

-8 Ba-139 6.16 x 10 1.72 x 10-17 2x 10-4 8.6 x 10-14 Ba-140 4.80 x 10-2 1.34 x 10-11 8 x 10-6 1.7 x 10-6 La-140 4.27 x 10-3 1.19 x 10-12 9 x 10-6 1.3 x 10-7 La-141 8.80 x 10-8 2.46 x 10-17 5 x 10-5 4.9 x 10-13 La-142 1.19 x 10-8 3.33 x 10-18 1x 10-4 3.3 x 10-14 Ce-141 1.58 x 10-4 4.43 x 10-14 3 x 10-5 1.5 x 10-9 Ce-143 3.25 x 10-4 9.11 x 10-14 2 x 10-5 4.6 x 10-9 Ce-144 2.99 x 10-3 8.36 x 10-13 3 x 10-6 2.8 x 10-7 Pr-143 6.93 x 10-5 1.94 x 10-14 2x 10-5 9.7 x 10-10 11.2-9 Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 11.2-4 (Sheet 3 of 3)

Projected Liquid Radioactive Effluent Concentrations in Watts Bar Reservoir Release Concentration (Ci/mL)

Nuclide (Ci/yr) River ECL Fraction of ECL Pr-144 1.69 x 10-3 4.73 x 10-13 6x 10-4 7.9 x 10-10 Nd-147 1.07 x 10-6 2.99 x 10-16 2 x 10-5 1.5 x 10-11 W-187 6.30 x 10-4 1.76 x 10-13 3x 10-5 5.9 x 10-9 Np-239 2.99 x 10-2 8.37 x 10-12 2 x 10-5 4.2 x 10-7 Pu-238 2.64 x 10-9 7.39 x 10-19 2 x 10-8 3.7 x 10-11 Pu-239 3.39 x 10-10 9.48 x 10-20 2 x 10-8 4.7 x 10-12 Pu-240 4.27 x 10-10 1.19 x 10-19 2x 10-8 6.0 x 10-12 Pu-241 1.28 x 10-7 3.57 x 10-17 1 x 10-6 3.6 x 10-11 Am-241 1.85 x 10-10 5.17 x 10-20 2 x 10-8 2.6 x 10-12 Cm-242 3.78 x 10-8 1.06 x 10-17 7 x 10-7 1.5 x 10-11 Cm-244 1.76 x 10-9 4.93 x 10-19 3x 10-8 1.6 x 10-11 Totals 8.87 x 102 3.5 x 10-4 Notes:

ECL = Effluent Concentration Limit Ci = Curies Dashes (-) = No Value 11.2-10 Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 11.2-5 Radioactive Liquid Effluent Doses per Reactor for the Maximally Exposed Individual Dose per Reactor (mrem/yr)

Other Organ Pathway Total Body GI-LLI(a) Bone Liver Kidney Thyroid Lung Skin

-3 1.3 x 10-2 2.2 x 10-2 1.1 x 10-2 7.0 x 10-3 3.0 x 10-3 1.1 x 10-3 0 Fish 8.5 x 10

-3 4.6 x 10-2 6.5 x 10-3 5.4 x 10-3 1.5 x 10-2 1.9 x 10-3 1.8 x 10-4 0 Invertebrate 2.6 x 10 Drinking 2.9 x 10-3 4.3 x 10-3 2.0 x 10-3 4.2 x 10-3 4.6 x 10-3 1.8 x 10-2 3.7 x 10-3 0

-5 1.2 x 10-5 1.4 x 10-5 1.4 x 10-5 1.4 x 10-5 1.4 x 10-5 1.4 x 10-5 7.9 x 10-5 Shoreline 1.2 x 10 Swimming 1.4 x 10-6 1.4 x 10-6 1.7 x 10-6 1.7 x 10-6 1.7 x 10-6 1.7 x 10-6 1.7 x 10-6 0

-7 7.2 x 10-7 8.4 x 10-7 8.4 x 10-7 8.4 x 10-7 8.4 x 10-7 8.4 x 10-7 0 Boating 7.2 x 10 Irrigated Vegetables 3.4 x 10-3 7.2 x 10-3 1.9 x 10-2 8.5 x 10-3 8.3 x 10-3 1.8 x 10-2 4.5 x 10-3 0

-3 2.1 x 10-3 9.1 x 10-3 6.0 x 10-3 4.0 x 10-3 2.3 x 10-2 2.8 x 10-3 0 Irrigated Milk 2.0 x 10

-4 2.5 x 10-2 2.0 x 10-3 6.8 x 10-4 2.9 x 10-3 7.6 x 10-4 3.4 x 10-4 0 Irrigated Meat 6.5 x 10

-2 9.7 x 10-2 6.0 x 10-2 3.5 x 10-2 4.2 x 10-2 6.4 x 10-2 1.3 x 10-2 7.9 x 10-5 Total 2.0 x 10 Maximum Dose Age Adult Adult Child Child Child Child Child Teen Group (a) GI-LLI = Gastrointestinal Tract - Lower Large Intestine 11.2-11 Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 11.2-6 Radioactive Liquid Effluent Doses for the Site for the Maximally Exposed Individual Site Dose (mrem/yr)

Other Organ Pathway Total Body GI-LLI(a) Bone Liver Kidney Thyroid Lung Skin

-2 4.5 x 10-2 1.6 x 10-1 1.1 x 10-1 4.8 x 10-2 3.2 x 10-2 1.2 x 10-2 0 Fish 9.2 x 10

-2 2.3 x 10-1 3.4 x 10-2 5.2 x 10-2 5.6 x 10-2 7.7 x 10-3 2.0 x 10-3 0 Invertebrate 2.3 x 10 Drinking 1.3 x 10-2 1.7 x 10-2 1.9 x 10-2 2.1 x 10-2 1.9 x 10-2 1.8 x 10-1 1.5 x 10-2 0

-4 1.1 x 10-4 1.3 x 10-4 1.3 x 10-4 1.3 x 10-4 1.3 x 10-4 1.3 x 10-4 7.0 x 10-4 Shoreline 1.1 x 10 Swimming 8.8 x 10-6 8.8 x 10-6 1.0 x 10-5 1.0 x 10-5 1.0 x 10-5 1.0 x 10-5 1.0 x 10-5 0

-6 4.4 x 10-6 5.1 x 10-6 5.1 x 10-6 5.1 x 10-6 5.1 x 10-6 5.1 x 10-6 0 Boating 4.4 x 10 Irrigated Vegetables 2.2 x 10-2 3.2 x 10-2 2.1 x 10-1 6.8 x 10-2 4.1 x 10-2 1.8 x 10-1 2.2 x 10-2 0

-2 1.5 x 10-2 1.1 x 10-1 5.1 x 10-2 2.5 x 10-2 2.5 x 10-1 1.4 x 10-2 0 Irrigated Milk 1.4 x 10

-3 9.9 x 10-2 1.4 x 10-2 4.2 x 10-3 1.0 x 10-2 5.0 x 10-3 1.7 x 10-3 0 Irrigated Meat 3.5 x 10

-1 4.4 x 10-1 5.4 x 10-1 3.1 x 10-1 2.0 x 10-1 6.6 x 10-1 6.8 x 10-2 7.0 x 10-4 Total 1.7 x 10 Maximum Dose Age Adult Adult Child Child Child Child Child Teen Group (a) GI-LLI = Gastrointestinal Tract - Lower Large Intestine 11.2-12 Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 11.2-7 Comparison of Doses to the Maximally Exposed Individual from Liquid and Gaseous Radioactive Effluents with 10 CFR 50, Appendix I, Criteria Annual Dose per Reactor Type of Dose Location Site Limit Liquid Effluents Total Body (mrem) Watts Bar Reservoir 0.020 3 Maximum Organ = GI-LLI (mrem) Watts Bar Reservoir 0.097 10 Gaseous Effluents Gamma Air (mrad) Site Boundary 9.5 10 Beta Air (mrad) Site Boundary 12 20 Total Body (mrem) Residence 0.9 5 Skin (mrem) Residence 1.9 15 Iodines and Particulates Residence/Garden/

Maximum Organ = Thyroid (mrem) 4.5 15 Beef Animal 11.2-13 Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 11.2-8 Comparison of Doses to the Maximally Exposed Individual from All Sources with 40 CFR 190 Criteria Site Dose (mrem/yr)

Type of Dose Liquid(a) Gaseous(b) Direct(c) Total Limit Total Body 0.17 10 1.0 11 25 Thyroid 0.66 24 0.0 25 75 Other Organ (Bone) 0.54 23 0.0 24 25 (a) From Table 11.2-6.

(b) From Table 11.3-5.

(c) It is conservatively assumed that the total direct radiation from all reactors at the Clinch River Nuclear (CRN) Site is 1 mrem/yr at the Site Boundary. Direct radiation dose from the pressurized water reactor (PWR) designs under consideration for the CRN Site is expected to be negligible, similar to doses from large PWRs - for example, AP1000 (Reference 11.2-3, Section 12.4.2.1).

11.2-14 Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 11.2-9 Collective Doses per Reactor to the Population within 50 Miles of the Clinch River Nuclear Site from Liquid and Gaseous Effluents Dose per Reactor (person-rem/yr)

Pathway Total Body Thyroid Liquid Effluents 2.4 1.8 Gaseous Effluents Noble Gases 0.8 0.8 Iodines 0.020 9.9 Particulates 0.72 0.57 C-14 10 10 H-3 3.3 3.3 Total for Gaseous Effluents 15 25 Total for Liquid and Gaseous Effluents 17 26 Natural Background(a) 8.3 x 105 (a) Obtained by multiplying the natural background dose of 311 mrem/yr (Reference 11.2-2) by the 2067 population of 2,658,157 persons (Table 11.2-2).

11.2-15 Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report 11.3.3 Gaseous Radioactive Releases This section describes the radiological impacts of gaseous radioactive waste effluents from normal plant operation at the Clinch River Nuclear (CRN) Site on members of the public.

Subsection 11.3.3.1 describes the exposure pathways by which radiation and radioactive effluents can be transmitted from the proposed nuclear units to individuals living near the site.

Subsection 11.3.3.2 provides an estimate of the maximum doses to the public and evaluates the impacts of these doses by comparing them to applicable regulatory limits.

11.3.3.1 Exposure Pathways Small quantities of radioactive gases would be discharged to the environment during normal operation of nuclear units at the CRN Site. The impact of these releases on individuals and the general population in the vicinity of the site is evaluated by considering the most important pathways from the release to the receptors of interest. The major pathways are those that could yield the highest radiological doses for a given receptor. The relative importance of a pathway is based on the type and amount of radioactivity released, the environmental transport mechanism, and the consumption or usage factors at the receptor.

The source term for the gaseous radioactive waste effluents from normal plant operations at the CRN Site is provided in Table 2.0-4. As compliance is evaluated on a per-unit basis in some cases (i.e., 10 CFR 50, Appendix I) and on a per-site basis in others (i.e., 10 CFR 20, Appendix B, and 40 CFR 190), a determination of the source term with releases from one unit and for the site (all units) was required. In both cases, the source term for the surrogate plant is a composite of the four small modular reactor (SMR) technologies being considered. The source term associated with the release from one unit is a composite developed by selecting a representative activity for each of the radionuclides from the information for the four SMR technologies, consistent with the guidance provided in NEI 10-01 (Reference 11.3-2). The source term associated with the site was determined by selecting a representative per-radionuclide site activity of those calculated for each of the SMR technologies (determined by multiplying the per-radionuclide activity for a specific SMR unit by the maximum number of units being considered for that SMR technology). In some cases, the maturity of the source term resulted in an excessive amount of conservatism. In these instances, a lower activity for certain radionuclides was used. An evaluation was performed to ensure that the source terms utilized to evaluate the dose consequences are conservative compared to source terms for large light water reactors (scaled to a comparable power output) and are considered to be reasonable for use.

The exposure pathways considered and the analytical methods used to estimate doses to the maximally exposed individual (MEI) and to the general population surrounding the CRN Site are based on Regulatory Guide (RG) 1.109 and RG 1.111. The MEI is defined as a member of the general public located to receive the maximum possible calculated dose; and the MEI approach supports dose comparisons with established criteria for the public.

The NRC-endorsed GASPAR II computer code (Reference 11.3-1) is used to calculate the doses to offsite receptors from the proposed nuclear units at the CRN Site. This program implements the radiological exposure models described in RG 1.109 to estimate the doses resulting from radioactive releases in gaseous effluents. The atmospheric dispersion component of the analysis is calculated with the NRC-endorsed XOQDOQ computer program, and its development (including assumed release points) is discussed in Subsection 2.3.5.

The following exposure pathways are considered in GASPAR II:

external exposure to an airborne plume 11.3-1 Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report external exposure to contaminated ground internal exposure from inhalation of airborne activity internal exposure from ingestion of contaminated vegetables, milk, and meat Population doses for the CRN Site are calculated for the year 2067, 40 years from the projected commencement of commercial operation of the last of potentially multiple units at the site. At that time, the affected population within 50 miles of the site (permanent and transient) is projected to be at its maximum during the period of plant operation. The total projected population (permanent and transient) for the year 2067 within 50 miles of the CRN site is provided in Table 11.2-2 and was calculated using the methodology presented in Subsection 2.1.3.

11.3.3.2 Gaseous Pathway Doses Based on the design inputs and assumptions shown in Table 11.3-1, the GASPAR II computer program is used to calculate doses to the MEI from gaseous radioactive effluents at the following locations:

nearest site boundary nearest residence nearest vegetable garden nearest meat animal As shown in Table 11.3-3, projected gaseous radioactive effluent concentrations at the CRN Site exclusion area boundary (EAB) are within the ECLs of 10 CFR 20, Appendix B, Table 2, Column 1.

The projected annual doses to the MEI from gaseous radioactive effluents from each reactor and from the site are shown in Tables 11.3-4 and 11.3-5, respectively.

The projected total annual doses per reactor from both liquid and gaseous radioactive effluents are within the design objectives of 10 CFR 50, Appendix I, as shown in Table 11.2-7.

The projected total site doses due to liquid and gaseous radioactive effluents and direct radiation are within the environmental standards of 40 CFR 190, as shown in Table 11.2-8.

Because 40 CFR 190 is more restrictive than 10 CFR 20.1301, compliance with the limits of 40 CFR 190 demonstrates compliance with the 0.1 rem (100 mrem) limit of 10 CFR 20.1301.

Projected annual collective doses to the population within 50 miles of the CRN Site are shown in Table 11.2-9.

11.3.4 References 11.3-1. NUREG/CR-4653, GASPAR II - Technical Reference and User Guide, 1987.

11.3-2. NEI 10-01, Industry Guidance for Developing a Plant Parameter Envelope in Support of an Early Site Permit, Revision 1, May 2012.

11.3-2 Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 11.3-1 Gaseous Effluent Dose Calculation Parameters Parameter Value Basis/Comment Atmospheric Dispersion and Deposition Factors Table 11.3-2 Site atmospheric dispersion factors (/Q values) and ground deposition factors (D/Q values) are shown in Subsection 2.3.5. The maximum /Q and D/Q values at the Site Boundary and at the nearest residence, beef animal, vegetable garden and biota are shown in Table 11.3-2.

Fraction of Year Leafy Vegetables Grown 1 Most conservative value.

Fraction of Year Milk Cows on Pasture 1 Most conservative value.

Fraction of Maximum Individuals Vegetable 0.76 Default value from RG 1.109, Table E-15.

Intake from own Garden Fraction of Milk-Cow Feed from Pasture 1 Most conservative value.

Average Absolute Humidity for Growing Season 8 g/m3 Default value in GASPAR II (Reference 11.3-1, Table 2.3), used when a value of zero is input.

Average Temperature over Growing Season 0 Not used if absolute humidity is specified.

Fraction of Year Goats at Pasture 1 Most conservative value.

Fraction of Goat Feed from Pasture 1 Most conservative value.

Fraction of Year Beef Cattle at Pasture 1 Most conservative value.

Fraction of Beef Cattle Feed from Pasture 1 Most conservative value.

Population Within 50 Miles Table 11.2-2 The table shows the total projected population distribution within 50 miles of the Clinch River Nuclear Site by sector and distance in 2067.

Milk Production Within 50 Miles 1.91 x 108 L/yr Projected values for 2067 from Table 11.2-3.

8 Meat Production Within 50 Miles 1.63 x 10 kg/yr Vegetable Production Within 50 Miles 7.00 x 108 kg/yr Radionuclide Release Rates Table 2.0-4 Values are shown per reactor and for all reactors on site.

11.3-3 Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 11.3-2 Atmospheric Dispersion and Ground Deposition Factors by Location Sector Distance (mi) Atmospheric Dispersion (/Q - s/m3)(a)

Undecayed 2.26-Day Decay 8-Day Decay Ground Deposition Location X/Q D/Q X/Q D/Q Undepleted Undepleted Depleted (D/Q - m-2)(b)

Site Boundary WNW ESE 0.21 0.21 2.0 x 10-4 2.0 x 10-4 1.9 x 10-4 7.9 x 10-8 Residence WNW ESE 0.66 0.69 2.5 x 10-5 2.5 x 10-5 2.3 x 10-5 1.2 x 10-8 Beef Animal WNW WNW 0.70 0.70 2.3 x 10-5 2.3 x 10-5 2.1 x 10-5 7.8 x 10-9 (c)

Vegetable Garden WNW ESE 1.15 0.92 1.0 x 10-5 9.9 x 10-6 8.7 x 10-6 7.3 x 10-9 (c)

Biota WNW ESE 0.25 0.25 1.5 x 10-4 1.5 x 10-4 1.4 x 10-4 6.0 x 10-8 (a) At each location, the X/Q values shown comprise the maximum set in any direction, considering all three values as a set.

(b) At each location, the D/Q value shown is the maximum in any direction based on vector wind direction data.

(c) At the beef animal and the vegetable garden, the maximum D/Q values based on scalar wind direction data are 8.0 x 10-9 m-2 at 0.70 mi in the WNW direction and 7.4 x 10-9 m-2 at 0.67 mi in the NE direction, respectively. The corresponding X/Q values based on scalar wind direction data are lower than those based on vector wind direction data at these locations. Taken as a complete set, the X/Q and D/Q values based on vector wind direction data, as shown in the table, bound those based on scalar wind direction data for the Maximally Exposed Individual gaseous effluent dose.

11.3-4 Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 11.3-3 (Sheet 1 of 2)

Projected Gaseous Radioactive Effluent Concentrations at the Site Exclusion Area Boundary Release Concentration (Ci/ml)

Nuclide (Ci/yr) EAB ECL Fraction of ECL H-3 1.01 x 103 6.41 x 10-9 1 x 10-7 6.4 x 10-2 C-14 1.00 x 101 6.34 x 10-11 3x 10-9 2.1 x 10-2 Na-24 2.50 x 10-3 1.59 x 10-14 7 x 10-9 2.3 x 10-6 P-32 5.68 x 10-4 3.60 x 10-15 5x 10-10 7.2 x 10-6 Ar-41 5.44 x 102 3.45 x 10-9 1 x 10-8 3.5 x 10-1 Cr-51 2.17 x 10-2 1.37 x 10-13 3 x 10-8 4.6 x 10-6 Mn-54 5.22 x 10-3 3.31 x 10-14 1x 10-9 3.3 x 10-5 Mn-56 2.17 x 10-3 1.37 x 10-14 2 x 10-8 6.9 x 10-7 Fe-55 4.01 x 10-3 2.54 x 10-14 3 x 10-9 8.5 x 10-6 Fe-59 9.55 x 10-4 6.06 x 10-15 5x 10-10 1.2 x 10-5 Co-57 1.10 x 10-4 6.98 x 10-16 9 x 10-10 7.8 x 10-7 Co-58 6.90 x 10-2 4.38 x 10-13 1x 10-9 4.4 x 10-4 Co-60 2.64 x 10-2 1.67 x 10-13 5 x 10-11 3.3 x 10-3 Ni-63 1.46 x 10-2 9.26 x 10-14 1 x 10-9 9.3 x 10-5 Cu-64 6.18 x 10-3 3.92 x 10-14 3x 10-8 1.3 x 10-6 Zn-65 6.86 x 10-3 4.35 x 10-14 4 x 10-10 1.1 x 10-4 Br-84 1.28 x 10-5 8.14 x 10-17 8 x 10-8 1.0 x 10-9 Kr-83m 1.28 x 10-2 8.14 x 10-14 5x 10-5 1.6 x 10-9 Kr-85m 3.39 x 102 2.15 x 10-9 1 x 10-7 2.1 x 10-2 Kr-85 7.20 x 102 4.57 x 10-9 7x 10-7 6.5 x 10-3 Kr-87 3.27 x 101 2.08 x 10-10 2 x 10-8 1.0 x 10-2 Kr-88 1.45 x 102 9.21 x 10-10 9 x 10-9 1.0 x 10-1 Kr-89 5.00 x 10-7 3.17 x 10-18 1x 10-9 3.2 x 10-9 Rb-88 9.80 x 10-6 6.22 x 10-17 9 x 10-8 6.9 x 10-10 Rb-89 2.67 x 10-5 1.69 x 10-16 2 x 10-7 8.5 x 10-10 Sr-89 9.00 x 10-3 5.71 x 10-14 2x 10-10 2.9 x 10-4 Sr-90 3.60 x 10-3 2.28 x 10-14 6 x 10-12 3.8 x 10-3 Sr-91 6.18 x 10-4 3.92 x 10-15 5x 10-9 7.8 x 10-7 Sr-92 4.84 x 10-4 3.07 x 10-15 9 x 10-9 3.4 x 10-7 Y-90 2.84 x 10-5 1.80 x 10-16 9 x 10-10 2.0 x 10-7 Y-91 1.49 x 10-4 9.44 x 10-16 2x 10-10 4.7 x 10-6 Y-92 3.84 x 10-4 2.44 x 10-15 1 x 10-8 2.4 x 10-7 Y-93 6.86 x 10-4 4.35 x 10-15 3 x 10-9 1.4 x 10-6 Zr-95 3.00 x 10-3 1.90 x 10-14 4x 10-10 4.8 x 10-5 Nb-95 7.50 x 10-3 4.76 x 10-14 2 x 10-9 2.4 x 10-5 Mo-99 3.68 x 10-2 2.33 x 10-13 2x 10-9 1.2 x 10-4 Tc-99m 1.83 x 10-4 1.16 x 10-15 2 x 10-7 5.8 x 10-9 Ru-103 2.17 x 10-3 1.37 x 10-14 9 x 10-10 1.5 x 10-5 Ru-106 2.34 x 10-4 1.48 x 10-15 2x 10-11 7.4 x 10-5 11.3-5 Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 11.3-3 (Sheet 2 of 2)

Projected Gaseous Radioactive Effluent Concentrations at the Site Exclusion Area Boundary Release Concentration (Ci/ml)

Nuclide (Ci/yr) EAB ECL Fraction of ECL Rh-103m 1.48 x 10-8 9.36 x 10-20 2x 10-6 4.7 x 10-14 Rh-106 4.57 x 10-11 2.90 x 10-22 1x 10-12 2.9 x 10-10 Ag-110m 2.14 x 10-3 1.35 x 10-14 1 x 10-10 1.4 x 10-4 Sb-124 1.12 x 10-4 7.09 x 10-16 3 x 10-10 2.4 x 10-6 Sb-125 3.77 x 10-5 2.39 x 10-16 7x 10-10 3.4 x 10-7 Te-129m 1.35 x 10-4 8.58 x 10-16 3 x 10-10 2.9 x 10-6 Te-131m 4.68 x 10-5 2.97 x 10-16 1 x 10-9 3.0 x 10-7 Te-132 7.13 x 10-5 4.52 x 10-16 9x 10-10 5.0 x 10-7 I-129 8.02 x 10-11 5.08 x 10-22 4 x 10-11 1.3 x 10-11 I-131 2.31 x 10-1 1.46 x 10-12 2x 10-10 7.3 x 10-3 I-132 1.35 x 100 8.58 x 10-12 2 x 10-8 4.3 x 10-4 I-133 1.05 x 100 6.66 x 10-12 1 x 10-9 6.7 x 10-3 I-134 2.33 x 100 1.48 x 10-11 6x 10-8 2.5 x 10-4 I-135 1.49 x 100 9.44 x 10-12 6 x 10-9 1.6 x 10-3 Xe-131m 1.67 x 103 1.06 x 10-8 2 x 10-6 5.3 x 10-3 Xe-133m 1.05 x 102 6.66 x 10-10 6x 10-7 1.1 x 10-3 Xe-133 2.24 x 103 1.42 x 10-8 5 x 10-7 2.8 x 10-2 Xe-135m 1.28 x 101 8.12 x 10-11 4x 10-8 2.0 x 10-3 Xe-135 2.82 x 102 1.79 x 10-9 7 x 10-8 2.6 x 10-2 Xe-137 3.00 x 100 1.90 x 10-11 1 x 10-9 1.9 x 10-2 Xe-138 1.14 x 101 7.23 x 10-11 2x 10-8 3.6 x 10-3 Cs-134 6.90 x 10-3 4.38 x 10-14 2 x 10-10 2.2 x 10-4 Cs-136 3.68 x 10-4 2.33 x 10-15 9 x 10-10 2.6 x 10-6 Cs-137 3.26 x 10-2 2.06 x 10-13 2x 10-10 1.0 x 10-3 Cs-138 1.05 x 10-4 6.66 x 10-16 8 x 10-8 8.3 x 10-9 Ba-140 1.67 x 10-2 1.06 x 10-13 2x 10-9 5.3 x 10-5 La-140 1.12 x 10-3 7.09 x 10-15 2 x 10-9 3.5 x 10-6 Ce-141 5.68 x 10-3 3.60 x 10-14 8 x 10-10 4.5 x 10-5

-7 -19 -9 Ce-143 1.16 x 10 7.33 x 10 2 x 10 3.7 x 10-10 Ce-144 1.17 x 10-5 7.40 x 10-17 2 x 10-11 3.7 x 10-6 Pr-144 1.17 x 10-5 7.40 x 10-17 2 x 10-7 3.7 x 10-10

-4 -16 -8 W-187 1.17 x 10 7.40 x 10 1 x 10 7.4 x 10-8 Np-239 7.35 x 10-3 4.66 x 10-14 3 x 10-9 1.6 x 10-5 Totals 7.13 x 103 6.8 x 10-1 Notes:

ECL = Effluent Concentration Limit EAB = Exclusion Area Boundary Ci = Curies 11.3-6 Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 11.3-4 (Sheet 1 of 2)

Gaseous Radioactive Effluent Doses per Reactor for the Maximally Exposed Individual Dose per Reactor (mrem/yr)

Location Pathway Total Body GI-Tract Bone Liver Kidney Thyroid Lung Skin Site Boundary External (0.21 mi WNW)

  • Plume 6.2 6.2 6.2 6.2 6.2 6.2 6.3 14
  • Ground 0.85 0.85 0.85 0.85 0.85 0.85 0.85 1.0
  • Total 7.1 7.1 7.1 7.1 7.1 7.1 7.2 15 Inhalation
  • Adult 1.5 1.5 0.29 1.5 1.5 12 2.0 0
  • Teen 1.5 1.5 0.35 1.6 1.6 15 2.4 0
  • Child 1.3 1.3 0.43 1.4 1.4 18 2.1 0
  • Infant 0.76 0.75 0.21 0.85 0.83 16 1.3 0 All
  • Adult 8.5 8.6 7.3 8.6 8.6 19 9.2 15
  • Teen 8.5 8.6 7.4 8.6 8.7 22 9.5 15
  • Child 8.4 8.4 7.5 8.5 8.5 25 9.2 15
  • Infant 7.8 7.8 7.3 7.9 7.9 23 8.5 15 Residence External (0.66 mi WNW)
  • Plume 0.78 0.78 0.78 0.78 0.78 0.78 0.79 1.8
  • Ground 0.13 0.13 0.13 0.13 0.13 0.13 0.13 0.15
  • Total 0.90 0.90 0.90 0.90 0.90 0.90 0.92 1.9 Inhalation
  • Adult 0.18 0.19 0.035 0.19 0.19 1.5 0.25 0
  • Teen 0.19 0.19 0.042 0.20 0.20 1.8 0.29 0
  • Child 0.16 0.16 0.052 0.18 0.18 2.2 0.25 0
  • Infant 0.095 0.094 0.026 0.11 0.10 1.9 0.16 0 Vegetable Garden Vegetables (1.15 mi WNW)
  • Adult 0.57 0.57 2.3 0.58 0.56 1.5 0.55 0
  • Teen 0.85 0.85 3.7 0.87 0.85 2.1 0.83 0
  • Child 1.9 1.9 8.9 1.9 1.9 4.2 1.9 0 11.3-7 Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 11.3-4 (Sheet 2 of 2)

Gaseous Radioactive Effluent Doses per Reactor for the Maximally Exposed Individual Dose per Reactor (mrem/yr)

Location Pathway Total Body GI-Tract Bone Liver Kidney Thyroid Lung Skin Meat Animal Meat (0.70 mi WNW)

  • Adult 0.44 0.46 2.0 0.44 0.44 0.51 0.44 0
  • Teen 0.36 0.37 1.6 0.36 0.36 0.41 0.36 0
  • Child 0.65 0.66 3.1 0.66 0.65 0.73 0.65 0 MEI All
  • Adult 2.1 2.1 5.2 2.1 2.1 4.4 2.2 1.9
  • Teen 2.3 2.3 6.3 2.3 2.3 5.2 2.4 1.9
  • Child 3.6 3.6 13 3.7 3.6 8.0 3.7 1.9
  • Infant 1.0 1.0 0.93 1.0 1.0 2.8 1.1 1.9 Maximum 3.6 3.6 13 3.7 3.6 8.0 3.7 1.9 Group Child Child Child Child Child Child Child All 11.3-8 Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 11.3-5 (Sheet 1 of 2)

Gaseous Radioactive Effluent Doses for the Site for the Maximally Exposed Individual Site Dose (mrem/yr)

Location Pathway Total Body GI-Tract Bone Liver Kidney Thyroid Lung Skin Site Boundary External (0.21 mi WNW)

  • Plume 40 40 40 40 40 40 41 84
  • Ground 2.9 2.9 2.9 2.9 2.9 2.9 2.9 3.3
  • Total 43 43 43 43 43 43 43 88 Inhalation
  • Adult 4.8 5.0 0.94 5.0 5.1 41 6.6 0
  • Teen 4.9 5.0 1.2 5.2 5.3 52 7.7 0
  • Child 4.3 4.3 1.4 4.7 4.7 62 6.7 0
  • Infant 2.5 2.5 0.73 2.8 2.8 55 4.2 0 All
  • Adult 48 48 44 48 48 84 50 88
  • Teen 48 48 44 48 48 95 51 88
  • Child 47 47 44 48 48 100 50 88
  • Infant 45 45 44 46 46 98 48 88 Residence External (0.66 mi WNW)
  • Plume 5.0 5.0 5.0 5.0 5.0 5.0 5.1 11
  • Ground 0.43 0.43 0.43 0.43 0.43 0.43 0.43 0.51
  • Total 5.4 5.4 5.4 5.4 5.4 5.4 5.5 11 Inhalation
  • Adult 0.60 0.62 0.11 0.63 0.64 5.1 0.82 0
  • Teen 0.61 0.63 0.14 0.65 0.66 6.4 0.96 0
  • Child 0.54 0.54 0.17 0.58 0.59 7.6 0.82 0
  • Infant 0.31 0.31 0.089 0.35 0.34 6.8 0.52 0 Vegetable Garden Vegetables (1.15 mi WNW)
  • Adult 1.1 1.1 3.7 1.1 1.0 4.0 1.0 0
  • Teen 1.5 1.5 5.8 1.6 1.5 5.2 1.4 0
  • Child 3.1 3.0 14 3.2 3.1 10 3.0 0 11.3-9 Revision 2

Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 11.3-5 (Sheet 2 of 2)

Gaseous Radioactive Effluent Doses for the Site for the Maximally Exposed Individual Site Dose (mrem/yr)

Location Pathway Total Body GI-Tract Bone Liver Kidney Thyroid Lung Skin Meat Animal Meat (0.70 mi WNW)

  • Adult 0.70 0.75 2.7 0.70 0.69 0.90 0.68 0
  • Teen 0.55 0.58 2.3 0.56 0.55 0.70 0.54 0
  • Child 0.96 0.98 4.3 0.98 0.96 1.2 0.96 0 MEI All
  • Adult 7.8 7.9 12 7.9 7.8 15 8.0 11
  • Teen 8.1 8.1 14 8.2 8.1 18 8.4 11
  • Child 10 10 23 10 10 24 10 11
  • Infant 5.8 5.8 5.5 5.8 5.8 12 6.0 11 Maximum 10 10 23 10 10 24 10 11 Group Child Child Child Child Child Child Child All 11.3-10 Revision 2
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