ML17215A115
| ML17215A115 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 02/23/2017 |
| From: | Fauver D ZionSolutions |
| To: | Office of Nuclear Material Safety and Safeguards |
| Shared Package | |
| ML17215A095 | List:
|
| References | |
| ZS-2017-0084 TSD 14-019, Rev. 2 | |
| Download: ML17215A115 (65) | |
Text
Technical Support Document TSD 14-019 Radionuclides of Concern for Soil and Basement Fill Model Source Terms Revision 2 Originator: ____________________________________________________ Date: 02/23/17 David Fauver Reviewer: _____________________________________________________ Date: 02/23/17 David Wojtkowiak Approval: ________________ _____________________ Date: 02/23/17 Robert F. Yetter
TSD 14-019 Revision 2 Summary of Changes in this Revision:
- Rev. 1 - Correct typo from TSD 14-031 for Crib House Ni-63 peak concentration in pCi/L and for Spent Fuel Building peak tritium concentration. Updated 0.15 cm soil DCGLs and corrected error in percent dose from using 2013 data.
- Rev. 2 - Revise section 4 pertaining to insignificant dose contributors.
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TSD 14-019 Revision 2 TABLE OF CONTENTS
- 1. PURPOSE ...................................................................................................................................... 5
- 2. DISCUSSION ................................................................................................................................ 5 2.1. TSD 11-001 Initial Suite of Potential Radionuclides ........................................... 5 2.2. Radionuclides Identified in Characterization Data ............................................... 6 2.3. Pathway Dose Factors......................................................................................... 13
- 3. CALCULATIONS ....................................................................................................................... 16 3.1. Normalized End State Basement Fill Source Terms .......................................... 16 3.2. Basement Fill Doses for Normalized Source Terms .......................................... 18 3.3. End State Basement Fill Radionuclide Mixes .................................................... 24 3.4. Soil Radionuclides of Concern ........................................................................... 26
- 4. INSIGNIFICANT DOSE CONTRIBUTORS ............................................................................. 34 4.1. Calculation IC Dose Percentage Using Mixtures ............................................... 38 4.2. Calculation of IC Dose from Individual Concrete Core Results ........................ 41 4.3. Calculation of IC Dose Percentage and IC Dose Using Drilling Spoils Basement Scenario DCGLs ................................................................................ 52 4.4. IC Dose Calculation for Average Soil Sample Results ...................................... 58 4.5. Surrogate Ratios.................................................................................................. 60
- 5. CONCLUSION............................................................................................................................ 62
- 6. REFERENCES ............................................................................................................................ 62
- 7. ATTACHMENTS........................................................................................................................ 63 7.1. Attachment A - Concrete Characterization Core Sample, Locations, and Analyses .............................................................................................................. 63 LIST OF TABLES Table 1 - TSD 11-001 Rev. 1 List of Radionuclides of Concern ............................................................. 5 Table 2 - Estimated January 1, 2013 Source Terms from On-Site Gamma Spectroscopy Results .......... 7 Table 3 - Off-Site Laboratory Suite of Radionuclides and Analysis Methods ......................................... 7 Table 4 - Hard-to-Detect Radionuclides from Off-Site Analysis and Table 2 Scaling Nuclide .............. 8 Table 5 - Estimated January 1, 2013 Unit 1 & 2 Reactor Building and Auxiliary Building Source Terms........................................................................................................................................ 9 Table 6 - January 1, 2013 Radionuclide Percent of Total Estimated Source Term for Each Area ....... 10 Table 7 - Estimated July 1, 2018 Unit 1 & 2 Reactor Building and Auxiliary Building Source Terms 11 Table 8 - July 1, 2018 Radionuclide Percent of Total Estimated Source Term for Each Area ............ 12 Table 9 - Radionuclides of Concern Evaluated in Characterization Samples at the Zion Power Plant 13 Table 10 - Groundwater Pathway Dose Factors for Initial Suite of Nuclides of Concern .................... 14 Table 11 - Drill Spoils Dose Factors ...................................................................................................... 15 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 ........................................... 17 Table 15 - January 1, 2013 Calculated Dose for Normalized 1 Ci Source Term ................................... 20 Table 16 - July 1, 2018 Calculated Dose for Normalized 1 Ci Source Term ......................................... 21 Table 17 - Basement July1, 2018 Mix Individual Nuclide Percent of Total Dose ................................ 23 Table 18 - July 1, 2018 Unit 1 and Unit 2 Containment Normalized Composite Mixes ....................... 24 Table 19 - Basement Fill End State July 1, 2018 Radionuclide Mixes for FSS ..................................... 25 Table 20 - ROCs Only Basement Fill End State July 1, 2018 Radionuclide Mixes for FSS ................ 26 Table 21 - ZSRP 0.15 Meter Soil DCGLs .............................................................................................. 27 Table 22 - July 1, 2018 Normalized Concrete and RCS Pipe Mix Soil Doses....................................... 29 Page 3 of 65
TSD 14-019 Revision 2 Table 23 - Soil July 1, 2018 Mix Individual Nuclide Percent of Total Dose ......................................... 31 Table 24 - Soil Radionuclides of Concern and Insignificant Dose ........................................................ 33 Table 25 - Basement Fill End State July 1, 2018 Radionuclide Mixes for Soil FSS ............................. 33 Table 26 - ROCs Only Soils July 1, 2018 Radionuclide Mixes for FSS ................................................ 34 Table 27 - DCGLs for Concrete Structures ........................................................................................... 36 Table 28 - DCGLs for Soil ..................................................................................................................... 37 Table 29 - IC Dose Using Average Mixture (Table 19) ........................................................................ 39 Table 30 - IC Dose Using Average Core Concentration ....................................................................... 40 Table 31 - Basement Insignificant Contributor Dose and Dose Percentage for Mixtures ..................... 41 Table 32 - IC Dose for Individual Concrete Core Samples ................................................................... 43 Table 33 - Basement Insignificant Contributor Dose and Dose Percentage for Individual Core Samples ........................................................................................................................ 52 Table 34 - Drilling Spoils DCGLs for Concrete Structures ................................................................... 53 Table 35 - IC Dose Percentage When Using DCGLBS .......................................................................... 54 Table 36 - Basement Insignificant Contributor Dose and Dose Percentage for Mixtures using DCGLBS............................................................................................................................... 57 Table 37 - Basement Insignificant Contributor Dose and Dose Percentage for Individual Core Samples using DCGLBS ............................................................................................... 57 Table 38 - IC Dose Using Average Soil Concentration ......................................................................... 59 Table 39 - Surrogate Ratios ................................................................................................................... 61 Page 4 of 65
TSD 14-019 Revision 2
- 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 Note: Half-lives from original TSD 11-001 in 2011 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 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.
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TSD 14-019 Revision 2 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 4 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 ones in order to ensure sufficient source term to quantify HTD nuclide ratios relative to the Table 3 scaling nuclides. Use of low concentration cores artificially reduces the ratio of the HTD nuclide to scaling nuclide due to the low scaling nuclide activity and the MDAs of the HTD nuclides.
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TSD 14-019 Revision 2 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 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 Page 7 of 65
TSD 14-019 Revision 2 Radionuclide Analytical Method 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 from interference of 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 building end state basement structure 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 ND Fe-55 ND I-129 ND Pu-238 Cs-137 Ni-59 ND 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 ND Pu-241 ND Sr-90 Cs-137 Pm-147 Cs-137 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 Cm-244 Cs-137 ND = Not Detected due to compromised results. See TSD 13-006 and TSD 14-013 Page 8 of 65
TSD 14-019 Revision 2 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, as seen in the two bottom rows of Table 5, the MDA values were used for each of the Table 2 radionuclides even when it was not positively identified in that puck. More significantly, the locations with the highest contact dose rates and/or visible evidence of leaks were chosen for concrete core sampling, which biased the scaling nuclide (Cs-137 and Co-60) 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. 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 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 Page 9 of 65
TSD 14-019 Revision 2 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 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 No MDA 7.17E+00 1.43E-02 7.19E+00 1.84E+00 1.90E-02 1.85E+00 7.86E-01 1.46E-01 9.32E-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%
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%
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TSD 14-019 Revision 2 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 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 due to decay.
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 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 Page 11 of 65
TSD 14-019 Revision 2 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 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%
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%
Page 12 of 65
TSD 14-019 Revision 2 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 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)
The model assumed that the basement saturated zone 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 RESRAD 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. There was a slight change to the Ni-63 Crib House DCF from the one used in revision 0 of this TSD based on a correction to TSD 14-031 that changed the value from 2.69E-04 to 3.44E-
- 04. As noted in TSD 14-010, the Spent Fuel Pool and Transfer Canal floor are at 576 elevation, Page 13 of 65
TSD 14-019 Revision 2 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 3.44E-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 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. There were slight changes to the Ni-63 and Sr-90 drill spoils DCFs as a result of new 0.15 meter soil DCGLs from RESRAD runs made to address NRC requests for additional information. In addition, some very minor changes to the Europium DCGLs as explained above Table 21 resulted in minor changes to the DCFs in Table 11.
Page 14 of 65
TSD 14-019 Revision 2 Table 11 - Drill Spoils Dose Factors Aux Building SFB Drill Turbine Crib House WWTF Drill Drill Spoils CTMT Drill Spoils Drill Spoils Drill Spoils Spoils mrem/yr per Spoils mrem mrem/yr per mrem/yr per mrem/yr per mrem/yr per Nuclide mCi per mCi mCi mCi mCi 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 1.46E-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 3.23E-08 5.61E-08 3.78E-07 1.86E-08 4.14E-08 4.16E-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 6.26E-05 1.39E-04 7.60E-04 4.61E-05 9.96E-05 1.04E-03 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. The revised Ni-63 and Sr-90 soil DCGLs resulted in minor changes to the Table 12 DCFs.
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 Page 15 of 65
TSD 14-019 Revision 2 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 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 5.63E-03 2.03E-02 8.25E-02 6.13E-03 9.97E-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 3.78E-07 4.01E-04 3.44E-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 7.60E-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.
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 Page 16 of 65
TSD 14-019 Revision 2 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 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 6.98E-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 3.22E-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 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 Page 17 of 65
TSD 14-019 Revision 2 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 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 6.16E-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 4.01E-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.
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.
There is a slight change to the Auxiliary Building missed dose totals due to the DCF changes described above and use of updated half-lives in Version 3 of NRC Radiological Toolbox. (14)
These changes were very minor resulting a change in the missed dose in the Aux Building changing Page 18 of 65
TSD 14-019 Revision 2 from 2.88E-01 to 3.00E-01 and the percent of missed dose changing from 1.266% to 1.320%. The rest of the values were unchanged.
As seen in Table 15 and Table 16, the activated concrete in the Unit 1 and 2 542 elevation 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 3% 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 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 composite of the Unit 1 and Unit 2 Overall normalized mix should be used for the Containment source term. 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.
Page 19 of 65
TSD 14-019 Revision 2 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 542' Total 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 7.28E-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 Page 20 of 65
TSD 14-019 Revision 2 Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bldg Total Total 542' Total 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 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
= 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 542' Total 542' Total Total 568' Floor & Overall Total 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 Page 21 of 65
TSD 14-019 Revision 2 Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bldg Total 542' Total 542' Total Total 568' Floor & Overall Total 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 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 4.84E-01 1.53E-02 2.23E-03 6.4E-01 8.13E-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 2.82E-01 3.95E-01 3.00E-01
% Missed 0.427% 4.566% 0.430% 0.691% 5.963% 0.708% 1.247% 1.708% 1.320%
No Np-237 0.234% 0.838% 0.235% 0.588% 2.327% 0.594% 0.386% 0.336% 0.378%
= Included in ROCs when Activated Concrete is Present Bold Italic = MDA
= Basement Fill ROCs Page 22 of 65
TSD 14-019 Revision 2 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 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 0.014% 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% 33.675% 93.118% 97.600% 95.112% 97.206%
Eu-152 0.018% 13.301% 0.028% 0.005% 46.017% 0.155% 0.004% 0.006% 0.004%
Eu-154 0.009% 0.713% 0.010% 0.003% 2.586% 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% 3.723% 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%
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 Page 23 of 65
TSD 14-019 Revision 2 Table 18 - July 1, 2018 Unit 1 and Unit 2 Containment Normalized Composite Mixes Overall Overall Composite 568' Composite Overall Composite Composite Nuclide Ci Incore Ci Composite 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%
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%
=ROCs All Basements Missed Dose 5.93E-04
=Additional ROCs for Containments % Missed 0.514%
No Np-237 0.344%
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 Spent Fuel Building. The Transfer Canal and Spent Page 24 of 65
TSD 14-019 Revision 2 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% 0.048%
C-14 7.71E-05 0.008% 0.019% 4.41E-04 0.044% 0.126%
Fe-55 1.74E-03 0.174% 0.000% 1.06E-03 0.106% 0.000%
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% 0.432%
Ni-63 2.63E-01 26.275% 0.366% 2.35E-01 23.480% 0.296%
Sr-90 2.73E-04 0.027% 1.072% 5.10E-04 0.051% 0.739%
Nb-94 1.78E-03 0.178% 0.044% 1.27E-04 0.013% 0.008%
Tc-99 7.59E-05 0.008% 0.042% 1.60E-04 0.016% 0.104%
Ag-108m 2.82E-03 0.282% 0.113% 1.72E-04 0.017% 0.014%
Sb-125 2.48E-04 0.025% 0.043% 1.74E-04 0.017% 0.010%
Cs-134 8.15E-05 0.008% 0.015% 1.03E-04 0.010% 0.007%
Cs-137 6.76E-01 67.582% 96.269% 7.46E-01 74.597% 97.206%
Eu-152 4.36E-03 0.436% 0.067% 1.75E-04 0.017% 0.0039%
Eu-154 5.79E-04 0.058% 0.010% 9.43E-05 0.009% 0.0023%
Eu-155 1.83E-04 0.018% 0.000% 7.74E-05 0.008% 0.0001%
Np-237 9.25E-07 0.000% 0.171% 4.37E-06 0.0004% 0.9453%
Pu-238 5.19E-06 0.001% 0.005% 1.29E-05 0.001% 0.0120%
Pu-239 1.95E-06 0.000% 0.002% 5.34E-06 0.0005% 0.0061%
Pu-240 1.95E-06 0.000% 0.002% 5.33E-06 0.001% 0.0061%
Pu-241 6.70E-05 0.007% 0.002% 2.82E-04 0.028% 0.0057%
Am-241 6.73E-05 0.007% 0.067% 1.27E-05 0.001% 0.0144%
Am-243 1.71E-06 0.000% 0.002% 9.50E-06 0.001% 0.0111%
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% 0.0002%
Total 1.00E+00 100% 100% 1.00E+00 100% 100%
Insignificant 8.64E-03 0.864% 0.514% 9.54E-03 0.954% 1.32%
=ROCs All Basements
=Additional ROCs for Containments There is a slight change to the Auxiliary Building percent annual dose values in the last column of Table 19 due to an error in the Rev. 0 spreadsheet that was referencing the January 1, 2013 % dose values instead of the July 18, 2018 values. This resulted in the insignificant dose increasing slightly from 1.207% to 1.32%.
Page 25 of 65
TSD 14-019 Revision 2 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% 0.432%
Ni-63 2.63E-01 26.275% 0.366% 2.35E-01 23.480% 0.296%
Sr-90 2.73E-04 0.027% 1.072% 5.10E-04 0.051% 0.739%
Cs-134 8.15E-05 0.008% 0.015% 1.03E-04 0.010% 0.007%
Cs-137 6.76E-01 67.582% 96.269% 7.46E-01 74.597% 97.206%
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% 1.32%
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. As described for Table 11, there were minor changes to the Rev. 0 DCGLs. The Rev 0. DCGLs were Eu-152, 1.073E+01, Eu-154, 9.963E+00, and Eu-155, 3.896E+02. The revised RESRAD runs described changed the Ni-63 and Sr-90 DCGLs from Ni-63, 3.996E+03 and Sr-90, 1.439E+01 to the values in Table 21.
Page 26 of 65
TSD 14-019 Revision 2 Table 21 - ZSRP 0.15 Meter Soil DCGLs DCGL DCGL Nuclide pCi/g Nuclide 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 3.969E+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 1.074E+01 Sb-125 3.360E+01 Eu-154 9.969E+00 Sr-90 1. 343E+01 Eu-155 3.909E+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. The changes in the DCGLs described for Table 21 and changes in half-lives used resulted in changes to the Rev. 0 missed doses calculated of 0.7%
or less. These were so minor they did not change the values of the insignificant doses reported in the Rev. 0 summary tables Table 24, Table 25, or Table 26 below.
As seen in Page 27 of 65
TSD 14-019 Revision 2 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.
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, Cs-134 and Cs-137 are the radionuclides of concern in soil.
Page 28 of 65
TSD 14-019 Revision 2 Table 22 - July 1, 2018 Normalized Concrete and RCS Pipe Mix Soil Doses Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bldg L48320-1 U2 RCS Total 542' Total 542' Total Inside Total 568' Floor & Overall Total 568' Floor & Overall Total 542' Contam Overall L50297 U1 Piping Floor Walls Total Floor Walls Total Floor Wall 542' Total RCS 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 1.43E-04 2.86E-04 1.43E-04 3.19E-03 1.0E-03 3.17E-03 1.48E-03 1.48E-03 1.48E-03 2.22E-03 1.99E-03 Sr-90 9.48E-04 1.82E-04 9.46E-04 7.18E-05 6.3E-05 7.17E-05 5.91E-04 2.89E-03 9.49E-04 4.88E-03 9.80E-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 3.86E-03 1.19E+00 5.95E-03 4.32E-04 1.5E+00 1.43E-02 3.65E-04 6.31E-04 4.07E-04 0 0 Eu-154 1.80E-03 5.99E-02 1.90E-03 2.76E-04 8.0E-02 1.01E-03 2.18E-04 3.38E-04 2.36E-04 6.00E-03 3.08E-03 Eu-155 1.11E-05 5.12E-04 1.20E-05 6.88E-06 5.0E-04 1.14E-05 4.78E-06 5.86E-06 4.95E-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 Page 29 of 65
TSD 14-019 Revision 2 Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bldg L48320-1 U2 RCS Total 542' Total 542' Total Inside Total 568' Floor & Overall Total 568' Floor & Overall Total 542' Contam Overall L50297 U1 Piping Floor Walls Total Floor Walls Total Floor Wall 542' Total RCS 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 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 8.76E-03 1.26E+00 1.10E-02 3.39E-02 1.63E+00 4.86E-02 4.42E-03 7.38E-03 4.88E-03 1.27E-01 6.71E-02
% Missed 0.544% 61.994% 0.681% 3.145% 82.475% 4.471% 0.359% 0.585% 0.395% 3.917% 3.360%
No Np-237 0.542% 61.987% 0.678% 3.144% 82.474% 4.470% 0.349% 0.569% 0.384% 0.999% 1.007%
ROC Missed Dose 1.84E-03 7.67E-03 1.85E-03 2.96E-02 3.29E-02 2.96E-02 2.10E-03 2.18E-03 2.11E-03 1.19E-01 6.36E-02
= Co-60 & Cs-137 Only All Others Missed Dose Bold Italic = MDA
= Included in ROCs when Activated Concrete is Present
= Basement Fill ROCs Page 30 of 65
TSD 14-019 Revision 2 Table 23 - Soil July 1, 2018 Mix Individual Nuclide Percent of Total Dose Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bldg L48320 Total -1 U2 Incore Total Total L50297 RCS Total 542' Total 542' Total Conta U1 Inside 568' Floor & Overall 568' Floor & Overall 542' m Wall Overall 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% 13.520% 5.290% 38.000% 13.419% 37.589% 3.493% 5.915% 3.878% 94.830% 68.862%
Ni-63 0.009% 0.014% 0.009% 0.295% 0.052% 0.291% 0.120% 0.118% 0.120% 0.068% 0.100%
Sr-90 0.059% 0.009% 0.059% 0.007% 0.003% 0.007% 0.048% 0.229% 0.077% 0.150% 0.049%
Nb-94 0.032% 0.157% 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% 1.502% 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% 0.119% 0.034% 0.021% 0.066% 0.028% 0.025% 0.024%
Cs-137 94.184% 24.485% 94.029% 58.855% 4.106% 57.940% 96.148% 93.500% 95.728% 1.253% 27.778%
Eu-152 0.240% 58.507% 0.370% 0.040% 76.595% 1.319% 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%
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% 2.947% 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%
Page 31 of 65
TSD 14-019 Revision 2 Unit 1 CTMT Concrete Unit 2 CTMT Concrete Aux Bldg L48320 Total -1 U2 Incore Total Total L50297 RCS Total 542' Total 542' Total Conta U1 Inside 568' Floor & Overall 568' Floor & Overall 542' m Wall Overall 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 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%
Co-60 &
Cs-137 99.456% 38.006% 99.319% 96.855% 17.525% 95.529% 99.641% 99.415% 99.605% 96.083% 96.640%
ROC Total 99.886% 99.624% 99.885% 97.256% 98.335% 97.274% 99.830% 99.827% 99.829% 96.327% 96.813%
Note - Yellow cells are greater than 0.5%
Page 32 of 65
TSD 14-019 Revision 2 Table 24 - Soil Radionuclides of Concern and Insignificant Dose Dose Dose Nuclide mrem/year Nuclide mrem/year H-3 9.51E-06 Eu-154 2.36E-04 C-14 1.23E-04 Eu-155 4.95E-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 1.48E-03 Pu-240 9.15E-07 Sr-90 9.49E-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.
Table 25 - Basement Fill End State July 1, 2018 Radionuclide Mixes for Soil FSS Dose Activity Percent Percent Nuclide mrem/year Ci Activity Annual Dose H-3 9.51E-06 1.74E-03 0.1743% 0.0008%
C-14 1.23E-04 4.41E-04 0.0441% 0.0100%
Fe-55 7.83E-07 1.06E-03 0.1057% 0.0001%
Ni-59 1.14E-05 4.98E-03 0.4982% 0.0009%
Co-60 4.79E-02 9.08E-03 0.9076% 3.8775%
Ni-63 1.48E-03 2.35E-01 23.4804% 0.1196%
Sr-90 9.49E-04 5.10E-04 0.0510% 0.0767%
Nb-94 4.24E-04 1.27E-04 0.0127% 0.0343%
Tc-99 3.13E-05 1.60E-04 0.0160% 0.0025%
Ag-108m 5.82E-04 1.72E-04 0.0172% 0.0471%
Sb-125 1.29E-04 1.74E-04 0.0174% 0.0105%
Cs-134 3.43E-04 1.03E-04 0.0103% 0.0277%
Cs-137 1.18E+00 7.46E-01 74.5965% 95.7278%
Eu-152 4.07E-04 1.75E-04 0.0175% 0.0329%
Eu-154 2.36E-04 9.43E-05 0.0094% 0.0191%
Eu-155 4.95E-06 7.74E-05 0.0077% 0.0004%
Np-237 1.36E-04 4.37E-06 0.0004% 0.0110%
Pu-238 2.00E-06 1.29E-05 0.0013% 0.0002%
Page 33 of 65
TSD 14-019 Revision 2 Pu-239 9.16E-07 5.34E-06 0.0005% 0.0001%
Pu-240 9.15E-07 5.33E-06 0.0005% 0.0001%
Pu-241 1.08E-06 2.82E-04 0.0282% 0.0001%
Am-241 2.37E-06 1.27E-05 0.0013% 0.0002%
Am-243 4.77E-06 9.50E-06 0.0009% 0.0004%
Cm-243 1.10E-06 3.35E-06 0.0003% 0.0001%
Cm-244 2.85E-07 3.09E-06 0.0003% 0.0000%
Total 1.24E+00 1.00E+00 1.00E+00 1.00E+00 Insignificant 2.11E-03 9.54E-03 9.54E-03 1.71E-03
=ROCs Soils Table 26 shows the percentages with only the dose significant ROCs.
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 1.48E-03 2.35E-01 23.48% 0.120%
Sr-90 9.49E-04 5.10E-04 0.05% 0.077%
Cs-134 3.43E-04 1.03E-04 0.01% 0.028%
Cs-137 1.18E+00 7.46E-01 74.60% 95.728%
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. INSIGNIFICANT DOSE CONTRIBUTORS The dose percentages for the initial suite radionuclides provided in Table 19 were calculated using the best estimate radionuclide mixture fractions and Basement Dose Factors to provide a list of expected ROC and the estimated dose percentage from the insignificant contributor (IC) radionuclides. Derived Concentration Guideline Levels (DCGL) were calculated for basement surfaces and soil in ZionSolutions TSD 14-010 (Reference 12).
DCGLs are used in this section to confirm the radionuclides designated as ROC and provide input to the selection of the IC dose percentage to be used in TSD 14-010 to adjust to the ROC DCGLs. The basis and rationale for the selection of the IC dose percentage used to adjust the ROC DCGLs is provided in Zion LTP Chapter 6, Revision 1. The DCGLs for basement concrete (DCGLB) and soil DCGLs from TSD 14-010 are reproduced in Tables 27 and 28.
Page 34 of 65
TSD 14-019 Revision 2 The DCGLB listed in Table 27 are the combination of the Groundwater DCGLs and Drilling Spoils DCGLs and are values used for Final Status Survey (FSS) (equivalent to the DCGLw as defined in MARSSIM). The IC dose percentage and IC dose were also calculated using the Drilling Spoils basement scenario DCGL (DCGLBS) separately since the DCGLBS is used in the Elevated Measurement Comparison test (see TSD 14-010). See section 4.3 for Drilling Spoils IC dose assessment.
Each radionuclide-specific DCGL is equivalent to the level of residual radioactivity (above background levels) that could, when considered independently, result in a Total Effective Dose Equivalent (TEDE) of 25 mrem per year to an Average Member of the Critical Group (AMCG).
When applied to soil, the DCGLs are expressed in units of activity per unit of mass (pCi/g).
When applied to basement surfaces, DCGLs are expressed in units of activity per area (pCi/m2).
NUREG-1757, Vol. 2, Rev. 1 defines radionuclides as insignificant dose contributors if the sum of the dose from the group of insignificant contributors (IC) is less than 10% of the total dose from all radionuclides combined. The IC can be eliminated from further detailed consideration in the LTP and FSS. However, the dose contribution from the insignificant contributors must be accounted for by adjusting the ROC DCGLs.
Calculations of IC dose percentages are provided for four mixtures:
Best Estimate mixtures for Containment and Auxiliary Basement in Table 19 Unit 1 Containment Mixture using HTD core results from Unit 1 only Unit 2 Containment Mixture using HTD core results from Unit 2 only Auxiliary Basement Mixture using HTD core results from Auxiliary Basement only Using radionuclide mixture fractions provides dose results only in terms of percentages which are assumed to be the percentage of 25 mrem/yr, i.e., an IC dose percentage of 10% represents a corresponding dose of 2.5 mrem/yr (25
- 0.1).
Since only a single dose percentage and corresponding dose can be calculated with mixtures, the dose was also calculated directly from each of the individual core and soil sample results using the actual reported concentrations as opposed to averages. The resulting dose values for the individual cores were used to evaluate the variability of the IC dose percentages (and corresponding dose) calculated using the mixtures. The mean, standard deviation of the mean, 95% Upper Confidence Level (UCL) and range of the IC dose based on individual core and soil sample data were calculated.
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TSD 14-019 Revision 2 Table 27 - DCGLs for Concrete Structures CTMT Auxiliary Bldg Radionuclide (pCi/m2) (pCi/m2)
H-3 2.64E+08 5.58E+08 C-14 2.53E+07 5.33E+07 Fe-55 4.76E+11 4.28E+12 Ni-59 1.22E+10 2.57E+10 Co-60 1.74E+08 3.20E+08 Ni-63 4.46E+09 1.21E+10 Sr-90 1.59E+06 1.05E+07 Nb-94 2.50E+08 2.46E+08 Tc-99 1.11E+07 2.34E+07 Ag-108m 1.55E+08 1.94E+08 Sb-125 3.62E+07 2.63E+08 Cs-134 3.34E+07 2.22E+08 Cs-137 4.37E+07 1.17E+08 Pm-147 1.26E+10 1.15E+11 Eu-152 4.07E+08 6.81E+08 Eu-154 3.54E+08 6.14E+08 Eu-155 5.24E+09 1.19E+10 Np-237 3.36E+04 7.04E+04 Pu-238 6.99E+06 1.64E+07 Pu-239/240 6.29E+06 1.32E+07 Pu-241 1.96E+08 7.56E+08 Am-241 6.25E+06 1.34E+07 Am-243 6.25E+06 1.31E+07 Cm-243/244 4.57E+07 1.28E+08 Page 36 of 65
TSD 14-019 Revision 2 Table 28 - DCGLs for Soil Soil Radionuclide (pCi/g)
H-3 4.58E+03 C-14 8.96E+01 Fe-55 3.37E+04 Ni-59 1.09E+04 Co-60 4.73E+00 Ni-63 3.97E+03 Sr-90 1.34E+01 Nb-94 7.51E+00 Tc-99 1.28E+02 Ag-108m 7.40E+00 Sb-125 3.36E+01 Cs-134 7.52E+00 Cs-137 1.58E+01 Pm-147 1.20E+05 Eu-152 1.07E+01 Eu-154 9.97E+00 Eu-155 3.91E+02 Np-237 8.01E-01 Pu-238 1.62E+02 Pu-239/240 1.46E+02 Pu-241 6.52E+03 Am-241 1.34E+02 Am-243 4.98E+01 Cm-243/244 7.61E+01 Page 37 of 65
TSD 14-019 Revision 2 4.1. Calculation IC Dose Percentage Using Mixtures The first calculation used the DCGLB in conjunction with the radionuclide mixture fractions in Table 19 to confirm that the IC dose percentage calculated using DCGLs is equal to the IC dose percentage calculated using Basement Dose Factors. Equal percentage is expected since the DCGLs were calculated in TSD 14-010 by multiplying the Basement Dose Factors by a constant.
As seen in Table 29, the IC dose percentages are the same (with trivial rounding error) using DCGLs and Basement Dose Factors (see Table 19)
In addition to the Table 19 mixture, IC dose calculations were also performed for each Containment separately as well as the Auxiliary Building separately using a mixture comprised of the mean activity of each radionuclide using only the core analyzed for the full initial suite in a specific basement. The basement-specific mixtures for Unit 1 Containment, Unit 2 Containment, and the Auxiliary Basement were based on populations of 11 cores, 10 cores and 6 cores, respectively. The evaluation of the basement specific mixtures was performed to ensure that no significant, unintended bias was introduced by using all core results in the Table 19 mixture.
The Table 19 mixture is based on all available results, from both onsite and offsite analyses, of cores from the Containment and Auxiliary basements and is considered the most representative data available for the site. Core samples collected from other basements exhibited minimal residual radioactivity and were therefore not useful for determining a radionuclide mixture. The most accurate mixture fractions are calculated when the HTD radionuclides are positively detected. If the HTD radionuclides are not positively detected, the mixture percentages assigned to the HTD radionuclides in concrete are based on the MDC values. However, the accuracy of the mixture fractions assigned to HTD radionuclides using MDC values will decrease as the sample activity, predominately Cs-137, decreases.
The IC dose percentages were calculated for each the four mixture fractions as described in the steps below.
- 1. The average mixture fractions for each of the initial suite radionuclides were divided by the corresponding DCGL (and multiplied by 25 mrem/yr) in Table 27 to calculate the relative dose.
- 2. The relative dose values were then summed.
- 3. The relative dose values for each radionuclide were then divided by the summation value to normalize the dose to 1.0 derive a dose percentage.
- 4. The IC dose percentage is calculated by summing the dose percentages of the IC radionuclides in column 4.
The results of this analysis are provided in Tables 29 and 30. A summary of the results is provided in Table 31. Note that Table 31 also includes a Corresponding Dose value which is the dose percentage corresponding to an assumed 25 mrem/yr total dose.
Page 38 of 65
TSD 14-019 Revision 2 Table 29 - IC Dose Using Average Mixture (Table 19)
CTMT Table 19 Mixture (Simplified Mixture Tab) Aux Bldg Table 19 Mixture (Simplified Mixture Tab)
Dose Dose Radionuclide Avg. Conc. Avg. Fraction Relative Dose Avg. Conc. Avg. Fraction Relative Dose Percentage Percentage (Ci) (mrem/yr) (Ci) (mrem/yr)
H-3 7.40E-04 0.000740 7.01E-11 0.02% 1.74E-03 0.001743 7.81E-11 0.05%
C-14 7.71E-05 0.000077 7.63E-11 0.02% 4.41E-04 0.000441 2.07E-10 0.13%
Fe-55 1.74E-03 0.001739 9.13E-14 0.00% 1.06E-03 0.001057 6.18E-15 0.00%
Ni-59 1.56E-03 0.001559 3.19E-12 0.00% 4.98E-03 0.004982 4.85E-12 0.00%
Co-60 4.68E-02 0.046753 6.70E-09 1.67% 9.08E-03 0.009076 7.10E-10 0.43%
Ni-63 2.63E-01 0.262754 1.47E-09 0.37% 2.35E-01 0.234806 4.85E-10 0.30%
Sr-90 2.73E-04 0.000273 4.30E-09 1.07% 5.10E-04 0.000510 1.21E-09 0.74%
Nb-94 1.78E-03 0.001782 1.78E-10 0.04% 1.27E-04 0.000127 1.29E-11 0.01%
Tc-99 7.59E-05 0.000076 1.70E-10 0.04% 1.60E-04 0.000160 1.71E-10 0.10%
Ag-108m 2.82E-03 0.002820 4.54E-10 0.11% 1.72E-04 0.000172 2.22E-11 0.01%
Sb-125 2.48E-04 0.000248 1.72E-10 0.04% 1.74E-04 0.000174 1.66E-11 0.01%
Cs-134 8.15E-05 0.000081 6.10E-11 0.02% 1.03E-04 0.000103 1.16E-11 0.01%
Cs-137 6.76E-01 0.675826 3.87E-07 96.27% 7.46E-01 0.745971 1.60E-07 97.21%
Pm-147 NA NA NA NA NA NA NA NA Eu-152 4.36E-03 0.004359 2.68E-10 0.07% 1.75E-04 0.000175 6.41E-12 0.00%
Eu-154 5.79E-04 0.000579 4.09E-11 0.01% 9.43E-05 0.000094 3.84E-12 0.00%
Eu-155 1.83E-04 0.000183 8.71E-13 0.00% 7.74E-05 0.000077 1.63E-13 0.00%
Np-237 9.25E-07 0.000001 6.87E-10 0.17% 4.37E-06 0.000004 1.55E-09 0.95%
Pu-238 5.19E-06 0.000005 1.86E-11 0.00% 1.29E-05 0.000013 1.97E-11 0.01%
Pu-239/240 1.95E-06 0.000002 7.74E-12 0.00% 5.34E-06 0.000005 1.01E-11 0.01%
Pu-241 6.70E-05 0.000067 8.53E-12 0.00% 2.82E-04 0.000282 9.33E-12 0.01%
Am-241 6.73E-05 0.000067 2.69E-10 0.07% 1.27E-05 0.000013 2.36E-11 0.01%
Am-243 1.71E-06 0.000002 6.83E-12 0.00% 9.50E-06 0.000009 1.81E-11 0.01%
Cm-243/244 6.05E-06 0.000006 3.31E-12 0.00% 3.35E-06 0.000003 6.51E-13 0.00%
IC Percentage 0.5119% IC Percentage 1.3136%
Notes: Average Concentrations decay corrected from sample date of 1/13/2013 to 7/1/2018 (5.5 years)
Half-lifes and Decay Constants from the NRC Radiological Toolbox Version 3.0.0 Page 39 of 65
TSD 14-019 Revision 2 Table 30 - IC Dose Using Average Core Concentration U1 CTMT Cores (11 cores) U2 CTMT Cores (10 cores) Aux Bldg. Cores (6 cores)
Dose Dose Dose Radionuclide Avg. Conc. Avg. Fraction Relative Dose Avg. Conc. Avg. Fraction Relative Dose Avg. Conc. Avg. Fraction Relative Dose Percentage Percentage Percentage (Ci) (mrem/yr) (Ci) (mrem/yr) (Ci) (mrem/yr)
H-3 5.62E+01 0.001298 1.23E-10 0.02% 5.63E+01 0.001794 1.70E-10 0.03% 9.16E+00 0.001844 8.27E-11 0.05%
C-14 5.03E+00 0.000116 1.15E-10 0.02% 2.74E+00 0.000087 8.63E-11 0.02% 2.10E+00 0.000423 1.98E-10 0.11%
Fe-55 NA NA NA NA NA NA NA NA 4.08E+00 0.000821 4.80E-15 0.00%
Ni-59 NA NA NA NA NA NA NA NA 1.77E+01 0.003571 3.47E-12 0.00%
Co-60 1.87E+03 0.043032 6.17E-09 1.20% 1.69E+02 0.005391 7.73E-10 0.14% 3.95E+01 0.007959 6.22E-10 0.35%
Ni-63 2.60E+03 0.059987 3.36E-10 0.07% 1.09E+03 0.034811 1.95E-10 0.04% 9.07E+02 0.182583 3.77E-10 0.21%
Sr-90 1.99E+01 0.000460 7.24E-09 1.41% 2.90E+00 0.000092 1.45E-09 0.27% 2.57E+00 0.000517 1.23E-09 0.70%
Nb-94 1.82E+01 0.000419 4.18E-11 0.01% 7.91E+00 0.000252 2.52E-11 0.00% 4.73E-01 0.000095 9.68E-12 0.01%
Tc-99 5.79E+00 0.000134 3.00E-10 0.06% 5.32E-01 0.000017 3.80E-11 0.01% 8.41E-01 0.000169 1.81E-10 0.10%
Ag-108m 3.24E+01 0.000747 1.20E-10 0.02% 1.20E+01 0.000382 6.15E-11 0.01% 6.12E-01 0.000123 1.59E-11 0.01%
Sb-125 1.44E+01 0.000333 2.30E-10 0.04% 1.83E+01 0.000583 4.03E-10 0.07% 9.83E-01 0.000198 1.88E-11 0.01%
Cs-134 2.50E+00 0.000058 4.32E-11 0.01% 2.10E+00 0.000067 5.00E-11 0.01% 1.34E-01 0.000027 3.03E-12 0.00%
Cs-137 3.76E+04 0.867560 4.96E-07 96.75% 2.95E+04 0.939943 5.38E-07 99.21% 3.98E+03 0.800607 1.71E-07 97.44%
Pm-147 9.90E+02 0.022832 4.52E-11 0.01% 4.35E+02 0.013835 2.74E-11 0.01% 1.48E+00 0.000299 6.50E-14 0.00%
Eu-152 8.36E+01 0.001930 1.19E-10 0.02% 6.26E+01 0.001994 1.23E-10 0.02% 9.52E-01 0.000192 7.04E-12 0.00%
Eu-154 2.94E+01 0.000678 4.79E-11 0.01% 1.12E+01 0.000356 2.51E-11 0.00% 5.12E-01 0.000103 4.20E-12 0.00%
Eu-155 7.13E+00 0.000165 7.85E-13 0.00% 8.49E+00 0.000270 1.29E-12 0.00% 4.24E-01 0.000085 1.79E-13 0.00%
Np-237 6.93E-02 0.000002 1.19E-09 0.23% 3.12E-02 0.000001 7.39E-10 0.14% 2.30E-02 0.000005 1.64E-09 0.94%
Pu-238 3.97E-01 0.000009 3.28E-11 0.01% 4.66E-02 0.000001 5.31E-12 0.00% 6.69E-02 0.000013 2.05E-11 0.01%
Pu-239/240 2.94E-01 0.000007 2.69E-11 0.01% 4.86E-02 0.000002 6.15E-12 0.00% 5.71E-02 0.000012 2.17E-11 0.01%
Pu-241 4.37E+00 0.000101 1.28E-11 0.00% 2.90E+00 0.000092 1.17E-11 0.00% 1.60E+00 0.000323 1.07E-11 0.01%
Am-241 4.92E+00 0.000114 4.54E-10 0.09% 6.97E-01 0.000022 8.88E-11 0.02% 6.69E-02 0.000013 2.51E-11 0.01%
Am-243 1.05E-01 0.000002 9.69E-12 0.00% 7.91E-02 0.000003 1.01E-11 0.00% 4.99E-02 0.000010 1.92E-11 0.01%
Cm-243/244 8.27E-01 0.000019 1.04E-11 0.00% 1.31E-01 0.000004 2.28E-12 0.00% 3.30E-02 0.000007 1.29E-12 0.00%
IC Percentage 0.5046% IC Percentage 0.2779% IC Percentage 1.2879%
Notes: Average Concentrations decay corrected from sample date of 1/13/2013 to 7/1/2018 (5.5 years)
Half-lifes and Decay Constants from the NRC Radiological Toolbox Version 3.0.0 Page 40 of 65
TSD 14-019 Revision 2 Table 31 - Basement Insignificant Contributor Dose and Dose Percentage for Mixtures Corresponding IC Percentage Core Data IC Dose1 (mrem/yr) (mrem/yr)
Containment Mean Mixture Fraction (Table 19) 0.51% 0.13 using DCGLB (Table 27)
Auxiliary Bldg Mean Mixture Fraction (Table 19) 1.31% 0.33 using DCGLB (Table 27)
Unit 1 Containment Avg. Conc. (Table 30) using 0.51% 0.13 DCGLB (Table 27)
Unit 2 Containment Avg. Conc. (Table 30) using 0.28% 0.07 DCGLB (Table 27)
Auxiliary Bldg Avg. Conc. (Table 30) using 1.29% 0.33 DCGLB (Table 27) 4.2. Calculation of IC Dose from Individual Concrete Core Results Since only a single dose percentage can be calculated with mixtures, the dose was also calculated directly from each of the individual core and soil sample results using the actual reported concentrations as opposed to averages. The resulting dose values for the individual cores were used to evaluate the variability of the actual IC dose (and corresponding dose percentage) calculated using the mixtures. The mean, standard deviation of the mean, 95% Upper Confidence Level (UCL) and range of the IC dose based on individual core and soil sample data were calculated.
The actual total and IC dose, were calculated from the activity in each of the 27 cores individually (11 from Unit 1 Containment, 10 from Unit 2 Containment and 6 from the Auxiliary Building). This calculation inputs and results are provided in Table 31.
The calculations were performed in accordance with the following steps.
- 1. The actual analytical results for each radionuclide in units of pCi/g were listed.
- 2. The activities were decay corrected to the anticipated license termination date of 07/01/18 and then summed to provide a total activity for the sample
- 3. The decay corrected activities were then converted to units of pCi/m2, assuming that the concentration identified in the sample was uniformly distributed to a depth of 1.27 cm in concrete and assuming a density of 2.35 g/cm3.
- 4. The dose for the activity for each radionuclide concentration was derived by dividing by the respective DCGLB from Table 27 and multiplying by 25 mrem/yr.
- 5. The dose was summed to derive total dose for the radioactivity concentration represented by the core sample and the IC dose was summed by subtracting the dose contribution of the dose Page 41 of 65
TSD 14-019 Revision 2 significant ROC (Co-60, Ni-63, Sr-90, Cs-134 and Cs-137 for the Auxiliary Building and H-3, Co-60, Ni-63, Sr-90, Cs-134, Cs-137, Eu-152 and Eu-154 for Containments) from the total dose.
- 6. If the total dose exceeded 25 mrem/yr, then the IC dose was normalized to a total dose of 25 mrem/yr, assuming that remediation would be required for any dose exceeding 25 mrem/yr.
Table 31 provides the dose calculations for all 27 concrete cores. A summary of the results is provided in Table 32.
Page 42 of 65
TSD 14-019 Revision 2 Table 32 - IC Dose for Individual Concrete Core Samples B101102-CJFCCV-002 B101103-CJFCCV-002 B101104-CJFCCV-001 Decay Decay Decay Radionuclide Result Corrected Activity Dose Result Corrected Activity Dose Result Corrected Activity Dose Result Result Result (pCi/g) (pCi/g) (pCi/m2) (mrem/yr) (pCi/g) (pCi/g) (pCi/m2) (mrem/yr) (pCi/g) (pCi/g) (pCi/m2) (mrem/yr)
H-3 1.91E+01 1.40E+01 4.18E+05 0.03960 2.60E+01 1.91E+01 5.69E+05 0.05390 3.75E+01 2.75E+01 8.21E+05 0.07774 C-14 2.50E+00 2.50E+00 7.46E+04 0.07376 3.62E+00 3.62E+00 1.08E+05 0.10681 4.40E+00 4.40E+00 1.31E+05 0.12983 Fe-55 NA NA NA NA NA NA NA NA NA NA NA NA Ni-59 NA NA NA NA NA NA NA NA NA NA NA NA Co-60 8.12E+01 3.94E+01 1.18E+06 0.16848 7.09E+03 3.44E+03 1.03E+08 14.71067 8.69E+01 4.22E+01 1.26E+06 0.18030 Ni-63 1.81E+04 1.74E+04 5.20E+08 2.91181 2.26E+03 2.18E+03 6.49E+07 0.36357 6.29E+03 6.05E+03 1.81E+08 1.01189 Sr-90 4.75E+01 4.16E+01 1.24E+06 19.54316 7.60E+00 6.66E+00 1.99E+05 3.12691 1.63E+02 1.43E+02 4.26E+06 67.06390 Nb-94 8.56E+01 8.56E+01 2.55E+06 0.25506 1.56E+01 1.56E+01 4.65E+05 0.04648 5.13E+01 5.13E+01 1.53E+06 0.15286 Tc-99 2.25E+01 2.25E+01 6.72E+05 1.50758 1.22E+00 1.22E+00 3.64E+04 0.08174 3.46E+01 3.46E+01 1.03E+06 2.31832 Ag-108m 2.39E+02 2.37E+02 7.07E+06 1.13690 1.72E+01 1.70E+01 5.09E+05 0.08182 5.72E+01 5.67E+01 1.69E+06 0.27210 Sb-125 1.92E+02 4.82E+01 1.44E+06 0.99501 5.54E+01 1.39E+01 4.15E+05 0.28710 1.23E+02 3.09E+01 9.22E+05 0.63743 Cs-134 5.47E+01 8.60E+00 2.57E+05 0.19201 1.61E+01 2.53E+00 7.55E+04 0.05651 3.68E+01 5.78E+00 1.73E+05 0.12917 Cs-137 1.45E+05 1.28E+05 3.81E+09 2181.75 9.44E+04 8.32E+04 2.48E+09 1420.40 1.22E+05 1.08E+05 3.21E+09 1835.68 Pm-147 1.49E+04 3.48E+03 1.04E+08 0.20525 1.38E+04 3.22E+03 9.61E+07 0.19009 3.49E+03 8.15E+02 2.43E+07 0.04807 Eu-152 4.52E+02 3.41E+02 1.02E+07 0.62538 7.31E+01 5.51E+01 1.64E+06 0.10114 2.52E+02 1.90E+02 5.67E+06 0.34866 Eu-154 2.26E+02 1.47E+02 4.37E+06 0.30892 3.58E+01 2.32E+01 6.93E+05 0.04893 1.29E+02 8.36E+01 2.50E+06 0.17633 Eu-155 5.39E+01 2.42E+01 7.22E+05 0.00344 2.37E+01 1.06E+01 3.18E+05 0.00151 3.54E+01 1.59E+01 4.74E+05 0.00226 Np-237 9.15E-02 9.15E-02 2.73E+03 2.02949 9.56E-02 9.56E-02 2.85E+03 2.12043 7.24E-02 7.24E-02 2.16E+03 1.60585 Pu-238 1.25E-01 1.20E-01 3.57E+03 0.01278 2.35E-01 2.25E-01 6.72E+03 0.02402 3.05E-01 2.92E-01 8.72E+03 0.03118 Pu-239/240 9.84E-02 9.84E-02 2.94E+03 0.01166 1.11E-01 1.11E-01 3.31E+03 0.01316 1.12E-01 1.12E-01 3.34E+03 0.01328 Pu-241 8.17E+00 6.27E+00 1.87E+05 0.02383 7.08E+00 5.43E+00 1.62E+05 0.02065 8.54E+00 6.55E+00 1.96E+05 0.02491 Am-241 3.58E-01 3.55E-01 1.06E+04 0.04236 1.39E+00 1.38E+00 4.11E+04 0.16446 4.25E-01 4.21E-01 1.26E+04 0.05028 Am-243 8.37E-02 8.37E-02 2.50E+03 0.00999 1.36E-01 1.36E-01 4.06E+03 0.01623 6.05E-03 6.05E-03 1.80E+02 0.00072 Cm-243/244 8.70E-02 7.05E-02 2.10E+03 0.00115 3.34E-01 2.71E-01 8.08E+03 0.00442 1.27E-01 1.03E-01 3.07E+03 0.00168 Total Dose = 2211.85 Total Dose = 1442.02 Total Dose = 1909.96 RATIOS IC Dose = 6.31 RATIOS IC Dose = 3.16 RATIOS IC Dose = 5.29 H-3/Cs-137 0.000110 NORMALIZED DOSE H-3/Cs-137 0.000229 NORMALIZED DOSE H-3/Cs-137 0.000256 NORMALIZED DOSE Ni-63/Co-60 442.317195 Total Dose = 25 Ni-63/Co-60 0.632519 Total Dose = 25 Ni-63/Co-60 143.629003 Total Dose = 25 Sr-90/Cs-137 0.000326 IC Dose = 0.07130 Sr-90/Cs-137 0.000080 IC Dose = 0.05477 Sr-90/Cs-137 0.001328 IC Dose = 0.06923 Notes: Average Concentrations decay corrected from sample date of 1/13/2013 to 7/1/2018 (5.5 years)
Half-lifes and Decay Constants from the NRC Radiological Toolbox Version 3.0.0 Concrete core analysis results from TSD 14-028, Radiological Characterization Report, Tables 16, 17 and 19 Bold indicates result greater than MDC Italized number indicates MDC value used Page 43 of 65
TSD 14-019 Revision 2 Table 32 (continued) - IC Dose for Individual Concrete Core Samples B101105-CJFCCV-001 B101105-CJFCCV-002 B101106-CJFCCV-002 Decay Decay Decay Radionuclide Result Corrected Activity Dose Result Corrected Activity Dose Result Corrected Activity Dose Result Result Result (pCi/g) (pCi/g) (pCi/m2) (mrem/yr) (pCi/g) (pCi/g) (pCi/m2) (mrem/yr) (pCi/g) (pCi/g) (pCi/m2) (mrem/yr)
H-3 2.71E+01 1.99E+01 5.93E+05 0.05618 1.19E+02 8.73E+01 2.61E+06 0.24670 8.11E+01 5.95E+01 1.78E+06 0.16813 C-14 2.46E+01 2.46E+01 7.34E+05 0.72585 2.71E+00 2.71E+00 8.08E+04 0.07996 1.51E+00 1.51E+00 4.50E+04 0.04455 Fe-55 NA NA NA NA NA NA NA NA NA NA NA NA Ni-59 NA NA NA NA NA NA NA NA NA NA NA NA Co-60 3.35E+04 1.63E+04 4.85E+08 69.50741 9.77E+02 4.74E+02 1.41E+07 2.02713 4.36E+01 2.12E+01 6.31E+05 0.09046 Ni-63 2.81E+03 2.70E+03 8.07E+07 0.45205 1.14E+01 1.10E+01 3.28E+05 0.00183 3.02E+01 2.91E+01 8.68E+05 0.00486 Sr-90 1.45E+01 1.27E+01 3.79E+05 5.96581 7.08E+00 6.20E+00 1.85E+05 2.91296 3.97E-01 3.48E-01 1.04E+04 0.16334 Nb-94 2.56E+01 2.56E+01 7.64E+05 0.07628 7.85E+00 7.85E+00 2.34E+05 0.02339 6.01E-01 6.01E-01 1.79E+04 0.00179 Tc-99 9.31E-01 9.31E-01 2.78E+04 0.06238 9.35E-01 9.35E-01 2.79E+04 0.06265 2.96E-01 2.96E-01 8.83E+03 0.01983 Ag-108m 2.05E+01 2.03E+01 6.06E+05 0.09752 9.25E+00 9.17E+00 2.74E+05 0.04400 4.50E-01 4.46E-01 1.33E+04 0.00214 Sb-125 3.88E+01 9.75E+00 2.91E+05 0.20107 4.78E+01 1.20E+01 3.58E+05 0.24772 1.86E+00 4.67E-01 1.39E+04 0.00964 Cs-134 1.53E+01 2.40E+00 7.18E+04 0.05371 9.47E+00 1.49E+00 4.44E+04 0.03324 4.45E-01 6.99E-02 2.09E+03 0.00156 Cs-137 2.72E+03 2.40E+03 7.16E+07 40.92664 4.27E+04 3.76E+04 1.12E+09 642.48805 1.38E+02 1.22E+02 3.63E+06 2.07643 Pm-147 2.75E+02 6.42E+01 1.92E+06 0.00379 5.26E+03 1.23E+03 3.66E+07 0.07246 1.42E+01 3.31E+00 9.89E+04 0.00020 Eu-152 1.25E+02 9.42E+01 2.81E+06 0.17295 2.29E+01 1.73E+01 5.15E+05 0.03168 1.82E+00 1.37E+00 4.10E+04 0.00252 Eu-154 5.16E+01 3.35E+01 9.99E+05 0.07053 1.48E+01 9.60E+00 2.86E+05 0.02023 9.41E-01 6.10E-01 1.82E+04 0.00129 Eu-155 1.70E+01 7.63E+00 2.28E+05 0.00109 1.68E+01 7.54E+00 2.25E+05 0.00107 6.24E-01 2.80E-01 8.36E+03 0.00004 Np-237 9.82E-02 9.82E-02 2.93E+03 2.17810 7.93E-02 7.93E-02 2.37E+03 1.75889 2.40E-02 2.40E-02 7.16E+02 0.53233 Pu-238 3.18E+00 3.04E+00 9.09E+04 0.32507 1.31E-01 1.25E-01 3.74E+03 0.01339 5.39E-02 5.16E-02 1.54E+03 0.00551 Pu-239/240 2.30E+00 2.30E+00 6.86E+04 0.27265 7.62E-02 7.62E-02 2.27E+03 0.00903 5.24E-02 5.24E-02 1.56E+03 0.00621 Pu-241 1.24E+01 9.52E+00 2.84E+05 0.03617 7.86E+00 6.03E+00 1.80E+05 0.02293 5.60E-01 4.30E-01 1.28E+04 0.00163 Am-241 5.15E+01 5.10E+01 1.52E+06 6.09320 2.68E-01 2.66E-01 7.93E+03 0.03171 1.67E-01 1.66E-01 4.94E+03 0.01976 Am-243 5.33E-01 5.33E-01 1.59E+04 0.06361 8.36E-02 8.36E-02 2.49E+03 0.00998 3.80E-02 3.80E-02 1.13E+03 0.00453 Cm-243/244 1.01E+01 8.18E+00 2.44E+05 0.13364 1.43E-01 1.16E-01 3.46E+03 0.00189 4.35E-02 3.52E-02 1.05E+03 0.00058 Total Dose = 127.48 Total Dose = 650.14 Total Dose = 3.15733 RATIOS IC Dose = 10.2704 RATIOS IC Dose = 2.38 RATIOS IC Dose = 0.64874 H-3/Cs-137 0.008291 NORMALIZED DOSE H-3/Cs-137 0.002319 NORMALIZED DOSE H-3/Cs-137 0.489056 Ni-63/Co-60 0.166446 Total Dose = 25 Ni-63/Co-60 0.023154 Total Dose = 25 Ni-63/Co-60 1.374459 Sr-90/Cs-137 0.005298 IC Dose = 2.01419 Sr-90/Cs-137 0.000165 IC Dose = 0.09148 Sr-90/Cs-137 0.002859 Notes: Average Concentrations decay corrected from sample date of 1/13/2013 to 7/1/2018 (5.5 years)
Half-lifes and Decay Constants from the NRC Radiological Toolbox Version 3.0.0 Concrete core analysis results from TSD 14-028, Radiological Characterization Report, Tables 16, 17 and 19 Bold indicates result greater than MDC Italized number indicates MDC value used Page 44 of 65
TSD 14-019 Revision 2 Table 32 (continued) - IC Dose for Individual Concrete Core Samples B101107-CJFCCV-002 B101108-CJFCCV-002 B101109-CJFCCV-001 Decay Decay Decay Radionuclide Result Corrected Activity Dose Result Corrected Activity Dose Result Corrected Activity Dose Result Result Result (pCi/g) (pCi/g) (pCi/m2) (mrem/yr) (pCi/g) (pCi/g) (pCi/m2) (mrem/yr) (pCi/g) (pCi/g) (pCi/m2) (mrem/yr)
H-3 5.05E+01 3.70E+01 1.11E+06 0.10469 7.61E+01 5.58E+01 1.67E+06 0.15777 5.40E+01 3.96E+01 1.18E+06 0.11195 C-14 1.12E+00 1.12E+00 3.34E+04 0.03305 9.52E+00 9.51E+00 2.84E+05 0.28090 1.09E+00 1.09E+00 3.25E+04 0.03216 Fe-55 NA NA NA NA NA NA NA NA NA NA NA NA Ni-59 NA NA NA NA NA NA NA NA NA NA NA NA Co-60 1.50E+01 7.28E+00 2.17E+05 0.03112 8.67E+01 4.21E+01 1.26E+06 0.17989 8.50E+00 4.12E+00 1.23E+05 0.01764 Ni-63 5.48E+00 5.28E+00 1.57E+05 0.00088 2.39E+01 2.30E+01 6.87E+05 0.00384 1.13E+01 1.09E+01 3.25E+05 0.00182 Sr-90 5.67E-01 4.97E-01 1.48E+04 0.23328 8.46E+00 7.41E+00 2.21E+05 3.48074 4.74E-01 4.15E-01 1.24E+04 0.19502 Nb-94 3.03E-01 3.03E-01 9.04E+03 0.00090 9.30E+00 9.30E+00 2.78E+05 0.02771 2.37E-01 2.37E-01 7.07E+03 0.00071 Tc-99 2.60E-01 2.60E-01 7.76E+03 0.01742 1.13E+00 1.13E+00 3.37E+04 0.07571 2.66E-01 2.66E-01 7.94E+03 0.01782 Ag-108m 2.35E-01 2.33E-01 6.95E+03 0.00112 1.19E+01 1.18E+01 3.52E+05 0.05661 2.09E-01 2.07E-01 6.18E+03 0.00099 Sb-125 1.65E+00 4.15E-01 1.24E+04 0.00855 5.62E+01 1.41E+01 4.21E+05 0.29125 2.96E-02 7.44E-03 2.22E+02 0.00015 Cs-134 3.31E-01 5.20E-02 1.55E+03 0.00116 3.92E+01 6.16E+00 1.84E+05 0.13760 3.54E-01 5.56E-02 1.66E+03 0.00124 Cs-137 1.60E+02 1.41E+02 4.21E+06 2.40745 5.91E+04 5.21E+04 1.55E+09 889.25160 1.43E+02 1.26E+02 3.76E+06 2.15166 Pm-147 1.74E+00 4.06E-01 1.21E+04 0.00002 8.49E+03 1.98E+03 5.91E+07 0.11695 2.02E+00 4.71E-01 1.41E+04 0.00003 Eu-152 8.56E-01 6.45E-01 1.93E+04 0.00118 1.95E+01 1.47E+01 4.39E+05 0.02698 1.06E+00 7.99E-01 2.39E+04 0.00147 Eu-154 5.26E-01 3.41E-01 1.02E+04 0.00072 1.76E+01 1.14E+01 3.41E+05 0.02406 5.44E-01 3.53E-01 1.05E+04 0.00074 Eu-155 6.11E-01 2.74E-01 8.19E+03 0.00004 1.89E+01 8.48E+00 2.53E+05 0.00121 6.41E-01 2.88E-01 8.59E+03 0.00004 Np-237 3.62E-02 3.62E-02 1.08E+03 0.80292 1.01E-01 1.01E-01 3.01E+03 2.24020 2.56E-02 2.56E-02 7.64E+02 0.56781 Pu-238 1.03E-01 9.86E-02 2.94E+03 0.01053 1.65E-01 1.58E-01 4.71E+03 0.01687 9.33E-02 8.93E-02 2.67E+03 0.00954 Pu-239/240 1.64E-01 1.64E-01 4.89E+03 0.01944 1.05E-01 1.05E-01 3.13E+03 0.01245 5.88E-02 5.88E-02 1.75E+03 0.00697 Pu-241 4.53E-01 3.48E-01 1.04E+04 0.00132 9.36E+00 7.18E+00 2.14E+05 0.02731 4.79E-01 3.68E-01 1.10E+04 0.00140 Am-241 8.80E-02 8.72E-02 2.60E+03 0.01041 1.01E-01 1.00E-01 2.99E+03 0.01195 5.40E-02 5.35E-02 1.60E+03 0.00639 Am-243 4.49E-02 4.49E-02 1.34E+03 0.00536 7.63E-02 7.63E-02 2.28E+03 0.00911 2.96E-02 2.96E-02 8.83E+02 0.00353 Cm-243/244 4.04E-02 3.27E-02 9.77E+02 0.00053 7.26E-02 5.88E-02 1.76E+03 0.00096 6.46E-02 5.23E-02 1.56E+03 0.00085 Total Dose = 2.92188 Total Dose = 896.43 Total Dose = 3.12994 RATIOS IC Dose = 0.14138 RATIOS IC Dose = 3.17 RATIOS IC Dose = 0.64840 H-3/Cs-137 0.262656 H-3/Cs-137 0.001072 NORMALIZED DOSE H-3/Cs-137 0.314249 Ni-63/Co-60 0.724938 Ni-63/Co-60 0.547003 Total Dose = 25 Ni-63/Co-60 2.637976 Sr-90/Cs-137 0.003522 Sr-90/Cs-137 0.000142 IC Dose = 0.08838 Sr-90/Cs-137 0.003294 Notes: Average Concentrations decay corrected from sample date of 1/13/2013 to 7/1/2018 (5.5 years)
Half-lifes and Decay Constants from the NRC Radiological Toolbox Version 3.0.0 Concrete core analysis results from TSD 14-028, Radiological Characterization Report, Tables 16, 17 and 19 Bold indicates result greater than MDC Italized number indicates MDC value used Page 45 of 65
TSD 14-019 Revision 2 Table 32 (continued) - IC Dose for Individual Concrete Core Samples B101110-CJFCCV-001 B101110-CJFCCV-002 B102102-CJFCCV-001 Decay Decay Decay Radionuclide Result Corrected Activity Dose Result Corrected Activity Dose Result Corrected Activity Dose Result Result Result (pCi/g) (pCi/g) (pCi/m2) (mrem/yr) (pCi/g) (pCi/g) (pCi/m2) (mrem/yr) (pCi/g) (pCi/g) (pCi/m2) (mrem/yr)
H-3 1.33E+02 9.76E+01 2.91E+06 0.27573 2.20E+02 1.61E+02 4.82E+06 0.45609 1.27E+02 9.32E+01 2.78E+06 0.26329 C-14 9.89E-01 9.88E-01 2.95E+04 0.02918 3.30E+00 3.30E+00 9.84E+04 0.09737 2.80E+00 2.80E+00 8.35E+04 0.08262 Fe-55 NA NA NA NA NA NA NA NA NA NA NA NA Ni-59 NA NA NA NA NA NA NA NA NA NA NA NA Co-60 4.45E+01 2.16E+01 6.44E+05 0.09233 3.60E+02 1.75E+02 5.21E+06 0.74695 9.96E+02 4.83E+02 1.44E+07 2.06655 Ni-63 1.40E+02 1.35E+02 4.02E+06 0.02252 2.98E+01 2.87E+01 8.56E+05 0.00479 4.35E+03 4.19E+03 1.25E+08 0.69980 Sr-90 3.16E-01 2.77E-01 8.26E+03 0.13001 6.01E-01 5.26E-01 1.57E+04 0.24727 4.84E+00 4.24E+00 1.27E+05 1.99135 Nb-94 1.47E+00 1.47E+00 4.39E+04 0.00438 1.97E+00 1.97E+00 5.88E+04 0.00587 1.92E+01 1.92E+01 5.73E+05 0.05721 Tc-99 2.63E-01 2.63E-01 7.85E+03 0.01762 1.33E+00 1.33E+00 3.97E+04 0.08911 2.86E-01 2.86E-01 8.54E+03 0.01916 Ag-108m 1.45E+00 1.44E+00 4.29E+04 0.00690 1.91E+00 1.89E+00 5.65E+04 0.00909 6.85E+01 6.79E+01 2.03E+06 0.32585 Sb-125 NA NA NA NA NA NA NA NA 2.39E+02 6.01E+01 1.79E+06 1.23858 Cs-134 6.39E-01 1.00E-01 3.00E+03 0.00224 1.61E+00 2.53E-01 7.55E+03 0.00565 6.09E+01 9.57E+00 2.86E+05 0.21377 Cs-137 8.83E+01 7.78E+01 2.32E+06 1.32861 2.84E+03 2.50E+03 7.47E+07 42.73223 2.14E+05 1.89E+05 5.63E+09 3219.96 Pm-147 1.63E+01 3.80E+00 1.14E+05 0.00022 3.94E+02 9.20E+01 2.74E+06 0.00543 1.23E+04 2.87E+03 8.57E+07 0.16943 Eu-152 1.64E+02 1.24E+02 3.69E+06 0.22691 1.08E+02 8.14E+01 2.43E+06 0.14943 3.98E+01 3.00E+01 8.96E+05 0.05507 Eu-154 1.29E+01 8.36E+00 2.50E+05 0.01763 8.69E+00 5.63E+00 1.68E+05 0.01188 2.70E+01 1.75E+01 5.23E+05 0.03691 Eu-155 3.69E+00 1.66E+00 4.94E+04 0.00024 3.52E+00 1.58E+00 4.72E+04 0.00022 7.97E+01 3.58E+01 1.07E+06 0.00509 Np-237 NA NA NA NA NA NA NA NA 2.74E-02 2.74E-02 8.18E+02 0.60774 Pu-238 5.21E-02 4.99E-02 1.49E+03 0.00533 1.22E-01 1.17E-01 3.49E+03 0.01247 4.15E-02 3.97E-02 1.19E+03 0.00424 Pu-239/240 4.50E-02 4.50E-02 1.34E+03 0.00533 1.09E-01 1.09E-01 3.25E+03 0.01292 4.40E-02 4.40E-02 1.31E+03 0.00522 Pu-241 4.21E-01 3.23E-01 9.64E+03 0.00123 7.28E+00 5.59E+00 1.67E+05 0.02124 3.38E+00 2.59E+00 7.74E+04 0.00986 Am-241 4.36E-02 4.32E-02 1.29E+03 0.00516 2.15E-01 2.13E-01 6.36E+03 0.02544 2.49E-01 2.47E-01 7.37E+03 0.02946 Am-243 3.04E-02 3.04E-02 9.07E+02 0.00363 9.33E-02 9.33E-02 2.78E+03 0.01113 4.86E-02 4.86E-02 1.45E+03 0.00580 Cm-243/244 6.35E-02 5.14E-02 1.54E+03 0.00084 1.56E-01 1.26E-01 3.77E+03 0.00206 9.04E-02 7.32E-02 2.19E+03 0.00120 Total Dose = 2.17604 Total Dose = 44.64664 Total Dose = 3227.85 RATIOS IC Dose = 0.08006 RATIOS IC Dose = 0.29236 RATIOS IC Dose = 2.56 H-3/Cs-137 1.253451 H-3/Cs-137 0.064465 NORMALIZED DOSE H-3/Cs-137 0.000494 NORMALIZED DOSE Ni-63/Co-60 6.242798 Ni-63/Co-60 0.164257 Total Dose = 25 Ni-63/Co-60 8.666449 Total Dose = 25 Sr-90/Cs-137 0.003557 Sr-90/Cs-137 0.000210 IC Dose = 0.16371 Sr-90/Cs-137 0.000022 IC Dose = 0.01984 Notes: Average Concentrations decay corrected from sample date of 1/13/2013 to 7/1/2018 (5.5 years)
Half-lifes and Decay Constants from the NRC Radiological Toolbox Version 3.0.0 Concrete core analysis results from TSD 14-028, Radiological Characterization Report, Tables 16, 17 and 19 Bold indicates result greater than MDC Italized number indicates MDC value used Page 46 of 65
TSD 14-019 Revision 2 Table 32 (continued) - IC Dose for Individual Concrete Core Samples B102103-CJFCCV-001 B102103-CJFCCV-002 B102105-CJFCCV-001 Decay Decay Decay Radionuclide Result Corrected Activity Dose Result Corrected Activity Dose Result Corrected Activity Dose Result Result Result (pCi/g) (pCi/g) (pCi/m2) (mrem/yr) (pCi/g) (pCi/g) (pCi/m2) (mrem/yr) (pCi/g) (pCi/g) (pCi/m2) (mrem/yr)
H-3 7.61E+01 5.58E+01 1.67E+06 0.15777 5.57E+00 4.09E+00 1.22E+05 0.01155 9.18E+00 6.73E+00 2.01E+05 0.01903 C-14 5.80E+00 5.80E+00 1.73E+05 0.17113 1.17E+00 1.17E+00 3.49E+04 0.03452 3.94E+00 3.94E+00 1.18E+05 0.11625 Fe-55 NA NA NA NA NA NA NA NA NA NA NA NA Ni-59 NA NA NA NA NA NA NA NA NA NA NA NA Co-60 6.91E+02 3.35E+02 1.00E+07 1.43372 2.59E+02 1.26E+02 3.75E+06 0.53739 1.09E+03 5.29E+02 1.58E+07 2.26158 Ni-63 1.23E+03 1.18E+03 3.53E+07 0.19787 2.72E+02 2.62E+02 7.81E+06 0.04376 4.85E+03 4.67E+03 1.39E+08 0.78024 Sr-90 1.41E+00 1.24E+00 3.69E+04 0.58012 1.46E+00 1.28E+00 3.82E+04 0.60070 1.76E+01 1.54E+01 4.60E+05 7.24125 Nb-94 1.77E+01 1.77E+01 5.28E+05 0.05274 1.77E+01 1.77E+01 5.28E+05 0.05274 3.50E+00 3.50E+00 1.04E+05 0.01043 Tc-99 2.22E+00 2.22E+00 6.63E+04 0.14875 6.85E-01 6.85E-01 2.04E+04 0.04590 3.97E-01 3.97E-01 1.18E+04 0.02660 Ag-108m 2.29E+01 2.27E+01 6.77E+05 0.10893 1.88E+00 1.86E+00 5.56E+04 0.00894 2.93E+00 2.90E+00 8.67E+04 0.01394 Sb-125 1.00E+02 2.51E+01 7.50E+05 0.51823 1.00E+02 2.51E+01 7.50E+05 0.51823 2.93E+00 7.36E-01 2.20E+04 0.01518 Cs-134 2.10E+01 3.30E+00 9.85E+04 0.07371 8.27E+00 1.30E+00 3.88E+04 0.02903 3.10E+00 4.87E-01 1.45E+04 0.01088 Cs-137 5.58E+04 4.92E+04 1.47E+09 839.60 8.45E+03 7.45E+03 2.22E+08 127.14 2.49E+03 2.19E+03 6.55E+07 37.46593 Pm-147 8.75E+02 2.04E+02 6.09E+06 0.01205 1.08E+03 2.52E+02 7.52E+06 0.01488 3.31E+01 7.72E+00 2.31E+05 0.00046 Eu-152 5.08E+01 3.83E+01 1.14E+06 0.07029 5.08E+01 3.83E+01 1.14E+06 0.07029 9.27E+00 6.99E+00 2.09E+05 0.01283 Eu-154 3.35E+01 2.17E+01 6.48E+05 0.04579 3.35E+01 2.17E+01 6.48E+05 0.04579 5.45E+00 3.53E+00 1.05E+05 0.00745 Eu-155 3.55E+01 1.59E+01 4.76E+05 0.00227 6.12E+00 2.75E+00 8.20E+04 0.00039 4.05E+00 1.82E+00 5.43E+04 0.00026 Np-237 2.85E-02 2.85E-02 8.51E+02 0.63214 2.85E-02 2.85E-02 8.51E+02 0.63214 2.96E-02 2.96E-02 8.83E+02 0.65653 Pu-238 3.99E-02 3.82E-02 1.14E+03 0.00408 2.59E-02 2.48E-02 7.40E+02 0.00265 1.64E-01 1.57E-01 4.69E+03 0.01676 Pu-239/240 5.00E-02 5.00E-02 1.49E+03 0.00593 4.74E-02 4.74E-02 1.41E+03 0.00562 1.54E-01 1.54E-01 4.60E+03 0.01826 Pu-241 4.01E+00 3.08E+00 9.18E+04 0.01170 2.79E+00 2.14E+00 6.39E+04 0.00814 6.17E+00 4.73E+00 1.41E+05 0.01800 Am-241 1.24E-01 1.23E-01 3.67E+03 0.01467 1.27E-01 1.26E-01 3.76E+03 0.01503 6.28E+00 6.22E+00 1.86E+05 0.74302 Am-243 3.28E-02 3.28E-02 9.78E+02 0.00391 3.92E-02 3.92E-02 1.17E+03 0.00468 3.80E-01 3.80E-01 1.13E+04 0.04535 Cm-243/244 4.54E-02 3.68E-02 1.10E+03 0.00060 5.56E-02 4.50E-02 1.34E+03 0.00074 1.19E+00 9.64E-01 2.88E+04 0.01575 Total Dose = 843.84 Total Dose = 129.83 Total Dose = 49.50 RATIOS IC Dose = 1.69 RATIOS IC Dose = 1.34459 RATIOS IC Dose = 1.69679 H-3/Cs-137 0.001135 NORMALIZED DOSE H-3/Cs-137 0.000549 NORMALIZED DOSE H-3/Cs-137 0.003068 NORMALIZED DOSE Ni-63/Co-60 3.532144 Total Dose = 25 Ni-63/Co-60 2.083917 Total Dose = 25 Ni-63/Co-60 8.829305 Total Dose = 25 Sr-90/Cs-137 0.000025 IC Dose = 0.04998 Sr-90/Cs-137 0.000172 IC Dose = 0.25892 Sr-90/Cs-137 0.007025 IC Dose = 0.85703 Notes: Average Concentrations decay corrected from sample date of 1/13/2013 to 7/1/2018 (5.5 years)
Half-lifes and Decay Constants from the NRC Radiological Toolbox Version 3.0.0 Concrete core analysis results from TSD 14-028, Radiological Characterization Report, Tables 16, 17 and 19 Bold indicates result greater than MDC Italized number indicates MDC value used Page 47 of 65
TSD 14-019 Revision 2 Table 32 (continued) - IC Dose for Individual Concrete Core Samples B102105-CJFCCV-002 B102106-CJFCCV-001 B102106-CJFCCV-002 Decay Decay Decay Radionuclide Result Corrected Activity Dose Result Corrected Activity Dose Result Corrected Activity Dose Result Result Result (pCi/g) (pCi/g) (pCi/m2) (mrem/yr) (pCi/g) (pCi/g) (pCi/m2) (mrem/yr) (pCi/g) (pCi/g) (pCi/m2) (mrem/yr)
H-3 2.06E+02 1.51E+02 4.51E+06 0.42706 1.12E+01 8.22E+00 2.45E+05 0.02322 5.19E+01 3.81E+01 1.14E+06 0.10760 C-14 1.23E+00 1.23E+00 3.67E+04 0.03629 2.72E+00 2.72E+00 8.11E+04 0.08026 2.51E+00 2.51E+00 7.49E+04 0.07406 Fe-55 NA NA NA NA NA NA NA NA NA NA NA NA Ni-59 NA NA NA NA NA NA NA NA NA NA NA NA Co-60 1.83E+02 8.88E+01 2.65E+06 0.37970 8.01E+01 3.89E+01 1.16E+06 0.16620 4.35E+01 2.11E+01 6.30E+05 0.09026 Ni-63 1.08E+02 1.04E+02 3.10E+06 0.01737 9.98E+00 9.61E+00 2.87E+05 0.00161 1.07E+02 1.03E+02 3.07E+06 0.01721 Sr-90 8.33E-01 7.30E-01 2.18E+04 0.34273 4.17E-01 3.65E-01 1.09E+04 0.17157 3.79E+00 3.32E+00 9.91E+04 1.55934 Nb-94 5.97E+00 5.97E+00 1.78E+05 0.01779 1.06E+00 1.06E+00 3.16E+04 0.00316 7.04E+00 7.04E+00 2.10E+05 0.02098 Tc-99 2.54E-01 2.54E-01 7.58E+03 0.01702 2.95E-01 2.95E-01 8.80E+03 0.01977 3.96E-01 3.96E-01 1.18E+04 0.02653 Ag-108m 7.03E+00 6.97E+00 2.08E+05 0.03344 8.09E-01 8.02E-01 2.39E+04 0.00385 9.72E+00 9.63E+00 2.87E+05 0.04624 Sb-125 5.56E+01 1.40E+01 4.17E+05 0.28814 6.51E+00 1.64E+00 4.88E+04 0.03374 6.41E+01 1.61E+01 4.81E+05 0.33219 Cs-134 8.75E+00 1.37E+00 4.10E+04 0.03071 1.26E+00 1.98E-01 5.91E+03 0.00442 1.12E+01 1.76E+00 5.25E+04 0.03931 Cs-137 2.09E+04 1.84E+04 5.50E+08 314.47307 1.13E+03 9.96E+02 2.97E+07 17.00261 2.66E+04 2.34E+04 7.00E+08 400.23845 Pm-147 2.62E+03 6.11E+02 1.82E+07 0.03609 1.28E+02 2.99E+01 8.92E+05 0.00176 1.12E+03 2.61E+02 7.80E+06 0.01543 Eu-152 1.22E+01 9.20E+00 2.75E+05 0.01688 3.28E+00 2.47E+00 7.38E+04 0.00454 1.11E+01 8.37E+00 2.50E+05 0.01536 Eu-154 9.97E+00 6.46E+00 1.93E+05 0.01363 1.43E+00 9.27E-01 2.77E+04 0.00195 1.21E+01 7.85E+00 2.34E+05 0.01654 Eu-155 2.00E+01 8.98E+00 2.68E+05 0.00128 2.32E+00 1.04E+00 3.11E+04 0.00015 2.39E+01 1.07E+01 3.20E+05 0.00153 Np-237 3.68E-02 3.68E-02 1.10E+03 0.81623 3.84E-02 3.84E-02 1.15E+03 0.85172 2.90E-02 2.90E-02 8.66E+02 0.64323 Pu-238 4.71E-02 4.51E-02 1.35E+03 0.00481 2.85E-02 2.73E-02 8.14E+02 0.00291 4.43E-02 4.24E-02 1.27E+03 0.00453 Pu-239/240 4.48E-02 4.48E-02 1.34E+03 0.00531 2.86E-02 2.86E-02 8.53E+02 0.00339 4.04E-02 4.04E-02 1.21E+03 0.00479 Pu-241 4.65E+00 3.57E+00 1.06E+05 0.01357 3.45E+00 2.65E+00 7.90E+04 0.01006 4.20E+00 3.22E+00 9.62E+04 0.01225 Am-241 5.08E-02 5.04E-02 1.50E+03 0.00601 4.55E-02 4.51E-02 1.35E+03 0.00538 4.48E-02 4.44E-02 1.33E+03 0.00530 Am-243 3.58E-02 3.58E-02 1.07E+03 0.00427 7.19E-02 7.19E-02 2.14E+03 0.00858 5.63E-02 5.63E-02 1.68E+03 0.00672 Cm-243/244 3.50E-02 2.84E-02 8.46E+02 0.00046 3.98E-02 3.22E-02 9.62E+02 0.00053 4.60E-02 3.73E-02 1.11E+03 0.00061 Total Dose = 316.98 Total Dose = 18.40 Total Dose = 403.28 RATIOS IC Dose = 1.28 RATIOS IC Dose = 1.02526 RATIOS IC Dose = 1.19 H-3/Cs-137 0.008202 NORMALIZED DOSE H-3/Cs-137 0.008248 H-3/Cs-137 0.001624 NORMALIZED DOSE Ni-63/Co-60 1.171073 Total Dose = 25 Ni-63/Co-60 0.247235 Ni-63/Co-60 4.880966 Total Dose = 25 Sr-90/Cs-137 0.000040 IC Dose = 0.10101 Sr-90/Cs-137 0.000367 Sr-90/Cs-137 0.000142 IC Dose = 0.07404 Notes: Average Concentrations decay corrected from sample date of 1/13/2013 to 7/1/2018 (5.5 years)
Half-lifes and Decay Constants from the NRC Radiological Toolbox Version 3.0.0 Concrete core analysis results from TSD 14-028, Radiological Characterization Report, Tables 16, 17 and 19 Bold indicates result greater than MDC Italized number indicates MDC value used Page 48 of 65
TSD 14-019 Revision 2 Table 32 (continued) - IC Dose for Individual Concrete Core Samples B102107-CJFCCV-001 B102110-CJFCCV-001 B102110-CJFCCV-002 Decay Decay Decay Radionuclide Result Corrected Activity Dose Result Corrected Activity Dose Result Corrected Activity Dose Result Result Result (pCi/g) (pCi/g) (pCi/m2) (mrem/yr) (pCi/g) (pCi/g) (pCi/m2) (mrem/yr) (pCi/g) (pCi/g) (pCi/m2) (mrem/yr)
H-3 7.26E+00 5.33E+00 1.59E+05 0.01505 2.41E+02 1.77E+02 5.28E+06 0.49962 3.29E+01 2.41E+01 7.20E+05 0.06821 C-14 4.44E+00 4.44E+00 1.32E+05 0.13101 9.72E-01 9.71E-01 2.90E+04 0.02868 1.84E+00 1.84E+00 5.49E+04 0.05429 Fe-55 NA NA NA NA NA NA NA NA NA NA NA NA Ni-59 NA NA NA NA NA NA NA NA NA NA NA NA Co-60 7.57E+01 3.67E+01 1.10E+06 0.15707 4.95E+01 2.40E+01 7.17E+05 0.10270 2.27E+01 1.10E+01 3.29E+05 0.04710 Ni-63 3.11E+02 2.99E+02 8.93E+06 0.05003 7.31E+01 7.04E+01 2.10E+06 0.01176 4.73E+01 4.55E+01 1.36E+06 0.00761 Sr-90 2.08E+00 1.82E+00 5.44E+04 0.85578 3.71E-01 3.25E-01 9.70E+03 0.15264 3.35E-01 2.93E-01 8.76E+03 0.13783 Nb-94 1.25E+00 1.25E+00 3.73E+04 0.00372 3.22E+00 3.22E+00 9.61E+04 0.00959 2.48E+00 2.48E+00 7.40E+04 0.00739 Tc-99 2.80E-01 2.80E-01 8.36E+03 0.01876 2.60E-01 2.60E-01 7.76E+03 0.01742 2.50E-01 2.50E-01 7.46E+03 0.01675 Ag-108m 1.08E+00 1.07E+00 3.19E+04 0.00514 4.17E+00 4.13E+00 1.23E+05 0.01984 2.08E+00 2.06E+00 6.15E+04 0.00989 Sb-125 1.52E+01 3.82E+00 1.14E+05 0.07877 NA NA NA NA NA NA NA NA Cs-134 1.68E+01 2.64E+00 7.88E+04 0.05897 1.30E+00 2.04E-01 6.10E+03 0.00456 8.19E-01 1.29E-01 3.84E+03 0.00287 Cs-137 4.51E+03 3.98E+03 1.19E+08 67.85998 1.05E+03 9.25E+02 2.76E+07 15.79889 1.56E+01 1.37E+01 4.10E+05 0.23473 Pm-147 3.88E+02 9.06E+01 2.70E+06 0.00534 4.78E+01 1.12E+01 3.33E+05 0.00066 2.79E+01 6.51E+00 1.94E+05 0.00038 Eu-152 3.58E+00 2.70E+00 8.06E+04 0.00495 3.97E+02 2.99E+02 8.93E+06 0.54928 2.53E+02 1.91E+02 5.69E+06 0.35005 Eu-154 1.75E+00 1.13E+00 3.39E+04 0.00239 2.58E+01 1.67E+01 4.99E+05 0.03527 2.17E+01 1.41E+01 4.20E+05 0.02966 Eu-155 4.58E+00 2.06E+00 6.14E+04 0.00029 7.02E+00 3.15E+00 9.41E+04 0.00045 5.98E+00 2.68E+00 8.01E+04 0.00038 Np-237 3.17E-02 3.17E-02 9.46E+02 0.70311 NA NA NA NA NA NA NA NA Pu-238 3.67E-02 3.51E-02 1.05E+03 0.00375 3.18E-02 3.04E-02 9.09E+02 0.00325 2.71E-02 2.59E-02 7.74E+02 0.00277 Pu-239/240 2.56E-02 2.56E-02 7.64E+02 0.00303 2.78E-02 2.78E-02 8.30E+02 0.00330 2.36E-02 2.36E-02 7.04E+02 0.00280 Pu-241 3.09E+00 2.37E+00 7.08E+04 0.00901 3.30E+00 2.53E+00 7.56E+04 0.00963 2.70E+00 2.07E+00 6.18E+04 0.00788 Am-241 4.25E-02 4.21E-02 1.26E+03 0.00503 4.95E-02 4.91E-02 1.46E+03 0.00586 1.94E-02 1.92E-02 5.74E+02 0.00230 Am-243 3.94E-02 3.94E-02 1.18E+03 0.00470 5.18E-02 5.18E-02 1.55E+03 0.00618 3.61E-02 3.61E-02 1.08E+03 0.00431 Cm-243/244 3.66E-02 2.96E-02 8.85E+02 0.00048 4.96E-02 4.02E-02 1.20E+03 0.00066 2.86E-02 2.32E-02 6.91E+02 0.00038 Total Dose = 69.98 Total Dose = 17.26 Total Dose = 0.99 RATIOS IC Dose = 0.97217 RATIOS IC Dose = 0.10551 RATIOS IC Dose = 0.10952 H-3/Cs-137 0.001340 NORMALIZED DOSE H-3/Cs-137 0.191005 H-3/Cs-137 1.755043 Ni-63/Co-60 8.152218 Total Dose = 25 Ni-63/Co-60 2.930377 Ni-63/Co-60 4.134724 Sr-90/Cs-137 0.000458 IC Dose = 0.34732 Sr-90/Cs-137 0.000351 Sr-90/Cs-137 0.021343 Notes: Average Concentrations decay corrected from sample date of 1/13/2013 to 7/1/2018 (5.5 years)
Half-lifes and Decay Constants from the NRC Radiological Toolbox Version 3.0.0 Concrete core analysis results from TSD 14-028, Radiological Characterization Report, Tables 16, 17 and 19 Bold indicates result greater than MDC Italized number indicates MDC value used Page 49 of 65
TSD 14-019 Revision 2 Table 32 (continued) - IC Dose for Individual Concrete Core Samples B105101- CJFCCV-001 B105103- CJFCCV-001 B105105- CJFCCV-001 Decay Decay Decay Radionuclide Result Corrected Activity Dose Result Corrected Activity Dose Result Corrected Activity Dose Result Result Result (pCi/g) (pCi/g) (pCi/m2) (mrem/yr) (pCi/g) (pCi/g) (pCi/m2) (mrem/yr) (pCi/g) (pCi/g) (pCi/m2) (mrem/yr)
H-3 1.12E+01 8.22E+00 2.45E+05 0.01099 1.68E+01 1.23E+01 3.68E+05 0.01649 6.98E+00 5.12E+00 1.53E+05 0.00685 C-14 9.56E-01 9.55E-01 2.85E+04 0.01337 4.88E+00 4.88E+00 1.46E+05 0.06823 9.98E-01 9.97E-01 2.98E+04 0.01395 Fe-55 1.20E+01 2.98E+00 8.91E+04 0.04176 3.16E+01 7.86E+00 2.35E+05 0.10996 1.81E+01 4.50E+00 1.34E+05 0.06298 Ni-59 1.59E+01 1.59E+01 4.75E+05 0.22243 2.08E+01 2.08E+01 6.21E+05 0.29098 1.81E+01 1.81E+01 5.40E+05 0.25321 Co-60 2.62E+01 1.27E+01 3.79E+05 0.02966 2.28E+02 1.11E+02 3.30E+06 0.25808 3.20E+00 1.55E+00 4.63E+04 0.00362 Ni-63 1.52E+02 1.46E+02 4.37E+06 0.00902 3.38E+03 3.25E+03 9.71E+07 0.20056 2.91E+02 2.80E+02 8.36E+06 0.01727 Sr-90 1.07E+00 9.37E-01 2.80E+04 0.06657 5.44E+00 4.77E+00 1.42E+05 0.33844 1.52E+00 1.33E+00 3.97E+04 0.09456 Nb-94 2.29E-01 2.29E-01 6.83E+03 0.00069 8.17E-01 8.17E-01 2.44E+04 0.00248 6.19E-01 6.19E-01 1.85E+04 0.00188 Tc-99 1.45E+00 1.45E+00 4.33E+04 0.04625 9.61E-01 9.61E-01 2.87E+04 0.03066 6.70E-01 6.70E-01 2.00E+04 0.02137 Ag-108m 2.06E-01 2.04E-01 6.09E+03 0.00078 1.66E+00 1.64E+00 4.91E+04 0.00632 8.06E-01 7.99E-01 2.38E+04 0.00307 Sb-125 2.27E+00 5.70E-01 1.70E+04 0.00162 7.79E+00 1.96E+00 5.84E+04 0.00556 4.39E+00 1.10E+00 3.29E+04 0.00313 Cs-134 4.53E-01 7.12E-02 2.12E+03 0.00024 1.47E+00 2.31E-01 6.89E+03 0.00077 8.63E-01 1.36E-01 4.05E+03 0.00045 Cs-137 1.35E+03 1.19E+03 3.55E+07 7.59394 1.33E+04 1.17E+04 3.50E+08 74.81438 5.29E+03 4.66E+03 1.39E+08 29.75700 Pm-147 1.43E+01 3.34E+00 9.96E+04 0.00002 8.17E-01 1.91E-01 5.69E+03 0.00000 9.63E-01 2.25E-01 6.71E+03 0.00000 Eu-152 7.57E-01 5.71E-01 1.70E+04 0.00063 2.58E+00 1.95E+00 5.81E+04 0.00213 1.05E+00 7.92E-01 2.36E+04 0.00087 Eu-154 4.00E-01 2.59E-01 7.74E+03 0.00032 1.38E+00 8.95E-01 2.67E+04 0.00109 1.19E+00 7.72E-01 2.30E+04 0.00094 Eu-155 5.76E-01 2.59E-01 7.72E+03 0.00002 1.76E+00 7.90E-01 2.36E+04 0.00005 1.16E+00 5.21E-01 1.55E+04 0.00003 Np-237 2.04E-02 2.04E-02 6.09E+02 0.21628 2.13E-02 2.13E-02 6.36E+02 0.22583 2.39E-02 2.39E-02 7.13E+02 0.25339 Pu-238 1.77E-02 1.69E-02 5.06E+02 0.00077 3.43E-01 3.28E-01 9.80E+03 0.01492 1.32E-02 1.26E-02 3.77E+02 0.00057 Pu-239/240 1.77E-02 1.77E-02 5.28E+02 0.00100 2.74E-01 2.74E-01 8.18E+03 0.01543 1.06E-02 1.06E-02 3.16E+02 0.00060 Pu-241 2.48E+00 1.90E+00 5.68E+04 0.00188 2.46E+00 1.89E+00 5.63E+04 0.00186 1.79E+00 1.37E+00 4.10E+04 0.00136 Am-241 3.03E-02 3.00E-02 8.96E+02 0.00167 2.29E-01 2.27E-01 6.77E+03 0.01262 4.38E-02 4.34E-02 1.30E+03 0.00241 Am-243 2.89E-02 2.89E-02 8.62E+02 0.00165 1.09E-01 1.09E-01 3.25E+03 0.00621 6.01E-02 6.01E-02 1.79E+03 0.00342 Cm-243/244 3.91E-02 3.17E-02 9.45E+02 0.00018 4.41E-02 3.57E-02 1.07E+03 0.00021 3.95E-02 3.20E-02 9.55E+02 0.00019 Total Dose = 8.26 Total Dose = 76.42 Total Dose = 30.50 RATIOS IC Dose = 0.56231 RATIOS IC Dose = 0.81102 RATIOS IC Dose = 0.63023 H-3/Cs-137 0.006904 H-3/Cs-137 0.001051 NORMALIZED DOSE H-3/Cs-137 0.001098 NORMALIZED DOSE Ni-63/Co-60 11.512074 Ni-63/Co-60 29.416644 Total Dose = 25 Ni-63/Co-60 180.448920 Total Dose = 25 Sr-90/Cs-137 0.000788 Sr-90/Cs-137 0.000407 IC Dose = 0.26531 Sr-90/Cs-137 0.000286 IC Dose = 0.51653 Notes: Average Concentrations decay corrected from sample date of 1/13/2013 to 7/1/2018 (5.5 years)
Half-lifes and Decay Constants from the NRC Radiological Toolbox Version 3.0.0 Concrete core analysis results from TSD 14-028, Radiological Characterization Report, Tables 16, 17 and 19 Bold indicates result greater than MDC Italized number indicates MDC value used Page 50 of 65
TSD 14-019 Revision 2 Table 32 (continued) - IC Dose for Individual Concrete Core Samples B105106- CJFCCV-002 B105108- CJFCCV-003 B105113-CJWCCV-003 Decay Decay Decay Radionuclide Result Corrected Activity Dose Result Corrected Activity Dose Result Corrected Activity Dose Result Result Result (pCi/g) (pCi/g) (pCi/m2) (mrem/yr) (pCi/g) (pCi/g) (pCi/m2) (mrem/yr) (pCi/g) (pCi/g) (pCi/m2) (mrem/yr)
H-3 2.96E+01 2.17E+01 6.48E+05 0.02906 5.61E+00 4.11E+00 1.23E+05 0.00551 4.71E+00 3.45E+00 1.03E+05 0.00462 C-14 1.48E+00 1.48E+00 4.41E+04 0.02069 1.19E+00 1.19E+00 3.55E+04 0.01664 3.10E+00 3.10E+00 9.25E+04 0.04334 Fe-55 1.12E+01 2.79E+00 8.31E+04 0.03897 8.17E+00 2.03E+00 6.07E+04 0.02843 1.73E+01 4.30E+00 1.28E+05 0.06020 Ni-59 1.74E+01 1.74E+01 5.19E+05 0.24342 1.67E+01 1.67E+01 4.98E+05 0.23362 1.75E+01 1.75E+01 5.22E+05 0.24481 Co-60 1.01E+01 4.90E+00 1.46E+05 0.01143 1.83E+01 8.88E+00 2.65E+05 0.02071 2.03E+02 9.85E+01 2.94E+06 0.22978 Ni-63 9.18E+01 8.84E+01 2.64E+06 0.00545 8.59E+01 8.27E+01 2.47E+06 0.00510 1.65E+03 1.59E+03 4.74E+07 0.09791 Sr-90 4.04E-01 3.54E-01 1.06E+04 0.02513 3.29E-01 2.88E-01 8.60E+03 0.02047 8.82E+00 7.73E+00 2.31E+05 0.54872 Nb-94 2.13E-01 2.13E-01 6.36E+03 0.00065 3.02E-01 3.02E-01 9.01E+03 0.00092 6.57E-01 6.57E-01 1.96E+04 0.00199 Tc-99 4.73E-01 4.73E-01 1.41E+04 0.01509 9.09E-01 9.09E-01 2.71E+04 0.02900 5.81E-01 5.81E-01 1.73E+04 0.01853 Ag-108m 2.53E-01 2.51E-01 7.48E+03 0.00096 1.82E-01 1.80E-01 5.38E+03 0.00069 5.96E-01 5.91E-01 1.76E+04 0.00227 Sb-125 2.46E+00 6.18E-01 1.84E+04 0.00176 1.99E+00 5.00E-01 1.49E+04 0.00142 4.57E+00 1.15E+00 3.43E+04 0.00326 Cs-134 8.11E-01 1.27E-01 3.80E+03 0.00043 2.90E-01 4.56E-02 1.36E+03 0.00015 1.23E+00 1.93E-01 5.77E+03 0.00065 Cs-137 1.88E+03 1.66E+03 4.95E+07 10.57527 1.05E+03 9.25E+02 2.76E+07 5.90640 4.19E+03 3.69E+03 1.10E+08 23.56934 Pm-147 5.30E+00 1.24E+00 3.69E+04 0.00001 9.57E+00 2.23E+00 6.67E+04 0.00001 7.19E+00 1.68E+00 5.01E+04 0.00001 Eu-152 6.75E-01 5.09E-01 1.52E+04 0.00056 7.10E-01 5.35E-01 1.60E+04 0.00059 1.80E+00 1.36E+00 4.05E+04 0.00149 Eu-154 3.95E-01 2.56E-01 7.64E+03 0.00031 3.21E-01 2.08E-01 6.21E+03 0.00025 1.05E+00 6.81E-01 2.03E+04 0.00083 Eu-155 6.33E-01 2.84E-01 8.48E+03 0.00002 4.84E-01 2.17E-01 6.48E+03 0.00001 1.05E+00 4.71E-01 1.41E+04 0.00003 Np-237 2.10E-02 2.10E-02 6.27E+02 0.22265 1.92E-02 1.92E-02 5.73E+02 0.20356 3.20E-02 3.20E-02 9.55E+02 0.33927 Pu-238 1.37E-02 1.31E-02 3.91E+02 0.00060 1.78E-02 1.70E-02 5.09E+02 0.00077 1.39E-02 1.33E-02 3.97E+02 0.00060 Pu-239/240 1.37E-02 1.37E-02 4.09E+02 0.00077 1.33E-02 1.33E-02 3.97E+02 0.00075 1.35E-02 1.35E-02 4.03E+02 0.00076 Pu-241 2.36E+00 1.81E+00 5.41E+04 0.00179 1.73E+00 1.33E+00 3.96E+04 0.00131 1.72E+00 1.32E+00 3.94E+04 0.00130 Am-241 2.72E-02 2.70E-02 8.05E+02 0.00150 4.29E-02 4.25E-02 1.27E+03 0.00236 3.17E-02 3.14E-02 9.38E+02 0.00175 Am-243 3.62E-02 3.62E-02 1.08E+03 0.00206 3.36E-02 3.36E-02 1.00E+03 0.00191 3.18E-02 3.18E-02 9.49E+02 0.00181 Cm-243/244 3.89E-02 3.15E-02 9.40E+02 0.00018 4.02E-02 3.26E-02 9.72E+02 0.00019 4.29E-02 3.48E-02 1.04E+03 0.00020 Total Dose = 11.20 Total Dose = 6.48 Total Dose = 25.17 RATIOS IC Dose = 0.58103 RATIOS IC Dose = 0.52795 RATIOS IC Dose = 0.72709 H-3/Cs-137 0.013102 H-3/Cs-137 0.004446 H-3/Cs-137 0.000935 NORMALIZED DOSE Ni-63/Co-60 18.035683 Ni-63/Co-60 9.314367 Ni-63/Co-60 16.128693 Total Dose = 25 Sr-90/Cs-137 0.000214 Sr-90/Cs-137 0.000311 Sr-90/Cs-137 0.002092 IC Dose = 0.72208 Notes: Average Concentrations decay corrected from sample date of 1/13/2013 to 7/1/2018 (5.5 years)
Half-lifes and Decay Constants from the NRC Radiological Toolbox Version 3.0.0 Concrete core analysis results from TSD 14-028, Radiological Characterization Report, Tables 16, 17 and 19 Bold indicates result greater than MDC Italized number indicates MDC value used Page 51 of 65
TSD 14-019 Revision 2 Table 33 - Basement Insignificant Contributor Dose and Dose Percentage for Individual Core Samples Mean IC IC Dose IC Dose Total Dose Core Data Dose 95% UCL (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr)
Unit 1 Containment Individual Cores 0.06 to 2.01 0.37 0.66 2.18 to 2,212 (Table 30) using DCGLB (Table 27) (0.22% to 8.06%)
Unit 2 Containment Individual Cores 0.02 to 1.03 0.30 0.48 0.99 to 3,228 (Table 30) using DCGLB (Table 27) (0.08% to 4.10%)
Auxiliary Bldg Individual Cores 0.27 to 0.73 0.53 0.63 6.48 to 76.42 (Table 30) using DCGLB (Table 27) (1.06% to 2.91%)
4.3. Calculation of IC Dose Percentage and IC Dose Using Drilling Spoils Basement Scenario DCGLs The same process for determining dose percentage and dose values in Tables 29, 30 and 32 using the DCGLB were also calculated using the DCGLBS for the Containment and Auxiliary Building basements. The Drilling Spoils Basement Scenario DCGLs were calculated in TSD 14-101 and are reproduced in Table 34. Note that in all calculations, use of the DCGLBS does not change any activity, decay corrected activity or converted activity from Tables 29, 30 and 32. These values remain constant. Only the total dose and IC dose are changed by using the DCGLBS. The results are provided in Table 35. Results summaries are provided in Tables 36 and 37.
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TSD 14-019 Revision 2 Table 34 - Drilling Spoils DCGLs for Concrete Structures CTMT Auxiliary Bldg Radionuclide (pCi/m2) (pCi/m2)
H-3 4.93E+15 2.38E+15 C-14 1.68E+13 1.12E+13 Fe-55 1.71E+15 1.16E+15 Ni-59 3.51E+14 2.28E+14 Co-60 2.42E+08 3.23E+08 Ni-63 1.28E+14 1.07E+14 Sr-90 5.14E+10 5.53E+10 Nb-94 3.62E+08 2.87E+08 Tc-99 4.93E+15 2.38E+15 Ag-108m 3.49E+08 2.80E+08 Sb-125 1.59E+09 1.26E+09 Cs-134 4.18E+08 5.50E+08 Cs-137 9.86E+08 1.07E+09 Pm-147 4.26E+13 3.71E+13 Eu-152 5.21E+08 6.89E+08 Eu-154 4.90E+08 6.22E+08 Eu-155 1.45E+10 1.22E+10 Np-237 1.77E+09 1.19E+09 Pu-238 6.90E+10 8.72E+10 Pu-239/240 6.26E+10 7.85E+10 Pu-241 1.19E+12 1.16E+12 Am-241 2.28E+10 2.29E+10 Am-243 2.62E+09 2.19E+09 Cm-243/244 4.21E+09 3.49E+09 Page 53 of 65
TSD 14-019 Revision 2 Table 35 - IC Dose Percentage When Using DCGLBS CTMT Aux Bldg U1 CTMT U2 CTMT Aux Bldg Radionuclide Table 19 Mixture Table 19 Mixture Avg Conc Avg Conc Avg Conc Dose Percentage Dose Percentage Dose Percentage Dose Percentage Dose Percentage H-3 0.00% 0.00% 0.00% 0.00% 0.00%
C-14 0.00% 0.00% 0.00% 0.00% 0.00%
Fe-55 0.00% 0.00% NA NA 0.00%
Ni-59 0.00% 0.00% NA NA 0.00%
Co-60 21.46% 3.88% 16.70% 2.27% 3.20%
Ni-63 0.00% 0.00% 0.00% 0.00% 0.00%
Sr-90 0.00% 0.00% 0.00% 0.00% 0.00%
Nb-94 0.55% 0.06% 0.11% 0.07% 0.04%
Tc-99 0.00% 0.00% 0.00% 0.00% 0.00%
Ag-108m 0.90% 0.08% 0.20% 0.11% 0.06%
Sb-125 0.02% 0.02% 0.02% 0.04% 0.02%
Cs-134 0.02% 0.03% 0.01% 0.02% 0.01%
Cs-137 76.00% 95.86% 82.48% 97.03% 96.61%
Pm-147 NA NA 0.00% 0.00% 0.00%
Eu-152 0.93% 0.04% 0.35% 0.39% 0.04%
Eu-154 0.13% 0.02% 0.13% 0.07% 0.02%
Eu-155 0.00% 0.00% 0.00% 0.00% 0.00%
Np-237 0.00% 0.00% 0.00% 0.00% 0.00%
Pu-238 0.00% 0.00% 0.00% 0.00% 0.00%
Pu-239/240 0.00% 0.00% 0.00% 0.00% 0.00%
Pu-241 0.00% 0.00% 0.00% 0.00% 0.00%
Am-241 0.00% 0.00% 0.00% 0.00% 0.00%
Am-243 0.00% 0.00% 0.00% 0.00% 0.00%
Cm-243/244 0.00% 0.00% 0.00% 0.00% 0.00%
IC Percentage 1.4605% 0.2234% 0.3309% 0.2219% 0.1804%
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TSD 14-019 Revision 2 Table 35 (continued) - IC Dose When Using DCGLBS Individual Concrete Cores B101102- B101103- B101104- B101105- B101105- B101106- B101107- B101108- B101109- B101110- B101110- B102102- B102103- B102103- B102105-CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV-Radionuclide 002 002 001 001 002 002 002 002 001 001 002 001 001 002 001 Dose Dose Dose Dose Dose Dose Dose Dose Dose Dose Dose Dose Dose Dose Dose (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr)
H-3 2.12E-09 2.88E-09 4.16E-09 3.01E-09 1.32E-08 9.00E-09 5.60E-09 8.44E-09 5.99E-09 1.48E-08 2.44E-08 1.41E-08 8.44E-09 6.18E-10 1.02E-09 C-14 1.11E-07 1.61E-07 1.95E-07 1.09E-06 1.20E-07 6.71E-08 4.98E-08 4.23E-07 4.84E-08 4.39E-08 1.47E-07 1.24E-07 2.58E-07 5.20E-08 1.75E-07 Fe-55 NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA Ni-59 NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA Co-60 0.12160 10.61761 0.13014 50.16783 1.46310 0.06529 0.02246 0.12984 0.01273 0.06664 0.53912 1.49156 1.03481 0.38786 1.63233 Ni-63 0.00010 0.00001 0.00004 0.00002 6.40E-08 1.70E-07 3.08E-08 1.34E-07 6.35E-08 7.86E-07 1.67E-07 0.00002 0.00001 1.53E-06 0.00003 Sr-90 0.00060 0.00010 0.00207 0.00018 0.00009 0.00001 0.00001 0.00011 0.00001 4.02E-06 0.00001 0.00006 0.00002 0.00002 0.00022 Nb-94 0.17638 0.03214 0.10570 0.05275 0.01617 0.00124 0.00062 0.01916 0.00049 0.00303 0.00406 0.03956 0.03647 0.03647 0.00721 Tc-99 3.40E-09 1.85E-10 5.23E-09 1.41E-10 1.41E-10 4.48E-11 3.93E-11 1.71E-10 4.02E-11 3.98E-11 2.01E-10 4.33E-11 3.36E-10 1.04E-10 6.00E-11 Ag-108m 0.50569 0.03639 0.12103 0.04338 0.01957 0.00095 0.00050 0.02518 0.00044 0.00307 0.00404 0.14494 0.04845 0.00398 0.00620 Sb-125 0.02270 0.00655 0.01454 0.00459 0.00565 0.00022 0.00020 0.00664 3.50E-06 NA NA 0.02825 0.01182 0.01182 0.00035 Cs-134 0.01535 0.00452 0.01032 0.00429 0.00266 0.00012 0.00009 0.01100 0.00010 0.00018 0.00045 0.01709 0.00589 0.00232 0.00087 Cs-137 96.66618 62.93302 81.33292 1.81332 28.46652 0.09200 0.10667 39.39980 0.09533 0.05887 1.89332 142.66595 37.19981 5.63330 1.65999 Pm-147 0.00006 0.00006 0.00001 1.12E-06 0.00002 5.81E-08 7.11E-09 0.00003 8.26E-09 6.67E-08 1.61E-06 0.00005 3.58E-06 4.42E-06 1.35E-07 Eu-152 0.48824 0.07896 0.27220 0.13502 0.02474 0.00197 0.00092 0.02106 0.00114 0.17715 0.11666 0.04299 0.05487 0.05487 0.01001 Eu-154 0.22325 0.03537 0.12743 0.05097 0.01462 0.00093 0.00052 0.01739 0.00054 0.01274 0.00858 0.02667 0.03309 0.03309 0.00538 Eu-155 0.00125 0.00055 0.00082 0.00039 0.00039 0.00001 0.00001 0.00044 0.00001 0.00009 0.00008 0.00184 0.00082 0.00014 0.00009 Np-237 0.00004 0.00004 0.00003 0.00004 0.00003 0.00001 0.00002 0.00004 0.00001 NA NA 0.00001 0.00001 0.00001 0.00001 Pu-238 1.29E-06 2.43E-06 3.16E-06 0.00003 1.36E-06 5.58E-07 1.07E-06 1.71E-06 9.66E-07 5.39E-07 1.26E-06 4.30E-07 4.13E-07 2.68E-07 1.70E-06 Pu-239/240 1.17E-06 1.32E-06 1.33E-06 0.00003 9.08E-07 6.25E-07 1.95E-06 1.25E-06 7.01E-07 5.36E-07 1.30E-06 5.24E-07 5.96E-07 5.65E-07 1.84E-06 Pu-241 3.93E-06 3.41E-06 4.11E-06 0.00001 3.79E-06 2.70E-07 2.18E-07 4.51E-06 2.31E-07 2.03E-07 3.51E-06 1.63E-06 1.93E-06 1.34E-06 2.97E-06 Am-241 0.00001 0.00005 0.00001 0.00167 0.00001 0.00001 2.85E-06 3.27E-06 1.75E-06 1.41E-06 0.00001 0.00001 4.02E-06 4.12E-06 0.00020 Am-243 0.00002 0.00004 0.00000 0.00015 0.00002 0.00001 0.00001 0.00002 0.00001 0.00001 0.00003 0.00001 0.00001 0.00001 0.00011 Cm-243/244 0.00001 0.00005 0.00002 0.00145 0.00002 0.00001 0.00001 0.00001 0.00001 0.00001 0.00002 0.00001 0.00001 0.00001 0.00017 Total Dose 98.22 73.75 82.12 52.28 30.01 0.16278 0.13204 39.63 0.11083 0.32179 2.56639 144.46 38.43 6.16 3.32 IC Dose 0.71 0.08 0.24 0.15 0.04 0.00246 0.00137 0.05 0.00098 0.00620 0.00825 0.21 0.10 0.05245 0.01435 NORMALIZED Total Dose 25 25 25 25 25 25 25 25 IC Dose 0.17974 0.02572 0.07373 0.04997 0.03490 0.03251 0.03715 0.06350 Page 55 of 65
TSD 14-019 Revision 2 Table 35 (continued) - IC Dose When Using DCGLBS Individual Concrete Cores B102105- B102106- B102106- B102107- B102110- B102110- B105101- B105103- B105105- B105106- B105108- B105113-CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJWCCV-Radionuclide 002 001 002 001 001 002 001 001 001 002 003 003 Dose Dose Dose Dose Dose Dose Dose Dose Dose Dose Dose Dose (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr)
H-3 2.29E-08 1.24E-09 5.76E-09 8.05E-10 2.67E-08 3.65E-09 2.58E-09 3.86E-09 1.60E-09 6.81E-09 1.29E-09 1.08E-09 C-14 5.46E-08 1.21E-07 1.12E-07 1.97E-07 4.32E-08 8.18E-08 6.35E-08 3.24E-07 6.63E-08 9.83E-08 7.90E-08 2.06E-07 Fe-55 NA NA NA NA NA NA 1.98E-07 5.22E-07 2.99E-07 1.85E-07 1.35E-07 2.86E-07 Ni-59 NA NA NA NA NA NA 1.06E-06 1.38E-06 1.20E-06 1.16E-06 1.11E-06 1.16E-06 Co-60 0.27405 0.11995 0.06514 0.11336 0.07413 0.03399 0.02938 0.25569 0.00359 0.01133 0.02052 0.22765 Ni-63 6.06E-07 5.60E-08 6.01E-07 1.75E-06 4.10E-07 2.66E-07 1.02E-06 0.00002 1.95E-06 6.16E-07 5.77E-07 0.00001 Sr-90 0.00001 0.00001 0.00005 0.00003 4.71E-06 4.26E-06 0.00001 0.00006 0.00002 4.78E-06 3.89E-06 0.00010 Nb-94 0.01230 0.00218 0.01451 0.00258 0.00663 0.00511 0.00059 0.00212 0.00161 0.00055 0.00078 0.00171 Tc-99 3.84E-11 4.46E-11 5.99E-11 4.24E-11 3.93E-11 3.78E-11 4.55E-10 3.01E-10 2.10E-10 1.48E-10 2.85E-10 1.82E-10 Ag-108m 0.01487 0.00171 0.02057 0.00229 0.00882 0.00440 0.00054 0.00438 0.00213 0.00067 0.00048 0.00157 Sb-125 0.00657 0.00077 0.00758 0.00180 NA NA 0.00034 0.00116 0.00065 0.00037 0.00030 0.00068 Cs-134 0.00245 0.00035 0.00314 0.00471 0.00036 0.00023 0.00010 0.00031 0.00018 0.00017 0.00006 0.00026 Cs-137 13.93326 0.75333 17.73324 3.00665 0.70000 0.01040 0.82600 8.13766 3.23671 1.15029 0.64245 2.56367 Pm-147 0.00001 5.23E-07 4.58E-06 1.59E-06 1.95E-07 1.14E-07 6.71E-08 3.83E-09 4.52E-09 0.00000 4.49E-08 3.37E-08 Eu-152 0.01318 0.00354 0.01199 0.00387 0.42883 0.27328 0.00062 0.00211 0.00086 0.00055 0.00058 0.00147 Eu-154 0.00985 0.00141 0.01195 0.00173 0.02549 0.02144 0.00031 0.00107 0.00093 0.00031 0.00025 0.00082 Eu-155 0.00046 0.00005 0.00055 0.00011 0.00016 0.00014 0.00002 0.00005 0.00003 0.00002 0.00001 0.00003 Np-237 0.00002 0.00002 0.00001 0.00001 NA NA 0.00001 0.00001 0.00002 0.00001 0.00001 0.00002 Pu-238 4.88E-07 2.95E-07 4.59E-07 3.80E-07 3.29E-07 2.81E-07 1.45E-07 2.81E-06 1.08E-07 1.12E-07 1.46E-07 1.14E-07 Pu-239/240 5.34E-07 3.41E-07 4.82E-07 3.05E-07 3.31E-07 2.81E-07 1.68E-07 2.60E-06 1.01E-07 1.30E-07 1.26E-07 1.28E-07 Pu-241 2.24E-06 1.66E-06 2.02E-06 1.49E-06 1.59E-06 1.30E-06 1.22E-06 1.21E-06 8.80E-07 1.16E-06 8.51E-07 8.46E-07 Am-241 1.65E-06 1.47E-06 1.45E-06 1.38E-06 1.60E-06 6.29E-07 9.80E-07 0.00001 1.42E-06 8.80E-07 1.39E-06 1.03E-06 Am-243 0.00001 0.00002 0.00002 0.00001 0.00001 0.00001 0.00001 0.00004 0.00002 0.00001 0.00001 0.00001 Cm-243/244 0.00001 0.00001 0.00001 0.00001 0.00001 4.11E-06 0.00001 0.00001 0.00001 0.00001 0.00001 0.00001 Total Dose 14.27 0.88 17.87 3.14 1.24 0.35 0.86 8.40 3.25 1.16 0.67 2.80 IC Dose 0.03 0.00477 0.04 0.00680 0.01565 0.00967 0.00246 0.01097 0.00625 0.00250 0.00244 0.00632 Page 56 of 65
TSD 14-019 Revision 2 Table 36 - Basement Insignificant Contributor Dose and Dose Percentage for Mixtures using DCGLBS Corresponding IC Percentage Core Data IC Dose (mrem/yr) (mrem/yr)
Containment Mean Mixture Fraction (Table 19) 0.15% 0.06 using DCGLBS (Table 34)
Auxiliary Bldg Mean Mixture Fraction (Table 19) 0.22% 0.01 using DCGLBS (Table 34)
Unit 1 Containment Avg. Conc. (Table 30) using 0.33% 0.08 DCGLBS (Table 34)
Unit 2 Containment Avg. Conc. (Table 30) using 0.22% 0.05 DCGLBS (Table 34)
Auxiliary Bldg Avg. Conc. (Table 30) using 0.18% 0.01 DCGLBS (Table 34)
Table 37 - Basement Insignificant Contributor Dose and Dose Percentage for Individual Core Samples using DCGLBS Mean IC IC Dose IC Dose Total Dose Core Data Dose 95% UCL (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr)
Unit 1 Containment Individual Cores 0.01 to 0.18 0.04 0.06 0.11 to 98 (Table 32) using DCGLBS (Table 34) (0.01% to 0.72%)
Unit 2 Containment Individual Cores 0.01 to 0.06 0.03 0.04 0.35 to 144 (Table 32) using DCGLBS (Table 34) (0.01% to 0.25%)
Auxiliary Bldg Individual Cores 0.01 to 0.01 0.01 0.01 0.67 to 8.4 (Table 32) using DCGLBS (Table 34) (0.01% to 0.05%)
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TSD 14-019 Revision 2 4.4. IC Dose Calculation for Average Soil Sample Results The results of surface and subsurface soil characterization in the impacted area surrounding Zion indicate that there is minimal residual radioactivity in soil. Essentially all of the soil results were reported as non-detectable. Other than Cs-137 at very low levels, and Co-60 at a concentration of 0.24 pCi/g in one sample, the results for all radionuclides were less than MDC. Therefore, the direct determination of radionuclide mixture fractions for initial suite radionuclides in soil is not technically feasible due to the MDC biasing issues discussed above. Based on a generalized assumption that the contaminated water that caused concrete contamination would be similar to the source of soil contamination, the ROC and radionuclide mixture derived for the Auxiliary Building concrete was considered to be reasonably representative of soils for FSS planning and implementation. Note that due to the very low concentrations of soil contamination expected, any uncertainties in the application of the concrete derived radionuclide mixture to soil would be very unlikely to cause significant dose variability in relation to the 25 mrem/yr dose criteria.
A similar but slightly different process to that used to evaluate the concrete core IC dose percentage from mixtures and dose from actual reported data was applied to the soil HTD data.
First, the Table 19 mixture was used to determine the IC dose percentage for using soil DCGLs under the assumption that the Table 19 mixture was the a generally representative mixture for soil. Second, as a cross-check of the Table 6-2 mixture, the IC dose was also calculated using data comprised of the mean results from the 10 soil samples analyzed for the initial suite.
The IC dose from the soil sample results was calculated in two ways; 1) using the mean of the results substituting MDC values for non-detect and 2) using the mean of the actual reported results. The analysis of individual soil sample data was not considered meaningful given that essentially all of the results are non-detectable. An unrealistic bias in the IC dose calculation was introduced by the use of MDC values. The use of reported results provides a more realistic evaluation of the IC dose from the soil data.
The mean concentrations of the 10 results, using MDC values and reported results, were calculated for each initial suite radionuclide. The dose was derived by dividing the average concentration by the DCGLs for soil (Table 28) and multiplying by 25 mrem/yr.
As seen in Table 38, the IC dose percentage from the Table 19 mixture was 0.17%. The IC dose from the average concentrations of the soil mixture based on actual results was 0.49 mrem/yr (1.96%). The IC dose using MDC values for non-detect was 2.47 mrem/yr (9.98%).
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TSD 14-019 Revision 2 Table 38 - IC Dose Using Average Soil Concentration Soil Table 19 Mixture Reported Results MDC Values Radionuclide Mixture Dose Avg. Conc. (2) Dose (3) Avg. Conc. (4) Dose (5)
Fraction (1) Percentage (pCi/g) (mrem/yr) (pCi/g) (mrem/yr)
H-3 0.001743 0.00% 2.52E-02 0.00014 2.12E+00 0.01158 C-14 0.000441 0.01% 4.80E-02 0.01338 9.13E-01 0.25488 Fe-55 0.001057 0.00% 0.00E+00 0.00000 9.86E-01 0.00073 Ni-59 0.004982 0.00% 0.00E+00 0.00000 6.74E+00 0.01541 Co-60 0.009076 3.88% 1.42E-02 0.07513 3.52E-02 0.18563 Ni-63 0.234806 0.12% 0.00E+00 0.00000 7.55E-01 0.00476 Sr-90 0.000510 0.08% 2.73E-01 0.50816 2.86E-01 0.53170 Nb-94 0.000127 0.03% 4.43E-03 0.01474 3.88E-02 0.12907 Tc-99 0.000160 0.00% 2.38E-01 0.04662 3.75E-01 0.07346 Ag-108m 0.000172 0.05% 0.00E+00 0.00000 3.79E-02 0.12815 Sb-125 0.000174 0.01% 0.00E+00 0.00000 2.97E-02 0.02214 Cs-134 0.000103 0.03% 0.00E+00 0.00000 6.46E-03 0.02145 Cs-137 0.745971 95.73% 6.91E-01 1.09685 6.95E-01 1.10183 Pm-147 NA NA 3.90E-02 0.00001 1.02E-01 0.00002 Eu-152 0.000175 0.03% 4.98E-02 0.11602 1.93E-01 0.44900 Eu-154 0.000094 0.02% 0.00E+00 0.00000 7.82E-02 0.19610 Eu-155 0.000077 0.00% 2.36E-02 0.00151 4.63E-02 0.00296 Np-237 0.000004 0.01% 6.82E-03 0.21295 3.59E-02 1.12139 Pu-238 0.000013 0.00% 2.11E-02 0.00326 4.71E-02 0.00728 Pu-239/240 0.000005 0.00% 1.76E-02 0.00301 4.74E-02 0.00814 Pu-241 0.000282 0.00% 1.11E+00 0.00427 3.96E+00 0.01518 Am-241 0.000013 0.00% 8.03E-03 0.00150 4.57E-02 0.00855 Am-243 0.000009 0.00% 1.31E-01 0.06583 3.48E-02 0.01747 Cm-243/244 0.000003 0.00% 1.79E-02 0.00589 4.06E-02 0.01335 IC Percentage 0.1705% Total Dose = 2.17 Total Dose = 4.32 Insig. Dose = 0.49 Insig. Dose = 2.47 Notes: (1) Mixture Fraction taken from Table 19 values for Auxiliary Building (2) Average concentrations of reported results from analysis of 9 surface and 1 subsurface soil samples (3) Dose based on average concentrations of actual reported results (4) Average concentrations using MDC for non-detect results from analysis of 9 surface and 1 subsurface soil samples (5) Dose based on average concentrations using MDC values for non-detect results Page 59 of 65
TSD 14-019 Revision 2 4.5. Surrogate Ratios The final ROC for the decommissioning of Zion are Co-60, Cs-134 and Cs-137 (as well as Eu-152 and Eu-154 for Containment), which are gamma emitters and Ni-63, Sr-90 and H-3 (applicable only to Containment), which are HTD radionuclides. During FSS, HTD concentrations will be inferred by using a surrogate approach. Cs-137 is the principle surrogate radionuclide for H-3 and Sr-90 and Co-60 is the principle surrogate radionuclide for Ni-63. The ratio of Sr-90 to Cs-137, H-3 to Cs-137 and Ni-63 to Co-60 is required to implement the surrogate approach.
As seen in Table 32, H-3 was positively detected in all 27 concrete core samples with the exception of one (B105106-CJFCCV-002 taken in the Auxiliary Building). Sr-90 was positively detected in all 27 concrete core samples with the exception of four (one sample from Unit 1 Containment, 2 samples from Unit 2 Containment and one sample from Auxiliary Building). Co-60 was positively detected in all 27 concrete core samples with the exception of one (B101102-CJFCCV-002 taken in Unit 1 Containment). Both Ni-63 and Cs-137 was positively detected in all 27 concrete core samples.
As shown at the bottom of Table 32 for each of the cores, the ratios were determined for each core individually. The mean, standard deviation of individual results, 95% Upper Confidence Level (UCL) of the surrogate ratios for the Containment and Auxiliary Building cores are presented in Table 36. The 95% UCL ratios will be used in the surrogate calculations during FSS. Note that the 95% UCL is conservatively based in the standard deviation of the individual values as opposed to the standard deviation of the mean.
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TSD 14-019 Revision 2 Table 39 - Surrogate Ratios Containments H-3/Cs-137 Ratio Count = 21 Mean = 0.208 Max = 1.755 Min = 0.000 SD = 0.458 95%UL = 0.961 Ni-63/Co-60 Ratio Count = 21 Mean = 30.623 Max = 442.317 Min = 0.023 SD = 99.226 95%UL = 193.910 Sr-90/Cs-137 Ratio Count = 21 Mean = 0.002 Max = 0.021 Min = 0.000 SD = 0.005 95%UL = 0.010 Auxiliary Building Ni-63/Co-60 Ratio Count = 6 Mean = 44.143 Max = 180.449 Min = 9.314 SD = 67.142 95%UL = 154.632 Sr-90/Cs-137 Ratio Count = 6 Mean = 0.001 Max = 0.002 Min = 0.000 SD = 0.001 95%UL = 0.002 Page 61 of 65
TSD 14-019 Revision 2
- 5. 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.
Based upon this analysis it was determined that Co-60, Ni-63, Sr-90, Cs-134 and Cs-137 accounted for 99.6% 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.
- 6. 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.
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TSD 14-019 Revision 2
- 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.
- 14. NUREG/CR-7166, Radiological Toolbox Users Guide, May 2013.
- 7. ATTACHMENTS 7.1. Attachment A - Concrete Characterization Core Sample, Locations, and Analyses Page 63 of 65
Attachment A TSD 14-019 Concrete Characterization Core Samples, Locations, and Analyses Revision 2 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 64 of 65
Attachment A TSD 14-019 Concrete Characterization Core Samples, Locations, and Analyses Revision 2 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 65 of 65