Text

TSD-14-019, Revision 0, Radionuclides of Concern for Soil and Basement Fill Model Source Terms
	ML15344A386
Person / Time
Site:	Zion File:ZionSolutions icon.png
Issue date:	12/18/2014
From:	Farr H, Wojtkowiak D, Yetter R; ZionSolutions
To:	; Office of Nuclear Material Safety and Safeguards
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ML15344A344	List: ML15344A342; ML15344A355; ML15344A356; ML15344A357; ML15344A358; ML15344A359; ML15344A361; ML15344A362; ML15344A363; ML15344A385; ML15344A386; ML15344A388; ML15344A389; ML15344A390; ML15344A391; ML15344A392; ML15344A393; ML15344A394; ML15344A413; ZS-2013-0082, NPDES Permit for Discharge; ZS-2015-0163, September 24, 2014 Email to Terry Sullivan;
References
	ZS-2015-0163 TSD-14-019, Rev. 0
	Download: ML15344A386 (31)
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Technical Support Document TSD 14-019 Radionuclides of Concern for Soil and Basement Fill Model Source Terms Revision 0 Originator: ___ _______________________ Date: ___12/18/14 _______

Harvey Farr Reviewer: __(signature on file)____________________ Date:__12/18/14_________

Dave Wojkowiak Approval: __(signature on file)____________________ Date:__12/18/14_________

Robert F. Yetter

TSD 14-019 Revision 0 Summary of Changes in this Revision:

Rev. 0 -Initial issuance.

Page 2 of 31

TSD 14-019 Revision 0

1. PURPOSE ...................................................................................................................................... 4

2. DISCUSSION ................................................................................................................................ 4 2.1. TSD 11-001 Initial Suite of Potential Radionuclides ........................................... 4 2.2. Radionuclides Identified in Characterization Data ............................................... 5 2.3. Pathway Dose Factors......................................................................................... 12

3. CALCULATIONS ....................................................................................................................... 15 3.1. Normalized End State Basement Fill Source Terms .......................................... 15 3.2. Basement Fill Doses for Normalized Source Terms .......................................... 17 3.3. End State Basement Fill Radionuclide Mixes .................................................... 22 3.4. Soil Radionuclides of Concern ........................................................................... 23

4. CONCLUSION............................................................................................................................ 28

5. REFERENCES ............................................................................................................................ 29

6. ATTACHMENTS........................................................................................................................ 29 6.1. Attachment A - Concrete Characterization Core Sample, Locations, and Analyses ....................................................................................................... 30 LIST OF TABLES Table 1 - TSD 11-001 Rev. 1 List of Radionuclides of Concern ............................................................. 4 Table 2 - Estimated January 1, 2013 Source Terms from On-Site Gamma Spectroscopy Results .......... 6 Table 3 - Off-Site Laboratory Suite of Radionuclides and Analysis Methods ......................................... 6 Table 4 - Hard-to-Detect Radionuclides from Off-Site Analysis and Table 2 Scaling Nuclide .............. 7 Table 5 - Estimated January 1, 2013 Unit 1 & 2 Reactor Building and Auxiliary Building Source Terms ......................................................................................................................................... 8 Table 6 - January 1, 2013 Radionuclide Percent of Total Estimated Source Term for Each Area ......... 9 Table 7 - Estimated July 1, 2018 Unit 1 & 2 Reactor Building and Auxiliary Building Source Terms 10 Table 8 - July 1, 2018 Radionuclide Percent of Total Estimated Source Term for Each Area ............. 11 Table 9 - Radionuclides of Concern Evaluated in Characterization Samples at the Zion Power Plant . 12 Table 10 - Groundwater Pathway Dose Factors for Initial Suite of Nuclides of Concern .................... 13 Table 11 - Drill Spoils Dose Factors ...................................................................................................... 14 Table 12 - Combined Dose Factor for Groundwater and Drill Spoils .................................................... 15 Table 13 - January 1, 2013 End State Concrete Source Terms Normalized to One Curie. .................... 16 Table 14- July 1, 2018 Concrete Source Terms Normalized to One Curie. ........................................... 16 Table 15 - January 1, 2013 Calculated Dose for Normalized 1 Ci Source Term ................................... 18 Table 16 - July 1, 2018 Calculated Dose for Normalized 1 Ci Source Term ......................................... 19 Table 17 - Basement July1, 2018 Mix Individual Nuclide Percent of Total Dose ................................ 20 Table 18 - July 1, 2018 Unit 1 and Unit 2 Containment Normalized Composite Mixes ....................... 21 Table 19 - Basement Fill End State July 1, 2018 Radionuclide Mixes for FSS ..................................... 22 Table 20 - ROCs Only Basement Fill End State July 1, 2018 Radionuclide Mixes for FSS ................ 23 Table 21 - ZSRP Soil DCGLs ................................................................................................................ 24 Table 22 - July 1, 2018 Normalized Concrete and RCS Pipe Mix Soil Doses....................................... 24 Table 23 - Soil July1, 2018 Mix Individual Nuclide Percent of Total Dose .......................................... 25 Table 24 - Soil Radionuclides of Concern and Insignificant Dose ........................................................ 26 Table 25 - Basement Fill End State July 1, 2018 Radionuclide Mixes for Soil FSS ............................. 27 Table 26 - ROCs Only Soils July 1, 2018 Radionuclide Mixes for FSS ................................................ 28 Page 3 of 31

TSD 14-019 Revision 0

1. PURPOSE This technical support document (TSD) refines the initial selection of radionuclides of concern (ROCs) for decommissioning at the Zion Station Restoration Project (ZSRP) completed in October of 2012. (1) The list of ROCs was evaluated using Containment Building(s) and Auxiliary Building concrete core analysis data to evaluate the dose significance of each radionuclide in the end state model.

2. DISCUSSION 2.1. TSD 11-001 Initial Suite of Potential Radionuclides The initial suite of potential radionuclides was used to help define sample analysis requirements associated with decommissioning activities including characterization activities and license termination plan (LTP) development. It was expected that as additional samples were collected and analyzed that this initial suite of radionuclides would be updated and would eventually represent those long lived radionuclides with a potential to be present at the time of final status survey (FSS).

(1) The TSD developed an initial suite of potential radionuclides based upon a review of Industry Guidance Documents NUREG/CR-3474 (2), NUREG/CR-4289 (3) and WINCO-1191 (4). The review also included evaluation of 19 post-shutdown waste stream analysis results. The positively identified radionuclides in the samples were decay corrected to January 1, 2011. Positively identified radionuclides whose decayed fractions of the total mix were equal to, or greater than, 0.0001 (e.g. 0.01%) were included in the ROCs developed from industry guidance. Radionuclides were eliminated if they were not identified in ZSRP samples or were less than 0.01% of the theoretical concentrations. The final list of ROCs was provided in Table 5-2 of TSD 11-001 and is provided as Table 1 below.

Table 1 - TSD 11-001 Rev. 1 List of Radionuclides of Concern Half Half Half Life Life Life Radionuclide (years) Radionuclide (years) Radionuclide (years)

H-3 1.24E+01 Nb-94 2.03E+04 Eu-154 8.80E+00 C-14 5.73E+03 Tc-99 2.13E+05 Np-237 2.14E+06 Fe-55 2.70E+00 Sb-125 2.77E+00 Pu-238 8.77E+01 Ni-59 7.50E+04 Cs-134 2.06E+00 Pu-239/240 2.41E+04 Co-60 5.27E+00 Cs-137 3.00E+01 Pu-241 1.44E+01 Ni-63 9.60E+01 Pm-147 2.62E+00 Am-241 4.32E+02 Sr-90 2.91E+01 Eu-152 1.33E+01 Am-243 7.38E+03 Cm-243/244 2.85E+01 The TSD stated, Some radionuclides may prove not to have been present, some radionuclides may be removed with the removal of a specific source term, some radionuclides may continue to decay to insignificant activity concentrations, and some radionuclides may be eliminated due to insignificant dose contributions. Eventually an updated suite of radionuclides representative of radionuclides with a potential to be present at the time of final status survey will be prepared. (1)

Additional characterization data has since been obtained through direct sampling of the Unit 1 and Unit 2 Containment Buildings, Auxiliary Building, Turbine Building and Crib House and land area Page 4 of 31

TSD 14-019 Revision 0 characterization surveys and sampling. In addition waste stream samples were obtained for the interior surface of reactor coolant piping in September 2011 in Unit 2 and April 2012 in Unit 1.

2.2. Radionuclides Identified in Characterization Data The radionuclides identified to date in land area surveys or samples have been Cs-137 and Co-60 at concentrations less than 1 pCi/g. Therefore there has been insufficient source term to date to support analysis for hard-to-detect radionuclides in soil. The results of concrete core samples were evaluated separately for the Reactor Building Containments (5), Auxiliary Building (6) and the Turbine Building. (7). The only ROC positively identified in the Turbine Building concrete cores was Cs-137. Due to the low levels present, all other nuclides were below the minimum detectable activity (MDA). Concrete cores were also obtained in the Crib House, but these were for the purpose of identifying background concentrations in clean, non-contaminated concrete. The potential end state concrete of the Fuel Handling Building has not yet been sampled. Only portions of the Transfer Canal and Spent Fuel Pool below the 588 foot elevation could potentially remain during the end state for the Fuel Handling Building. The remainder is above the 588 foot elevation and will be disposed of as waste. Since the Spent Fuel Pool is still in use, no characterization of end state concrete under the liner has been possible. Similarly, the Waste Water Treatment Facility (WWTF) is still in use and the end state concrete has not yet been characterized.

Concrete core locations in the Auxiliary Building and Containments were chosen based upon contact dose rates and/or visible indication of leakage. This ensured the core samples would be from the most contaminated locations and provide good indications of hard-to-detect (HTD) nuclide source terms. As seen in Attachment A, there were 69 concrete cores from the Containment Building(s), Auxiliary Building, and Turbine Building collected and analyzed on site. As seen in Attachment A, the Containment Building samples included concrete cores from the Under Vessel Incore areas where activated concrete was present. The concrete cores were sectioned into 1/2 inch slices or pucks and analyzed on the top and bottom of each slice by on-site gamma spectroscopy.

Five plant related radionuclides were positively identified; Co-60, Cs-134, Cs-137, Eu-152, and Eu-154. As described in the TSDs, (5), (6), (7) the top and bottom results of each puck were averaged to determine the activity in units of picocuries per gram (pCi/g) at depth. In order to ensure the estimated source terms were bounding and conservative, the MDA was used when no activity was positively identified. The concentrations were decay corrected to January 1, 2013. This provided a worst case depth profile for each core in 1/2 inch increments in pCi/g. The calculated surface area of the walls and floors of the end state structure (8), (6), (7) was multiplied by 1/2 inch [1.27 centimeters (cm)] to calculate the volume of concrete equal to a 1/2 inch thickness for the location sampled. A density of 2.40 grams (5) per cubic centimeter (g/cm3) was used to calculate the mass equal to the 1/2 inch thick volume. The estimated masses at each 1/2 depth were multiplied times the average in-house gamma spectroscopy concentration to determine the total estimated source term in each area based upon the on-site gamma spectroscopy results as shown in Table 2. The Turbine Building estimated source term consists of Cs-137 with no other ROCs above the MDA identified.

The Turbine Building source term is insignificant in comparison to the Auxiliary Building and Containment Buildings. (7)

In addition, the top pucks of 27 concrete cores were sent for off-site laboratory analysis that included the Table 3 full suite of 39 radionuclides as opposed to the 22 radionuclides identified in TSD 11-001 Rev. 1 list in Table 1. (1) The pucks sent for analysis tended to be the highest activity Page 5 of 31

TSD 14-019 Revision 0 ones in order to ensure sufficient source term to quantify HTD nuclide ratios relative to the Table 3 scaling nuclides.

Table 2 - Estimated January 1, 2013 Source Terms from On-Site Gamma Spectroscopy Results Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bldg Total Total Total 542' 542' Total Contam Total 568' Floor & Overall Total 568' Floor & Overall 542' Wall Overall Nuclide Floor Ci Walls Ci Total Ci Floor Ci Walls Ci Total Ci Floor Ci 542' Ci Total Ci Co-60 2.08E-01 1.19E-03 2.09E-01 2.55E-01 1.53E-03 2.57E-01 1.2E-02 3.79E-03 1.57E-02 Cs-134 2.00E-03 5.95E-05 2.06E-03 1.07E-03 6.60E-05 1.13E-03 3.4E-04 2.06E-04 5.47E-04 Cs-137 6.80E+00 3.94E-03 6.80E+00 7.24E-01 8.59E-04 7.25E-01 5.99E-01 1.10E-01 7.09E-01 Eu-152 ND 7.49E-03 2.13E-02 ND 1.27E-02 1.31E-02 ND ND ND Eu-154 ND 4.07E-04 7.33E-03 ND 7.26E-04 9.96E-04 ND ND ND ND = Not Detected Above MDA Table 3 - Off-Site Laboratory Suite of Radionuclides and Analysis Methods Radionuclide Analytical Method Ac-228 Actinium-228 LANL ER-130 Modified Am-241 Americium-241 EML Am-01 Modified Am-243 Americium-243 EML Am-01 Modified Sb-125 Antimony-125 LANL ER-130 Modified Ba-133 Barium-133 LANL ER-130 Modified Bi-214 Bismuth-214 LANL ER-130 Modified C-14 Carbon-14 EPA 520.0 Modified Cs-134 Cesium-134 LANL ER-130 Modified Cs-137 Cesium-137 LANL ER-130 Modified Co-60 Cobalt-60 LANL ER-130 Modified Cm-243/244 Curium-243/244 EML Am-01 Modified Eu-152 Europium-152 LANL ER-130 Modified Eu-154 Europium-154 LANL ER-130 Modified Eu-155 Europium-155 LANL ER-130 Modified Ho-166 Holmium-166m LANL ER-130 Modified I-129 Iodine-129 LANL ER-130 Modified Fe-55 Iron-55 EML Fe-01-01 Modified Pb-210 Lead-210 LANL ER-130 Modified Pb-212 Lead-212 LANL ER-130 Modified Pb-214 Lead-214 LANL ER-130 Modified Mn-54 Manganese-54 LANL ER-130 Modified Np-237 Neptunium-237 EIChroM ACW08 Mod Ni-59 Nickel-59 ASTM 3500-Ni Modified Ni-63 Nickel-63 ASTM 3500-Ni Modified Nb-94 Niobium-94 LANL ER-130 Modified Page 6 of 31

TSD 14-019 Revision 0 Radionuclide Analytical Method Pu-238 Plutonium-238 EML Pu-02 Modified Pu-239/240 Plutonium-239/240 EML Pu-02 Modified Pu-241 Plutonium-241 EML Pu-02 Modified K-40 Potassium-40 LANL ER-130 Modified Pm-145 Promethium-145 LANL ER-130 Modified Pm-147 Promethium-147 EML Pm-01 Modified Rn-226 Radium-226 LANL ER-130 Modified Ag-110m Silver-108m LANL ER-130 Modified Sr-90 Strontium-90 EIChroM SRW01 Modified Tc-99 Technetium-99 EIChroM TCS01 Modified Tl-208 Thallium-208 LANL ER-130 Modified Th-234 Thorium-234 LANL ER-130 Modified H-3 Tritium LANL ER-210 Modified U-235 Uranium-235 LANL ER-130 Modified The off-site analysis results including MDAs were decay corrected to January 1, 2013 and used to calculate average concentrations and estimate source terms in the first half inch in each building as described above. As is documented in the off-site laboratory reports and in the technical support documents (5) (6), three radionuclides I-129, Pm-145, and Pm-147 were eliminated from the decayed mixes due to false positive results due to interference from very high Cs-137 concentrations. The estimated source terms in the first half inch were used to develop scaling factors for each area shown in Table 2. The scaling factors applied were specific to each area based upon the ratio of radionuclides in the concrete cores for that area. Since pucks from only 27 of the 69 concrete cores were sent for off-site analysis, the positively identified HTD radionuclide source terms were estimated by multiplying the scaling factor times the Table 2 source term of the scaling nuclide. (5) (6) The scaling nuclide used for each HTD radionuclide positively identified is shown in Table 4. Co-60 was used to scale metallic activation products, Eu-152 was used for concrete activation products and Cs-137 was used for the remaining radionuclides. The calculated source terms from on-site gamma spectroscopy results were used for Cs-134 and Eu-154.

Table 4 - Hard-to-Detect Radionuclides from Off-Site Analysis and Table 2 Scaling Nuclide Scaling Scaling Scaling Nuclide Nuclide Nuclide Nuclide Nuclide Nuclide H-3 Cs-137 Ag-108m Co-60 Eu-155 Eu-152 C-14 Cs-137 Sb-125 Sb-125 Np-237 Cs-137 Fe-55 Co-60 I-129 NA Pu-238 Cs-137 Ni-59 Co-60 Cs-134 Cs-134 Pu-239 Cs-137 Co-60 Co-60 Cs-137 Cs-137 Pu-240 Cs-137 Ni-63 Co-60 Pm-145 NA Pu-241 Cs-137 Sr-90 Cs-137 Pm-147 NA Am-241 Cs-137 Nb-94 Co-60 Eu-152 Eu-152 Am-243 Cs-137 Tc-99 Cs-137 Eu-154 Eu-154 Cm-243 Cs-137 Page 7 of 31

TSD 14-019 Revision 0 Cm-244 Cs-137 NA = Not Applicable due to compromised results. See TSD 13-006 and TSD 14-013 As noted above, Ag-108m and Eu-155 were positively detected in some samples. Based upon this, they were added to the list of radionuclides of concern in Table 1. The source terms [in units of curies (Ci)] estimated by this method as identified in the Containment Building(s) and Auxiliary Building TSDs (5), (6), are provided in Table 5. It is important to note that these are very conservative estimates of the source terms in concrete at the time of characterization. The estimates are conservative because the MDA values were used for each of the Table 2 radionuclides even when it was not positively identified in that puck. This biased the source term of the scaling nuclides high. In addition, the locations with the highest contact dose rates and/or visible evidence of leaks were chosen for concrete core sampling, which again biased the scaling nuclide average concentrations and total activities high as the average concentration is applied to the entire surface area. In addition, all concrete interior to the steel liners in the Unit 1 and 2 Containment Buildings is planned to be removed and Auxiliary Building concrete will be remediated to ALARA levels. Thus the Table 5 source terms are extremely conservative and bounding with regard to potential end state source terms embedded in the concrete. In addition, the samples from inside the Unit 1 and Unit 2 reactor coolant system (RCS) whose results are provided in Attachment A were decay corrected to January 1, 2013.

Table 5 - Estimated January 1, 2013 Unit 1 & 2 Reactor Building and Auxiliary Building Source Terms Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bldg Total Total 542' Total 542' Contam Total 568' Floor & Overall Total 568' Floor & Overall Total 542' Wall 542' Overall Nuclide Floor Ci Walls Ci Total Ci Floor Ci Walls Ci Total Ci Floor Ci Ci Total Ci H-3 7.15E-03 4.69E-04 7.62E-03 1.07E-03 2.2E-04 1.29E-03 1.87E-03 1.22E-04 1.99E-03 C-14 7.46E-04 5.82E-06 7.52E-04 5.34E-05 2.3E-06 5.57E-05 2.88E-04 8.16E-05 3.69E-04 Fe-55 4.88E-03 3.93E-05 4.92E-03 2.11E-02 1.4E-04 2.13E-02 3.25E-03 3.13E-04 3.56E-03 Ni-59 1.03E-03 7.31E-05 1.11E-03 4.43E-03 3.0E-04 4.73E-03 3.83E-03 3.39E-04 4.17E-03 Co-60 2.08E-01 1.19E-03 2.09E-01 2.55E-01 1.5E-03 2.57E-01 1.19E-02 3.79E-03 1.57E-02 Ni-63 1.47E-01 5.21E-04 1.48E-01 8.38E-01 2.5E-03 8.41E-01 1.72E-01 3.19E-02 2.04E-01 Sr-90 3.64E-03 1.23E-06 3.64E-03 7.02E-05 5.7E-07 7.08E-05 2.56E-04 2.31E-04 4.87E-04 Nb-94 9.79E-04 1.06E-05 9.90E-04 5.47E-03 1.1E-05 5.48E-03 9.38E-05 1.27E-05 1.07E-04 Tc-99 9.08E-04 2.16E-06 9.10E-04 1.04E-05 4.1E-07 1.09E-05 1.19E-04 1.53E-05 1.34E-04 Ag-108m 1.78E-03 1.03E-05 1.79E-03 8.57E-03 1.3E-04 8.70E-03 1.34E-04 1.15E-05 1.45E-04 Sb-125 7.43E-03 1.36E-05 7.45E-03 1.27E-03 6.6E-06 1.27E-03 4.68E-04 1.12E-04 5.80E-04 Cs-134 2.00E-03 5.95E-05 2.06E-03 1.07E-03 6.6E-05 1.13E-03 3.41E-04 2.06E-04 5.47E-04 Cs-137 6.80E+00 3.94E-03 6.80E+00 7.24E-01 8.6E-04 7.25E-01 5.99E-01 1.10E-01 7.09E-01 Eu-152 1.38E-02 7.49E-03 2.13E-02 3.92E-04 1.3E-02 1.31E-02 1.47E-04 4.68E-05 1.94E-04 Eu-154 6.92E-03 4.07E-04 7.33E-03 2.70E-04 7.3E-04 9.96E-04 9.46E-05 2.71E-05 1.22E-04 Eu-155 2.42E-03 1.97E-04 2.62E-03 3.82E-04 2.6E-04 6.37E-04 1.18E-04 2.66E-05 1.44E-04 Np-237 9.11E-06 1.32E-07 9.24E-06 5.42E-07 6.4E-08 6.07E-07 2.81E-06 8.43E-07 3.66E-06 Pu-238 6.41E-05 2.35E-07 6.43E-05 9.29E-07 4.8E-08 9.76E-07 1.09E-05 3.66E-07 1.13E-05 Pu-239 2.24E-05 1.05E-07 2.25E-05 4.71E-07 2.1E-08 4.92E-07 4.29E-06 1.78E-07 4.47E-06 Page 8 of 31

TSD 14-019 Revision 0 Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bldg Total Total 542' Total 542' Contam Total 568' Floor & Overall Total 568' Floor & Overall Total 542' Wall 542' Overall Nuclide Floor Ci Walls Ci Total Ci Floor Ci Walls Ci Total Ci Floor Ci Ci Total Ci Pu-240 2.24E-05 1.05E-07 2.25E-05 4.71E-07 2.1E-08 4.92E-07 4.29E-06 1.78E-07 4.47E-06 Pu-241 7.99E-04 1.03E-05 8.10E-04 6.89E-05 4.8E-06 7.37E-05 2.63E-04 4.48E-05 3.08E-04 Am-241 7.94E-04 3.57E-07 7.94E-04 1.51E-05 5.5E-08 1.52E-05 9.87E-06 8.35E-07 1.07E-05 Am-243 1.50E-05 1.68E-07 1.52E-05 1.53E-06 7.1E-08 1.60E-06 7.12E-06 8.39E-07 7.96E-06 Cm-243 8.01E-05 1.48E-07 8.02E-05 1.66E-06 3.2E-08 1.70E-06 2.64E-06 5.62E-07 3.20E-06 Cm-244 8.00E-05 1.47E-07 8.02E-05 1.66E-06 3.2E-08 1.70E-06 2.63E-06 5.60E-07 3.19E-06 Total 7.21E+00 1.44E-02 7.22E+00 1.86E+00 1.95E-02 1.88E+00 7.94E-01 1.47E-01 9.41E-01 NR = Not Reported The as left, post remediation source terms will be determined by post remediation surveys of the end state structures. Despite the fact that source terms are likely to be substantially lower than these initial estimates, it is unlikely that the radionuclide ratios or profiles will be changed as a result of remediation activities. The radionuclide ratios corresponding to the Table 5 estimated activities are provided in Table 6.

Table 6 - January 1, 2013 Radionuclide Percent of Total Estimated Source Term for Each Area Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bldg Total Total Total Total Incore Total 542' Total Contam 568' 542' Floor Overall 568' Floor & Overall 542' Wall Overall Floor & Walls Total Floor Walls Total Floor 542' Total Nuclide Percent Percent Percent Percent Percent Percent Percent Percent Percent H-3 0.10% 3.25% 0.11% 0.06% 1.13% 0.07% 0.23% 0.08% 0.21%

C-14 0.01% 0.04% 0.01% 0.00% 0.01% 0.00% 0.04% 0.06% 0.04%

Fe-55 0.07% 0.27% 0.07% 1.14% 0.70% 1.13% 0.41% 0.21% 0.38%

Ni-59 0.01% 0.51% 0.02% 0.24% 1.55% 0.25% 0.48% 0.23% 0.44%

Co-60 2.88% 8.22% 2.89% 13.70% 7.84% 13.64% 1.49% 2.58% 1.66%

Ni-63 2.04% 3.61% 2.05% 45.02% 12.94% 44.69% 21.70% 21.66% 21.69%

Sr-90 0.05% 0.01% 0.05% 0.00% 0.00% 0.00% 0.03% 0.16% 0.05%

Nb-94 0.01% 0.07% 0.01% 0.29% 0.05% 0.29% 0.01% 0.01% 0.01%

Tc-99 0.01% 0.01% 0.01% 0.00% 0.00% 0.00% 0.01% 0.01% 0.01%

Ag-108m 0.02% 0.07% 0.02% 0.46% 0.67% 0.46% 0.02% 0.01% 0.02%

Sb-125 0.10% 0.09% 0.10% 0.07% 0.03% 0.07% 0.06% 0.08% 0.06%

Cs-134 0.03% 0.41% 0.03% 0.06% 0.34% 0.06% 0.04% 0.14% 0.06%

Cs-137 94.30% 27.28% 94.17% 38.90% 4.40% 38.54% 75.38% 74.68% 75.27%

Eu-152 0.19% 51.89% 0.29% 0.02% 65.28% 0.70% 0.02% 0.03% 0.02%

Eu-154 0.10% 2.82% 0.10% 0.01% 3.72% 0.05% 0.01% 0.02% 0.01%

Eu-155 0.03% 1.36% 0.04% 0.02% 1.31% 0.03% 0.01% 0.02% 0.02%

Np-237 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00%

Pu-238 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00%

Page 9 of 31

TSD 14-019 Revision 0 Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bldg Total Total Total Total Incore Total 542' Total Contam 568' 542' Floor Overall 568' Floor & Overall 542' Wall Overall Floor & Walls Total Floor Walls Total Floor 542' Total Nuclide Percent Percent Percent Percent Percent Percent Percent Percent Percent Pu-239 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00%

Pu-240 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00%

Pu-241 0.01% 0.07% 0.01% 0.00% 0.02% 0.00% 0.03% 0.03% 0.03%

Am-241 0.01% 0.00% 0.01% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00%

Am-243 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00%

Cm-243 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00%

Cm-244 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00%

Total 100% 100% 100% 100 % 100% 100% 100% 100% 100%

NR = Not Reported The source terms in each area are dominated by Cs-137, Ni-63 and Co-60. Many radionuclides constitute less than 0.01% of the mix.

The earliest potential date at which license termination could be achieved is estimated at July 1, 2018. As seen in Table 7 this resulted in an 11% to 25% reduction in the overall concrete source term.

Table 7 - Estimated July 1, 2018 Unit 1 & 2 Reactor Building and Auxiliary Building Source Terms Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bldg Total Total Total Total 542' 542' Contam Half-Life 568' Floor & Overall Total 568' Floor & Overall Total 542' Wall 542' Overall Nuclide years Floor Ci Walls Ci Total Ci Floor Ci Walls Ci Total Ci Floor Ci Ci Total Ci H-3 1.23E+01 5.25E-03 3.44E-04 5.60E-03 7.86E-04 1.6E-04 9.49E-04 1.37E-03 8.97E-05 1.46E-03 C-14 5.70E+03 7.45E-04 5.81E-06 7.51E-04 5.34E-05 2.3E-06 5.56E-05 2.88E-04 8.16E-05 3.69E-04 Fe-55 2.74E+00 1.21E-03 9.76E-06 1.22E-03 5.25E-03 3.4E-05 5.28E-03 8.07E-04 7.77E-05 8.85E-04 Ni-59 1.01E+05 1.03E-03 7.31E-05 1.11E-03 4.43E-03 3.0E-04 4.73E-03 3.83E-03 3.39E-04 4.17E-03 Co-60 5.27E+00 1.01E-01 5.76E-04 1.01E-01 1.24E-01 7.4E-04 1.25E-01 5.76E-03 1.84E-03 7.60E-03 Ni-63 1.00E+02 1.42E-01 5.02E-04 1.42E-01 8.07E-01 2.4E-03 8.09E-01 1.66E-01 3.07E-02 1.97E-01 Sr-90 2.88E+01 3.19E-03 1.08E-06 3.19E-03 6.15E-05 5.0E-07 6.20E-05 2.24E-04 2.02E-04 4.27E-04 Nb-94 2.03E+04 9.79E-04 1.06E-05 9.90E-04 5.47E-03 1.1E-05 5.48E-03 9.38E-05 1.27E-05 1.07E-04 Tc-99 2.11E+05 9.08E-04 2.16E-06 9.10E-04 1.04E-05 4.1E-07 1.09E-05 1.19E-04 1.53E-05 1.34E-04 Ag-108m 4.18E+02 1.76E-03 1.02E-05 1.77E-03 8.49E-03 1.3E-04 8.62E-03 1.33E-04 1.14E-05 1.44E-04 Sb-125 2.76E+00 1.87E-03 3.42E-06 1.87E-03 3.18E-04 1.7E-06 3.20E-04 1.17E-04 2.82E-05 1.46E-04 Cs-134 2.06E+00 3.16E-04 9.39E-06 3.25E-04 1.69E-04 1.0E-05 1.79E-04 5.38E-05 3.25E-05 8.63E-05 Cs-137 3.02E+01 5.99E+00 3.47E-03 5.99E+00 6.38E-01 7.6E-04 6.39E-01 5.28E-01 9.68E-02 6.25E-01 Eu-152 1.35E+01 1.04E-02 5.65E-03 1.61E-02 2.96E-04 9.6E-03 9.92E-03 1.11E-04 3.53E-05 1.46E-04 Eu-154 8.80E+00 4.49E-03 2.64E-04 4.75E-03 1.75E-04 4.7E-04 6.46E-04 6.13E-05 1.76E-05 7.89E-05 Eu-155 4.76E+00 1.09E-03 8.83E-05 1.18E-03 1.72E-04 1.1E-04 2.86E-04 5.28E-05 1.19E-05 6.48E-05 Np-237 2.14E+06 9.11E-06 1.32E-07 9.24E-06 5.42E-07 6.4E-08 6.07E-07 2.81E-06 8.43E-07 3.66E-06 Page 10 of 31

TSD 14-019 Revision 0 Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bldg Total Total Total Total 542' 542' Contam Half-Life 568' Floor & Overall Total 568' Floor & Overall Total 542' Wall 542' Overall Nuclide years Floor Ci Walls Ci Total Ci Floor Ci Walls Ci Total Ci Floor Ci Ci Total Ci Pu-238 8.77E+01 6.14E-05 2.25E-07 6.16E-05 8.89E-07 4.6E-08 9.35E-07 1.05E-05 3.51E-07 1.08E-05 Pu-239 2.41E+04 2.24E-05 1.04E-07 2.25E-05 4.71E-07 2.1E-08 4.92E-07 4.29E-06 1.78E-07 4.47E-06 Pu-240 6.56E+03 2.24E-05 1.04E-07 2.25E-05 4.71E-07 2.1E-08 4.92E-07 4.29E-06 1.78E-07 4.47E-06 Pu-241 1.44E+01 6.13E-04 7.89E-06 6.21E-04 5.28E-05 3.7E-06 5.65E-05 2.02E-04 3.43E-05 2.36E-04 Am-241 4.32E+02 7.87E-04 3.54E-07 7.87E-04 1.50E-05 5.5E-08 1.50E-05 9.78E-06 8.28E-07 1.06E-05 Am-243 7.37E+03 1.50E-05 1.68E-07 1.52E-05 1.53E-06 7.1E-08 1.60E-06 7.11E-06 8.38E-07 7.95E-06 Cm-243 2.85E+01 7.01E-05 1.30E-07 7.02E-05 1.46E-06 2.8E-08 1.48E-06 2.31E-06 4.92E-07 2.80E-06 Cm-244 1.81E+01 6.48E-05 1.19E-07 6.49E-05 1.35E-06 2.6E-08 1.37E-06 2.13E-06 4.54E-07 2.58E-06 Total 6.27E+00 1.10E-02 6.28E+00 1.59E+00 1.48E-02 1.61E+00 7.07E-01 1.30E-01 8.37E-01

% Reduction 13% 24% 13% 14% 24% 14% 11% 11% 11%

NR = Not Reported As seen in Table 8, the decay corrected end state source term continues to be comprised largely of Cs-137, Ni-63 and Co-60. If the Unit 1 and 2 Containment interior concrete is removed to the liner, only trace levels of contamination will remain. Consequently, the Auxiliary Building concrete will contain the bounding end state source term for the end state structures.

Table 8 - July 1, 2018 Radionuclide Percent of Total Estimated Source Term for Each Area Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bldg Total Total Total Incore 542' Total 542' Total Contam Total 568' Floor & Overall 568' Floor & Overall 542' Wall Overall Floor Walls Total Floor Walls Total Floor 542' Total Nuclide Percent Percent Percent Percent Percent Percent Percent Percent Percent H-3 0.084% 3.1% 0.089% 0.049% 1.098% 0.059% 0.194% 0.069% 0.174%

C-14 0.012% 0.053% 0.012% 0.003% 0.015% 0.003% 0.041% 0.063% 0.044%

Fe-55 0.019% 0.088% 0.019% 0.329% 0.228% 0.328% 0.114% 0.060% 0.106%

Ni-59 0.017% 0.662% 0.018% 0.278% 2.045% 0.294% 0.542% 0.260% 0.498%

Co-60 1.61% 5.22% 1.61% 7.76% 5.02% 7.74% 0.81% 1.41% 0.91%

Ni-63 2.26% 4.5% 2.27% 50.6% 16.44% 50.3% 23.47% 23.54% 23.48%

Sr-90 0.051% 0.010% 0.051% 0.004% 0.003% 0.004% 0.032% 0.155% 0.051%

Nb-94 0.016% 0.096% 0.0158% 0.343% 0.072% 0.341% 0.013% 0.010% 0.013%

Tc-99 0.014% 0.020% 0.014% 0.0007% 0.003% 0.0007% 0.017% 0.012% 0.016%

Ag-108m 0.028% 0.093% 0.028% 0.533% 0.878% 0.536% 0.019% 0.009% 0.017%

Sb-125 0.030% 0.031% 0.030% 0.020% 0.011% 0.020% 0.017% 0.022% 0.017%

Cs-134 0.005% 0.085% 0.005% 0.011% 0.070% 0.011% 0.008% 0.02% 0.010%

Cs-137 95.6% 31.5% 95.5% 40.0% 5.1% 39.7% 74.7% 74.3% 74.6%

Eu-152 0.166% 51.2% 0.256% 0.019% 65.01% 0.616% 0.016% 0.027% 0.017%

Eu-154 0.072% 2.4% 0.076% 0.011% 3.18% 0.040% 0.009% 0.013% 0.009%

Eu-155 0.017% 0.8% 0.019% 0.011% 0.774% 0.018% 0.007% 0.009% 0.008%

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TSD 14-019 Revision 0 Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bldg Total Total Total Incore 542' Total 542' Total Contam Total 568' Floor & Overall 568' Floor & Overall 542' Wall Overall Floor Walls Total Floor Walls Total Floor 542' Total Nuclide Percent Percent Percent Percent Percent Percent Percent Percent Percent Np-237 0.000% 0.001% 0.000% 0.000% 0.000% 0.000% 0.000% 0.001% 0.000%

Pu-238 0.001% 0.002% 0.001% 0.0001% 0.000% 0.0001% 0.001% 0.000% 0.001%

Pu-239 0.000% 0.001% 0.000% 0.0000% 0.000% 0.0000% 0.001% 0.000% 0.001%

Pu-240 0.000% 0.001% 0.000% 0.0000% 0.000% 0.0000% 0.001% 0.000% 0.001%

Pu-241 0.010% 0.071% 0.010% 0.003% 0.025% 0.004% 0.029% 0.026% 0.028%

Am-241 0.013% 0.003% 0.013% 0.001% 0.000% 0.001% 0.001% 0.001% 0.001%

Am-243 0.000% 0.002% 0.000% 0.0001% 0.000% 0.000% 0.001% 0.001% 0.001%

Cm-243 0.001% 0.001% 0.001% 0.0001% 0.000% 0.0001% 0.000% 0.000% 0.000%

Cm-244 0.001% 0.001% 0.001% 0.0001% 0.000% 0.0001% 0.000% 0.000% 0.000%

Total 100% 100% 100% 100% 100% 100% 100% 100% 100%

NR = Not Reported The radionuclides Ag-110m and Eu-155 were added to the Table 1 list since they were positively identified in the characterization samples. The list of potential ROCs developed for dose significance evaluations is shown in Table 9.

Table 9 - Radionuclides of Concern Evaluated in Characterization Samples at the Zion Power Plant Radionuclides Radionuclides Radionuclides Radionuclides Radionuclides Radionuclides H-3 Co-60 Tc-99 Cs-137 Eu-155 Pu-241 C-14 Ni-63 Ag-108m Pm-147 Np-237 Am-241 Fe-55 Sr-90 Sb-125 Eu-152 Pu-238 Am-243 Ni-59 Nb-94 Cs-134 Eu-154 Pu-239/240 Cm-243/244 The Table 9 list of ROCs were used for fate and transport screening evaluations using DUST MS and RESRAD models.

2.3. Pathway Dose Factors The fate and transport of the Table 9 ROCs in the Auxiliary Building end state was modeled by Brookhaven National Laboratories (BNL) using the DUST MS code. Although some of the radionuclides were not positively identified, they were retained in the list because they were previously identified in waste streams at ZSRP. The DUST MS results could be used to evaluate their dose significance if they are detected in end state FSSs or samples.

An evaluation for the Auxiliary Building was performed using the DUST MS model to determine the maximum concentration in the basement fill for the ROCs. (9) This evaluation used worst case distribution coefficients for potential basement fill materials. (10) The calculation assumed the future resident farmer well (11) was within each end state basement footprint. The inventory was based on a uniform contamination level of 1 pCi/m2 on the wall and floor surfaces. This contamination level was used for modeling convenience only. The Auxiliary Building has 6503 m2 of total wall and floor surface area below the 588 foot elevation, resulting in a total of 6503 pCi.

This equates to a source term of 6.50E-09 Ci per nuclide used in the DUST-MS model. Other buildings were modeled similarly as described in TSD 14-031. (9)

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TSD 14-019 Revision 0 The model assumed that the groundwater concentration of each contaminant was initially zero everywhere. The contamination in the Auxiliary Basement is found at depth in the concrete, predominantly in the floor. Diffusion Controlled Release was therefore used to estimate the rate of radionuclide release for the Auxiliary Building basement and Spent Fuel Pool. (9) The results of the DUST MS evaluation (9) and the REARAD results (12) were used to develop an initial suite of groundwater pathway dose factors (e.g., mrem/yr per mCi) in TSD 14-010 (12). These are provided in Table 10 for each of the Table 9 radionuclides and end state structures. As noted in TSD 14-010, the Spent Fuel Pool and Transfer Canal floor are at 576 elevation, leaving only 3 feet to the water table. The ground water pathway is therefore an implausible pathway and there are no groundwater pathway dose factors used for the Fuel Handling Building.

Table 10 - Groundwater Pathway Dose Factors for Initial Suite of Nuclides of Concern Not Valid Pathway Crib Aux Containment Spent Fuel Turbine House WWTF mrem/year mrem/year mrem/year mrem/year mrem/year mrem/year Radionuclide per mCi per mCi per mCi per mCi per mCi per mCi Ag-108m 5.47E-03 2.56E-02 7.46E-01 6.39E-03 5.46E-03 1.16E+00 Am-241 2.58E-01 1.15E+00 3.52E+01 2.86E-01 2.45E-01 5.22E+01 Am-243 2.63E-01 1.14E+00 3.59E+01 2.86E-01 2.45E-01 5.21E+01 C-14 6.49E-02 2.84E-01 8.92E+00 7.09E-02 6.08E-02 1.29E+01 Cm-243 2.59E-02 1.55E-01 3.54E+00 3.88E-02 3.33E-02 7.08E+00 Cm-244 1.74E-02 1.24E-01 2.37E+00 3.11E-02 2.67E-02 5.66E+00 Co-60 1.00E-04 1.14E-02 1.36E-02 2.87E-03 2.45E-03 5.21E-01 Cs-134 9.27E-03 1.98E-01 1.27E+00 4.94E-02 4.22E-02 9.03E+00 Cs-137 2.64E-02 1.57E-01 3.62E+00 3.92E-02 3.35E-02 7.17E+00 Eu-152 5.95E-05 3.87E-03 8.12E-03 9.68E-04 8.29E-04 1.76E-01 Eu-154 6.77E-05 5.62E-03 9.23E-03 1.41E-03 1.20E-03 2.56E-01 Eu-155 8.01E-06 8.72E-04 1.09E-03 2.18E-04 1.87E-04 3.98E-02 Fe-55 8.06E-07 1.51E-05 1.11E-04 3.77E-06 3.22E-06 6.85E-04 H-3 6.21E-03 2.72E-02 8.47E-01 6.80E-03 5.80E-03 1.23E+00 Nb-94 2.03E-03 8.84E-03 2.77E-01 2.21E-03 1.89E-03 4.04E-01 Ni-59 1.35E-04 5.87E-04 1.84E-02 1.47E-04 1.26E-04 2.67E-02 Ni-63 2.86E-04 1.61E-03 3.93E-02 4.01E-04 2.69E-04 7.31E-02 Np-237 4.92E+01 2.13E+02 6.70E+03 5.34E+01 4.57E+01 9.73E+03 Pm-147 3.00E-05 5.67E-04 4.10E-03 1.42E-04 1.22E-04 2.59E-02 Pu-238 2.11E-01 1.03E+00 2.87E+01 2.56E-01 2.19E-01 4.66E+01 Pu-239 2.61E-01 1.14E+00 3.56E+01 2.84E-01 2.43E-01 5.18E+01 Pu-240 2.61E-01 1.14E+00 3.56E+01 2.84E-01 2.43E-01 5.18E+01 Pu-241 4.57E-03 3.65E-02 6.25E-01 9.11E-03 7.80E-03 1.66E+00 Sb-125 1.04E-02 1.94E-01 1.42E+00 4.84E-02 4.13E-02 8.78E+00 Sr-90 3.29E-01 4.51E+00 4.50E+01 1.13E+00 9.66E-01 2.06E+02 Tc-99 1.48E-01 6.44E-01 2.02E+01 1.61E-01 1.38E-01 2.93E+01 Page 13 of 31

TSD 14-019 Revision 0 TSD 14-021 (13) evaluated alternate exposure scenarios and found that the well drilling scenario has the potential to result in significant exposures. Dose factors were developed for drill spoils in TSD 14-021. (13) The drill spoils pathway dose factors are provided in Table 11.

Table 11 - Drill Spoils Dose Factors Aux Crib Building CTMT Turbine House WWTF Drill Drill FHB Drill Drill Drill Drill Spoils Spoils Spoils Spoils Spoils Spoils mrem/yr mrem per mrem/yr mrem/yr mrem/yr mrem/yr Nuclide per mCi mCi per mCi per mCi per mCi per mCi Ag-108m 1.23E-02 2.05E-02 1.85E-01 6.61E-03 1.23E-02 1.57E-01 Am-241 1.51E-04 3.14E-04 3.06E-03 9.76E-05 1.49E-04 2.91E-03 Am-243 1.58E-03 2.73E-03 2.51E-02 8.75E-04 1.55E-03 2.16E-02 C-14 3.08E-07 4.27E-07 3.72E-06 1.42E-07 3.08E-07 3.11E-06 Cm-243 9.93E-04 1.70E-03 1.56E-02 5.47E-04 9.87E-04 1.34E-02 Cm-244 2.55E-05 6.63E-05 7.09E-04 1.97E-05 2.50E-05 7.21E-04 Co-60 1.07E-02 2.97E-02 1.58E-01 9.58E-03 1.78E-02 2.26E-01 Cs-134 6.29E-03 1.72E-02 9.41E-02 5.54E-03 1.02E-02 1.31E-01 Cs-137 3.22E-03 7.27E-03 4.83E-02 2.35E-03 4.34E-03 5.57E-02 Eu-152 5.02E-03 1.38E-02 7.46E-02 4.45E-03 8.24E-03 1.05E-01 Eu-154 5.57E-03 1.47E-02 8.25E-02 4.73E-03 8.77E-03 1.12E-01 Eu-155 2.83E-04 4.95E-04 4.55E-03 1.58E-04 2.77E-04 3.84E-03 Fe-55 2.97E-09 4.20E-09 3.71E-08 1.39E-09 2.97E-09 3.29E-08 H-3 0.00E+00 0.00E+00 1.45E-09 0.00E+00 0.00E+00 0.00E+00 Nb-94 1.20E-02 1.98E-02 1.79E-01 6.40E-03 1.19E-02 1.52E-01 Ni-59 1.51E-08 2.04E-08 1.77E-07 6.77E-09 1.50E-08 1.52E-07 Ni-63 3.21E-08 5.57E-08 3.75E-07 1.84E-08 4.11E-08 4.13E-07 Np-237 2.91E-03 4.04E-03 3.53E-02 1.34E-03 2.89E-03 3.01E-02 Pm-147 9.32E-08 1.68E-07 1.56E-06 5.35E-08 9.15E-08 1.35E-06 Pu-238 3.97E-05 1.04E-04 1.11E-03 3.08E-05 3.89E-05 1.13E-03 Pu-239 4.41E-05 1.15E-04 1.23E-03 3.40E-05 4.30E-05 1.25E-03 Pu-240 4.38E-05 1.14E-04 1.22E-03 3.38E-05 4.28E-05 1.24E-03 Pu-241 2.97E-06 6.03E-06 5.85E-05 1.88E-06 2.92E-06 5.56E-05 Sb-125 2.75E-03 4.52E-03 4.11E-02 1.46E-03 2.69E-03 3.45E-02 Sr-90 5.84E-05 1.30E-04 7.09E-04 4.31E-05 9.30E-05 9.69E-04 Tc-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 The combined dose factors that account for dose from both pathways are provided in Table 12.

Page 14 of 31

TSD 14-019 Revision 0 Table 12 - Combined Dose Factor for Groundwater and Drill Spoils Crib Aux Containment Spent Fuel Turbine House WWTF mrem/year mrem/year mrem/year mrem/year mrem/year mrem/year Radionuclide per mCi per mCi per mCi per mCi per mCi per mCi Ag-108m 1.78E-02 4.61E-02 1.85E-01 1.30E-02 1.77E-02 1.32E+00 Am-241 2.58E-01 1.15E+00 3.06E-03 2.86E-01 2.45E-01 5.22E+01 Am-243 2.64E-01 1.15E+00 2.51E-02 2.86E-01 2.46E-01 5.22E+01 C-14 6.49E-02 2.84E-01 3.72E-06 7.09E-02 6.08E-02 1.29E+01 Cm-243 2.69E-02 1.57E-01 1.56E-02 3.94E-02 3.43E-02 7.09E+00 Cm-244 1.74E-02 1.24E-01 7.09E-04 3.11E-02 2.67E-02 5.66E+00 Co-60 1.08E-02 4.11E-02 1.58E-01 1.25E-02 2.03E-02 7.48E-01 Cs-134 1.56E-02 2.15E-01 9.41E-02 5.49E-02 5.25E-02 9.16E+00 Cs-137 2.96E-02 1.64E-01 4.83E-02 4.16E-02 3.79E-02 7.22E+00 Eu-152 5.08E-03 1.76E-02 7.46E-02 5.41E-03 9.07E-03 2.81E-01 Eu-154 5.64E-03 2.03E-02 8.25E-02 6.14E-03 9.98E-03 3.68E-01 Eu-155 2.91E-04 1.37E-03 4.55E-03 3.77E-04 4.64E-04 4.36E-02 Fe-55 8.09E-07 1.51E-05 3.71E-08 3.78E-06 3.23E-06 6.85E-04 H-3 6.21E-03 2.72E-02 1.45E-09 6.80E-03 5.80E-03 1.23E+00 Nb-94 1.41E-02 2.86E-02 1.79E-01 8.61E-03 1.37E-02 5.55E-01 Ni-59 1.35E-04 5.87E-04 1.77E-07 1.47E-04 1.26E-04 2.67E-02 Ni-63 2.86E-04 1.61E-03 3.75E-07 4.01E-04 2.69E-04 7.31E-02 Np-237 4.92E+01 2.13E+02 3.53E-02 5.34E+01 4.57E+01 9.73E+03 Pm-147 3.01E-05 5.67E-04 1.56E-06 1.42E-04 1.22E-04 2.59E-02 Pu-238 2.11E-01 1.03E+00 1.11E-03 2.56E-01 2.19E-01 4.66E+01 Pu-239 2.61E-01 1.14E+00 1.23E-03 2.84E-01 2.43E-01 5.18E+01 Pu-240 2.61E-01 1.14E+00 1.22E-03 2.84E-01 2.43E-01 5.18E+01 Pu-241 4.58E-03 3.65E-02 5.85E-05 9.11E-03 7.80E-03 1.66E+00 Sb-125 1.32E-02 1.98E-01 4.11E-02 4.99E-02 4.40E-02 8.82E+00 Sr-90 3.29E-01 4.51E+00 7.09E-04 1.13E+00 9.67E-01 2.06E+02 Tc-99 1.48E-01 6.44E-01 0.00E+00 1.61E-01 1.38E-01 2.93E+01

3. CALCULATIONS 3.1. Normalized End State Basement Fill Source Terms The January 1, 2013 Table 6 source term distributions and Table 8 July 1, 2018 source term distributions can be used to estimate the source term distribution of the basement fill water in pCi/L for positively detected radionuclides using the Table 10 DUST MS screening results. In this evaluation, each column is normalized to a 1 Ci source term as seen in Table 13 and Table 14. The overall source terms were also normalized to one Curie so the values do not equal the sum of the two columns.

Page 15 of 31

TSD 14-019 Revision 0 Table 13 - January 1, 2013 End State Concrete Source Terms Normalized to One Curie.

Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bldg Total Total Total Total 542' Total 542' Total Contam 568' Floor & Overall 568' Floor & Overall 542' Wall Overall Nuclide Floor Ci Walls Ci Total Ci Floor Ci Walls Ci Total Ci Floor Ci 542' Ci Total Ci H-3 9.93E-04 3.25E-02 1.06E-03 5.75E-04 1.1E-02 6.87E-04 2.35E-03 8.32E-04 2.11E-03 C-14 1.03E-04 4.03E-04 1.04E-04 2.87E-05 1.2E-04 2.96E-05 3.62E-04 5.55E-04 3.92E-04 Fe-55 6.77E-04 2.72E-03 6.81E-04 1.14E-02 7.0E-03 1.13E-02 4.09E-03 2.13E-03 3.78E-03 Ni-59 1.44E-04 5.06E-03 1.53E-04 2.38E-03 1.5E-02 2.52E-03 4.82E-03 2.31E-03 4.43E-03 Co-60 2.88E-02 8.22E-02 2.89E-02 1.37E-01 7.8E-02 1.36E-01 1.49E-02 2.58E-02 1.66E-02 Ni-63 2.04E-02 3.61E-02 2.05E-02 4.50E-01 1.3E-01 4.47E-01 2.17E-01 2.17E-01 2.17E-01 Sr-90 5.05E-04 8.55E-05 5.05E-04 3.77E-05 2.9E-05 3.76E-05 3.22E-04 1.57E-03 5.17E-04 Nb-94 1.36E-04 7.32E-04 1.37E-04 2.94E-03 5.5E-04 2.91E-03 1.18E-04 8.66E-05 1.13E-04 Tc-99 1.26E-04 1.49E-04 1.26E-04 5.61E-06 2.1E-05 5.77E-06 1.49E-04 1.04E-04 1.42E-04 Ag-108m 2.46E-04 7.15E-04 2.47E-04 4.60E-03 6.7E-03 4.63E-03 1.69E-04 7.85E-05 1.55E-04 Sb-125 1.03E-03 9.42E-04 1.03E-03 6.81E-04 3.4E-04 6.78E-04 5.89E-04 7.62E-04 6.16E-04 Cs-134 2.78E-04 4.12E-03 2.85E-04 5.73E-04 3.4E-03 6.03E-04 4.29E-04 1.40E-03 5.81E-04 Cs-137 9.43E-01 2.73E-01 9.42E-01 3.89E-01 4.4E-02 3.85E-01 7.54E-01 7.47E-01 7.53E-01 Eu-152 1.91E-03 5.19E-01 2.95E-03 2.11E-04 6.5E-01 6.99E-03 1.85E-04 3.18E-04 2.06E-04 Eu-154 9.60E-04 2.82E-02 1.01E-03 1.45E-04 3.7E-02 5.30E-04 1.19E-04 1.84E-04 1.29E-04 Eu-155 3.36E-04 1.36E-02 3.63E-04 2.05E-04 1.3E-02 3.39E-04 1.48E-04 1.81E-04 1.53E-04 Np-237 1.26E-06 9.16E-06 1.28E-06 2.91E-07 3.3E-06 3.23E-07 3.54E-06 5.73E-06 3.88E-06 Pu-238 8.89E-06 1.63E-05 8.91E-06 4.99E-07 2.4E-06 5.19E-07 1.37E-05 2.49E-06 1.20E-05 Pu-239 3.11E-06 7.24E-06 3.12E-06 2.53E-07 1.1E-06 2.62E-07 5.40E-06 1.21E-06 4.75E-06 Pu-240 3.11E-06 7.24E-06 3.12E-06 2.53E-07 1.1E-06 2.62E-07 5.40E-06 1.21E-06 4.75E-06 Pu-241 1.11E-04 7.12E-04 1.12E-04 3.70E-05 2.5E-04 3.92E-05 3.31E-04 3.04E-04 3.27E-04 Am-241 1.10E-04 2.47E-05 1.10E-04 8.12E-06 2.8E-06 8.06E-06 1.24E-05 5.68E-06 1.14E-05 Am-243 2.09E-06 1.16E-05 2.11E-06 8.20E-07 3.6E-06 8.49E-07 8.96E-06 5.70E-06 8.45E-06 Cm-243 1.11E-05 1.03E-05 1.11E-05 8.94E-07 1.6E-06 9.02E-07 3.32E-06 3.82E-06 3.40E-06 Cm-244 1.11E-05 1.02E-05 1.11E-05 8.94E-07 1.6E-06 9.02E-07 3.31E-06 3.81E-06 3.39E-06 Total 1.00E+00 1.00E+00 1.00E+00 1.00E+00 1.00E+00 1.00E+00 1.00E+00 1.00E+00 1.00E+00 NR = Not Reported Table 14- July 1, 2018 Concrete Source Terms Normalized to One Curie.

Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bldg Total Total Total Total 542' Total 542' Total Contam 568' Floor & Overall 568' Floor & Overall 542' Wall Overall Nuclide Floor Ci Walls Ci Total Ci Floor Ci Walls Ci Total Ci Floor Ci 542' Ci Total Ci H-3 8.38E-04 3.12E-02 8.91E-04 4.93E-04 1.1E-02 5.90E-04 1.94E-03 6.89E-04 1.74E-03 C-14 1.19E-04 5.27E-04 1.20E-04 3.35E-05 1.5E-04 3.46E-05 4.07E-04 6.26E-04 4.41E-04 Fe-55 1.93E-04 8.84E-04 1.95E-04 3.29E-03 2.3E-03 3.28E-03 1.14E-03 5.97E-04 1.06E-03 Page 16 of 31

TSD 14-019 Revision 0 Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bldg Total Total Total Total 542' Total 542' Total Contam 568' Floor & Overall 568' Floor & Overall 542' Wall Overall Nuclide Floor Ci Walls Ci Total Ci Floor Ci Walls Ci Total Ci Floor Ci 542' Ci Total Ci Ni-59 1.65E-04 6.62E-03 1.76E-04 2.78E-03 2.0E-02 2.94E-03 5.42E-03 2.60E-03 4.98E-03 Co-60 1.61E-02 5.22E-02 1.61E-02 7.76E-02 5.0E-02 7.74E-02 8.15E-03 1.41E-02 9.08E-03 Ni-63 2.26E-02 4.55E-02 2.27E-02 5.06E-01 1.6E-01 5.03E-01 2.35E-01 2.35E-01 2.35E-01 Sr-90 5.09E-04 9.80E-05 5.08E-04 3.86E-05 3.4E-05 3.85E-05 3.17E-04 1.55E-03 5.10E-04 Nb-94 1.56E-04 9.58E-04 1.58E-04 3.43E-03 7.2E-04 3.41E-03 1.33E-04 9.78E-05 1.27E-04 Tc-99 1.45E-04 1.95E-04 1.45E-04 6.55E-06 2.8E-05 6.74E-06 1.68E-04 1.18E-04 1.60E-04 Ag-108m 2.81E-04 9.28E-04 2.82E-04 5.33E-03 8.8E-03 5.36E-03 1.88E-04 8.78E-05 1.72E-04 Sb-125 2.98E-04 3.10E-04 2.98E-04 2.00E-04 1.1E-04 1.99E-04 1.66E-04 2.16E-04 1.74E-04 Cs-134 5.04E-05 8.51E-04 5.18E-05 1.06E-04 7.0E-04 1.11E-04 7.62E-05 2.49E-04 1.03E-04 Cs-137 9.56E-01 3.15E-01 9.55E-01 4.00E-01 5.1E-02 3.97E-01 7.47E-01 7.43E-01 7.46E-01 Eu-152 1.66E-03 5.12E-01 2.56E-03 1.86E-04 6.5E-01 6.17E-03 1.57E-04 2.71E-04 1.75E-04 Eu-154 7.16E-04 2.39E-02 7.57E-04 1.10E-04 3.2E-02 4.02E-04 8.68E-05 1.35E-04 9.43E-05 Eu-155 1.74E-04 8.01E-03 1.87E-04 1.08E-04 7.7E-03 1.78E-04 7.47E-05 9.16E-05 7.74E-05 Np-237 1.45E-06 1.20E-05 1.47E-06 3.40E-07 4.4E-06 3.77E-07 3.98E-06 6.47E-06 4.37E-06 Pu-238 9.79E-06 2.04E-05 9.81E-06 5.58E-07 3.1E-06 5.81E-07 1.48E-05 2.69E-06 1.29E-05 Pu-239 3.58E-06 9.47E-06 3.59E-06 2.96E-07 1.4E-06 3.06E-07 6.07E-06 1.37E-06 5.34E-06 Pu-240 3.58E-06 9.47E-06 3.59E-06 2.95E-07 1.4E-06 3.06E-07 6.06E-06 1.37E-06 5.33E-06 Pu-241 9.78E-05 7.15E-04 9.89E-05 3.31E-05 2.5E-04 3.51E-05 2.86E-04 2.63E-04 2.82E-04 Am-241 1.26E-04 3.21E-05 1.25E-04 9.39E-06 3.7E-06 9.34E-06 1.38E-05 6.35E-06 1.27E-05 Am-243 2.40E-06 1.52E-05 2.42E-06 9.57E-07 4.8E-06 9.92E-07 1.01E-05 6.43E-06 9.50E-06 Cm-243 1.12E-05 1.17E-05 1.12E-05 9.13E-07 1.9E-06 9.22E-07 3.27E-06 3.78E-06 3.35E-06 Cm-244 1.03E-05 1.08E-05 1.03E-05 8.46E-07 1.7E-06 8.54E-07 3.01E-06 3.48E-06 3.09E-06 Total 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 NR = Not Reported These source terms are much higher than the probable end state source terms, due to the fact that the concrete in the Containments will be removed to the liner and the concrete surfaces in the Auxiliary Building basement will be remediated to accommodate open air demolition. However, they allow the predicted worst case groundwater concentrations and resulting maximum doses to be evaluated for the variations in the mixes on a uniform basis.

3.2. Basement Fill Doses for Normalized Source Terms The Table 12 dose factors can be used to estimate the relative dose contribution of the nuclides in the normalized source terms by multiplying the dose factors times the source term in Table 13. The dose calculation results for the Containment Buildings and Auxiliary Building are provided in Table 15 and Table 16. The results show that in both the January 1, 2013 and July 1, 2018, the normalized source terms for Co-60, Ni-63, Sr-90, Cs-134 and Cs-137 account for greater than 99.5% of the dose. Therefore the insignificant dose consequences from eliminating the other nuclides is less than 0.5% as seen in the last row of each table.

Page 17 of 31

TSD 14-019 Revision 0 It should also be noted that since the source term is approximately fifty feet below grade (e.g., grade is the 592 elevation and the Auxiliary Building basement floor is at the 542 elevation) there is no inhalation or direct radiation component with corresponding minor doses consequences. The total dose for each building ranges from ten to hundreds of millirem a year for a Curie of source term which greatly exceeds the estimated source terms (5) (6) and any potential remaining post remediation source term.

Table 15 - January 1, 2013 Calculated Dose for Normalized 1 Ci Source Term Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bldg Total Total Total 542' Total 542' Total 568' Floor & Overall 568' Floor & Overall Total 542' Contam Overall Floor Walls Total Floor Walls Total Floor Wall 542' Total Nuclide mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr H-3 2.70E-02 8.83E-01 2.87E-02 1.56E-02 3.1E-01 1.87E-02 1.46E-02 5.16E-03 1.31E-02 C-14 2.94E-02 1.14E-01 2.95E-02 8.14E-03 3.3E-02 8.40E-03 2.35E-02 3.60E-02 2.55E-02 Fe-55 1.02E-05 4.10E-05 1.03E-05 1.71E-04 1.0E-04 1.70E-04 3.31E-06 1.72E-06 3.06E-06 Ni-59 8.42E-05 2.97E-03 9.00E-05 1.40E-03 9.1E-03 1.48E-03 6.50E-04 3.11E-04 5.97E-04 Co-60 1.18E+00 3.38E+00 1.19E+00 5.63E+00 3.2E+00 5.61E+00 1.62E-01 2.79E-01 1.80E-01 Ni-63 3.28E-02 5.80E-02 3.29E-02 7.23E-01 2.1E-01 7.18E-01 6.20E-02 6.19E-02 6.20E-02 Sr-90 2.28E+00 3.86E-01 2.28E+00 1.70E-01 1.3E-01 1.70E-01 1.06E-01 5.17E-01 1.70E-01 Nb-94 3.89E-03 2.10E-02 3.93E-03 8.42E-02 1.6E-02 8.35E-02 1.66E-03 1.22E-03 1.59E-03 Tc-99 8.11E-02 9.62E-02 8.12E-02 3.61E-03 1.4E-02 3.71E-03 2.21E-02 1.54E-02 2.10E-02 Ag-108m 1.14E-02 3.30E-02 1.14E-02 2.12E-01 3.1E-01 2.13E-01 3.00E-03 1.40E-03 2.75E-03 Sb-125 2.04E-01 1.87E-01 2.04E-01 1.35E-01 6.7E-02 1.34E-01 7.76E-03 1.00E-02 8.11E-03 Cs-134 5.96E-02 8.84E-01 6.12E-02 1.23E-01 7.3E-01 1.29E-01 6.68E-03 2.18E-02 9.04E-03 Cs-137 1.55E+02 4.48E+01 1.55E+02 6.38E+01 7.2E+00 6.32E+01 2.23E+01 2.21E+01 2.23E+01 Eu-152 3.37E-02 9.15E+00 5.20E-02 3.72E-03 1.2E+01 1.23E-01 9.40E-04 1.62E-03 1.05E-03 Eu-154 1.95E-02 5.71E-01 2.06E-02 2.94E-03 7.5E-01 1.07E-02 6.71E-04 1.04E-03 7.29E-04 Eu-155 4.60E-04 1.86E-02 4.96E-04 2.81E-04 1.8E-02 4.63E-04 4.31E-05 5.25E-05 4.45E-05 Np-237 2.70E-01 1.95E+00 2.73E-01 6.21E-02 7.0E-01 6.87E-02 1.74E-01 2.82E-01 1.91E-01 Pu-238 9.12E-03 1.67E-02 9.14E-03 5.12E-04 2.5E-03 5.33E-04 2.90E-03 5.25E-04 2.53E-03 Pu-239 3.55E-03 8.25E-03 3.56E-03 2.88E-04 1.2E-03 2.98E-04 1.41E-03 3.16E-04 1.24E-03 Pu-240 3.55E-03 8.25E-03 3.56E-03 2.88E-04 1.2E-03 2.98E-04 1.41E-03 3.16E-04 1.24E-03 Pu-241 4.05E-03 2.60E-02 4.10E-03 1.35E-03 9.1E-03 1.43E-03 1.52E-03 1.39E-03 1.50E-03 Am-241 1.26E-01 2.84E-02 1.26E-01 9.31E-03 3.2E-03 9.25E-03 3.20E-03 1.46E-03 2.93E-03 Am-243 2.40E-03 1.33E-02 2.42E-03 9.41E-04 4.2E-03 9.74E-04 2.37E-03 1.51E-03 2.23E-03 Cm-243 1.74E-03 1.61E-03 1.74E-03 1.40E-04 2.5E-04 1.42E-04 8.95E-05 1.03E-04 9.16E-05 Cm-244 1.38E-03 1.27E-03 1.38E-03 1.11E-04 2.0E-04 1.12E-04 5.77E-05 6.64E-05 5.90E-05 Total 1.59E+02 6.26E+01 1.59E+02 7.10E+01 2.53E+01 7.05E+01 2.29E+01 2.33E+01 2.30E+01 Missed Dose 7.52E-01 2.53E+00 7.56E-01 5.20E-01 1.19E+00 5.27E-01 2.62E-01 3.60E-01 2.77E-01

% Missed 0.473% 4.039% 0.476% 0.733% 4.715% 0.747% 1.143% 1.542% 1.207%

No Np-237 0.304% 0.951% 0.305% 0.646% 1.989% 0.651% 0.386% 0.338% 0.379%

= Included in ROCs when Activated Concrete is Present Bold Italic = MDA Page 18 of 31

TSD 14-019 Revision 0 Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bldg Total Total Total 542' Total 542' Total 568' Floor & Overall 568' Floor & Overall Total 542' Contam Overall Floor Walls Total Floor Walls Total Floor Wall 542' Total Nuclide mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr

= Basement Fill ROCs Table 16 - July 1, 2018 Calculated Dose for Normalized 1 Ci Source Term Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bldg Total Total 542' Total 542' Total Total 568' Floor & Overall 568' Floor & Overall Total 542' Contam Overall Floor Walls Total Floor Walls Total Floor Wall 542' Total Nuclide mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr H-3 2.28E-02 8.48E-01 2.42E-02 1.34E-02 3.0E-01 1.60E-02 1.20E-02 4.27E-03 1.08E-02 C-14 3.37E-02 1.49E-01 3.40E-02 9.50E-03 4.4E-02 9.81E-03 2.64E-02 4.06E-02 2.86E-02 Fe-55 2.91E-06 1.33E-05 2.93E-06 4.96E-05 3.4E-05 4.94E-05 9.24E-07 4.83E-07 8.56E-07 Ni-59 9.68E-05 3.89E-03 1.04E-04 1.63E-03 1.2E-02 1.73E-03 7.30E-04 3.51E-04 6.71E-04 Co-60 6.61E-01 2.15E+00 6.63E-01 3.19E+00 2.1E+00 3.18E+00 8.82E-02 1.53E-01 9.82E-02 Ni-63 3.64E-02 7.30E-02 3.64E-02 8.13E-01 2.6E-01 8.08E-01 6.71E-02 6.73E-02 6.71E-02 Sr-90 2.30E+00 4.42E-01 2.29E+00 1.74E-01 1.5E-01 1.74E-01 1.05E-01 5.11E-01 1.68E-01 Nb-94 4.47E-03 2.74E-02 4.51E-03 9.83E-02 2.1E-02 9.76E-02 1.87E-03 1.38E-03 1.79E-03 Tc-99 9.33E-02 1.26E-01 9.34E-02 4.22E-03 1.8E-02 4.34E-03 2.48E-02 1.74E-02 2.37E-02 Ag-108m 1.30E-02 4.28E-02 1.30E-02 2.46E-01 4.1E-01 2.47E-01 3.34E-03 1.56E-03 3.07E-03 Sb-125 5.91E-02 6.14E-02 5.91E-02 3.96E-02 2.2E-02 3.94E-02 2.19E-03 2.85E-03 2.29E-03 Cs-134 1.08E-02 1.83E-01 1.11E-02 2.27E-02 1.5E-01 2.39E-02 1.18E-03 3.88E-03 1.60E-03 Cs-137 1.57E+02 5.16E+01 1.57E+02 6.57E+01 8.4E+00 6.51E+01 2.21E+01 2.20E+01 2.21E+01 Eu-152 2.93E-02 9.04E+00 4.51E-02 3.27E-03 1.1E+01 1.09E-01 7.97E-04 1.38E-03 8.88E-04 Eu-154 1.45E-02 4.85E-01 1.53E-02 2.23E-03 6.4E-01 8.14E-03 4.89E-04 7.60E-04 5.31E-04 Eu-155 2.38E-04 1.09E-02 2.56E-04 1.47E-04 1.1E-02 2.43E-04 2.17E-05 2.66E-05 2.25E-05 Np-237 3.10E-01 2.55E+00 3.14E-01 7.25E-02 9.3E-01 8.04E-02 1.96E-01 3.18E-01 2.15E-01 Pu-238 1.00E-02 2.09E-02 1.01E-02 5.72E-04 3.2E-03 5.96E-04 3.12E-03 5.67E-04 2.72E-03 Pu-239 4.08E-03 1.08E-02 4.09E-03 3.37E-04 1.6E-03 3.48E-04 1.58E-03 3.57E-04 1.39E-03 Pu-240 4.08E-03 1.08E-02 4.09E-03 3.37E-04 1.6E-03 3.48E-04 1.58E-03 3.56E-04 1.39E-03 Pu-241 3.57E-03 2.61E-02 3.61E-03 1.21E-03 9.2E-03 1.28E-03 1.31E-03 1.21E-03 1.29E-03 Am-241 1.44E-01 3.68E-02 1.44E-01 1.08E-02 4.3E-03 1.07E-02 3.57E-03 1.64E-03 3.27E-03 Am-243 2.75E-03 1.75E-02 2.78E-03 1.10E-03 5.5E-03 1.14E-03 2.66E-03 1.70E-03 2.51E-03 Cm-243 1.75E-03 1.84E-03 1.76E-03 1.43E-04 2.9E-04 1.45E-04 8.80E-05 1.02E-04 9.01E-05 Cm-244 1.29E-03 1.34E-03 1.29E-03 1.05E-04 2.2E-04 1.06E-04 5.25E-05 6.07E-05 5.38E-05 Total 1.61E+02 6.79E+01 1.60E+02 7.04E+01 2.49E+01 7.00E+01 2.26E+01 2.31E+01 2.27E+01 Missed Dose 6.85E-01 3.10E+00 6.90E-01 4.86E-01 1.49E+00 4.95E-01 2.69E-01 3.88E-01 2.88E-01

% Missed 0.427% 4.566% 0.430% 0.691% 5.963% 0.708% 1.188% 1.680% 1.266%

No Np-237 0.234% 0.838% 0.235% 0.588% 2.327% 0.594% 0.327% 0.308% 0.324%

Page 19 of 31

TSD 14-019 Revision 0 Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bldg Total Total 542' Total 542' Total Total 568' Floor & Overall 568' Floor & Overall Total 542' Contam Overall Floor Walls Total Floor Walls Total Floor Wall 542' Total Nuclide mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr

= Included in ROCs when Activated Concrete is Present Bold Italic = MDA

= Basement Fill ROCs As seen in Table 15 and Table 16, the activated concrete in the Unit 1 and 2 Incore Areas have the highest dose contributions from radionuclides other than the yellow and purple highlighted radionuclides. Excluding the theoretical dose from Np-237, which was not detected above the MDA in any samples, lowers the potential missed dose to less than 1% for all radionuclide mixes.

Table 17 shows each radionuclide percent contribution to the total dose of each radionuclide mix for the July 1, 2018 decayed data. Radionuclides that contribute greater than 0.5% of the dose within a mix are highlighted in yellow cells.

Table 17 - Basement July1, 2018 Mix Individual Nuclide Percent of Total Dose Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bldg Total Total Total Total Incore 542' Total 542' Total Contam 568' Floor & Overall 568' Floor & Overall 542' Wall Overall Floor Walls Total Floor Walls Total Floor 542' Total Nuclide Percent Percent Percent Percent Percent Percent Percent Percent Percent H-3 0.014% 1.248% 0.015% 0.019% 1.198% 0.023% 0.053% 0.018% 0.048%

C-14 0.021% 0.220% 0.021% 0.013% 0.175% 0.014% 0.117% 0.176% 0.126%

Fe-55 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000%

Ni-59 0.000% 0.006% 0.000% 0.002% 0.048% 0.002% 0.003% 0.002% 0.003%

Co-60 0.411% 3.158% 0.413% 4.534% 8.282% 4.547% 0.389% 0.661% 0.432%

Ni-63 0.023% 0.107% 0.023% 1.155% 1.060% 1.155% 0.296% 0.291% 0.296%

Sr-90 1.431% 0.651% 1.431% 0.247% 0.612% 0.249% 0.462% 2.212% 0.739%

Nb-94 0.003% 0.040% 0.003% 0.140% 0.083% 0.139% 0.008% 0.006% 0.008%

Tc-99 0.058% 0.185% 0.058% 0.006% 0.072% 0.006% 0.110% 0.075% 0.104%

Ag-108m 0.008% 0.063% 0.008% 0.349% 1.626% 0.353% 0.015% 0.007% 0.014%

Sb-125 0.037% 0.090% 0.037% 0.056% 0.090% 0.056% 0.010% 0.012% 0.010%

Cs-134 0.007% 0.269% 0.007% 0.032% 0.607% 0.034% 0.005% 0.017% 0.007%

Cs-137 97.660% 75.987% 97.644% 93.313% 33.674% 93.118% 97.600% 95.112% 97.206%

Eu-152 0.018% 13.301% 0.028% 0.005% 46.016% 0.155% 0.004% 0.006% 0.004%

Eu-154 0.009% 0.713% 0.010% 0.003% 2.588% 0.012% 0.002% 0.003% 0.002%

Eu-155 0.000% 0.016% 0.000% 0.000% 0.042% 0.000% 0.000% 0.000% 0.000%

Np-237 0.193% 3.759% 0.196% 0.103% 3.722% 0.115% 0.864% 1.377% 0.945%

Pu-238 0.006% 0.031% 0.006% 0.001% 0.013% 0.001% 0.014% 0.002% 0.012%

Pu-239 0.003% 0.016% 0.003% 0.000% 0.006% 0.000% 0.007% 0.002% 0.006%

Pu-240 0.003% 0.016% 0.003% 0.000% 0.006% 0.000% 0.007% 0.002% 0.006%

Pu-241 0.002% 0.038% 0.002% 0.002% 0.037% 0.002% 0.006% 0.005% 0.006%

Page 20 of 31

TSD 14-019 Revision 0 Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bldg Total Total Total Total Incore 542' Total 542' Total Contam 568' Floor & Overall 568' Floor & Overall 542' Wall Overall Floor Walls Total Floor Walls Total Floor 542' Total Nuclide Percent Percent Percent Percent Percent Percent Percent Percent Percent Am-241 0.090% 0.054% 0.090% 0.015% 0.017% 0.015% 0.016% 0.007% 0.014%

Am-243 0.002% 0.026% 0.002% 0.002% 0.022% 0.002% 0.012% 0.007% 0.011%

Cm-243 0.001% 0.003% 0.001% 0.000% 0.001% 0.000% 0.000% 0.000% 0.000%

Cm-244 0.001% 0.002% 0.001% 0.000% 0.001% 0.000% 0.000% 0.000% 0.000%

Total 100% 100% 100% 100% 100% 100% 100% 100% 100%

= Greater than 0.5% dose contribution Table 17 shows that only a few radionuclides contribute greater than a half of one percent (i.e.

0.5%) to the total dose. It also shows that the percentage of dose contributed by transuranics (e.g.,

Np-237) in the Containment source terms is consistently higher in the activated Incore areas than in the 568 foot elevation concrete. This is because the overall source term and concentration levels in the Incore areas are much lower and therefore the MDAs of the transuranics contribute a higher percentage of the overall dose. The overall mix source terms are therefore more representative of the transuranic ratios that will be present in the final mix and the Table 18 composite of the Unit 1 and Unit 2 Overall normalized mix should be used for the Containment source term.

Table 18 - July 1, 2018 Unit 1 and Unit 2 Containment Normalized Composite Mixes Normalized U1 and U2 Composite Overall Overall Overall Composite Composite Composite Composite Composite Nuclide 568' Ci Incore Ci Ci mrem/yr % Dose H-3 6.65E-04 2.11E-02 7.40E-04 2.01E-05 0.017%

C-14 7.62E-05 3.40E-04 7.71E-05 2.19E-05 0.019%

Fe-55 1.74E-03 1.58E-03 1.74E-03 2.62E-08 0.000%

Ni-59 1.47E-03 1.35E-02 1.56E-03 9.15E-07 0.001%

Co-60 4.68E-02 5.12E-02 4.68E-02 1.92E-03 1.669%

Ni-63 2.64E-01 1.05E-01 2.63E-01 4.22E-04 0.366%

Sr-90 2.74E-04 6.59E-05 2.73E-04 1.23E-03 1.072%

Nb-94 1.79E-03 8.41E-04 1.78E-03 5.10E-05 0.044%

Tc-99 7.57E-05 1.12E-04 7.59E-05 4.89E-05 0.042%

Ag-108m 2.80E-03 4.86E-03 2.82E-03 1.30E-04 0.113%

Sb-125 2.49E-04 2.11E-04 2.48E-04 4.92E-05 0.043%

Cs-134 7.80E-05 7.78E-04 8.15E-05 1.75E-05 0.015%

Cs-137 6.78E-01 1.83E-01 6.76E-01 1.11E-01 96.269%

Eu-152 9.23E-04 5.81E-01 4.36E-03 7.69E-05 0.067%

Eu-154 4.13E-04 2.79E-02 5.79E-04 1.17E-05 0.0102%

Eu-155 1.41E-04 7.87E-03 1.83E-04 2.50E-07 0.000%

Np-237 8.97E-07 8.17E-06 9.25E-07 1.97E-04 0.171%

Pu-238 5.17E-06 1.17E-05 5.19E-06 5.33E-06 0.005%

Page 21 of 31

TSD 14-019 Revision 0 Pu-239 1.94E-06 5.44E-06 1.95E-06 2.22E-06 0.002%

Pu-240 1.94E-06 5.43E-06 1.95E-06 2.22E-06 0.002%

Pu-241 6.55E-05 4.83E-04 6.70E-05 2.45E-06 0.002%

Am-241 6.75E-05 1.79E-05 6.73E-05 7.73E-05 0.067%

Am-243 1.68E-06 1.00E-05 1.71E-06 1.96E-06 0.002%

Cm-243 6.05E-06 6.80E-06 6.05E-06 9.50E-07 0.001%

Cm-244 5.59E-06 6.27E-06 5.60E-06 6.96E-07 0.001%

Total 1.00E+00 1.00E+00 1.00E+00 1.15E-01 100.000%

= ROC Missed Dose 5.93E-04

= Actv Concrete ROC % Missed 0.514%

No Np-237 0.344%

This results in an insignificant dose fraction that is conservative compared to the 568 and overall total insignificant doses in Table 16, but is not disproportionately biased by the transuranic MDAs as is the case for the Incore Area 542 foot elevation activated source terms.

3.3. End State Basement Fill Radionuclide Mixes Based upon the above analysis, the radionuclides of concern for the Containment basement fill end state mix are H-3, Co-60, Ni-63, Sr-90, Cs-134, Cs-137, Eu-152, Eu-154. The radionuclides of concern for the Auxiliary Building are Co-60, Ni-63, Sr-90, Cs-134, and Cs-137. Since the source terms in the Turbine Building, Crib House, Waste Water Treatment Facility, etc. will be too low to obtain good radionuclide mix data, the Auxiliary Building mix should be used for all other basement fill end state buildings, except the Fuel Handling Building. The Transfer Canal and Spent Fuel Pool mixes will require characterization when access becomes available. The July 1, 2018 Containment and Auxiliary Building radionuclide mixtures are provided in Table 19.

Table 19 - Basement Fill End State July 1, 2018 Radionuclide Mixes for FSS CTMT AUX Percent Percent Activity Percent Annual Activity Percent Annual Nuclide Ci Activity Dose Ci Activity Dose H-3 7.40E-04 0.074% 0.017% 1.74E-03 0.174% 0.057%

C-14 7.71E-05 0.008% 0.019% 4.41E-04 0.044% 0.111%

Fe-55 1.74E-03 0.174% 0.000% 1.06E-03 0.106% 0.00001%

Ni-59 1.56E-03 0.156% 0.001% 4.98E-03 0.498% 0.003%

Co-60 4.68E-02 4.675% 1.669% 9.08E-03 0.908% 0.783%

Ni-63 2.63E-01 26.275% 0.366% 2.35E-01 23.480% 0.270%

Sr-90 2.73E-04 0.027% 1.072% 5.10E-04 0.051% 0.742%

Nb-94 1.78E-03 0.178% 0.044% 1.27E-04 0.013% 0.007%

Tc-99 7.59E-05 0.008% 0.042% 1.60E-04 0.016% 0.092%

Ag-108m 2.82E-03 0.282% 0.113% 1.72E-04 0.017% 0.012%

Sb-125 2.48E-04 0.025% 0.043% 1.74E-04 0.017% 0.035%

Cs-134 8.15E-05 0.008% 0.015% 1.03E-04 0.010% 0.039%

Cs-137 6.76E-01 67.582% 96.269% 7.46E-01 74.597% 96.959%

Eu-152 4.36E-03 0.436% 0.067% 1.75E-04 0.017% 0.0046%

Page 22 of 31

TSD 14-019 Revision 0 Eu-154 5.79E-04 0.058% 0.010% 9.43E-05 0.009% 0.00317%

Eu-155 1.83E-04 0.018% 0.000% 7.74E-05 0.008% 0.00019%

Np-237 9.25E-07 0.000% 0.171% 4.37E-06 0.0004% 0.831%

Pu-238 5.19E-06 0.001% 0.005% 1.29E-05 0.001% 0.011%

Pu-239 1.95E-06 0.000% 0.002% 5.34E-06 0.0005% 0.005%

Pu-240 1.95E-06 0.000% 0.002% 5.33E-06 0.001% 0.005%

Pu-241 6.70E-05 0.007% 0.002% 2.82E-04 0.028% 0.007%

Am-241 6.73E-05 0.007% 0.067% 1.27E-05 0.001% 0.013%

Am-243 1.71E-06 0.000% 0.002% 9.50E-06 0.001% 0.010%

Cm-243 6.05E-06 0.001% 0.001% 3.35E-06 0.0003% 0.0004%

Cm-244 5.60E-06 0.001% 0.001% 3.09E-06 0.0003% 0.0003%

Total 1.00E+00 100% 100% 1.00E+00 100% 100%

Insignificant 8.64E-03 0.864% 0.514% 9.54E-03 0.954% 1.21%

=ROCs All Basements

=Additional ROCs for Containments The source term and dose fractions with only the ROCs are as shown Table 20 below. The Auxiliary Building mix applies to all buildings except for the Containments and the Fuel Handling Building, which has yet to be characterized.

Table 20 - ROCs Only Basement Fill End State July 1, 2018 Radionuclide Mixes for FSS CTMT AUX Percent Percent Activity Percent Annual Activity Percent Annual Nuclide Ci Activity Dose Ci Activity Dose H-3 7.40E-04 0.074% 0.017% Insig Insig Insig Co-60 4.68E-02 4.675% 1.669% 9.08E-03 0.908% 0.783%

Ni-63 2.63E-01 26.275% 0.366% 2.35E-01 23.480% 0.270%

Sr-90 2.73E-04 0.027% 1.072% 5.10E-04 0.051% 0.742%

Cs-134 8.15E-05 0.008% 0.015% 1.03E-04 0.010% 0.039%

Cs-137 6.76E-01 67.582% 96.269% 7.46E-01 74.597% 96.959%

Eu-152 4.36E-03 0.436% 0.067% Insig Insig Insig Eu-154 5.79E-04 0.058% 0.010% Insig Insig Insig Insignificant 8.64E-03 0.864% 0.514% 9.54E-03 0.954% 1.207%

Total 1.00E+00 100% 100% 1.00E+00 100% 100%

=ROCs All Basements

=Additional ROCs for Containments 3.4. Soil Radionuclides of Concern The Zion Restoration Project RESRAD model was used to develop the soil DCGLs equal to a peak dose of 25 mrem/year provided in Table 21.

Page 23 of 31

TSD 14-019 Revision 0 Table 21 - ZSRP Soil DCGLs Nuclide DCGL pCi/g Nuclide DCGL pCi/g Ag-108m 7.400E+00 H-3 4.581E+03 Am-241 1.336E+02 Nb-94 7.507E+00 Am-243 4.979E+01 Ni-59 1.094E+04 C-14 8.959E+01 Ni-63 3.996E+03 Cm-243 7.606E+01 Np-237 8.006E-01 Cm-244 2.708E+02 Pu-238 1.617E+02 Co-60 4.734E+00 Pu-239 1.456E+02 Cs-134 7.524E+00 Pu-240 1.457E+02 Cs-137 1.576E+01 Pu-241 6.519E+03 Eu-152 1.073E+01 Sb-125 3.360E+01 Eu-154 9.963E+00 Sr-90 1.439E+01 Eu-155 3.896E+02 Tc-99 1.277E+02 Fe-55 3.374E+04 If the July 1, 2018 normalized concrete and RCS piping mixes in Table 14 are considered to be in pCi/g rather than Ci, the value divided by the DCGL and multiplied by 25 mrem/year equals the dose associated with each mix as seen in Table 22.

Table 22 - July 1, 2018 Normalized Concrete and RCS Pipe Mix Soil Doses Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bld L48320-1 U2 Total Total Total RCS Total 542' Total 542' Total Contam L50297 Inside 568' Floor & Overall 568' Floor & Overall 542' Wall Overall U1 RCS Piping Floor Walls Total Floor Walls Total Floor 542' Total 2012 Smears Nuclide mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr H-3 4.57E-06 1.70E-04 4.86E-06 2.69E-06 6.0E-05 3.22E-06 1.06E-05 3.76E-06 9.51E-06 5.87E-06 1.96E-06 C-14 3.32E-05 1.47E-04 3.34E-05 9.34E-06 4.3E-05 9.65E-06 1.14E-04 1.75E-04 1.23E-04 6.98E-05 1.52E-04 Fe-55 1.43E-07 6.55E-07 1.44E-07 2.44E-06 1.7E-06 2.43E-06 8.46E-07 4.42E-07 7.83E-07 9.78E-06 4.19E-05 Ni-59 3.77E-07 1.51E-05 4.03E-07 6.35E-06 4.7E-05 6.72E-06 1.24E-05 5.95E-06 1.14E-05 7.78E-06 1.08E-05 Co-60 8.49E-02 2.76E-01 8.52E-02 4.10E-01 2.7E-01 4.09E-01 4.30E-02 7.45E-02 4.79E-02 3.08E+00 1.37E+00 Ni-63 1.42E-04 2.84E-04 1.42E-04 3.17E-03 1.0E-03 3.15E-03 1.47E-03 1.47E-03 1.47E-03 2.21E-03 1.98E-03 Sr-90 8.84E-04 1.70E-04 8.83E-04 6.70E-05 5.9E-05 6.70E-05 5.51E-04 2.70E-03 8.85E-04 4.56E-03 9.15E-04 Nb-94 5.20E-04 3.19E-03 5.25E-04 1.14E-02 2.4E-03 1.13E-02 4.42E-04 3.26E-04 4.24E-04 7.67E-03 6.26E-03 Tc-99 2.84E-05 3.83E-05 2.84E-05 1.28E-06 5.4E-06 1.32E-06 3.28E-05 2.30E-05 3.13E-05 3.43E-04 2.95E-04 Ag-108m 9.49E-04 3.13E-03 9.53E-04 1.80E-02 3.0E-02 1.81E-02 6.34E-04 2.97E-04 5.82E-04 8.47E-03 3.70E-03 Sb-125 2.22E-04 2.30E-04 2.22E-04 1.49E-04 8.4E-05 1.48E-04 1.24E-04 1.61E-04 1.29E-04 8.97E-04 2.60E-03 Cs-134 1.67E-04 2.83E-03 1.72E-04 3.51E-04 2.3E-03 3.69E-04 2.53E-04 8.29E-04 3.43E-04 8.19E-04 4.87E-04 Cs-137 1.52E+00 4.99E-01 1.51E+00 6.35E-01 8.1E-02 6.30E-01 1.18E+00 1.18E+00 1.18E+00 4.07E-02 5.55E-01 Eu-152 3.87E-03 1.19E+00 5.96E-03 4.32E-04 1.5E+00 1.44E-02 3.66E-04 6.32E-04 4.07E-04 0 0 Eu-154 1.80E-03 6.00E-02 1.90E-03 2.76E-04 8.0E-02 1.01E-03 2.18E-04 3.38E-04 2.37E-04 6.00E-03 3.08E-03 Page 24 of 31

TSD 14-019 Revision 0 Eu-155 1.11E-05 5.14E-04 1.20E-05 6.90E-06 5.0E-04 1.14E-05 4.80E-06 5.88E-06 4.96E-06 0 0 Np-237 4.54E-05 3.74E-04 4.60E-05 1.06E-05 1.4E-04 1.18E-05 1.24E-04 2.02E-04 1.36E-04 9.57E-02 4.75E-02 Pu-238 1.51E-06 3.15E-06 1.52E-06 8.62E-08 4.8E-07 8.98E-08 2.29E-06 4.16E-07 2.00E-06 2.83E-05 1.26E-05 Pu-239 6.15E-07 1.63E-06 6.17E-07 5.07E-08 2.4E-07 5.25E-08 1.04E-06 2.35E-07 9.16E-07 3.29E-06 2.76E-06 Pu-240 6.14E-07 1.62E-06 6.16E-07 5.07E-08 2.4E-07 5.24E-08 1.04E-06 2.34E-07 9.15E-07 3.29E-06 2.75E-06 Pu-241 3.75E-07 2.74E-06 3.79E-07 1.27E-07 9.6E-07 1.35E-07 1.10E-06 1.01E-06 1.08E-06 1.54E-05 1.29E-06 Am-241 2.35E-05 6.00E-06 2.35E-05 1.76E-06 6.9E-07 1.75E-06 2.59E-06 1.19E-06 2.37E-06 3.60E-05 1.67E-05 Am-243 1.20E-06 7.64E-06 1.22E-06 4.80E-07 2.4E-06 4.98E-07 5.05E-06 3.23E-06 4.77E-06 0 0 Cm-243 3.67E-06 3.86E-06 3.67E-06 3.00E-07 6.1E-07 3.03E-07 1.07E-06 1.24E-06 1.10E-06 4.77E-06 4.30E-06 Cm-244 9.55E-07 9.99E-07 9.55E-07 7.81E-08 1.6E-07 7.88E-08 2.78E-07 3.22E-07 2.85E-07 1.24E-06 1.12E-06 Total 1.61E+00 2.04E+00 1.61E+00 1.08E+00 1.98E+00 1.09E+00 1.23E+00 1.26E+00 1.24E+00 3.25E+00 2.00E+00 Missed Dose 8.70E-03 1.26E+00 1.09E-02 3.39E-02 1.63E+00 4.86E-02 4.37E-03 7.18E-03 4.81E-03 1.27E-01 6.70E-02

% Missed 0.541% 62.015% 0.678% 3.143% 82.488% 4.469% 0.355% 0.569% 0.389% 3.907% 3.356%

No Np-237 0.538% 62.009% 0.675% 3.142% 82.487% 4.468% 0.345% 0.553% 0.378% 0.988% 1.003%

= Included in ROCs when Activated Concrete is Present Bold Italic = MDA

= Basement Fill ROCs As seen in Table 23, Co-60 and Cs-137 account for over 99% of the dose except in the activated concrete mix and the RCS pipe mixes.

Table 23 - Soil July1, 2018 Mix Individual Nuclide Percent of Total Dose Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bld L48320-Total 1 U2 Incore Total Total RCS Total 542' Total 542' Total Contam L50297 Inside 568' Floor & Overall 568' Floor & Overall 542' Wall Overall U1 RCS Piping Floor Walls Total Floor Walls Total Floor 542' Total 2012 Smears Nuclide Percent Percent Percent Percent Percent Percent Percent Percent Percent Percent Percent H-3 0.000% 0.008% 0.000% 0.000% 0.003% 0.000% 0.001% 0.000% 0.001% 0.000% 0.000%

C-14 0.002% 0.007% 0.002% 0.001% 0.002% 0.001% 0.009% 0.014% 0.010% 0.002% 0.008%

Fe-55 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.002%

Ni-59 0.000% 0.001% 0.000% 0.001% 0.002% 0.001% 0.001% 0.000% 0.001% 0.000% 0.001%

Co-60 5.272% 13.513% 5.290% 38.001% 13.409% 37.590% 3.493% 5.916% 3.878% 94.840% 68.865%

Ni-63 0.009% 0.014% 0.009% 0.293% 0.052% 0.289% 0.119% 0.117% 0.119% 0.068% 0.099%

Sr-90 0.055% 0.008% 0.055% 0.006% 0.003% 0.006% 0.045% 0.214% 0.072% 0.140% 0.046%

Nb-94 0.032% 0.156% 0.033% 1.059% 0.122% 1.043% 0.036% 0.026% 0.034% 0.236% 0.313%

Tc-99 0.002% 0.002% 0.002% 0.000% 0.000% 0.000% 0.003% 0.002% 0.003% 0.011% 0.015%

Ag-108m 0.059% 0.154% 0.059% 1.668% 1.501% 1.665% 0.051% 0.024% 0.047% 0.261% 0.185%

Sb-125 0.014% 0.011% 0.014% 0.014% 0.004% 0.014% 0.010% 0.013% 0.010% 0.028% 0.130%

Cs-134 0.010% 0.139% 0.011% 0.033% 0.118% 0.034% 0.021% 0.066% 0.028% 0.025% 0.024%

Cs-137 94.187% 24.472% 94.032% 58.857% 4.103% 57.941% 96.152% 93.515% 95.733% 1.254% 27.779%

Eu-152 0.240% 58.529% 0.370% 0.040% 76.611% 1.321% 0.030% 0.050% 0.033% 0.000% 0.000%

Eu-154 0.112% 2.941% 0.118% 0.026% 4.037% 0.093% 0.018% 0.027% 0.019% 0.185% 0.154%

Page 25 of 31

TSD 14-019 Revision 0 Eu-155 0.001% 0.025% 0.001% 0.001% 0.025% 0.001% 0.000% 0.000% 0.000% 0.000% 0.000%

Np-237 0.003% 0.018% 0.003% 0.001% 0.007% 0.001% 0.010% 0.016% 0.011% 2.948% 2.377%

Pu-238 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.001% 0.001%

Pu-239 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000%

Pu-240 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000%

Pu-241 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000%

Am-241 0.001% 0.000% 0.001% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.001% 0.001%

Am-243 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000%

Cm-243 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000%

Cm-244 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000%

Total 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100%

Note - Yellow cells are greater than 0.5%

It is highly unlikely that there would be any significant activated concrete in contaminated soil. The AUX mixture in Table 19 results in less than 1% insignificant dose when only Co-60 and Cs-137 are the radionuclides of concern in soil.

Table 24 - Soil Radionuclides of Concern and Insignificant Dose Dose Dose Nuclide mrem/year Nuclide mrem/year H-3 9.51E-06 Eu-154 2.37E-04 C-14 1.23E-04 Eu-155 4.96E-06 Fe-55 7.83E-07 Np-237 1.36E-04 Ni-59 1.14E-05 Pu-238 2.00E-06 Co-60 4.79E-02 Pu-239 9.16E-07 Ni-63 1.47E-03 Pu-240 9.15E-07 Sr-90 8.85E-04 Pu-241 1.08E-06 Nb-94 4.24E-04 Am-241 2.37E-06 Tc-99 3.13E-05 Am-243 4.77E-06 Ag-108m 5.82E-04 Cm-243 1.10E-06 Sb-125 1.29E-04 Cm-244 2.85E-07 Cs-134 3.43E-04 Total 1.24E+00 Cs-137 1.18E+00 Insignificant 2.11E-03 Eu-152 4.07E-04 =ROCs Soils Table 25 summarizes the activity and dose contribution for the AUX mixture.

Page 26 of 31

TSD 14-019 Revision 0 Table 25 - Basement Fill End State July 1, 2018 Radionuclide Mixes for Soil FSS Percent Activity Percent Annual Nuclide Ci Activity Dose H-3 1.74E-03 0.1743% 0.0008%

C-14 4.41E-04 0.0441% 0.0100%

Fe-55 1.06E-03 0.1057% 0.0001%

Ni-59 4.98E-03 0.4982% 0.0009%

Co-60 9.08E-03 0.9076% 3.8778%

Ni-63 2.35E-01 23.4804% 0.1188%

Sr-90 5.10E-04 0.0510% 0.0716%

Nb-94 1.27E-04 0.0127% 0.0343%

Tc-99 1.60E-04 0.0160% 0.0025%

Ag-108m 1.72E-04 0.0172% 0.0471%

Sb-125 1.74E-04 0.0174% 0.0105%

Cs-134 1.03E-04 0.0103% 0.0277%

Cs-137 7.46E-01 74.5965% 95.7334%

Eu-152 1.75E-04 0.0175% 0.0329%

Eu-154 9.43E-05 0.0094% 0.0191%

Eu-155 7.74E-05 0.0077% 0.0004%

Np-237 4.37E-06 0.0004% 0.0110%

Pu-238 1.29E-05 0.0013% 0.0002%

Pu-239 5.34E-06 0.0005% 0.0001%

Pu-240 5.33E-06 0.0005% 0.0001%

Pu-241 2.82E-04 0.0282% 0.0001%

Am-241 1.27E-05 0.0013% 0.0002%

Am-243 9.50E-06 0.0009% 0.0004%

Cm-243 3.35E-06 0.0003% 0.0001%

Cm-244 3.09E-06 0.0003% 0.0000%

Total 1.00E+00 1.00E+00 1.00E+00 Insignificant 9.54E-03 0.954% 0.171%

=ROCs Soils Table 26 shows the percentages with only the dose significant ROCs.

Page 27 of 31

TSD 14-019 Revision 0 Table 26 - ROCs Only Soils July 1, 2018 Radionuclide Mixes for FSS Percent Dose Activity Percent Annual Nuclide mrem/year Ci Activity Dose Co-60 4.79E-02 9.08E-03 0.91% 3.878%

Ni-63 1.47E-03 2.35E-01 23.48% 0.119%

Sr-90 8.85E-04 5.10E-04 0.05% 0.072%

Cs-134 3.43E-04 1.03E-04 0.01% 0.028%

Cs-137 1.18E+00 7.46E-01 74.60% 95.733%

Insignificant 2.11E-03 9.54E-03 0.95% 0.171%

Total 1.24E+00 1.00E+00 100% 100%

=ROCs Soils Thus the ROCs for soils are the same as those for all end state buildings except the Containments.

4. CONCLUSION Extensive concrete core samples of potential end state concrete were obtained from the Unit 1 and 2 Containment Buildings and the Auxiliary Building. (5) (6) These cores were obtained at locations with high contact dose rates and/or evidence of leaks/spills. They are therefore heavily biased toward locations with high concentrations or radionuclides in the concrete. The end state Fuel Handling Building is below the Spent Fuel Pool liner and will need to be evaluated once the fuel pool is drained. The other potentially contaminated structures, such as the Turbine Building and Main Steam Tunnel end states, are bounded by the source terms in these structures. Each concrete core section was analyzed by on-site gamma spectroscopy identifying Eu-152, Eu-154 in Containment Incore Area activated concrete cores and Co-60, Cs-137 and Cs-134 in Auxiliary Building and Containment cores. Conservatism was added to the estimated source terms by using MDAs for these nuclides along with positively identified concentrations for these radionuclides.

The calculated source terms from these nuclides were used to scale the activities of additional radionuclides positively identified in off-site analysis of cores from an area. Based upon the off-site laboratory results, Ag-110m and Eu-155 were added to the list of potential ROCs. Both the end state DUST MS model (9) and the RESRAD model (12) used the full suite of radionuclides, even though some were not positively identified in the concrete characterization data. This was done to ensure data was available to calculate basement fill water concentrations and annual doses if they were detected during FSS or sampling.

The DUST MS estimates of basement fill water concentrations per unit of activity were very conservative. The models used distribution coefficients that were the lowest site specific values determined for potential fill materials, or were the lowest 25th percentile values calculated from the RESRAD cumulative probability distribution or from the literature. In addition a very low total porosity value was used, minimizing the water available for dilution of the source term in the fill material. (9) Similarly sensitive parameters for the RESRAD model were assigned 25th percentile values of the probability density function. (12) The calculated concentrations and doses from the normalized source terms are therefore extremely conservative and represent worst case end state conditions.

Page 28 of 31

TSD 14-019 Revision 0 Based upon this analysis it was determined that Co-60, Ni-63, Sr-90, Cs-134 and Cs-137 accounted for 99.5% of all dose in the contaminated concrete mixes. For activated concrete, H-3, Eu-152, and Eu-154, in addition to the five aforementioned nuclides, accounted for 99% of the dose. The Containment composite mix in Table 19 can be used for the Unit 1 and Unit 2 Containment Building basement fill end states. The Auxiliary Building mix in the table can be used for all other buildings and soil.

5. REFERENCES

1. TSD 11-001 Rev. 1, Potential Radionuclides of Concern During the Decommissioning of the Zion Station, October 2012.

2. NUREG/CR-3474, Long-Lived Activation Products in Reactor Materials, Pacific Northwest Laboratory, 1984.

3. NUREG/CR-4289, Residual Radionuclide Concentration Within and Around Commercial Nuclear Power Plants; Origin, Distribution, Inventory, and Decommissioning Assessment, Pacific Northwest Laboratory, 1985.

4. WINCO-1191, Radionuclides in United States Commercial Nuclear Power Reactors, Westinghouse Idaho Nuclear Company, Inc., 1994.

5. TSD 13-006 Reactor Building Units 1 and 2 End State Concrete and Liner Initial Characterization Source Terms and Distributions.

6. TSD 14-013 Zion Auxiliary Building End State Estimated Concrete Volumes, Surface Areas, and Source Terms.

7. TSD 14-014 End State Surface Areas, Volumes, and Source Terms of Ancillary Buildings.

8. TSD 13-005 Unit 1 & 2 Reactor Building Estimated End State Concrete and Liner Volumes and Surface Areas.

9. TSD 14-031 BNL Report: Basement Fill Model Evaluation of Maximum Radionuclide Concentrations for Initial Suite of Radionuclides.

10. TSD 004 BNL Report: Recommended Values for the Distribution Coefficient (KD) to be Used in Dose Assessments for Decommissioning the Zion Nuclear Power Plant.

11. TSD 14-008 Future Land Use and Conceptual Site Model for Compliance.

12. TSD 14-010 RESRAD Dose Modeling for Basement Fill Model and Soil DCGL and Calculation of Basement Fill Model Dose Factors.

13. TSD 14-021 BFM Drilling Spoils and Alternate Exposure Scenarios.

6. ATTACHMENTS 6.1. Attachment A - Concrete Characterization Core Sample, Locations, and Analyses Page 29 of 31

Attachment A TSD 14-019 Concrete Characterization Core Samples, Locations, and Analyses Revision 0 In-Number House Survey Characterization Survey Package of Gamma Off-Site Unit Identification Survey Unit Description Cores Spec Analysis Reactor Building Unit 1 1101 B101101C-U1 CTMT Bioshield Vessel Bioshield U1 CTMT 1 1 0 1102 B101102C-U1 CTMT A Loop IMB 568 Inside Missile Barrier - A Loop 568 Ft U1 CTMT 2 2 1 1103 B101103C-U1 CTMT B Loop IMB 568 Inside Missile Barrier - B Loop 568 Ft U1 CTMT 2 2 1 1104 B101104C-U1 CTMT C Loop IMB 568 Inside Missile Barrier - C Loop 568 Ft U1 CTMT 2 2 1 1105 B101105C-U1 CTMT D Loop IMB 568 Inside Missile Barrier - D Loop 568 Ft U1 CTMT 2 2 2 1106 B101106C-U1 CTMT A Loop OMB 568 Outside Missile Barrier - A Loop 568 Ft U1 CTMT 2 2 1 1107 B101107C-U1 CTMT B Loop OMB 568 Outside Missile Barrier - B Loop 568 Ft U1 CTMT 2 2 1 1108 B101108C-U1 CTMT C Loop OMB 568 Outside Missile Barrier - C Loop 568 Ft U1 CTMT 2 2 1 1109 B101109C-U1 CTMT D Loop OMB 568 Outside Missile Barrier - D Loop 568 Ft U1 CTMT 2 2 1 1110 B101110C-U1 CTMT Undervessel 543 Incore Area 543 Ft Elevation U1 CTMT 3 3 2 Total Cores 20 20 11 Reactor Building Unit 2 2102 B102102C-U2 CTMT A Loop IMB 568 Inside Missile Barrier - A Loop 568 Ft U2 CTMT 2 2 1 2103 B102103C-U2 CTMT B Loop IMB 568 Inside Missile Barrier - B Loop 568 Ft U2 CTMT 2 2 2 2104 B102104C-U2 CTMT C Loop IMB 568 Inside Missile Barrier - C Loop 568 Ft U2 CTMT 2 2 0 2105 B102105C-U2 CTMT D Loop IMB 568 Inside Missile Barrier - D Loop 568 Ft U2 CTMT 2 2 2 2106 B102106C-U2 CTMT A Loop OMB 568 Outside Missile Barrier - A Loop 568 Ft U2 CTMT 2 2 2 2107 B102107C-U2 CTMT B Loop OMB 568 Outside Missile Barrier - B Loop 568 Ft U2 CTMT 2 2 1 2108 B102108C-U2 CTMT C Loop OMB 568 Outside Missile Barrier - C Loop 568 Ft U2 CTMT 2 2 0 2109 B102109C-U2 CTMT D Loop OMB 568 Outside Missile Barrier - D Loop 568 Ft U2 CTMT 2 2 0 2110 B102110C-U2 CTMT Undervessel 543 Incore Area 543 Ft Elevation U2 CTMT 3 3 2 Total Cores 19 19 10 Auxiliary Building 05101 B105101C-Aux 542 1A RHR Pmp Unit 1 A RHR Pump Room 542 Ft Auxiliary Building 1 1 1 05102 B105102C-Aux 542 1B RHR Pmp Unit 1 B RHR Pump Room 542 Ft Auxiliary Building 05103 B105103C-Aux 542 2A RHR Pmp Unit 2A RHR Pump Room 542 Ft Auxiliary Building 1 1 1 Page 30 of 31

Attachment A TSD 14-019 Concrete Characterization Core Samples, Locations, and Analyses Revision 0 In-Number House Survey Characterization Survey Package of Gamma Off-Site Unit Identification Survey Unit Description Cores Spec Analysis 05104 B105104C-Aux 542 2B RHR Pmp Unit 2B RHR Pump Room 542 Ft Auxiliary Building 1 1 1 05105 B105105C-Aux 542 U1 Pipe Tunnel Unit 1 Pipe Chase 542 Ft Auxiliary Building 1 1 05106 B105106C-Aux 542 U2 Pipe Tunnel Unit 2 Pipe Chase 542 Ft Auxiliary Building 2 2 05107 B105107C-Aux 542 HUT Cubicles Hold Up Tanks 542 Ft Auxiliary Building 1 1 05108 B105108C-Aux 542 Central Area Central Area 542 Ft Auxiliary Building 4 4 2 05109 B105109C-Aux 542 South Area South Area 542 Ft Auxiliary Building 1 1 05110 B105110C-Aux 542 North Area North Area 542 Ft Auxiliary Building 2 2 05111 B105111C-Aux 542 East Area West Area 542 Ft Auxiliary Building 2 2 05112 B105112C-Aux 542 Gas Decay Tks Gas Decay Tanks 542 Ft Auxiliary Building 05113 B105113C-Aux 542 U1 EDCT Rm Unit 1 Equipment Drain Collection Tank 542 Ft Auxiliary Building 3 3 1 05114 B105114C-Aux 542 U2 EDCT Rm Unit 2 Equipment Drain Collection Tank 542 Ft Auxiliary Building 1 1 B105115C-Aux 542 HUT Recirc BAE HUT Recirculation and BAE Feed Pumps 542 Ft Auxiliary Building 05115 Feed Aux Building Equipment Drain Tank and Pumps 542 Ft Auxiliary 05116 B105116C-Aux 542 EDT Building 05117 B105117C-Aux 542 A Sump Aux Building Sump A 542 Ft Auxiliary Building 05118 B105118C-Aux 542 B Sump Aux Building Sump B 542 Ft Auxiliary Building Total Cores 20 20 6 Turbine Building 06104 B206104 - North Area Turbine Building 560 Ft. Unit 1 North Area 3 3 0 06207 B206207 - Unit 1 Steam Pipe Tunnel Turbine Building 570 Ft. Unit 1 Steam Pipe Tunnel 5 5 0 06208 B206208 - Unit 2 Steam Pipe Tunnel Turbine Building 570 Ft. Unit 2 Steam Pipe Tunnel 2 2 0 Total Cores 10 10 0 Overall Totals 69 69 27 Page 31 of 31

Technical Support Document TSD 14-019 Radionuclides of Concern for Soil and Basement Fill Model Source Terms Revision 0 Originator: ___ _______________________ Date: ___12/18/14 _______

Harvey Farr Reviewer: __(signature on file)____________________ Date:__12/18/14_________

Dave Wojkowiak Approval: __(signature on file)____________________ Date:__12/18/14_________

Robert F. Yetter

TSD 14-019 Revision 0 Summary of Changes in this Revision:

Rev. 0 -Initial issuance.