ML21271A175

License Amendment Request (LAR) 21-01, Chapter 2 14 Radiation Safety and Control Services, Tsd 21-043, Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan

ML21271A175
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Site:	Fort Calhoun
Issue date:	08/02/2021
From:	Davis L Omaha Public Power District
To:	Office of Nuclear Reactor Regulation
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ML21271A178	List: LIC-20-0013, License Amendment Request (LAR) 21-01, Response Re Revised Post-Shutdown Decommissioning Activities Report, Chapter 8 2 Updated Environmental Report, File No. 127690-003 (LIC-20-0013, ML 20202A654) LIC-21-0005, License Amendment Request (LAR) 21-01, Chapter 8, 15, Omaha Public Power District, Avian Protection Plan CAC ML21271A143 ML21271A144 ML21271A145 ML21271A148 ML21271A149 ML21271A150 ML21271A151 ML21271A152 ML21271A153 ML21271A172 ML21271A173 ML21271A174 ML21271A175 ML21271A176 ML21271A177 ML21271A180 ML21271A182 ML21271A183 ML21271A184 ML21271A185 ML21271A192 ML21271A193 ML21271A194 ML21271A196 ML21271A197 ML21271A198 ML21271A199 ML21271A200 ML21271A206 ML21271A207 ML21271A208 ML21271A209 ML21271A210 ML21271A211 ML21271A212 ML21271A213 ML21271A214 ML21271A215 ML21271A219 ML21271A258 ML21271A259 ML21271A260 ML21271A261 ML21271A262 ML21271A265 ML21271A266 ML21271A267 ML21271A268 ... further results
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LIC-21-0005
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Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan Tech nical Support Document No. 21043 Revision 01 L. J. Davis Prepared by:_____________________________________________________

L. J. Davis L. J. Davis Calc ulations Reviewed by:_____________________________________________________

L. J. Davis Calc ulations Reviewed by:_____________________________________________________

Eric L. Darois, CHP Reviewed by: ___________________________________________________

Terry Sullivan, PhD Approved by: ___________________________________________________

Fred eric k Stracc ia, CHP, Executive Director Accepted by: ___________________________________________________

Robert Yetter, E S Director Radiolog ic al Site Closure Radiation Safety & Control Services, Inc 93 Ledge Road, Seabrook, NH 03874 18005258339 (603) 7782871 (Outside USA) www.radsafety.com August 2, 2021

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 2 of 54 Table of Contents 1 Calculations/Document Review and Validations ..................................................................................6 2 Executive Summary ...............................................................................................................................6 3 Introduction.........................................................................................................................................10 4 Industry Document Review .................................................................................................................11 5 Initial Suite of Radionuclides ...............................................................................................................11 5.1 FC-18-002 Potential Radionuclides of Concern During the Decommissioning of Fort Calhoun Station....................................................................................................................................................11 5.2 FC-20-007 Fort Calhoun Station Potential Radionuclides of Concern ......................................12 5.3 Additional Analysis of Concrete Samples ....................................................................................14 5.4 Summary of Concrete Samples ...................................................................................................14 5.5 Soil Sample Analysis ....................................................................................................................17 6 Insignificant Dose Contributors and Radionuclide Mixture ................................................................18 6.1 Radionuclide Mixture Fractions ..................................................................................................18 6.1.1 Containment sample population Nuclide Fractions ............................................................20 6.1.2 AB/TB/RWPB sample population Nuclide Fractions ...........................................................25 6.2 Insignificant Dose Contributors and Radionuclides of Concern ..................................................30 6.3 Selection of Overall Nuclide Fraction ..........................................................................................40 6.4 ROC Mixture Fractions ................................................................................................................41 6.5 Surrogate Ratios ..........................................................................................................................41 7

References:

..........................................................................................................................................47 8 Attachments: .......................................................................................................................................48 8.1 Attachment 1: Decay Corrected Analytical Results for Concrete Samples, With Negative Value Reset to Zero ...........................................................................................................................................49 8.2 Attachment 2: Derived Concentration Guide Limits ...................................................................53 8.3 Attachment 3: LLBP Scenario Concentrations that Result in 25 mrem .......................................54

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 3 of 54 Table 1: Initial List of Radionuclides from FC-18-002 ..................................................................................12 Table 2: Radionuclides Analyzed at GEL Laboratories for the Initial 37 Samples .......................................13 Table 3: Initial Suite of FCS Site-Specific Radionuclides From FC-20-007 ...................................................13 Table 4: Radionuclides Analyzed at GEL Laboratories for the 20 Additional Samples................................14 Table 5: Sample Location Summary of the 57 Concrete Samples Sent for Offsite Analysis .......................14 Table 6: Listing of Concrete Sample ID Numbers, Types and Locations .....................................................15 Table 7: Average Decay Corrected MDCs from 57 GEL Analysis Results of Concrete Samples for Each Radionuclide ................................................................................................................................................16 Table 8: Comparison of AB Only Sample Fractions with AB/TB/RWPB Sample Fractions ..........................19 Table 9: Radionuclide Activity Fractions, fAi,j and fAi,j,.75, Using Sample Data for Containment Building Samples, First Set of Radionuclides .............................................................................................................21 Table 10: Radionuclide Activity Fractions, fAi,j and fAi,j,.75, Using Sample Data for Containment Building Samples, Second Set of Radionuclides ........................................................................................................21 Table 11: Radionuclide Activity Fractions, fAi,j and fAi,j,.75, Using Sample Data for Containment Building Samples, Third Set of Radionuclides ...........................................................................................................22 Table 12: Radionuclide Activity Ratios to Cs-137, fRAi,j, Using Combined Sample Data for Containment Building, First Set of Radionuclides .............................................................................................................22 Table 13: Radionuclide Activity Ratios to Cs-137, fRAi,j, Using Combined Sample Data for Containment Building, Second Set of Radionuclides ........................................................................................................23 Table 14: Radionuclide Activity Ratios to Cs-137, fRAi,j, Using Combined Sample Data for Containment Building, Third Set of Radionuclides ............................................................................................................24 Table 15: Radionuclide Activity Fractions for Containment Building Sample Population Using Three Methods ......................................................................................................................................................24 Table 16: Radionuclide Activity Fractions, fAi,j and fAi,j,.75, Using All ores Sample Data for AB/TB/RWPB Samples, First Set of Radionuclides .............................................................................................................25 Table 17: Radionuclide Activity Fractions, fAi,j and fAi,j,.75, Using All Sample Data for AB/TB/RWPB Samples, Second Set of Radionuclides ........................................................................................................26 Table 18: Radionuclide Activity Fractions, fAi,j and fAi,j,.75, Using All Sample Data for AB/TB/RWPB Samples, Third Set of Radionuclides ...........................................................................................................27

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 4 of 54 Table 19: Radionuclide Activity Ratios to Cs-137, fRAi,j, Using Combined Sample Data for AB/TB/RWPB Samples, First Set of Radionuclides .............................................................................................................27 Table 20: Radionuclide Activity Ratios to Cs-137, fRAi,j, Using Combined Sample Data for AB/TB/RWPB Samples, Second Set of Radionuclides ........................................................................................................28 Table 21: Radionuclide Activity Ratios to Cs-137, fRAi,j, Using Combined Sample Data for AB/TB/RWPB Samples, Third Set of Radionuclides ...........................................................................................................29 Table 22: Radionuclide Activity Fractions for AB/TB/RWPB Sample Population Using Three Methods ....29 Table 23: List of DCGLs Evaluated in this TSD .............................................................................................31 Table 24 List of LLBP Scenarios Evaluated in this TSD .................................................................................31 Table 25: Relative Dose Fractions, RDFi,k, Containment Mix Fraction, Using 75th Percentiles of the Averages, CB BFM Wall/Floor DCGL Scenario .............................................................................................31 Table 26: Relative Dose Fractions, RDFi,k, Containment Mix Fraction, Using 75th Percentiles of the Nuclide Ratios to Cs-137, BFM Wall/Floor of CB DCGL Scenario .............................................................................32 Table 27: Relative Dose Fractions, RDFi,k, Containment Mix Fraction, Using 75th Percentiles of the Averages, CB Soil, BP & Fill Material DCGL Scenarios .................................................................................32 Table 28: Relative Dose Fractions, RDFi,k, Containment Mix Fraction, Using 75th Percentiles of the Nuclide Ratios to Cs-137, CB Soil, BP & Fill Material DCGL Scenarios ......................................................................33 Table 29: Relative Dose Fractions, RDFi,k, AB/TB/RWPB Mix Fraction, Using 75th Percentiles of the Averages, BFM Other Walls/Floors DCGL Scenario .....................................................................................34 Table 30: Relative Dose Fractions, RDFi,k, AB/TB/RWPB Mix Fraction, Using 75th Percentiles of the Nuclide Ratios to Cs-137, BFM Other Walls/Floors DCGL Scenario .........................................................................34 Table 31: Relative Dose Fractions, RDFi,k, AB/TB/RWPB Mix Fraction, Using 75th Percentiles of the Averages, Embedded Pipe DCGL Scenarios*...............................................................................................35 Table 32: Relative Dose Fractions, RDFi,k, AB/TB/RWPB Mix Fraction, Using 75th Percentiles of the Nuclide Ratios to Cs-137, Embedded Pipe DCGL Scenarios* ...................................................................................35 Table 33: Relative Dose Fractions, RDFi,k, AB/TB/RWPB Mix Fraction, Using 75th Percentiles of the Averages, Soil, Buried Pipe, & Fill Material DCGL Scenarios .......................................................................36 Table 34: Relative Dose Fractions, RDFi,k, AB/TB/RWPB Mix Fraction, Using 75th Percentiles of the Nuclide Ratios to Cs-137, Soil, Buried Pipe & Fill Material DCGL Scenarios.............................................................36 Table 35: Relative Dose Fractions, RDFi,k, Containment Mix Fraction, Using 75th Percentiles of the Averages, LLBP Scenarios ............................................................................................................................37

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 5 of 54 Table 36: Relative Dose Fractions, RDFi,k, Containment Mix Fraction, Using 75th Percentiles of the Nuclide Ratios to Cs-137, LLBP Scenarios .................................................................................................................37 Table 37: Relative Dose Fractions, RDFi,k, AB/TB/RWPB Mix Fraction, Using 75th Percentiles of the Averages, LLBP Scenarios* ..........................................................................................................................38 Table 38: Relative Dose Fractions, RDFi,k, AB/TB/RWPB Mix Fraction, Using 75th Percentiles of the Nuclide Ratios to Cs-137, LLBP Scenarios* ...............................................................................................................39 Table 39: Summary of ROC Lists..................................................................................................................39 Table 40: Final Radionuclide Mixtures for FCS ............................................................................................40 Table 41: ROC Mixture Fraction ..................................................................................................................41 Table 42: Gamma ROC Mixture Fractions ...................................................................................................41 Table 43: Sr-90 and Cs-137 Decayed Reported Concentrations, MDCs and Ratios ....................................42 Table 44: C-14 and Cs-137 Decayed Reported Concentrations, MDCs and Ratios .....................................44 Table 45: Sr-90/Cs-137 Ratio .......................................................................................................................46 Table 46: C-14/Cs-137 Ratio ........................................................................................................................46 Table 47: Cs-137 Surrogate Ratios ..............................................................................................................47 Table 48: Sample Analytical Results, First Set of Radionuclides (pCi/g) .....................................................49 Table 49: Sample Analytical Results, Second Set of Radionuclides (pCi/g) .................................................50 Table 50: Sample Analytical Results, Third Set of Radionuclides (pCi/g) ....................................................51 Table 51: DCGLs...........................................................................................................................................53 Table 52: LLBP Scenario Concentrations that Result in 25 mrem ...............................................................54

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 6 of 54 1 Calculations/Document Review and Validations During the development of this TSD, several spreadsheets were developed to create the contained data tables. As noted in this coversheet, three reviewers are listed. The roles of each reviewer were different as described below.

Eric Darois. Mr. Darois developed a spreadsheet to extract data from the GEL Electronic Data Delivery (EDD) file(s) for each sample ID and for each radionuclide while decay-correcting the measurement result from the analysis date to the estimated date of license termination. This spreadsheet set any negative analytical results to zero. This extraction also calculated ingrowth of Am-241 from the decay of Pu-241. Due to the size of this spreadsheet, the original spreadsheet was divided into stand-alone spreadsheets and further developed by Mr. Davis for the final data tables contained within this document. Mr. Darois did a comprehensive review of Mr. Davis spreadsheets. Mr. Darois also did a comprehensive review of the completed TSD for grammar, format, and textual accuracy.

Joe Davis. Mr. Davis was the primary author of this TSD. However, he performed a comprehensive review of the spreadsheet developed by Mr. Darois including validations and hand-calculations.

Terry Sullivan. Mr. Sullivan performed a comprehensive and independent review of the document and the associated data. He was not involved in the development of this TSD.

2 Executive Summary To assist in decommissioning planning for the Fort Calhoun Nuclear Generating Station (FCS), this Technical Support Document (TSD) identifies a comprehensive suite of radionuclides potentially present at the site. The identified radionuclides are then used in conjunction with the calculated Derived Concentration Guide Limits (DCGLs) to determine the Radionuclides of Concern (ROCs) and Insignificant Contributors (IC) to dose. Surrogate ratios are also determined for the Hard to Detect (HTD) radionuclides.

Radionuclide Selection A systematic approach was taken including reviewing applicable nuclear industry guidance documents, relevant FCS specific historical information and representative available sample radionuclide data. The selection of the initial suite of radionuclides included identifying the potential radionuclides as well as eliminating those radionuclides which would not be present due to decay or may be present but in insignificant concentrations.

A preliminary evaluation was performed to document an initial suite of radionuclides for the decommissioning of FCS. This was contained in FC-018-002 Potential Radionuclides of Concern During the Decommissioning of Fort Calhoun Station.

From November 2019 through March 2020, the staff at Fort Calhoun station implemented a comprehensive concrete characterization program. From this sample population, 37 samples were then sent to an offsite laboratory for a wide range of radionuclide analytes.

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 7 of 54 FC-20-007 Fort Calhoun Station Potential Radionuclides of Concern pCi/g used the offsite results to calculate the fractional results for each radionuclide to identify those present in the sampled plant environments. It then compared these results to the initial listing from FC-018-002 and selected the initial suite of radionuclides for Derived Concentration Guide Limit (DCGL) development.

In April 2021, twenty additional concrete samples were analyzed by GEL for Np-237 in addition to the previous suite of radionuclides. This brought the total number of concrete samples analyzed at the off-site laboratory to 57.

Soil Sampling Results FC-18-003 Evaluation of Cs-137 Global Fallout in Soils at Fort Calhoun Station provides a review of information from published global fallout studies and Fort Calhoun Station soil sample data. It provides the technical basis for anticipated soil concentrations attributable to fallout.

As part of this study, fifteen background samples were taken in areas around Fort Calhoun. Of these background samples, eight showed positive Cs-137 activity levels detectable by gamma spectroscopy.

For the three samples that did not have an identifiable Cs-137 peak, the Cs-137 activity calculated by the spectroscopy software was used. Two of the gamma spectroscopy results had an identified Cs-137 peak and were less than the minimum detectable activity (MDA). These five values were included as part of the statistical analysis. The three samples which had no identified Cs-137 were not used in the statistical analysis. The mean of the data used was 0.104 pCi/g and the standard deviation was 0.105 pCi/g. At the 95% confidence interval the activity of Cs-137 was 0.314 pCi/g.

In 2018 as part of a partial site release process, The U.S. Nuclear Regulatory Commission (NRC) requested that Oak Ridge Institute for Science and Education (ORISE) perform confirmatory survey activities of areas classified by FCS as non-impacted. The confirmatory survey included surface gamma scanning and collection of randomly selected volumetric soil samples. No elevated direct radiation was identified during surface gamma scanning. Subsequently, no judgmental samples were collected.

Radionuclides that were identified in the random soil samples were attributable to natural sources and not site operations.

Cesium-137 was positively identified, above the analytical Minimum Detectable Concentration (MDC), in 16 of the 25 randomly selected confirmatory soil samples. The maximum Cs-137 concentration was 0.372 pCi/g. The average Cs-137 concentration for the confirmatory survey FCS Non-Impacted Land Areas was 0.09 pCi/g, which is less than the mean background concentration. Other radionuclides detected in the soil samples were naturally occurring and not attributable to site operations.

As part of site characterization in August 2020, 47 soil samples were sent to an offsite laboratory for a wide range of radionuclide analytes. The only positively identified radionuclides above MDA was Cs-137.

The average of the positive Cs-137 results was 1.14E-01 pCi/g. The average MDA for C-14 was 3.51 pCi/g. The average Ni-63 MDA was 2.89E+00 pCi/g. The average Sr-90 MDA was 8.82E-02 pCi/g.

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 8 of 54 Radionuclide Mixture Fractions The mixture fraction of each radionuclide in the initial suite at the projected time of license termination (October 5, 2026) has been determined using the results of the 57 concrete characterization sample analyses. Two separate sample populations were analyzed. The first population consisted solely of the Containment Building (CB) samples. The second population consisted of the Auxiliary Building, Turbine Building and Radioactive Waste Processing Building samples. The Containment Bldg. and AB/TB/RWPB sample populations were analyzed separately to recognize the potential that these may contain different radionuclide mixtures.

For each of these populations, the radionuclide fractions were determined from the decayed analytical data using three separate approaches. The three methods were chosen to represent common and conservative methods in determining activity fractions to ensure that the final selection of the radionuclide mixtures account for variability and represent conservative estimates. Each of the analysis methods use the actual reported laboratory values, whether detected or less than the reported MDC values. All negative decay corrected results were set to zero to avoid having fractional results greater than one. The results were then decay-corrected from the date of sample analysis to the anticipated date of license termination. The Am-241 decay corrected value was also adjusted to account for its in-growth from Pu-241.

The first method was to calculate the radionuclide activity fraction for each sample and each radionuclide, within each population from the reported radionuclide activity concentrations and then calculate the average activity fraction for each radionuclide, and population of samples.

The second method was to calculate the 75 th percentile of the population of samples. Once the 75 th percentile fraction were calculated for each radionuclide, the data set was re-normalized to determine the percentile-based activity fractions.

The third method was to calculate the individual radionuclide ratios to Cs-137 for each sample, calculate the 75th percentile for the sample group, then renormalize to determine the activity fractions.

The analyses described above remove the activity weighting and give equal statistical weight to each of the sample results. Based on the evaluation using the three statistical methods, the two methods involving the use of the 75th percentiles result in very similar results, particularly the IC dose fractions.

Using the 75th percentile provides sufficient overall conservatism in the development of the radionuclide mixtures. In addition, there is prior precedence in using the 75 th percentile, particularly in the parameter selection process for dose modeling to support DCGL calculations and that this approach also results in satisfactory conservatism.

The 75th percentile of the Cs-137 fractions has been selected to represent the overall nuclide mix for the Combined sample population, the Containment Building sample population, and the AB/TB/RWPB sample population.

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 9 of 54 The CB mix fraction contains an unusually high proportion of C-14 at 54.9%. The potential for cross contamination from this source term will be closely monitored during decommissioning.

Radionuclides of Concern and Insignificant Contributors to Dose In accordance with NUREG-1757, radionuclides that contribute, in aggregate, less than 10% of the 25 mrem/yr dose criteria are considered to be insignificant. The insignificant contributor radionuclides may be eliminated from further consideration in FSS and from detailed dose modeling but the aggregate dose from the insignificant contributors must be accounted for in demonstrating compliance. The remaining radionuclides, after the insignificant contributors are removed, and the associated mixture fractions, will comprise the final ROC list that will undergo evaluation in the LTP.

The Relative Dose Fraction for each nuclide is calculated using the applicable DCGL and radionuclide mixture fraction. The evaluation provided in this TSD uses the radionuclide mixture fractions of the initial suite of radionuclides and selects the radionuclides that are insignificant dose contributors (IC) as defined in NUREG-1757, albeit a substantially lower IC dose fraction. The radionuclides remaining after the insignificant dose contributors are eliminated are the radionuclides of concern (ROCs) that will undergo detailed analysis on Chapters 4, 5 and 6 of the FCS LTP. The insignificant contributor (IC) dose fraction will be accounted for by adjusting the final DCGLs for each ROC.

The ROCs for the CB walls and floors are C-14, Co-60, Sr-90, Cs-137 and Eu-152.

The ROCs for the CB mix fraction soil, fill material and buried pipe scenarios are C-14, Co-60, Cs-137 and Eu-152.

The ROCs for Other walls/floors are C-14, Co-60, Sr-90, Cs-137 and Eu-152.

The ROCs for AB/TB embedded pipes are C-14, Co-60, Sr-90, Cs-137 and Eu-152.

The ROCs for the AB/TB/RWPB mix fraction soil, fill material and buried pipe scenarios are C-14, Co-60, Cs-137 and Eu-152.

The remaining radionuclides are eliminated from further detailed evaluation. The ROCs were selected to ensure that sufficient margin has been attributed to the estimated dose contribution from the insignificant radionuclides. This decreases the risk of having to recalculate the adjusted DCGLS.

The IC dose fraction ranges from approximately 0.28% to 8.88% of the total dose depending on the source and the method used for determining the fractions. The highest value for the IC dose fraction is from the AB/TB/RWPB mix fraction for the Backfill Material scenario using the 75th percentiles of the nuclide ratios to Cs-137 statistical method.

In addition to the analysis described above for the DCGL scenarios, five Less Likely But Plausible (LLBP) scenarios were also analyzed. This analysis used the same sample population mix fractions and statistical methods as was used in the DCGL scenario analyses.

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 10 of 54 The IC dose fraction for the LLBP scenarios ranges from approximately 0.01% to 0.90% of the total dose depending on the source and the method used for determining the fractions. The highest LLBP IC dose fraction is from the Steel Recycling/Disposal scenario in the Containment Building using 75 th percentiles of the nuclide ratios to Cs-137.

Surrogate Ratios From the data provided in sections 6.1, 6.2, 6.3 and 6.4, it is evident that Cs-137 is the predominant ROC gamma-emitting radionuclide. Co-60 and Eu-152 are also gamma emitting ROCs but are present at much lower fractions than Cs-137. Also, C-14, and Sr-90 are identified as ROCs while also being HTD radionuclides.

Cs-137 was selected as the most appropriate gamma emitter for the surrogate relationship for both Sr-90 and C-14. This was based on the high percentage of Cs-137 (93-98%) and the low percentage of Co-60 (2.0-2.5%). Due to the high percentage of C-14 in the mix fractions (83% in the CB and 5% in the AB/TB/RWPB) the resulting surrogate ratio to Co-60 would have been impractical to use. Due to instrument sensitivities and the high C-14/Co-60 ratios, it would not be possible to meet the required scan MDCs.

The ratio of HTDs to gamma emitters is required to develop a surrogate relationship as defined in MARSSIM. The concentration of HTDs can be inferred from the concentration of a gamma emitter in cases where samples are not subject to HTD analysis during FSS activities.

For the samples where neither nuclide was detected, the ratio of the MDCs was not used since this is merely a ratio of the detectability of the two nuclides for that specific sample and has no relationship to the activity ratio.

Of the 57 samples, 43 of the Sr-90, 55 of the C-14 and 56 of the Cs-137 results were greater than MDC.

One sample was non-detectable for both Sr-90 and Cs-137 and one sample was non-detectable for both C-14 and Cs-137.

To account for the variability and level of uncertainty in the data, the 95 th percentile values were selected for the final surrogate ratios. Using the 95 th percentile value along with the MDC substituted will provide reasonable conservatism during the final status surveys.

The C-14/Cs-137 ratio for the CB mix fraction is 3.83E+01. The C-14/Cs-137 ratio for the AB/TB/RWPB mix fraction is 1.11E+00.

The Sr-90/Cs-137 ratio for the CB mix fraction is 1.25E-02.The Sr-90/Cs-137 ratio for the AB/TB/RWPB mix fraction is 1.97E-01.

3 Introduction An important part of assessing and developing characterization plans, FSS plans and performing dose assessments at FCS is the identification of radionuclides that could result in a significant dose

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 11 of 54 contribution at the time of license termination. A technical evaluation was performed to document an initial suite of radionuclides for the decommissioning of FCS. A final ROC list is then developed that provides the radionuclides that will undergo detailed evaluation for FSS design and dose modeling in the License Termination Plan (LTP) (Chapters 5 and 6).

A systematic approach was taken including reviewing applicable nuclear industry guidance documents, relevant FCS specific historical information and representative available sample radionuclide data. The selection of the initial suite of radionuclides includes identifying the potential radionuclides as well as eliminating those radionuclides which would not be present due to decay or may be present but in insignificant concentrations.

The mixture fraction of each radionuclide in the initial suite at the time of license termination uses the results of concrete characterization sample analyses. The mixture fraction will be used in conjunction with the dose assessment methods developed for Chapter 6 of the FCS LTP to calculate the relative dose significance of the radionuclides in the initial suite. In accordance with NUREG-1757, Volume 2, Revision 1, Section 3.3 [1.] radionuclides that contribute, in aggregate, less than 10% of the 25 mrem/yr dose criteria are considered to be insignificant. The insignificant contributor radionuclides may be eliminated from further consideration in FSS and from detailed dose modeling but the aggregate dose from the insignificant contributors must be accounted for in demonstrating compliance. The remaining radionuclides, after the insignificant contributors are removed, and the associated mixture fractions, will comprise the final ROC list that will undergo evaluation in the LTP.

4 Industry Document Review For the development of the suite of potential radionuclides of concern, several nuclear industry guidance documents were reviewed, including NUREG/CR-3474 [2.] and NUREG/CR-4289 [3.].

NUREG/CR-3474 provides tables of theoretical activation products for both pressurized water reactors (PWR) and boiling water reactors (BWR) based on typical materials of construction, anticipated impurities, assumed neutron flux, etc. An initial list of radionuclides, as shown in was developed by listing those radionuclides noted in both Table 5.13 Activity Inventory of PWR Internals at Shutdown (Total Ci) and Table 5.15, Inventories of PWR and BWR Vessel Walls at Shutdown (Total Ci) from NUREG/CR-3474.

5 Initial Suite of Radionuclides 5.1 FC-18-002 Potential Radionuclides of Concern During the Decommissioning of Fort Calhoun Station In March 2018, the Fort Calhoun RP technical staff prepared Technical Basis Document (TBD) FC-18-002, Potential Radionuclides of Concern During the Decommissioning of Fort Calhoun Station [4.]. This TBD evaluated expected radionuclides based on a review of industry guidance and site-specific FCS sample

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 12 of 54 results. This consisted of the results from 14 samples collected within various waste streams from 2016 through 2018 and analyzed by an offsite laboratory for nuclides typically required by 10 CFR 61. Based upon the review of theoretical radionuclides noted in NUREG PWR studies, and the waste/process stream sample results, an initial suite of radionuclides was generated for consideration as listed in Table 1.

Table 1: Initial List of Radionuclides from FC-18-002 Radionuclide Half-Life, years H-3 12.3 Fe-55 2.73 Co-60 5.27 Ni-63 100.1 Sr-90 28.74 Cs-134 2.07 Cs-137 30.04 Pu-238 87.7 Pu-239/240 24110 Pu-241 14.35 Am-241 432.2 Cm-243/244 29.1 5.2 FC-20-007 Fort Calhoun Station Potential Radionuclides of Concern From November 2019 through March 2020, the staff at Fort Calhoun station implemented a comprehensive concrete characterization program.

Four separate sample plans were developed and implemented using the Tru-Pro concrete sampling techniques representing 744 discrete samples at multiple depths up to 6 inches. The sample plans are contained in references [8.], [9.], [10.] and [11.]. The samples were collected in the following buildings:

containment building, auxiliary building, turbine building, and radwaste processing building.

Each of the 744 samples were analyzed using the onsite gamma spectroscopy system. From this sample population, 37 samples were then sent to an offsite laboratory for a wide range of radionuclide analytes.

This analysis included alpha, beta and gamma emitting radionuclides typically considered during nuclear power plant decommissioning projects. The offsite analysis was performed by GEL Laboratories LLC in Charleston SC and the results are reported in references [13.], [14.], [15.] and [16.].

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 13 of 54 The list of radionuclide analyses conducted by GEL are listed in Table 2: Radionuclides Analyzed at GEL Laboratories below:

Table 2: Radionuclides Analyzed at GEL Laboratories for the Initial 37 Samples H-3 Zn-65 Eu-152 C-14 Nb-94 Eu-154 Mn-54 Tc-99 Eu-155 Fe-55 Sr-90 Pu-238 Co-57 Ag-110m Pu-239/ 240 Co-58 Sb-125 Pu-241 Ni-59 Cs-134 Am-241 Ni-63 Cs-137 Cm-242 Co-60 Ce-144 Cm-243/ 244 It should be noted that due to alpha energy resolution limitations, the laboratories report two radionuclide pairs; Pu-239/240, and Cm-243/244. Each of these pairs are considered a single reported nuclide in this analysis.

FC-20-007 Fort Calhoun Station Potential Radionuclides of Concern [5.] calculated the fractional results for each radionuclide to identify those present in the sampled plant environments and compared this list to the initial listing from FC-018-002 and selected the initial suite of radionuclides for Derived Concentration Guide Limit (DCGL) development.

The results of the analysis were used to evaluate whether additional radionuclides should be added or removed from the list provided in FC-018-002. This analysis identified 22 radionuclides that should be included in the initial listing of radionuclides as compared to the 12 that were initially identified in FC-018-002. No radionuclides were identified in the concrete samples that were not accounted for by the assessments described above. The initial suite of radionuclides is listed in Table 3: Initial Suite of FCS Site-Specific Radionuclides From FC-20-007 below.

Table 3: Initial Suite of FCS Site-Specific Radionuclides From FC-20-007 Radionuclide Half Life (Years)

H-3 1.23E+01 C-14 5.70E+03 Fe-55 2.74E+00 Co-58 1.94E-01 Ni-59 1.01E+05 Co-60 5.27E+00 Ni-63 1.00E+02 Sr-90 2.88E+01 Tc-99 2.11E+05 Sb-125 2.76E+01 Cs-134 2.06E+00 Cs-137 3.02E+01 Ce-144 7.80E-01 Eu-152 1.35E+01 Eu-154 8.80E+00

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 14 of 54 Eu-155 4.76E+00 Np-237 2.14E+06 Pu-238 8.77E+01 Pu-239/240* 2.41E+04 Pu-241 1.44E+01 Am-241 4.32E+02 Cm-243/244* 2.85E+01

• For each of these radionuclide pairs the shortest half-life was selected.

5.3 Additional Analysis of Concrete Samples In April 2021, 20 additional concrete samples were also analyzed by GEL. These analyses included Np-237 bringing the total number of concrete samples analyzed offsite to 57.

Table 4: Radionuclides Analyzed at GEL Laboratories for the 20 Additional Samples H-3 Zn-65 Eu-152 C-14 Nb-94 Eu-154 Mn-54 Tc-99 Eu-155 Fe-55 Sr-90 Pu-238 Co-57 Ag-110m Pu-239/ 240 Co-58 Sb-125 Pu-241 Ni-59 Cs-134 Am-241 Ni-63 Cs-137 Cm-242 Co-60 Ce-144 Cm-243/ 244 Np-237 The concrete samples sent for offsite analysis were collected in the following locations, twenty-seven (27) from the Containment Building, twenty-six(26) from the Auxiliary Building, two (2) from the Turbine Building and two(2) from the Radwaste Processing Building. A summary of the samples is provided in Table 5.

5.4 Summary of Concrete Samples Table 5: Sample Location Summary of the 57 Concrete Samples Sent for Offsite Analysis Area Name Sample ID Prefix # Of Samples CB 977 Elevation - Under Vessel Area 1100 3 CB 995/996 Elevation G/A 1200 17 CB 1013 Elevation G/A 1300 5 CB 1045 Elevation G/A 1400 2 AB 971 Elevation G/A 2100 6 AB 989 Elevation G/A 2200 13 AB 1007 Elevation G/A 2300 6 AB 1025 Elevation G/A 2600 1

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 15 of 54 TB 990 Elevation G/A 3100 2 Radwaste Processing Building 4100 2 Total 57 Table 6 provides the sample identification numbers, types and general locations for all 57 concrete samples analyzed by GEL.

Table 6: Listing of Concrete Sample ID Numbers, Types and Locations Sample ID Elevation Surface (floor/wall) 1100X-1-CJ-FCV1-005 CB 977 Elevation - Under Vessel Concrete Floor 1100X-1-CJ-WCV1-003 CB 977 Elevation - Under Vessel Concrete Wall 1100X-1-CJ-WCV1-004 CB 977 Elevation - Under Vessel Concrete Wall 1200X-1-CJ-FCV1-001 CB 995/996 Elevation G/A Concrete Floor 1200X-1-CJ-FCV1-002 CB 995/996 Elevation G/A Concrete Floor 1200X-1-CJ-FCV1-003 CB 995/996 Elevation G/A Concrete Floor 1200X-1-CJ-FCV1-010 CB 995/996 Elevation G/A Concrete Floor 1200X-1-CJ-FCV1-018 CB 995/996 Elevation G/A Concrete Floor 1200X-1-CJ-FCV1-023 CB 995/996 Elevation G/A Concrete Floor 1200X-1-CJ-FCV1-025 CB 995/996 Elevation G/A Concrete Floor 1200X-1-CJ-FCV1-027 CB 995/996 Elevation G/A Concrete Floor 1200X-1-CJ-WCV1-005 CB 995/996 Elevation G/A Concrete Wall 1200X-1-CJ-WCV1-006 CB 995/996 Elevation G/A Concrete Wall 1200X-1-CJ-WCV1-008 CB 995/996 Elevation G/A Concrete Wall 1200X-1-CJ-WCV1-009 CB 995/996 Elevation G/A Concrete Wall 1200X-1-CJ-WCV1-011 CB 995/996 Elevation G/A Concrete Wall 1200X-1-CJ-WCV1-012 CB 995/996 Elevation G/A Concrete Wall 1200X-1-CJ-WCV1-015 CB 995/996 Elevation G/A Concrete Wall 1200X-1-CJ-WCV1-028 CB 995/996 Elevation G/A Concrete Wall 1200X-1-CJ-WCV1-029 CB 995/996 Elevation G/A Concrete Wall 1300X-1-CJ-FCV1-003 CB 1013 Elevation G/A Concrete Floor 1300X-1-CJ-FCV1-005 CB 1013 Elevation G/A Concrete Floor 1300X-1-CJ-FCV1-006 CB 1013 Elevation G/A Concrete Floor 1300X-1-CJ-FCV1-008 CB 1013 Elevation G/A Concrete Floor 1300X-1-CJ-WCV1-007 CB 1013 Elevation G/A Concrete Wall 1400X-1-CJ-FCV1-002 CB 1045 Elevation G/A Concrete Floor 1400X-1-CJ-FCV1-021 CB 1045 Elevation G/A Concrete Floor 2100X-1-CJ-FCV1-001 AB 971 Elevation G/A Concrete Floor 2100X-1-CJ-FCV1-003 AB 971 Elevation G/A Concrete Floor 2100X-1-CJ-FCV1-005 AB 971 Elevation G/A Concrete Floor 2100X-1-CJ-FCV1-006 AB 971 Elevation G/A Concrete Floor 2100X-1-CJ-FCV1-011 AB 971 Elevation G/A Concrete Floor 2100X-1-CJ-FCV1-014 AB 971 Elevation G/A Concrete Floor 2200X-1-CJ-FCV1-006 AB 989 Elevation G/A Concrete Floor 2200X-1-CJ-FCV1-008 AB 989 Elevation G/A Concrete Floor 2200X-1-CJ-FCV1-010 AB 989 Elevation G/A Concrete Floor 2200X-1-CJ-FCV1-020 AB 989 Elevation G/A Concrete Floor 2200X-1-CJ-FCV1-021 AB 989 Elevation G/A Concrete Floor 2200X-1-CJ-FCV1-022 AB 989 Elevation G/A Concrete Floor 2200X-1-CJ-FCV1-026 AB 989 Elevation G/A Concrete Floor 2200X-1-CJ-FCV1-030 AB 989 Elevation G/A Concrete Floor 2200X-1-CJ-FCV1-031 AB 989 Elevation G/A Concrete Floor 2200X-1-CJ-FCV1-035 AB 989 Elevation G/A Concrete Floor 2200X-1-CJ-FCV1-038 AB 989 Elevation G/A Concrete Floor 2200X-1-CJ-FCV1-039 AB 989 Elevation G/A Concrete Floor 2200X-1-CJ-WCV1-009 AB 989 Elevation G/A Concrete Wall

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 16 of 54 Sample ID Elevation Surface (floor/wall) 2300X-1-CJ-FCV1-001 AB 1007 Elevation G/A Concrete Floor 2300X-1-CJ-FCV1-002 AB 1007 Elevation G/A Concrete Floor 2300X-1-CJ-FCV1-003 AB 1007 Elevation G/A Concrete Floor 2300X-1-CJ-FCV1-005 AB 1007 Elevation G/A Concrete Floor 2300X-1-CJ-FCV1-007 AB 1007 Elevation G/A Concrete Floor Table 7 shows the average decay corrected MDCs from all 57 samples analyzed by GEL for each radionuclide. This listing demonstrates that an effective average MDC was achieved by GEL for each analysis.

Table 7: Average Decay Corrected MDCs from 57 GEL Analysis Results of Concrete Samples for Each Radionuclide Radionuclide Average MDC (pCi/g)

H-3 9.06E+00 C-14 2.08E+01 Mn-54 4.38E-03 Fe-55 3.70E+00 Co-57 2.41E-01 Co-58 4.82E-08 Ni-59 2.17E+00 Ni-63 1.93E+01 Co-60 1.25E+00 Zn-65 4.02E-03 Nb-94 3.02E-01 Tc-99 1.27E+00 Sr-90 2.93E-01 Ag-110m 2.57E-03 Sb-125 5.29E-01 Cs-134 1.11E-01 Cs-137 2.33E+01 Ce-144 1.83E-02 Eu-152 7.70E+00 Eu-154 1.19E+00 Eu-155 6.08E-01 Pu-238 3.79E-02 Pu-239/240 4.06E-02 Pu-241 2.32E+00 Am-241 7.35E-02 Cm-242 3.74E-05 Cm-243/244 5.15E-02 Np-237 2.37E-03 Attachment 1 provides the analytical results for all 57 concrete samples. These results include all results as reported by GEL, whether or not they were less than any screening value including the MDC. Negative decay corrected results have been reset to zero to avoid generating fractional results greater than one.

The reported concrete sample concentrations were decay corrected from the sample analysis dates to the anticipated license termination date of October 5, 2026.

The decay corrected Am-241 concentrations include the in-growth of activity from the decay of Pu-241.

Equation 1 represents how this was accounted for.

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 17 of 54 Equation 1

() = +

These 57 sample results represent the total population used for the ROC and IC fraction analyses in this TSD. This data is used in the determination of the radionuclide mixtures and the potential dose from IC radionuclides and their associated relative contributions.

5.5 Soil Sample Analysis FC-18-003 Evaluation of Cs-137 Global Fallout in Soils at Fort Calhoun Station [6.] provides a review of information from published global fallout studies and Fort Calhoun Station soil sample data. It provides the technical basis for anticipated soil concentrations attributable to fallout.

As part of this study, fifteen background samples were taken in areas around Fort Calhoun. Of these background samples, eight showed positive Cs-137 activity levels detectable by gamma spectroscopy.

For the three samples that did not have an identifiable Cs-137 peak, the Cs-137 activity was calculated by the spectroscopy software was conservatively used. Two of the gamma spectroscopy results had an identified Cs-137 peak and were less than the minimum detectable activity (MDA). These five values were included as part of the statistical analysis. The three samples analyzed offsite which had no identified Cs-137 were not used in the statistical analysis. The mean of the data used was 0.104 pCi/g and the standard deviation (k=1) was 0.105 pCi/g. At the 95% confidence interval (k=2) the activity of Cs-137 was 0.314 pCi/g.

In 2018 as part of a partial site release process, The U.S. Nuclear Regulatory Commission (NRC) requested that Oak Ridge Institute for Science and Education (ORISE) perform confirmatory survey activities of areas classified by FCS as non-impacted [7.]. The confirmatory survey included surface gamma scanning and collection of randomly selected volumetric soil samples. No elevated direct radiation was identified during surface gamma scanning. Subsequently, no judgmental samples were collected. Radionuclides that were identified in the random soil samples were attributable to natural sources and not site operations.

Cesium-137 was positively identified, above the analytical MDC, in 16 of the 25 randomly selected confirmatory soil samples. The maximum Cs-137 concentration was 0.372 pCi/g. The average Cs-137 concentration for the confirmatory survey FCS Non-Impacted Land Areas was 0.09 pCi/g, which is less than the mean background concentration. Other radionuclides detected in the soil samples were naturally occurring and not attributable to site operations.

As part of site characterization in August 2020, 47 soil samples were sent to an offsite laboratory for a wide range of radionuclide analytes [12.]. The only positively identified radionuclides above MDA was

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 18 of 54 Cs-137. The average of the positive Cs-137 results was 1.14E-01 pCi/g. The average MDA for C-14 was 3.51 pCi/g. The average Ni-63 MDA was 2.89E+00 pCi/g. The average Sr-90 MDA was 8.82E-02 pCi/g.

6 Insignificant Dose Contributors and Radionuclide Mixture One of the objectives of site characterization is to establish the radionuclide profiles for the various media for the purposes of ALARA analysis, dose assessment and FSS planning. The evaluation provided in this section determines the radionuclide mixture fractions of the initial suite of radionuclides and selects the radionuclides that are insignificant dose contributors as defined in NUREG-1757, Vol. 2, Rev 1 [1.]. The radionuclides remaining after the insignificant dose contributors are eliminated are the radionuclides of concern (ROCs) that will undergo detailed analysis on Chapters 4, 5 and 6 of the FCS LTP. The insignificant contributor (IC) dose fraction will be accounted for by adjusting the final DCGLs for each ROC. This TSD section is divided into two subsections; one for determining radionuclide mixture fractions using three methods, and a second to establish the IC dose fraction for each medias set of DCGLs.

6.1 Radionuclide Mixture Fractions The radionuclide mixture fractions are derived from the results of the 57 concrete samples. Two separate sample populations were analyzed. The first population consisted solely of the Containment Building samples. The second population consisted of the Auxiliary Building, Turbine Building and Radioactive Waste Processing Building (AB/TB/RWPB) samples. The Containment Building and AB/TB/RWPB sample populations were analyzed separately to recognize the potential that these may contain different radionuclide mixtures.

The composition of the two sample populations was based on process knowledge and the initial evaluation of the sample results. This initial evaluation showed that the Containment Building and the Auxiliary Building formed two distinct sample populations.

For each of these two populations, k, the radionuclide fractions were determined from the decay corrected analytical data using three separate approaches as described below. The three methods were chosen to represent common and conservative methods in determining activity fractions to ensure that the final selection of the radionuclide mixtures account for variability and represent conservative estimates. Each of the three analysis methods use the actual reported laboratory values, whether detected or less than the reported MDC values. All negative results were reset to zero to avoid generating fractional results greater than one. The results were decay corrected from the date of sample analysis to the anticipated date of license termination. The Am-241 results also account for the in-growth from Pu-241.

An additional evaluation was performed to determine the impact of combining the 2 TB and 2 RWPB samples with the 26 AB samples into a single population. This evaluation showed that adding these 4 samples to the AB sample population did not result in a significant change to the AB mixture fraction. The results of this comparison are contained in Table 8. These fractions were calculated using the methods described above.

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 19 of 54 Table 8: Comparison of AB Only Sample Fractions with AB/TB/RWPB Sample Fractions AB, TB &

AB Only RWPB Normalized Normalized Fractions, Fractions, 75th 75th Percentile Percentile AB, TB & AB, TB & of the of the AB Only RWPB AB Only RWPB Individual Individual Average Average 75 Perc. 75 Perc. Sample Sample Activity Activity Norm. Norm. Ratios to Cs- Ratios to Radionuclide Fractions Fractions Frac. Frac. 137 Cs-137 H-3 3.00E-02 2.60E-02 2.93E-02 2.76E-02 3.22E-02 2.52E-02 C-14 4.05E-02 9.72E-02 2.97E-02 4.43E-02 3.94E-02 5.14E-02 Fe-55 1.43E-03 7.83E-03 6.61E-04 1.42E-03 5.78E-04 2.33E-03 Co-58 8.01E-11 6.94E-11 6.07E-15 4.54E-14 5.31E-15 7.00E-14 Ni-59 1.98E-03 3.11E-03 1.81E-03 1.82E-03 2.51E-03 2.48E-03 Ni-63 2.37E-01 2.25E-01 2.53E-01 2.55E-01 3.47E-01 3.43E-01 Co-60 6.89E-03 7.79E-03 6.93E-03 6.99E-03 7.96E-03 1.15E-02 Tc-99 8.18E-03 7.09E-03 5.66E-04 4.68E-04 7.30E-04 5.23E-04 Sr-90 2.70E-03 9.22E-03 1.95E-03 2.79E-03 2.13E-03 2.51E-03 Sb-125 9.18E-05 3.12E-04 8.46E-05 1.81E-04 1.34E-04 1.65E-04 Cs-134 9.58E-05 2.05E-04 9.54E-05 1.16E-04 1.59E-04 1.67E-04 Cs-137 6.67E-01 6.08E-01 6.72E-01 6.55E-01 5.62E-01 5.55E-01 Ce-144 3.82E-06 1.91E-05 1.23E-06 3.38E-06 1.83E-06 3.36E-06 Eu-152 5.41E-04 1.35E-03 4.03E-04 5.09E-04 5.00E-04 7.15E-04 Eu-154 7.08E-05 2.33E-03 4.85E-05 6.67E-05 7.22E-05 1.13E-04 Eu-155 1.85E-04 3.45E-04 1.67E-04 1.69E-04 2.75E-04 2.72E-04 Pu-238 2.48E-05 3.86E-04 2.48E-05 3.69E-05 2.62E-05 3.01E-05 Pu-239/240 2.06E-05 9.74E-05 2.50E-05 3.01E-05 2.47E-05 2.47E-05 Pu-241 3.03E-03 4.09E-03 3.16E-03 3.19E-03 4.82E-03 4.77E-03 Am-241 7.47E-05 9.73E-05 1.01E-04 1.02E-04 1.34E-04 1.32E-04 Cm-243/244 2.35E-05 8.54E-05 1.06E-05 1.07E-05 1.53E-05 1.51E-05 Np-237 7.28E-07 7.28E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1. The first was to calculate the radionuclide activity fraction, fAi,j,k, for each sample, j, each radionuclide, i, within each population, k, from the reported decay corrected radionuclide activity concentrations, Ci,j,k, using Equation 2 and then calculating the average activity fraction, fAi,j,k, for each radionuclide, i, and population, k, of N samples using Equation 3.

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 20 of 54

, , Equation 2

, , =

() , ,

() , ,

Equation 3

, , =

2. The second was to calculate the 75th percentile of the population of samples from Equation 2 above. Once the 75th percentile fraction were calculated for each radionuclide, fi,k,.75, the data set was re-normalized to determine the percentile-based activity fractions, fAi,k,.75 using Equation 4.

, , ,. Equation 4

, ,. =

() , , ,.

3. The third was to calculate the individual radionuclide ratios to Cs-137 for each sample, Ri,Cs-137,j, calculate the 75th percentile for the sample group, Ri,Cs-137,k, .75 then renormalize to determine the activity fractions, fRAi,k,.75 using Equation 5.

, , ,. Equation 5

, ,. =

() , , ,.

The analyses described above remove the activity weighting and give equal statistical weight to each of the sample results. The results of the three methods are provided within each of the following subsections.

6.1.1 CONTAINMENT SAMPLE POPULATION NUCLIDE FRACTIONS Tables 9 through 11 provide the radionuclide activity fractions for all sample data that will represent the Containment Building (CB) mixture. The data is subdivided into three tables to allow for convenient inspection of all 22 radionuclides. The last three rows of these tables provide the average fraction, the 75th percentile of each fractional data set, and the normalized 75 th data set as described above. Tables 12 through 14 provide the radionuclide activity ratios to Cs-137 for all sample data that will represent the CB fractions. Similar to the previous three tables, the data is subdivided into three tables to allow for convenient inspection of all 22 radionuclides. The last two rows of these tables provide the 75 th percentile of each ratio data set, and the normalized 75 th data set as described above.

In the following tables, NA indicates Not Analyzed for the 37 samples in which Np-237 was not analyzed.

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 21 of 54 Table 9: Radionuclide Activity Fractions, fAi,j and fAi,j,.75, Using Sample Data for Containment Building Samples, First Set of Radionuclides Sample ID H-3 C-14 Fe-55 Co-58 Ni-59 Ni-63 Co-60 Tc-99 1100X-1-CJ-FCV1-005 9.13E-02 1.15E-01 5.26E-02 0.00E+00 8.27E-04 7.41E-02 3.39E-02 3.33E-06 1100X-1-CJ-WCV1-003 5.60E-02 2.01E-01 8.25E-02 0.00E+00 0.00E+00 8.04E-02 4.08E-02 7.56E-05 1100X-1-CJ-WCV1-004 1.33E-01 6.82E-02 4.86E-02 8.33E-14 2.00E-03 1.45E-01 6.05E-02 1.65E-04 1200X-1-CJ-FCV1-001 2.34E-01 6.56E-01 0.00E+00 9.56E-15 3.05E-05 5.33E-02 8.64E-03 2.94E-04 1200X-1-CJ-FCV1-002 1.27E-01 6.41E-01 2.49E-04 0.00E+00 0.00E+00 1.25E-01 8.77E-03 9.87E-05 1200X-1-CJ-FCV1-003 1.40E-01 5.46E-01 0.00E+00 3.33E-16 6.13E-04 5.33E-02 4.84E-03 1.54E-04 1200X-1-CJ-FCV1-010 5.21E-01 1.18E-01 0.00E+00 0.00E+00 0.00E+00 1.09E-01 4.31E-03 3.30E-04 1200X-1-CJ-FCV1-018 2.50E-01 6.40E-01 4.77E-04 8.84E-16 0.00E+00 2.22E-02 3.07E-04 3.45E-05 1200X-1-CJ-FCV1-023 2.98E-02 1.24E-02 0.00E+00 2.11E-15 1.68E-03 1.66E-01 5.09E-03 3.21E-05 1200X-1-CJ-FCV1-025 1.17E-01 6.54E-01 0.00E+00 0.00E+00 5.60E-05 2.76E-02 1.24E-03 5.89E-05 1200X-1-CJ-FCV1-027 6.25E-02 2.72E-01 0.00E+00 4.38E-15 1.51E-04 1.61E-02 2.25E-03 0.00E+00 1200X-1-CJ-WCV1-005 2.19E-01 6.79E-01 0.00E+00 0.00E+00 4.43E-05 1.96E-02 9.68E-04 2.09E-04 1200X-1-CJ-WCV1-006 2.36E-03 9.88E-01 0.00E+00 5.56E-13 1.27E-04 7.75E-04 1.26E-04 0.00E+00 1200X-1-CJ-WCV1-008 6.22E-02 8.83E-01 0.00E+00 5.23E-11 2.07E-03 1.89E-02 1.90E-03 4.39E-04 1200X-1-CJ-WCV1-009 5.56E-02 8.56E-01 0.00E+00 6.05E-15 1.67E-04 3.37E-03 1.29E-04 2.16E-05 1200X-1-CJ-WCV1-011 4.99E-02 8.21E-01 0.00E+00 1.04E-11 0.00E+00 2.94E-03 1.92E-04 5.68E-04 1200X-1-CJ-WCV1-012 6.48E-02 7.84E-01 0.00E+00 5.20E-11 4.90E-04 3.31E-02 6.70E-04 4.52E-03 1200X-1-CJ-WCV1-015 6.75E-02 8.71E-01 0.00E+00 0.00E+00 0.00E+00 2.49E-03 7.04E-04 4.19E-03 1200X-1-CJ-WCV1-028 6.75E-02 1.32E-01 0.00E+00 4.95E-12 8.03E-03 2.59E-02 2.47E-02 4.38E-02 1200X-1-CJ-WCV1-029 4.73E-02 8.98E-01 0.00E+00 0.00E+00 0.00E+00 5.23E-03 5.88E-04 1.20E-02 1300X-1-CJ-FCV1-003 4.40E-02 2.19E-01 0.00E+00 0.00E+00 0.00E+00 2.18E-02 1.20E-03 6.89E-05 1300X-1-CJ-FCV1-005 2.52E-02 9.33E-01 0.00E+00 2.08E-12 1.46E-04 3.99E-03 4.95E-04 0.00E+00 1300X-1-CJ-FCV1-006 1.22E-01 1.56E-01 9.08E-04 5.54E-15 0.00E+00 3.07E-02 9.48E-04 0.00E+00 1300X-1-CJ-FCV1-008 3.76E-02 2.03E-01 3.45E-04 1.20E-14 1.13E-03 2.70E-02 8.68E-04 6.78E-05 1300X-1-CJ-WCV1-007 3.71E-02 8.83E-01 0.00E+00 0.00E+00 0.00E+00 6.93E-03 2.10E-04 3.22E-03 1400X-1-CJ-FCV1-002 2.36E-02 7.59E-01 0.00E+00 5.97E-17 1.80E-04 4.12E-03 1.27E-04 1.53E-05 1400X-1-CJ-FCV1-021 1.39E-01 8.27E-01 0.00E+00 0.00E+00 7.43E-05 2.43E-03 5.83E-04 7.03E-05 Average 1.05E-01 5.49E-01 6.88E-03 4.54E-12 6.60E-04 4.00E-02 7.59E-03 2.61E-03 75 Percentile Frac. 1.30E-01 8.41E-01 1.25E-04 4.76E-14 5.51E-04 5.33E-02 4.96E-03 3.85E-04 75 Perc. Norm. Frac. 9.72E-02 6.28E-01 9.31E-05 3.56E-14 4.12E-04 3.98E-02 3.70E-03 2.87E-04 Table 10: Radionuclide Activity Fractions, fAi,j and fAi,j,.75, Using Sample Data for Containment Building Samples, Second Set of Radionuclides Sample ID Sr-90 Sb-125 Cs-134 Cs-137 Ce-144 Eu-152 Eu-154 1100X-1-CJ-FCV1-005 3.91E-04 0.00E+00 1.05E-03 3.09E-01 0.00E+00 2.94E-01 2.69E-02 1100X-1-CJ-WCV1-003 8.31E-04 0.00E+00 1.73E-03 1.33E-01 2.21E-05 3.69E-01 3.37E-02 1100X-1-CJ-WCV1-004 5.43E-04 0.00E+00 7.65E-04 2.96E-01 0.00E+00 2.23E-01 2.12E-02 1200X-1-CJ-FCV1-001 2.58E-04 4.73E-05 5.05E-06 4.57E-02 3.77E-07 0.00E+00 1.15E-04 1200X-1-CJ-FCV1-002 4.49E-04 0.00E+00 1.14E-05 9.66E-02 0.00E+00 2.88E-05 0.00E+00 1200X-1-CJ-FCV1-003 1.01E-03 1.62E-05 3.48E-05 2.53E-01 1.79E-07 0.00E+00 8.04E-05 1200X-1-CJ-FCV1-010 3.51E-04 0.00E+00 5.70E-06 2.45E-01 1.88E-06 1.37E-03 8.22E-06 1200X-1-CJ-FCV1-018 1.55E-04 9.41E-05 7.13E-06 8.65E-02 0.00E+00 4.48E-06 0.00E+00 1200X-1-CJ-FCV1-023 2.26E-03 1.96E-04 6.40E-05 7.80E-01 1.26E-06 2.87E-05 1.26E-05 1200X-1-CJ-FCV1-025 4.30E-04 1.44E-04 1.07E-05 1.99E-01 1.18E-06 0.00E+00 0.00E+00 1200X-1-CJ-FCV1-027 1.51E-04 5.57E-05 6.62E-05 6.46E-01 0.00E+00 4.81E-05 0.00E+00 1200X-1-CJ-WCV1-005 8.64E-05 6.81E-05 3.68E-06 7.60E-02 2.44E-06 0.00E+00 1.57E-04 1200X-1-CJ-WCV1-006 7.65E-05 1.30E-07 2.87E-06 7.90E-03 1.45E-06 3.96E-04 1.62E-05 1200X-1-CJ-WCV1-008 2.10E-04 0.00E+00 4.79E-06 2.08E-02 1.74E-05 1.81E-03 1.65E-04 1200X-1-CJ-WCV1-009 2.28E-05 0.00E+00 2.06E-06 8.35E-02 0.00E+00 3.13E-04 4.68E-05 1200X-1-CJ-WCV1-011 2.21E-04 0.00E+00 2.20E-05 1.15E-01 1.64E-05 3.07E-03 1.94E-04 1200X-1-CJ-WCV1-012 5.48E-04 2.32E-04 2.35E-05 1.00E-01 8.35E-06 4.84E-03 2.32E-04 1200X-1-CJ-WCV1-015 2.85E-04 0.00E+00 3.36E-05 4.85E-02 5.27E-06 2.51E-03 5.21E-04 1200X-1-CJ-WCV1-028 0.00E+00 2.54E-04 3.15E-04 6.76E-01 0.00E+00 6.15E-03 1.58E-04 1200X-1-CJ-WCV1-029 3.65E-05 9.21E-05 6.13E-05 3.15E-02 0.00E+00 3.40E-03 7.80E-05

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 22 of 54 Sample ID Sr-90 Sb-125 Cs-134 Cs-137 Ce-144 Eu-152 Eu-154 1300X-1-CJ-FCV1-003 6.74E-05 2.08E-05 6.72E-05 7.14E-01 0.00E+00 0.00E+00 6.70E-06 1300X-1-CJ-FCV1-005 3.15E-05 5.64E-06 1.20E-05 3.63E-02 6.68E-07 5.67E-05 2.59E-06 1300X-1-CJ-FCV1-006 1.88E-04 6.87E-05 9.00E-05 6.86E-01 2.63E-07 0.00E+00 0.00E+00 1300X-1-CJ-FCV1-008 8.19E-04 2.65E-05 4.23E-05 7.27E-01 2.53E-06 9.06E-04 1.37E-04 1300X-1-CJ-WCV1-007 2.41E-04 0.00E+00 1.94E-05 6.70E-02 0.00E+00 8.71E-04 0.00E+00 1400X-1-CJ-FCV1-002 7.78E-04 6.80E-06 2.16E-06 2.12E-01 5.61E-07 0.00E+00 1.64E-05 1400X-1-CJ-FCV1-021 0.00E+00 0.00E+00 0.00E+00 3.13E-02 0.00E+00 1.48E-04 2.31E-05 Average 3.87E-04 4.92E-05 1.65E-04 2.49E-01 3.05E-06 3.37E-02 3.10E-03 75 Percentile Frac. 4.96E-04 6.84E-05 6.51E-05 3.02E-01 2.16E-06 2.79E-03 1.62E-04 75 Perc. Norm. Frac. 3.70E-04 5.11E-05 4.86E-05 2.26E-01 1.61E-06 2.08E-03 1.21E-04 Table 11: Radionuclide Activity Fractions, fAi,j and fAi,j,.75, Using Sample Data for Containment Building Samples, Third Set of Radionuclides Sample ID Eu-155 Pu-238 Pu-239/240 Pu-241 Am-241 Cm-243/244 Np-237 1100X-1-CJ-FCV1-005 5.19E-04 2.12E-05 9.08E-05 5.30E-04 2.97E-05 6.67E-06 NA 1100X-1-CJ-WCV1-003 5.71E-04 2.55E-05 1.08E-04 5.31E-04 3.37E-05 3.82E-06 5.05E-07 1100X-1-CJ-WCV1-004 1.78E-04 8.92E-05 1.11E-04 1.13E-03 1.74E-04 4.08E-05 NA 1200X-1-CJ-FCV1-001 3.23E-05 1.84E-05 0.00E+00 2.09E-03 4.27E-05 1.98E-06 NA 1200X-1-CJ-FCV1-002 0.00E+00 5.95E-05 2.01E-05 9.40E-04 1.28E-04 3.44E-05 NA 1200X-1-CJ-FCV1-003 0.00E+00 1.58E-05 1.35E-05 9.72E-04 3.84E-05 9.22E-06 NA 1200X-1-CJ-FCV1-010 1.47E-05 1.22E-05 0.00E+00 1.43E-03 4.62E-05 9.06E-06 NA 1200X-1-CJ-FCV1-018 0.00E+00 8.03E-06 0.00E+00 7.03E-04 1.24E-05 1.08E-06 NA 1200X-1-CJ-FCV1-023 0.00E+00 1.05E-04 6.12E-05 1.74E-03 1.65E-04 1.52E-05 NA 1200X-1-CJ-FCV1-025 0.00E+00 4.30E-07 2.45E-06 6.69E-04 1.05E-05 0.00E+00 NA 1200X-1-CJ-FCV1-027 0.00E+00 1.25E-06 1.80E-06 6.51E-04 9.37E-06 2.44E-07 NA 1200X-1-CJ-WCV1-005 7.30E-05 7.27E-06 0.00E+00 3.90E-03 6.03E-05 0.00E+00 NA 1200X-1-CJ-WCV1-006 3.09E-06 3.71E-07 1.15E-06 5.75E-04 1.42E-05 0.00E+00 0.00E+00 1200X-1-CJ-WCV1-008 0.00E+00 0.00E+00 0.00E+00 8.32E-03 1.85E-05 1.19E-05 0.00E+00 1200X-1-CJ-WCV1-009 0.00E+00 4.97E-06 0.00E+00 8.69E-04 2.05E-05 5.99E-06 NA 1200X-1-CJ-WCV1-011 5.51E-05 0.00E+00 1.18E-05 6.20E-03 9.17E-05 0.00E+00 5.97E-06 1200X-1-CJ-WCV1-012 0.00E+00 6.83E-06 3.17E-05 5.87E-03 0.00E+00 1.07E-04 0.00E+00 1200X-1-CJ-WCV1-015 0.00E+00 0.00E+00 3.40E-05 2.59E-03 4.17E-05 1.26E-05 0.00E+00 1200X-1-CJ-WCV1-028 7.52E-04 4.44E-05 0.00E+00 1.44E-02 0.00E+00 1.09E-04 0.00E+00 1200X-1-CJ-WCV1-029 3.33E-05 0.00E+00 0.00E+00 2.01E-03 2.40E-05 4.64E-05 1.59E-05 1300X-1-CJ-FCV1-003 3.95E-05 3.27E-06 1.75E-06 5.34E-04 7.11E-06 0.00E+00 NA 1300X-1-CJ-FCV1-005 1.99E-05 3.27E-06 2.49E-06 9.97E-04 3.38E-05 1.88E-05 9.56E-07 1300X-1-CJ-FCV1-006 0.00E+00 5.64E-06 5.93E-07 2.76E-03 2.96E-05 5.35E-06 NA 1300X-1-CJ-FCV1-008 2.40E-05 1.89E-05 1.55E-05 9.72E-04 4.88E-05 1.06E-06 NA 1300X-1-CJ-WCV1-007 9.23E-05 0.00E+00 8.01E-06 9.05E-04 0.00E+00 2.20E-05 0.00E+00 1400X-1-CJ-FCV1-002 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.58E-07 0.00E+00 NA 1400X-1-CJ-FCV1-021 2.05E-05 6.71E-06 1.73E-05 0.00E+00 3.37E-06 0.00E+00 NA Average 8.99E-05 1.70E-05 1.97E-05 2.31E-03 4.02E-05 1.72E-05 2.33E-06 75 Percentile Frac. 4.73E-05 1.86E-05 1.87E-05 2.34E-03 4.44E-05 1.70E-05 8.43E-07 75 Perc. Norm. Frac. 3.53E-05 1.39E-05 1.40E-05 1.75E-03 3.32E-05 1.27E-05 6.29E-07 Table 12: Radionuclide Activity Ratios to Cs-137, fRAi,j, Using Combined Sample Data for Containment Building, First Set of Radionuclides Sample ID H-3 C-14 Fe-55 Co-58 Ni-59 Ni-63 Co-60 Tc-99 1100X-1-CJ-FCV1-005 2.95E-01 3.72E-01 1.70E-01 0.00E+00 2.67E-03 2.40E-01 1.10E-01 1.08E-05 1100X-1-CJ-WCV1-003 4.20E-01 1.51E+00 6.19E-01 0.00E+00 0.00E+00 6.04E-01 3.06E-01 5.68E-04 1100X-1-CJ-WCV1-004 4.50E-01 2.31E-01 1.64E-01 2.82E-13 6.75E-03 4.91E-01 2.05E-01 5.58E-04 1200X-1-CJ-FCV1-001 5.11E+00 1.43E+01 0.00E+00 2.09E-13 6.68E-04 1.17E+00 1.89E-01 6.42E-03 1200X-1-CJ-FCV1-002 1.32E+00 6.63E+00 2.58E-03 0.00E+00 0.00E+00 1.29E+00 9.08E-02 1.02E-03 1200X-1-CJ-FCV1-003 5.54E-01 2.16E+00 0.00E+00 1.32E-15 2.42E-03 2.11E-01 1.91E-02 6.11E-04 1200X-1-CJ-FCV1-010 2.13E+00 4.80E-01 0.00E+00 0.00E+00 0.00E+00 4.46E-01 1.76E-02 1.35E-03

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 23 of 54 Sample ID H-3 C-14 Fe-55 Co-58 Ni-59 Ni-63 Co-60 Tc-99 1200X-1-CJ-FCV1-018 2.89E+00 7.39E+00 5.52E-03 1.02E-14 0.00E+00 2.56E-01 3.55E-03 3.98E-04 1200X-1-CJ-FCV1-023 3.81E-02 1.59E-02 0.00E+00 2.71E-15 2.15E-03 2.13E-01 6.52E-03 4.12E-05 1200X-1-CJ-FCV1-025 5.86E-01 3.29E+00 0.00E+00 0.00E+00 2.81E-04 1.38E-01 6.21E-03 2.96E-04 1200X-1-CJ-FCV1-027 9.67E-02 4.21E-01 0.00E+00 6.78E-15 2.33E-04 2.49E-02 3.49E-03 0.00E+00 1200X-1-CJ-WCV1-005 2.89E+00 8.94E+00 0.00E+00 0.00E+00 5.82E-04 2.58E-01 1.27E-02 2.75E-03 1200X-1-CJ-WCV1-006 2.98E-01 1.25E+02 0.00E+00 7.04E-11 1.61E-02 9.81E-02 1.59E-02 0.00E+00 1200X-1-CJ-WCV1-008 2.99E+00 4.25E+01 0.00E+00 2.52E-09 9.98E-02 9.09E-01 9.14E-02 2.11E-02 1200X-1-CJ-WCV1-009 6.65E-01 1.03E+01 0.00E+00 7.25E-14 2.00E-03 4.04E-02 1.54E-03 2.58E-04 1200X-1-CJ-WCV1-011 4.33E-01 7.13E+00 0.00E+00 9.06E-11 0.00E+00 2.55E-02 1.66E-03 4.93E-03 1200X-1-CJ-WCV1-012 6.45E-01 7.81E+00 0.00E+00 5.18E-10 4.88E-03 3.29E-01 6.67E-03 4.50E-02 1200X-1-CJ-WCV1-015 1.39E+00 1.79E+01 0.00E+00 0.00E+00 0.00E+00 5.13E-02 1.45E-02 8.63E-02 1200X-1-CJ-WCV1-028 9.99E-02 1.96E-01 0.00E+00 7.33E-12 1.19E-02 3.84E-02 3.65E-02 6.48E-02 1200X-1-CJ-WCV1-029 1.50E+00 2.85E+01 0.00E+00 0.00E+00 0.00E+00 1.66E-01 1.87E-02 3.81E-01 1300X-1-CJ-FCV1-003 6.17E-02 3.06E-01 0.00E+00 0.00E+00 0.00E+00 3.05E-02 1.68E-03 9.65E-05 1300X-1-CJ-FCV1-005 6.92E-01 2.57E+01 0.00E+00 5.74E-11 4.02E-03 1.10E-01 1.36E-02 0.00E+00 1300X-1-CJ-FCV1-006 1.78E-01 2.27E-01 1.32E-03 8.08E-15 0.00E+00 4.48E-02 1.38E-03 0.00E+00 1300X-1-CJ-FCV1-008 5.18E-02 2.79E-01 4.75E-04 1.65E-14 1.56E-03 3.71E-02 1.19E-03 9.32E-05 1300X-1-CJ-WCV1-007 5.54E-01 1.32E+01 0.00E+00 0.00E+00 0.00E+00 1.03E-01 3.13E-03 4.81E-02 1400X-1-CJ-FCV1-002 1.11E-01 3.58E+00 0.00E+00 2.81E-16 8.50E-04 1.94E-02 5.97E-04 7.20E-05 1400X-1-CJ-FCV1-021 4.44E+00 2.64E+01 0.00E+00 0.00E+00 2.38E-03 7.77E-02 1.87E-02 2.25E-03 75th Percentile Each 1.45E+00 1.38E+01 2.37E-04 2.45E-13 2.55E-03 2.94E-01 2.78E-02 5.68E-03 Sample 75th Normalized Fraction 8.70E-02 8.27E-01 1.43E-05 1.47E-14 1.53E-04 1.76E-02 1.67E-03 3.41E-04 Table 13: Radionuclide Activity Ratios to Cs-137, fRAi,j, Using Combined Sample Data for Containment Building, Second Set of Radionuclides Sample ID Sr-90 Sb-125 Cs-134 Cs-137 Ce-144 Eu-152 Eu-154 1100X-1-CJ-FCV1-005 1.26E-03 0.00E+00 3.39E-03 1.00E+00 0.00E+00 9.50E-01 8.69E-02 1100X-1-CJ-WCV1-003 6.24E-03 0.00E+00 1.30E-02 1.00E+00 1.66E-04 2.77E+00 2.53E-01 1100X-1-CJ-WCV1-004 1.84E-03 0.00E+00 2.59E-03 1.00E+00 0.00E+00 7.53E-01 7.16E-02 1200X-1-CJ-FCV1-001 5.64E-03 1.04E-03 1.10E-04 1.00E+00 8.25E-06 0.00E+00 2.51E-03 1200X-1-CJ-FCV1-002 4.65E-03 0.00E+00 1.18E-04 1.00E+00 0.00E+00 2.98E-04 0.00E+00 1200X-1-CJ-FCV1-003 3.99E-03 6.40E-05 1.38E-04 1.00E+00 7.10E-07 0.00E+00 3.18E-04 1200X-1-CJ-FCV1-010 1.43E-03 0.00E+00 2.33E-05 1.00E+00 7.68E-06 5.58E-03 3.36E-05 1200X-1-CJ-FCV1-018 1.79E-03 1.09E-03 8.24E-05 1.00E+00 0.00E+00 5.18E-05 0.00E+00 1200X-1-CJ-FCV1-023 2.89E-03 2.52E-04 8.20E-05 1.00E+00 1.61E-06 3.67E-05 1.62E-05 1200X-1-CJ-FCV1-025 2.16E-03 7.26E-04 5.37E-05 1.00E+00 5.94E-06 0.00E+00 0.00E+00 1200X-1-CJ-FCV1-027 2.33E-04 8.63E-05 1.02E-04 1.00E+00 0.00E+00 7.45E-05 0.00E+00 1200X-1-CJ-WCV1-005 1.14E-03 8.96E-04 4.84E-05 1.00E+00 3.21E-05 0.00E+00 2.06E-03 1200X-1-CJ-WCV1-006 9.69E-03 1.64E-05 3.64E-04 1.00E+00 1.84E-04 5.01E-02 2.06E-03 1200X-1-CJ-WCV1-008 1.01E-02 0.00E+00 2.31E-04 1.00E+00 8.35E-04 8.70E-02 7.95E-03 1200X-1-CJ-WCV1-009 2.73E-04 0.00E+00 2.46E-05 1.00E+00 0.00E+00 3.75E-03 5.60E-04 1200X-1-CJ-WCV1-011 1.92E-03 0.00E+00 1.91E-04 1.00E+00 1.42E-04 2.66E-02 1.69E-03 1200X-1-CJ-WCV1-012 5.45E-03 2.31E-03 2.34E-04 1.00E+00 8.32E-05 4.82E-02 2.31E-03 1200X-1-CJ-WCV1-015 5.88E-03 0.00E+00 6.92E-04 1.00E+00 1.09E-04 5.18E-02 1.07E-02 1200X-1-CJ-WCV1-028 0.00E+00 3.76E-04 4.66E-04 1.00E+00 0.00E+00 9.09E-03 2.34E-04 1200X-1-CJ-WCV1-029 1.16E-03 2.92E-03 1.95E-03 1.00E+00 0.00E+00 1.08E-01 2.48E-03 1300X-1-CJ-FCV1-003 9.45E-05 2.92E-05 9.42E-05 1.00E+00 0.00E+00 0.00E+00 9.39E-06 1300X-1-CJ-FCV1-005 8.66E-04 1.55E-04 3.30E-04 1.00E+00 1.84E-05 1.56E-03 7.12E-05 1300X-1-CJ-FCV1-006 2.73E-04 1.00E-04 1.31E-04 1.00E+00 3.83E-07 0.00E+00 0.00E+00 1300X-1-CJ-FCV1-008 1.13E-03 3.64E-05 5.82E-05 1.00E+00 3.48E-06 1.25E-03 1.89E-04 1300X-1-CJ-WCV1-007 3.60E-03 0.00E+00 2.89E-04 1.00E+00 0.00E+00 1.30E-02 0.00E+00 1400X-1-CJ-FCV1-002 3.66E-03 3.20E-05 1.02E-05 1.00E+00 2.64E-06 0.00E+00 7.74E-05 1400X-1-CJ-FCV1-021 0.00E+00 0.00E+00 0.00E+00 1.00E+00 0.00E+00 4.72E-03 7.39E-04 75th Percentile Each 4.32E-03 3.14E-04 3.47E-04 1.00E+00 2.53E-05 4.92E-02 2.39E-03 Sample 75th Normalized Fraction 2.59E-04 1.89E-05 2.08E-05 6.01E-02 1.52E-06 2.95E-03 1.44E-04

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 24 of 54 Table 14: Radionuclide Activity Ratios to Cs-137, fRAi,j, Using Combined Sample Data for Containment Building, Third Set of Radionuclides Sample ID Eu-155 Pu-238 Pu-239/240 Pu-241 Am-241 Cm-243/244 Np-237 1100X-1-CJ-FCV1-005 1.68E-03 6.85E-05 2.94E-04 1.71E-03 9.61E-05 2.16E-05 NA 1100X-1-CJ-WCV1-003 4.28E-03 1.91E-04 8.12E-04 3.99E-03 2.53E-04 2.87E-05 3.79E-06 1100X-1-CJ-WCV1-004 6.02E-04 3.02E-04 3.75E-04 3.84E-03 5.88E-04 1.38E-04 NA 1200X-1-CJ-FCV1-001 7.06E-04 4.02E-04 0.00E+00 4.56E-02 9.33E-04 4.34E-05 NA 1200X-1-CJ-FCV1-002 0.00E+00 6.16E-04 2.08E-04 9.73E-03 1.33E-03 3.56E-04 NA 1200X-1-CJ-FCV1-003 0.00E+00 6.23E-05 5.35E-05 3.85E-03 1.52E-04 3.65E-05 NA 1200X-1-CJ-FCV1-010 6.01E-05 4.97E-05 0.00E+00 5.86E-03 1.89E-04 3.70E-05 NA 1200X-1-CJ-FCV1-018 0.00E+00 9.28E-05 0.00E+00 8.13E-03 1.43E-04 1.24E-05 NA 1200X-1-CJ-FCV1-023 0.00E+00 1.35E-04 7.84E-05 2.22E-03 2.12E-04 1.95E-05 NA 1200X-1-CJ-FCV1-025 0.00E+00 2.16E-06 1.23E-05 3.36E-03 5.26E-05 0.00E+00 NA 1200X-1-CJ-FCV1-027 0.00E+00 1.94E-06 2.78E-06 1.01E-03 1.45E-05 3.77E-07 NA 1200X-1-CJ-WCV1-005 9.60E-04 9.57E-05 0.00E+00 5.13E-02 7.94E-04 0.00E+00 NA 1200X-1-CJ-WCV1-006 3.91E-04 4.69E-05 1.45E-04 7.29E-02 1.80E-03 0.00E+00 0.00E+00 1200X-1-CJ-WCV1-008 0.00E+00 0.00E+00 0.00E+00 4.00E-01 8.90E-04 0.00E+00 0.00E+00 1200X-1-CJ-WCV1-009 0.00E+00 5.95E-05 0.00E+00 1.04E-02 2.45E-04 7.18E-05 NA 1200X-1-CJ-WCV1-011 4.78E-04 0.00E+00 1.03E-04 5.38E-02 7.96E-04 0.00E+00 5.18E-05 1200X-1-CJ-WCV1-012 0.00E+00 6.80E-05 3.15E-04 5.84E-02 0.00E+00 1.07E-03 0.00E+00 1200X-1-CJ-WCV1-015 0.00E+00 0.00E+00 7.00E-04 5.34E-02 8.60E-04 2.60E-04 0.00E+00 1200X-1-CJ-WCV1-028 1.11E-03 6.58E-05 0.00E+00 2.13E-02 0.00E+00 1.62E-04 0.00E+00 1200X-1-CJ-WCV1-029 1.06E-03 0.00E+00 0.00E+00 6.37E-02 7.63E-04 1.47E-03 5.05E-04 1300X-1-CJ-FCV1-003 5.53E-05 4.58E-06 2.46E-06 7.48E-04 9.96E-06 0.00E+00 NA 1300X-1-CJ-FCV1-005 5.49E-04 9.00E-05 6.84E-05 2.74E-02 9.30E-04 5.17E-04 2.63E-05 1300X-1-CJ-FCV1-006 0.00E+00 8.22E-06 8.64E-07 4.03E-03 4.31E-05 7.79E-06 NA 1300X-1-CJ-FCV1-008 3.30E-05 2.60E-05 2.13E-05 1.34E-03 6.71E-05 1.46E-06 NA 1300X-1-CJ-WCV1-007 1.38E-03 0.00E+00 1.19E-04 1.35E-02 0.00E+00 3.28E-04 0.00E+00 1400X-1-CJ-FCV1-002 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.10E-06 0.00E+00 NA 1400X-1-CJ-FCV1-021 6.54E-04 2.14E-04 5.54E-04 0.00E+00 1.08E-04 0.00E+00 NA 75th Percentile Each 6.80E-04 9.42E-05 1.77E-04 4.85E-02 7.95E-04 2.11E-04 2.07E-05 Sample 75th Normalized Fraction 4.09E-05 5.66E-06 1.06E-05 2.91E-03 4.78E-05 1.27E-05 1.24E-06 Table 15 summarizes the radionuclide activity fractions using the three methods described above.

Table 15: Radionuclide Activity Fractions for Containment Building Sample Population Using Three Methods 75 Percentile of the Activity 75th Percentile of Average the Individual Average Activity Fractions, Sample Ratios to Cs-Nuclide Fractions, fAi, fAi,,.75 137, fRAi,.75 H-3 1.05E-01 9.72E-02 8.70E-02 C-14 5.49E-01 6.28E-01 8.27E-01 Fe-55 6.88E-03 9.31E-05 1.43E-05 Co-58 4.54E-12 3.56E-14 1.47E-14 Ni-59 6.60E-04 4.12E-04 1.53E-04 Ni-63 4.00E-02 3.98E-02 1.76E-02 Co-60 7.59E-03 3.70E-03 1.67E-03 Tc-99 2.61E-03 2.87E-04 3.41E-04 Sr-90 3.87E-04 3.70E-04 2.59E-04 Sb-125 4.92E-05 5.11E-05 1.89E-05 Cs-134 1.65E-04 4.86E-05 2.08E-05

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 25 of 54 Cs-137 2.49E-01 2.26E-01 6.01E-02 Ce-144 3.05E-06 1.61E-06 1.52E-06 Eu-152 3.37E-02 2.08E-03 2.95E-03 Eu-154 3.10E-03 1.21E-04 1.44E-04 Eu-155 8.99E-05 3.53E-05 4.09E-05 Pu-238 1.70E-05 1.39E-05 5.66E-06 Pu-239/240 1.97E-05 1.40E-05 1.06E-05 Pu-241 2.31E-03 1.75E-03 2.91E-03 Am-241 4.02E-05 3.32E-05 4.78E-05 Cm-243/244 1.72E-05 1.27E-05 1.27E-05 Np-237 2.33E-06 6.29E-07 1.24E-06 As can be seen from the above table, the FCS Containment Building concrete contains an unusually high average fraction of C-14 at 54.9%. The potential for cross contamination from this source term will be closely monitored throughout decommissioning.

6.1.2 AB/TB/RWPB SAMPLE POPULATION NUCLIDE FRACTIONS Tables 16 through 18 provide the radionuclide activity fractions for all sample data that will represent the Auxiliary Building, Turbine Building and Radioactive Waste Processing Building mixture. The data is subdivided into three tables to allow for convenient inspection of all 22 radionuclides. The last three rows of these tables provide the average fraction, the 75 th percentile of each fractional data set, and the normalized 75th data set as described above. Tables 19 through 21 provide the radionuclide activity ratios to Cs-137 for all sample data that will represent the AB/TB/RWPB fractions. Similar to the previous set of tables, the data is subdivided into three tables to allow for convenient inspection of all 22 radionuclides. The last two rows of these tables provide the average fraction, the 75 th percentile of each ratio data set, and the normalized 75th data set as described above.

In the following tables, NA indicates Not Analyzed for the 37 samples in which Np-237 was not analyzed.

Table 16: Radionuclide Activity Fractions, fAi,j and fAi,j,.75, Using All ores Sample Data for AB/TB/RWPB Samples, First Set of Radionuclides Sample ID H-3 C-14 Fe-55 Co-58 Ni-59 Ni-63 Co-60 Tc-99 2100X-1-CJ-FCV1-001 3.07E-03 4.59E-03 0.00E+00 1.70E-11 2.39E-03 4.45E-01 6.40E-04 7.18E-04 2100X-1-CJ-FCV1-003 2.68E-03 5.85E-03 1.51E-03 1.40E-13 6.51E-03 8.06E-01 4.69E-04 5.64E-06 2100X-1-CJ-FCV1-005 2.12E-02 1.83E-02 0.00E+00 0.00E+00 0.00E+00 5.13E-02 7.08E-04 2.37E-04 2100X-1-CJ-FCV1-006 1.32E-01 1.84E-02 0.00E+00 3.36E-14 0.00E+00 1.99E-01 7.22E-03 7.33E-04 2100X-1-CJ-FCV1-011 3.79E-02 2.86E-02 0.00E+00 0.00E+00 3.16E-03 4.65E-01 1.40E-02 4.35E-02 2100X-1-CJ-FCV1-014 3.96E-03 4.02E-02 0.00E+00 0.00E+00 0.00E+00 2.35E-01 2.06E-03 1.33E-01 2200X-1-CJ-FCV1-006 2.42E-03 3.29E-02 0.00E+00 7.73E-12 1.17E-03 1.11E-01 6.00E-04 1.59E-02 2200X-1-CJ-FCV1-008 5.13E-02 1.91E-02 0.00E+00 6.43E-15 0.00E+00 7.27E-02 1.56E-02 0.00E+00 2200X-1-CJ-FCV1-010 2.85E-02 2.06E-02 0.00E+00 0.00E+00 0.00E+00 2.92E-01 9.25E-03 0.00E+00 2200X-1-CJ-FCV1-020 3.36E-03 1.67E-03 5.68E-05 1.43E-15 4.13E-04 1.14E-01 8.07E-04 1.35E-04 2200X-1-CJ-FCV1-021 3.92E-03 2.63E-02 0.00E+00 0.00E+00 0.00E+00 2.31E-01 6.82E-04 0.00E+00 2200X-1-CJ-FCV1-022 6.59E-04 1.37E-03 5.18E-06 0.00E+00 3.93E-04 3.67E-02 3.17E-05 0.00E+00 2200X-1-CJ-FCV1-026 6.24E-04 7.13E-04 6.26E-06 3.28E-16 0.00E+00 9.87E-03 0.00E+00 0.00E+00 2200X-1-CJ-FCV1-030 3.76E-02 7.80E-02 3.46E-03 0.00E+00 7.02E-03 6.07E-01 5.75E-02 0.00E+00 2200X-1-CJ-FCV1-031 2.25E-01 6.81E-03 2.11E-03 2.88E-15 3.25E-03 2.97E-01 4.05E-03 0.00E+00 2200X-1-CJ-FCV1-035 7.52E-03 1.67E-02 1.92E-03 3.21E-15 2.79E-03 3.36E-01 6.54E-03 0.00E+00 2200X-1-CJ-FCV1-038 7.24E-03 3.02E-02 0.00E+00 5.04E-11 1.83E-03 4.89E-01 8.94E-03 0.00E+00

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 26 of 54 Sample ID H-3 C-14 Fe-55 Co-58 Ni-59 Ni-63 Co-60 Tc-99 2200X-1-CJ-FCV1-039 1.49E-02 4.00E-02 0.00E+00 0.00E+00 2.16E-03 5.00E-01 8.90E-03 0.00E+00 2200X-1-CJ-WCV1-009 6.67E-02 2.96E-01 0.00E+00 0.00E+00 1.70E-02 9.42E-02 2.90E-03 6.86E-03 2300X-1-CJ-FCV1-001 2.49E-04 1.16E-02 3.73E-04 0.00E+00 4.96E-04 4.35E-02 6.02E-05 0.00E+00 2300X-1-CJ-FCV1-002 9.74E-04 5.37E-03 2.51E-05 0.00E+00 6.69E-04 7.51E-02 3.51E-04 0.00E+00 2300X-1-CJ-FCV1-003 4.75E-04 2.21E-02 1.01E-03 0.00E+00 1.16E-03 1.47E-01 1.04E-02 2.17E-05 2300X-1-CJ-FCV1-005 1.07E-03 9.19E-03 1.19E-03 0.00E+00 1.16E-03 1.12E-01 3.26E-04 5.12E-05 2300X-1-CJ-FCV1-007 3.78E-02 6.18E-02 0.00E+00 8.28E-15 0.00E+00 6.70E-02 3.93E-03 0.00E+00 2300X-1-CJ-FCV1-010 0.00E+00 4.08E-02 2.54E-02 2.01E-09 0.00E+00 1.64E-01 1.62E-02 9.99E-03 2600X-1-CJ-FCV1-002 8.89E-02 2.15E-01 0.00E+00 0.00E+00 0.00E+00 1.62E-01 7.07E-03 1.34E-03 3100X-3-CJ-FCV1-006 0.00E+00 8.04E-01 7.09E-02 2.25E-13 0.00E+00 0.00E+00 2.55E-03 0.00E+00 3100X-3-CJ-FCV1-014 0.00E+00 4.60E-01 8.62E-03 2.02E-13 0.00E+00 4.13E-01 5.77E-03 0.00E+00 4100X-1-CJ-FCV1-004 0.00E+00 4.69E-01 2.46E-02 0.00E+00 4.18E-02 1.04E-01 6.89E-03 0.00E+00 4100X-1-CJ-FCV1-005 0.00E+00 1.30E-01 9.38E-02 6.63E-14 2.53E-05 5.86E-02 3.93E-02 0.00E+00 Average 2.60E-02 9.72E-02 7.83E-03 6.94E-11 3.11E-03 2.25E-01 7.79E-03 7.09E-03 75 Percentile Frac. 3.53E-02 5.66E-02 1.82E-03 5.81E-14 2.33E-03 3.26E-01 8.93E-03 5.98E-04 75 Perc. Norm. Frac. 2.76E-02 4.43E-02 1.42E-03 4.54E-14 1.82E-03 2.55E-01 6.99E-03 4.68E-04 Table 17: Radionuclide Activity Fractions, fAi,j and fAi,j,.75, Using All Sample Data for AB/TB/RWPB Samples, Second Set of Radionuclides Sample ID Sr-90 Sb-125 Cs-134 Cs-137 Ce-144 Eu-152 Eu-154 2100X-1-CJ-FCV1-001 4.29E-03 4.25E-05 1.40E-05 5.34E-01 0.00E+00 0.00E+00 7.50E-05 2100X-1-CJ-FCV1-003 5.10E-04 0.00E+00 1.06E-06 1.72E-01 0.00E+00 1.67E-04 5.39E-05 2100X-1-CJ-FCV1-005 2.01E-03 2.57E-04 3.29E-04 9.01E-01 3.50E-05 1.50E-03 0.00E+00 2100X-1-CJ-FCV1-006 2.42E-03 0.00E+00 8.38E-05 6.28E-01 2.79E-06 1.93E-03 3.24E-04 2100X-1-CJ-FCV1-011 1.33E-03 0.00E+00 1.18E-04 4.05E-01 0.00E+00 0.00E+00 1.92E-05 2100X-1-CJ-FCV1-014 1.08E-03 1.11E-04 4.59E-05 5.84E-01 1.30E-05 0.00E+00 0.00E+00 2200X-1-CJ-FCV1-006 6.84E-05 0.00E+00 4.35E-05 8.29E-01 0.00E+00 6.03E-04 6.13E-05 2200X-1-CJ-FCV1-008 1.18E-03 2.53E-04 1.20E-04 8.40E-01 1.87E-07 0.00E+00 8.86E-05 2200X-1-CJ-FCV1-010 2.54E-03 5.77E-04 0.00E+00 6.46E-01 0.00E+00 5.33E-04 0.00E+00 2200X-1-CJ-FCV1-020 5.50E-04 5.54E-05 2.27E-04 8.79E-01 1.69E-07 1.88E-04 2.91E-06 2200X-1-CJ-FCV1-021 1.55E-03 0.00E+00 0.00E+00 7.32E-01 4.82E-06 0.00E+00 0.00E+00 2200X-1-CJ-FCV1-022 9.07E-04 0.00E+00 1.61E-06 9.60E-01 0.00E+00 6.82E-05 0.00E+00 2200X-1-CJ-FCV1-026 1.04E-03 0.00E+00 1.26E-06 9.88E-01 6.01E-07 9.27E-05 0.00E+00 2200X-1-CJ-FCV1-030 9.07E-03 3.91E-04 1.24E-04 1.97E-01 0.00E+00 2.75E-04 0.00E+00 2200X-1-CJ-FCV1-031 1.37E-03 0.00E+00 3.04E-05 4.61E-01 1.91E-06 0.00E+00 6.28E-05 2200X-1-CJ-FCV1-035 1.30E-03 8.03E-05 1.66E-05 6.27E-01 3.49E-07 8.58E-05 3.41E-05 2200X-1-CJ-FCV1-038 9.27E-03 1.68E-04 1.90E-04 4.28E-01 3.24E-05 1.70E-04 0.00E+00 2200X-1-CJ-FCV1-039 1.52E-02 1.04E-04 4.58E-05 4.07E-01 0.00E+00 1.46E-03 3.13E-04 2200X-1-CJ-WCV1-009 0.00E+00 0.00E+00 1.57E-04 5.16E-01 0.00E+00 0.00E+00 0.00E+00 2300X-1-CJ-FCV1-001 2.23E-03 0.00E+00 0.00E+00 9.41E-01 1.45E-07 0.00E+00 5.71E-06 2300X-1-CJ-FCV1-002 2.05E-03 1.35E-05 2.18E-06 9.15E-01 0.00E+00 1.27E-04 4.32E-06 2300X-1-CJ-FCV1-003 1.67E-03 4.97E-05 0.00E+00 8.15E-01 0.00E+00 0.00E+00 3.76E-05 2300X-1-CJ-FCV1-005 1.55E-03 0.00E+00 2.36E-06 8.74E-01 2.81E-07 0.00E+00 0.00E+00 2300X-1-CJ-FCV1-007 3.88E-03 2.65E-04 2.97E-04 8.23E-01 7.76E-06 4.78E-04 1.84E-04 2300X-1-CJ-FCV1-010 2.66E-03 0.00E+00 5.34E-04 7.32E-01 0.00E+00 6.67E-04 0.00E+00 2600X-1-CJ-FCV1-002 4.14E-04 2.17E-05 1.06E-04 5.16E-01 0.00E+00 5.74E-03 5.75E-04 3100X-3-CJ-FCV1-006 2.22E-02 2.19E-03 0.00E+00 7.48E-02 9.23E-05 1.42E-02 0.00E+00 3100X-3-CJ-FCV1-014 1.37E-02 5.84E-04 3.11E-03 3.33E-02 3.33E-04 0.00E+00 5.16E-02 4100X-1-CJ-FCV1-004 0.00E+00 0.00E+00 5.36E-04 3.42E-01 0.00E+00 2.89E-03 7.32E-03 4100X-1-CJ-FCV1-005 1.70E-01 4.21E-03 0.00E+00 4.41E-01 4.95E-05 9.44E-03 9.25E-03 Average 9.22E-03 3.12E-04 2.05E-04 6.08E-01 1.91E-05 1.35E-03 2.33E-03 75 Percentile Frac. 3.57E-03 2.32E-04 1.48E-04 8.37E-01 4.32E-06 6.51E-04 8.52E-05 75 Perc. Norm. Frac. 2.79E-03 1.81E-04 1.16E-04 6.55E-01 3.38E-06 5.09E-04 6.67E-05

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 27 of 54 Table 18: Radionuclide Activity Fractions, fAi,j and fAi,j,.75, Using All Sample Data for AB/TB/RWPB Samples, Third Set of Radionuclides Sample ID Eu-155 Pu-238 Pu-239/240 Pu-241 Am-241 Cm-243/244 Np-237 2100X-1-CJ-FCV1-001 0.00E+00 1.08E-05 4.36E-06 4.84E-03 6.79E-05 1.65E-04 0.00E+00 2100X-1-CJ-FCV1-003 1.01E-04 1.22E-04 5.16E-05 3.04E-03 1.34E-04 7.64E-05 0.00E+00 2100X-1-CJ-FCV1-005 5.04E-04 1.84E-05 4.02E-05 2.59E-03 0.00E+00 0.00E+00 0.00E+00 2100X-1-CJ-FCV1-006 2.23E-03 9.70E-05 0.00E+00 8.03E-03 1.69E-04 0.00E+00 NA 2100X-1-CJ-FCV1-011 0.00E+00 0.00E+00 0.00E+00 5.66E-04 0.00E+00 0.00E+00 NA 2100X-1-CJ-FCV1-014 2.28E-04 1.16E-04 0.00E+00 0.00E+00 0.00E+00 2.92E-06 NA 2200X-1-CJ-FCV1-006 4.34E-04 0.00E+00 0.00E+00 5.96E-03 0.00E+00 0.00E+00 0.00E+00 2200X-1-CJ-FCV1-008 0.00E+00 1.37E-06 1.09E-05 0.00E+00 1.14E-05 0.00E+00 NA 2200X-1-CJ-FCV1-010 4.10E-04 0.00E+00 2.81E-05 0.00E+00 0.00E+00 0.00E+00 NA 2200X-1-CJ-FCV1-020 0.00E+00 7.09E-07 1.18E-06 0.00E+00 1.44E-06 0.00E+00 NA 2200X-1-CJ-FCV1-021 0.00E+00 1.13E-05 7.15E-05 4.42E-03 0.00E+00 0.00E+00 5.60E-06 2200X-1-CJ-FCV1-022 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NA 2200X-1-CJ-FCV1-026 0.00E+00 2.15E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NA 2200X-1-CJ-FCV1-030 0.00E+00 9.29E-05 4.51E-05 2.68E-03 2.24E-04 1.62E-05 1.68E-06 2200X-1-CJ-FCV1-031 0.00E+00 0.00E+00 1.85E-05 0.00E+00 5.28E-06 1.51E-05 NA 2200X-1-CJ-FCV1-035 0.00E+00 3.38E-05 2.77E-05 0.00E+00 2.24E-05 3.61E-06 NA 2200X-1-CJ-FCV1-038 2.93E-04 1.81E-05 1.86E-05 2.46E-02 2.46E-04 2.43E-04 0.00E+00 2200X-1-CJ-FCV1-039 1.36E-05 6.50E-06 0.00E+00 1.06E-02 3.40E-06 0.00E+00 0.00E+00 2200X-1-CJ-WCV1-009 1.78E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NA 2300X-1-CJ-FCV1-001 9.04E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NA 2300X-1-CJ-FCV1-002 0.00E+00 4.98E-05 3.35E-05 2.99E-04 9.43E-05 9.50E-06 NA 2300X-1-CJ-FCV1-003 1.40E-05 3.92E-05 1.76E-05 9.38E-04 1.19E-04 3.44E-05 0.00E+00 2300X-1-CJ-FCV1-005 0.00E+00 1.08E-06 0.00E+00 0.00E+00 1.32E-05 0.00E+00 NA 2300X-1-CJ-FCV1-007 0.00E+00 2.62E-05 3.99E-07 1.01E-03 3.15E-04 0.00E+00 NA 2300X-1-CJ-FCV1-010 0.00E+00 0.00E+00 4.37E-05 7.67E-03 2.93E-04 9.91E-11 0.00E+00 2600X-1-CJ-FCV1-002 3.09E-04 0.00E+00 1.24E-04 1.61E-03 2.25E-04 4.51E-05 NA 3100X-3-CJ-FCV1-006 0.00E+00 5.13E-03 1.71E-03 0.00E+00 0.00E+00 1.95E-03 NA 3100X-3-CJ-FCV1-014 5.54E-03 5.18E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NA 4100X-1-CJ-FCV1-004 0.00E+00 6.36E-04 6.71E-04 0.00E+00 0.00E+00 0.00E+00 NA 4100X-1-CJ-FCV1-005 0.00E+00 0.00E+00 0.00E+00 4.37E-02 9.76E-04 0.00E+00 NA Average 3.45E-04 3.86E-04 9.74E-05 4.09E-03 9.73E-05 8.54E-05 7.28E-07 75 Percentile Frac. 2.16E-04 4.71E-05 3.85E-05 4.07E-03 1.30E-04 1.37E-05 0.00E+00 75 Perc. Norm. Frac. 1.69E-04 3.69E-05 3.01E-05 3.19E-03 1.02E-04 1.07E-05 0.00E+00 Table 19: Radionuclide Activity Ratios to Cs-137, fRAi,j, Using Combined Sample Data for AB/TB/RWPB Samples, First Set of Radionuclides Radionuclide H-3 C-14 Fe-55 Co-58 Ni-59 Ni-63 Co-60 Tc-99 2100X-1-CJ-FCV1-001 5.74E-03 8.59E-03 0.00E+00 3.19E-11 4.46E-03 8.32E-01 1.20E-03 1.34E-03 2100X-1-CJ-FCV1-003 1.56E-02 3.40E-02 8.79E-03 8.12E-13 3.78E-02 4.68E+00 2.72E-03 3.27E-05 2100X-1-CJ-FCV1-005 2.35E-02 2.03E-02 0.00E+00 0.00E+00 0.00E+00 5.69E-02 7.86E-04 2.63E-04 2100X-1-CJ-FCV1-006 2.09E-01 2.94E-02 0.00E+00 5.35E-14 0.00E+00 3.17E-01 1.15E-02 1.17E-03 2100X-1-CJ-FCV1-011 9.35E-02 7.06E-02 0.00E+00 0.00E+00 7.80E-03 1.15E+00 3.45E-02 1.07E-01 2100X-1-CJ-FCV1-014 6.78E-03 6.89E-02 0.00E+00 0.00E+00 0.00E+00 4.03E-01 3.52E-03 2.28E-01 2200X-1-CJ-FCV1-006 2.92E-03 3.97E-02 0.00E+00 9.32E-12 1.41E-03 1.34E-01 7.24E-04 1.92E-02 2200X-1-CJ-FCV1-008 6.11E-02 2.28E-02 0.00E+00 7.66E-15 0.00E+00 8.66E-02 1.86E-02 0.00E+00 2200X-1-CJ-FCV1-010 4.41E-02 3.19E-02 0.00E+00 0.00E+00 0.00E+00 4.52E-01 1.43E-02 0.00E+00 2200X-1-CJ-FCV1-020 3.82E-03 1.90E-03 6.46E-05 1.63E-15 4.70E-04 1.30E-01 9.19E-04 1.54E-04 2200X-1-CJ-FCV1-021 5.35E-03 3.60E-02 0.00E+00 0.00E+00 0.00E+00 3.16E-01 9.32E-04 0.00E+00 2200X-1-CJ-FCV1-022 6.87E-04 1.42E-03 5.39E-06 0.00E+00 4.10E-04 3.83E-02 3.30E-05 0.00E+00 2200X-1-CJ-FCV1-026 6.32E-04 7.22E-04 6.34E-06 3.32E-16 0.00E+00 9.99E-03 0.00E+00 0.00E+00 2200X-1-CJ-FCV1-030 1.91E-01 3.96E-01 1.76E-02 0.00E+00 3.56E-02 3.08E+00 2.92E-01 0.00E+00 2200X-1-CJ-FCV1-031 4.87E-01 1.48E-02 4.58E-03 6.25E-15 7.05E-03 6.44E-01 8.79E-03 0.00E+00 2200X-1-CJ-FCV1-035 1.20E-02 2.67E-02 3.06E-03 5.12E-15 4.44E-03 5.36E-01 1.04E-02 0.00E+00 2200X-1-CJ-FCV1-038 1.69E-02 7.06E-02 0.00E+00 1.18E-10 4.28E-03 1.14E+00 2.09E-02 0.00E+00

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 28 of 54 2200X-1-CJ-FCV1-039 3.66E-02 9.83E-02 0.00E+00 0.00E+00 5.30E-03 1.23E+00 2.19E-02 0.00E+00 2200X-1-CJ-WCV1-009 1.29E-01 5.74E-01 0.00E+00 0.00E+00 3.30E-02 1.83E-01 5.62E-03 1.33E-02 2300X-1-CJ-FCV1-001 2.65E-04 1.23E-02 3.96E-04 0.00E+00 5.26E-04 4.63E-02 6.39E-05 0.00E+00 2300X-1-CJ-FCV1-002 1.06E-03 5.87E-03 2.74E-05 0.00E+00 7.31E-04 8.21E-02 3.84E-04 0.00E+00 2300X-1-CJ-FCV1-003 5.82E-04 2.71E-02 1.24E-03 0.00E+00 1.43E-03 1.80E-01 1.28E-02 2.67E-05 2300X-1-CJ-FCV1-005 1.22E-03 1.05E-02 1.37E-03 0.00E+00 1.33E-03 1.28E-01 3.73E-04 5.86E-05 2300X-1-CJ-FCV1-007 4.59E-02 7.51E-02 0.00E+00 1.01E-14 0.00E+00 8.14E-02 4.78E-03 0.00E+00 2300X-1-CJ-FCV1-010 0.00E+00 5.58E-02 3.47E-02 2.74E-09 0.00E+00 2.24E-01 2.21E-02 1.36E-02 2600X-1-CJ-FCV1-002 1.72E-01 4.17E-01 0.00E+00 0.00E+00 0.00E+00 3.14E-01 1.37E-02 2.61E-03 3100X-3-CJ-FCV1-006 0.00E+00 1.08E+01 9.48E-01 3.01E-12 0.00E+00 0.00E+00 3.41E-02 0.00E+00 3100X-3-CJ-FCV1-014 0.00E+00 1.38E+01 2.59E-01 6.06E-12 0.00E+00 1.24E+01 1.73E-01 0.00E+00 4100X-1-CJ-FCV1-004 0.00E+00 1.37E+00 7.19E-02 0.00E+00 1.22E-01 3.03E-01 2.01E-02 0.00E+00 4100X-1-CJ-FCV1-005 0.00E+00 2.94E-01 2.13E-01 1.50E-13 5.74E-05 1.33E-01 8.92E-02 0.00E+00 75th Percentile Each 4.54E-02 9.25E-02 4.20E-03 1.26E-13 4.46E-03 6.17E-01 2.07E-02 9.42E-04 Sample 75th Normalized Fraction 2.52E-02 5.14E-02 2.33E-03 7.00E-14 2.48E-03 3.43E-01 1.15E-02 5.23E-04 Table 20: Radionuclide Activity Ratios to Cs-137, fRAi,j, Using Combined Sample Data for AB/TB/RWPB Samples, Second Set of Radionuclides Radionuclide Sr-90 Sb-125 Cs-134 Cs-137 Ce-144 Eu-152 Eu-154 2100X-1-CJ-FCV1-001 8.04E-03 7.96E-05 2.61E-05 1.00E+00 0.00E+00 0.00E+00 1.40E-04 2100X-1-CJ-FCV1-003 2.96E-03 0.00E+00 6.18E-06 1.00E+00 0.00E+00 9.70E-04 3.13E-04 2100X-1-CJ-FCV1-005 2.23E-03 2.85E-04 3.65E-04 1.00E+00 3.88E-05 1.66E-03 0.00E+00 2100X-1-CJ-FCV1-006 3.85E-03 0.00E+00 1.34E-04 1.00E+00 4.45E-06 3.07E-03 5.16E-04 2100X-1-CJ-FCV1-011 3.28E-03 0.00E+00 2.91E-04 1.00E+00 0.00E+00 0.00E+00 4.73E-05 2100X-1-CJ-FCV1-014 1.84E-03 1.90E-04 7.87E-05 1.00E+00 2.23E-05 0.00E+00 0.00E+00 2200X-1-CJ-FCV1-006 8.25E-05 0.00E+00 5.24E-05 1.00E+00 0.00E+00 7.27E-04 7.40E-05 2200X-1-CJ-FCV1-008 1.41E-03 3.01E-04 1.43E-04 1.00E+00 2.23E-07 0.00E+00 1.06E-04 2200X-1-CJ-FCV1-010 3.94E-03 8.93E-04 0.00E+00 1.00E+00 0.00E+00 8.26E-04 0.00E+00 2200X-1-CJ-FCV1-020 6.26E-04 6.31E-05 2.58E-04 1.00E+00 1.92E-07 2.14E-04 3.32E-06 2200X-1-CJ-FCV1-021 2.12E-03 0.00E+00 0.00E+00 1.00E+00 6.59E-06 0.00E+00 0.00E+00 2200X-1-CJ-FCV1-022 9.45E-04 0.00E+00 1.67E-06 1.00E+00 0.00E+00 7.11E-05 0.00E+00 2200X-1-CJ-FCV1-026 1.05E-03 0.00E+00 1.27E-06 1.00E+00 6.09E-07 9.39E-05 0.00E+00 2200X-1-CJ-FCV1-030 4.61E-02 1.99E-03 6.28E-04 1.00E+00 0.00E+00 1.39E-03 0.00E+00 2200X-1-CJ-FCV1-031 2.98E-03 0.00E+00 6.59E-05 1.00E+00 4.15E-06 0.00E+00 1.36E-04 2200X-1-CJ-FCV1-035 2.08E-03 1.28E-04 2.64E-05 1.00E+00 5.58E-07 1.37E-04 5.44E-05 2200X-1-CJ-FCV1-038 2.17E-02 3.93E-04 4.45E-04 1.00E+00 7.57E-05 3.98E-04 0.00E+00 2200X-1-CJ-FCV1-039 3.74E-02 2.55E-04 1.13E-04 1.00E+00 0.00E+00 3.58E-03 7.69E-04 2200X-1-CJ-WCV1-009 0.00E+00 0.00E+00 3.04E-04 1.00E+00 0.00E+00 0.00E+00 0.00E+00 2300X-1-CJ-FCV1-001 2.37E-03 0.00E+00 0.00E+00 1.00E+00 1.54E-07 0.00E+00 6.06E-06 2300X-1-CJ-FCV1-002 2.24E-03 1.47E-05 2.38E-06 1.00E+00 0.00E+00 1.38E-04 4.72E-06 2300X-1-CJ-FCV1-003 2.05E-03 6.09E-05 0.00E+00 1.00E+00 0.00E+00 0.00E+00 4.61E-05 2300X-1-CJ-FCV1-005 1.78E-03 0.00E+00 2.70E-06 1.00E+00 3.22E-07 0.00E+00 0.00E+00 2300X-1-CJ-FCV1-007 4.71E-03 3.21E-04 3.61E-04 1.00E+00 9.43E-06 5.81E-04 2.23E-04 2300X-1-CJ-FCV1-010 3.64E-03 0.00E+00 7.30E-04 1.00E+00 0.00E+00 9.11E-04 0.00E+00 2600X-1-CJ-FCV1-002 8.02E-04 4.20E-05 2.05E-04 1.00E+00 0.00E+00 1.11E-02 1.11E-03 3100X-3-CJ-FCV1-006 2.97E-01 2.92E-02 0.00E+00 1.00E+00 1.23E-03 1.90E-01 0.00E+00 3100X-3-CJ-FCV1-014 4.11E-01 1.75E-02 9.34E-02 1.00E+00 9.99E-03 0.00E+00 1.55E+00 4100X-1-CJ-FCV1-004 0.00E+00 0.00E+00 1.57E-03 1.00E+00 0.00E+00 8.45E-03 2.14E-02 4100X-1-CJ-FCV1-005 3.87E-01 9.55E-03 0.00E+00 1.00E+00 1.12E-04 2.14E-02 2.10E-02 75th Percentile Each Sample 4.52E-03 2.97E-04 3.01E-04 1.00E+00 6.06E-06 1.29E-03 2.03E-04 75th Normalized Fraction 2.51E-03 1.65E-04 1.67E-04 5.55E-01 3.36E-06 7.15E-04 1.13E-04

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 29 of 54 Table 21: Radionuclide Activity Ratios to Cs-137, fRAi,j, Using Combined Sample Data for AB/TB/RWPB Samples, Third Set of Radionuclides Radionuclide Eu-155 Pu-238 Pu-239/240 Pu-241 Am-241 Cm-243/244 Np-237 2100X-1-CJ-FCV1-001 0.00E+00 2.01E-05 8.16E-06 9.05E-03 1.27E-04 3.09E-04 0.00E+00 2100X-1-CJ-FCV1-003 5.87E-04 7.10E-04 2.99E-04 1.76E-02 7.75E-04 4.43E-04 0.00E+00 2100X-1-CJ-FCV1-005 5.59E-04 2.04E-05 4.46E-05 2.88E-03 0.00E+00 0.00E+00 0.00E+00 2100X-1-CJ-FCV1-006 3.56E-03 1.54E-04 0.00E+00 1.28E-02 2.68E-04 0.00E+00 NA 2100X-1-CJ-FCV1-011 0.00E+00 0.00E+00 0.00E+00 1.40E-03 0.00E+00 0.00E+00 NA 2100X-1-CJ-FCV1-014 3.91E-04 1.99E-04 0.00E+00 0.00E+00 0.00E+00 5.00E-06 NA 2200X-1-CJ-FCV1-006 5.24E-04 0.00E+00 0.00E+00 7.19E-03 0.00E+00 0.00E+00 0.00E+00 2200X-1-CJ-FCV1-008 0.00E+00 1.63E-06 1.29E-05 0.00E+00 1.36E-05 0.00E+00 NA 2200X-1-CJ-FCV1-010 6.35E-04 0.00E+00 4.36E-05 0.00E+00 0.00E+00 0.00E+00 NA 2200X-1-CJ-FCV1-020 0.00E+00 8.07E-07 1.34E-06 0.00E+00 1.64E-06 0.00E+00 NA 2200X-1-CJ-FCV1-021 0.00E+00 1.55E-05 9.77E-05 6.04E-03 0.00E+00 0.00E+00 7.66E-06 2200X-1-CJ-FCV1-022 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NA 2200X-1-CJ-FCV1-026 0.00E+00 2.17E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NA 2200X-1-CJ-FCV1-030 0.00E+00 4.72E-04 2.29E-04 1.36E-02 1.14E-03 8.22E-05 8.53E-06 2200X-1-CJ-FCV1-031 0.00E+00 0.00E+00 4.01E-05 0.00E+00 1.15E-05 3.28E-05 NA 2200X-1-CJ-FCV1-035 0.00E+00 5.39E-05 4.42E-05 0.00E+00 3.58E-05 5.75E-06 NA 2200X-1-CJ-FCV1-038 6.84E-04 4.22E-05 4.36E-05 5.75E-02 5.75E-04 5.67E-04 0.00E+00 2200X-1-CJ-FCV1-039 3.35E-05 1.60E-05 0.00E+00 2.61E-02 8.36E-06 0.00E+00 0.00E+00 2200X-1-CJ-WCV1-009 3.45E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NA 2300X-1-CJ-FCV1-001 9.60E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NA 2300X-1-CJ-FCV1-002 0.00E+00 5.44E-05 3.66E-05 3.27E-04 1.03E-04 1.04E-05 NA 2300X-1-CJ-FCV1-003 1.72E-05 4.81E-05 2.16E-05 1.15E-03 1.46E-04 4.22E-05 0.00E+00 2300X-1-CJ-FCV1-005 0.00E+00 1.23E-06 0.00E+00 0.00E+00 1.51E-05 0.00E+00 NA 2300X-1-CJ-FCV1-007 0.00E+00 3.18E-05 4.85E-07 1.22E-03 3.83E-04 0.00E+00 NA 2300X-1-CJ-FCV1-010 0.00E+00 0.00E+00 5.97E-05 1.05E-02 4.00E-04 1.35E-10 0.00E+00 2600X-1-CJ-FCV1-002 5.99E-04 0.00E+00 2.40E-04 3.12E-03 4.36E-04 8.74E-05 NA 3100X-3-CJ-FCV1-006 0.00E+00 6.85E-02 2.29E-02 0.00E+00 0.00E+00 2.61E-02 0.00E+00 3100X-3-CJ-FCV1-014 1.66E-01 1.55E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NA 4100X-1-CJ-FCV1-004 0.00E+00 1.86E-03 1.96E-03 0.00E+00 0.00E+00 0.00E+00 NA 4100X-1-CJ-FCV1-005 0.00E+00 0.00E+00 0.00E+00 9.93E-02 2.22E-03 0.00E+00 0.00E+00 75th Percentile Each Sample 4.90E-04 5.43E-05 4.45E-05 8.59E-03 2.38E-04 2.72E-05 0.00E+00 75th Normalized Fraction 2.72E-04 3.01E-05 2.47E-05 4.77E-03 1.32E-04 1.51E-05 0.00E+00 Table 22 summarizes the radionuclide activity fractions using the three methods described above. The Np-237 values for the 75th Percentile of the Activity Average Fractions and the 75th Percentile of the Individual Sample Ratios to Cs-137 are zero due to the very small number of positive activity concentrations for this nuclide.

Table 22: Radionuclide Activity Fractions for AB/TB/RWPB Sample Population Using Three Methods 75 Percentile of the Activity 75th Percentile of Average the Individual Average Activity Fractions, Sample Ratios to Cs-Nuclide Fractions, fAi, fAi,,.75 137, fRAi,.75 H-3 2.60E-02 2.76E-02 2.52E-02 C-14 9.72E-02 4.43E-02 5.14E-02 Fe-55 7.83E-03 1.42E-03 2.33E-03 Co-58 6.94E-11 4.54E-14 7.00E-14 Ni-59 3.11E-03 1.82E-03 2.48E-03 Ni-63 2.25E-01 2.55E-01 3.43E-01

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 30 of 54 75 Percentile of the Activity 75th Percentile of Average the Individual Average Activity Fractions, Sample Ratios to Cs-Nuclide Fractions, fAi, fAi,,.75 137, fRAi,.75 Co-60 7.79E-03 6.99E-03 1.15E-02 Tc-99 7.09E-03 4.68E-04 5.23E-04 Sr-90 9.22E-03 2.79E-03 2.51E-03 Sb-125 3.12E-04 1.81E-04 1.65E-04 Cs-134 2.05E-04 1.16E-04 1.67E-04 Cs-137 6.08E-01 6.55E-01 5.55E-01 Ce-144 1.91E-05 3.38E-06 3.36E-06 Eu-152 1.35E-03 5.09E-04 7.15E-04 Eu-154 2.33E-03 6.67E-05 1.13E-04 Eu-155 3.45E-04 1.69E-04 2.72E-04 Pu-238 3.86E-04 3.69E-05 3.01E-05 Pu-239/240 9.74E-05 3.01E-05 2.47E-05 Pu-241 4.09E-03 3.19E-03 4.77E-03 Am-241 9.73E-05 1.02E-04 1.32E-04 Cm-243/244 8.54E-05 1.07E-05 1.51E-05 Np-237 7.28E-07 0.00E+00 0.00E+00 6.2 Insignificant Dose Contributors and Radionuclides of Concern NUREG-1757, Vol. 2, Rev. 1 [1] defines radionuclides as insignificant dose contributors if the sum of the dose from the group of insignificant contributors is less than 10% of the total dose from all radionuclides combined. The insignificant contributors can be eliminated from further detailed consideration in the LTP and FSS. However, the dose contribution from the insignificant contributors must be accounted for in the final DCGLs. The radionuclides remaining after the insignificant contributors are removed are the ROC for FCS.

The ROCs were selected to ensure that sufficient margin has been attributed to the estimated dose contribution from the insignificant radionuclides. This decreases the risk of having to recalculate the adjusted DCGLS.

The Relative Dose Fraction, RDFi,k, for nuclide i and population k is calculated using the applicable DCGLs from Attachment 2 , and the nuclide activity fraction from Section 5.1 and Equation 6.

Equation 6

, 1

, =

()

The values of , are listed in Attachment 2. A list of the 12 DCGLs evaluated in this TSD is summarized in Table 23.

It should be noted that for the nuclide pairs Pu-239/240 and Cm-243/244 that the most limiting DCGL for each pair was selected for use in Equation 6.

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 31 of 54 Table 23: List of DCGLs Evaluated in this TSD Soil 0.15 m DCGL (pCi/g)

Soil 1.0 m DCGL (pCi/g)

Buried Pipe Excavation Scenario DCGL (dpm/100 cm2)

BFM1 Wall/Floor DCGL (Auxiliary, Turbine, Circulating Water Tunnels, Intake Structure) LTP Chapter 6 Equation 6-18 (pCi/m2)

BFM Wall/Floor DCGL (Containment Building LTP Chapter 6 Equation 6-18 (pCi/m2)

Embedded Pipe Auxiliary Floor 971' elevation LTP Chapter 6 Equation 6-14 (pCi/m2)

Embedded Pipe Auxiliary Floor 989' elevation LTP Chapter 6 Equation 6-14 (pCi/m2)

Embedded Pipe Turbine Floor 990' elevation LTP Chapter 6 Equation 6-14 (pCi/m2)

BFM fill material (pCi/g)

The results of these calculations are provided in Tables 25 through 38. The tables show the dose fractions for each sample population. For each sample population the normalized 75th percentile mix fraction and the 75th percentile off the normalized Cs-137 ratios are evaluated.

In addition to the DCGLs evaluated using Equation 6, five Less Likely But Plausible Scenarios(LLBP) were also evaluated. Each scenario was evaluated using the same set of radionuclide mix fractions and mathematical methods that were used in the DCGL evaluations.

Table 24 List of LLBP Scenarios Evaluated in this TSD Embedded Pipe LLBP Drilling Spoils Concentration AB EP 4.03 in ID (pCi/m2 per 25 mrem/yr)

Embedded Pipe LLBP Drilling Spoils Concentration AB EP 18.81 in ID (pCi/m2 per 25 mrem/yr)

Embedded Pipe LLBP Drilling Spoils Concentration TB EP 9.4 in ID (pCi/m2 per 25 mrem/yr)

Recycle/Disposal LLBP Scenario Concrete (pCi/m2 per 25 mrem/yr)

Recycle/Disposal LLBP Scenario Steel (pCi/m2 per 25 mrem/yr)

Table 25: Relative Dose Fractions, RDFi,k, Containment Mix Fraction, Using 75th Percentiles of the Averages, CB BFM Wall/Floor DCGL Scenario Containment CB Mix Wall/Floor Dose Nuclide ROC? Fraction Fraction H-3 9.72E-02 2.66E-03 C-14 Y 6.28E-01 4.53E-01 Fe-55 9.31E-05 9.11E-08 Co-58 3.56E-14 2.72E-14 Ni-59 4.12E-04 2.26E-06 Ni-63 3.98E-02 5.99E-04 Co-60 Y 3.70E-03 2.65E-02 Tc-99 2.87E-04 2.91E-04 Sr-90 Y 3.70E-04 2.57E-03 Sb-125 5.11E-05 5.54E-05 Cs-134 4.86E-05 2.23E-04 Cs-137 Y 2.26E-01 5.07E-01 Ce-144 1.61E-06 1.68E-07 Eu-152 Y 2.08E-03 6.48E-03 1

BFM represents Basement Fill Model

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 32 of 54 Containment CB Mix Wall/Floor Dose Nuclide ROC? Fraction Fraction Eu-154 1.21E-04 4.05E-04 Eu-155 3.53E-05 3.21E-06 Pu-238 1.39E-05 2.92E-05 Pu-239/240 1.40E-05 3.26E-05 Pu-241 1.75E-03 8.30E-05 Am-241 3.32E-05 5.06E-05 Cm-243/244 1.27E-05 1.11E-05 Np-237 6.29E-07 4.96E-05 Sum 1.00E+00 ROC 9.96E-01 IC Dose 4.50E-03 Table 26: Relative Dose Fractions, RDFi,k, Containment Mix Fraction, Using 75th Percentiles of the Nuclide Ratios to Cs-137, BFM Wall/Floor of CB DCGL Scenario Containment Wall/Floor CB Mix Dose Nuclide ROC? Fraction Fraction H-3 8.70E-02 3.14E-03 C-14 Y 8.27E-01 7.87E-01 Fe-55 1.43E-05 1.84E-08 Co-58 1.47E-14 1.49E-14 Ni-59 1.53E-04 1.11E-06 Ni-63 1.76E-02 3.51E-04 Co-60 Y 1.67E-03 1.58E-02 Tc-99 3.41E-04 4.57E-04 Sr-90 Y 2.59E-04 2.37E-03 Sb-125 1.89E-05 2.70E-05 Cs-134 2.08E-05 1.26E-04 Cs-137 Y 6.01E-02 1.78E-01 Ce-144 1.52E-06 2.09E-07 Eu-152 Y 2.95E-03 1.21E-02 Eu-154 1.44E-04 6.36E-04 Eu-155 4.09E-05 4.90E-06 Pu-238 5.66E-06 1.57E-05 Pu-239/240 1.06E-05 3.26E-05 Pu-241 2.91E-03 1.83E-04 Am-241 4.78E-05 9.61E-05 Cm-243/244 1.27E-05 1.46E-05 Np-237 1.24E-06 1.29E-04 Sum 1.00E+00 ROC 9.95E-01 IC Dose 5.22E-03 Table 27: Relative Dose Fractions, RDFi,k, Containment Mix Fraction, Using 75th Percentiles of the Averages, CB Soil, BP & Fill Material DCGL Scenarios CB Mix 0.15 m Soil 1.0 m Soil Buried Pipe Fill Material Dose Nuclide ROC? Fraction Dose Fraction Dose Fraction Dose Fraction Fraction H-3 9.72E-02 2.89E-04 1.21E-03 5.82E-04 9.32E-03 C-14 Y 6.28E-01 3.72E-01 6.63E-01 5.66E-02 7.28E-01 Fe-55 9.31E-05 9.04E-08 4.72E-08 2.25E-08 9.01E-08 Co-58 3.56E-14 3.48E-14 1.22E-14 6.07E-14 1.29E-15 Ni-59 4.12E-04 1.30E-06 1.92E-06 5.56E-07 5.74E-06 Ni-63 3.98E-02 3.43E-04 5.08E-04 1.47E-04 1.52E-03

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 33 of 54 CB Mix 0.15 m Soil 1.0 m Soil Buried Pipe Fill Material Dose Nuclide ROC? Fraction Dose Fraction Dose Fraction Dose Fraction Fraction Co-60 Y 3.70E-03 3.31E-02 1.29E-02 5.71E-02 3.48E-03 Tc-99 2.87E-04 7.52E-05 2.00E-04 1.57E-04 8.84E-04 Sr-90 3.70E-04 1.18E-03 2.30E-03 1.48E-03 6.94E-03 Sb-125 5.11E-05 6.82E-05 2.34E-05 1.20E-04 1.04E-05 Cs-134 4.86E-05 2.69E-04 1.23E-04 4.29E-04 6.74E-05 Cs-137 Y 2.26E-01 5.84E-01 3.17E-01 8.68E-01 2.49E-01 Ce-144 1.61E-06 2.09E-07 7.48E-08 3.66E-07 2.62E-08 Eu-152 Y 2.08E-03 8.35E-03 2.89E-03 1.46E-02 5.66E-05 Eu-154 1.21E-04 5.21E-04 1.81E-04 9.13E-04 4.77E-06 Eu-155 3.53E-05 4.07E-06 1.25E-06 7.10E-06 2.17E-07 Pu-238 1.39E-05 2.82E-06 4.23E-06 4.71E-06 1.08E-04 Pu-239/240 1.40E-05 3.15E-06 4.72E-06 5.25E-06 1.21E-04 Pu-241 1.75E-03 1.09E-05 1.80E-05 1.87E-05 2.92E-04 Am-241 3.32E-05 8.41E-06 1.17E-05 1.44E-05 1.77E-04 Cm-243/244 1.27E-05 6.68E-06 4.46E-06 1.17E-05 2.36E-05 Np-237 6.29E-07 4.73E-06 8.88E-06 5.16E-06 1.85E-04 Sum 1.00E+00 1.00E+00 1.00E+00 1.00E+00 ROC 9.97E-01 9.95E-01 9.96E-01 9.80E-01 IC Dose 2.79E-03 4.60E-03 3.90E-03 1.97E-02 Table 28: Relative Dose Fractions, RDFi,k, Containment Mix Fraction, Using 75th Percentiles of the Nuclide Ratios to Cs-137, CB Soil, BP & Fill Material DCGL Scenarios 0.15 m Soil 1.0 m Soil Buried Pipe Fill Material CB Mix Dose Dose Dose Dose Nuclide ROC? Fraction Fraction Fraction Fraction Fraction H-3 8.70E-02 3.84E-04 1.11E-03 1.47E-03 8.00E-03 C-14 Y 8.27E-01 7.27E-01 8.99E-01 2.10E-01 9.19E-01 Fe-55 1.43E-05 2.05E-08 7.45E-09 9.71E-09 1.33E-08 Co-58 1.47E-14 2.14E-14 5.22E-15 7.09E-14 5.14E-16 Ni-59 1.53E-04 7.16E-07 7.36E-07 5.82E-07 2.05E-06 Ni-63 1.76E-02 2.26E-04 2.32E-04 1.84E-04 6.47E-04 Co-60 Y 1.67E-03 2.22E-02 6.00E-03 7.25E-02 1.51E-03 Tc-99 3.41E-04 1.33E-04 2.45E-04 5.24E-04 1.01E-03 Sr-90 2.59E-04 1.23E-03 1.66E-03 2.92E-03 4.67E-03 Sb-125 1.89E-05 3.73E-05 8.91E-06 1.25E-04 3.68E-06 Cs-134 2.08E-05 1.71E-04 5.45E-05 5.18E-04 2.77E-05 Cs-137 Y 6.01E-02 2.30E-01 8.70E-02 6.50E-01 6.35E-02 Ce-144 1.52E-06 2.91E-07 7.25E-08 9.68E-07 2.36E-08 Eu-152 Y 2.95E-03 1.76E-02 4.22E-03 5.85E-02 7.71E-05 Eu-154 1.44E-04 9.21E-04 2.22E-04 3.06E-03 5.45E-06 Eu-155 4.09E-05 6.99E-06 1.50E-06 2.31E-05 2.41E-07 Pu-238 5.66E-06 1.70E-06 1.77E-06 5.39E-06 4.23E-05 Pu-239/240 1.06E-05 3.54E-06 3.69E-06 1.12E-05 8.81E-05 Pu-241 2.91E-03 2.71E-05 3.10E-05 8.81E-05 4.68E-04 Am-241 4.78E-05 1.80E-05 1.73E-05 5.86E-05 2.44E-04 Cm-243/244 1.27E-05 9.90E-06 4.59E-06 3.30E-05 2.26E-05 Np-237 1.24E-06 1.39E-05 1.81E-05 2.86E-05 3.50E-04 Sum 1.00E+00 1.00E+00 1.00E+00 1.00E+00 ROC 9.97E-01 9.96E-01 9.91E-01 9.84E-01 IC Dose 3.18E-03 3.62E-03 9.05E-03 1.56E-02

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 34 of 54 Table 29: Relative Dose Fractions, RDFi,k, AB/TB/RWPB Mix Fraction, Using 75th Percentiles of the Averages, BFM Other Walls/Floors DCGL Scenario AB/TB/RWPB Other Wall/Floor Nuclide ROC? Mix Fraction Dose Fraction H-3 2.76E-02 1.23E-03 C-14 Y 4.43E-02 5.06E-02 Fe-55 1.42E-03 1.01E-06 Co-58 4.54E-14 1.14E-14 Ni-59 1.82E-03 1.47E-05 Ni-63 2.55E-01 5.66E-03 Co-60 Y 6.99E-03 1.93E-02 Tc-99 4.68E-04 7.82E-04 Sr-90 Y 2.79E-03 3.18E-02 Sb-125 1.81E-04 7.23E-05 Cs-134 1.16E-04 2.61E-04 Cs-137 Y 6.55E-01 8.89E-01 Ce-144 3.38E-06 1.30E-07 Eu-152 Y 5.09E-04 4.96E-04 Eu-154 6.67E-05 7.04E-05 Eu-155 1.69E-04 4.60E-06 Pu-238 3.69E-05 1.22E-04 Pu-239/240 3.01E-05 1.11E-04 Pu-241 3.19E-03 2.40E-04 Am-241 1.02E-04 2.41E-04 Cm-243/244 1.07E-05 1.05E-05 Np-237 0.00E+00 0.00E+00 Sum 1.00E+00 ROC 9.91E-01 IC Dose 8.82E-03 Table 30: Relative Dose Fractions, RDFi,k, AB/TB/RWPB Mix Fraction, Using 75th Percentiles of the Nuclide Ratios to Cs-137, BFM Other Walls/Floors DCGL Scenario AB/TB/RWPB Other Wall/Floor Nuclide ROC? Mix Fraction Dose Fraction H-3 2.52E-02 1.27E-03 C-14 Y 5.14E-02 6.64E-02 Fe-55 2.33E-03 1.88E-06 Co-58 7.00E-14 1.99E-14 Ni-59 2.48E-03 2.27E-05 Ni-63 3.43E-01 8.58E-03 Co-60 Y 1.15E-02 3.58E-02 Tc-99 5.23E-04 9.88E-04 Sr-90 Y 2.51E-03 3.23E-02 Sb-125 1.65E-04 7.44E-05 Cs-134 1.67E-04 4.24E-04 Cs-137 Y 5.55E-01 8.52E-01 Ce-144 3.36E-06 1.47E-07 Eu-152 Y 7.15E-04 7.88E-04 Eu-154 1.13E-04 1.34E-04 Eu-155 2.72E-04 8.39E-06 Pu-238 3.01E-05 1.13E-04 Pu-239/240 2.47E-05 1.03E-04 Pu-241 4.77E-03 4.06E-04 Am-241 1.32E-04 3.53E-04 Cm-243/244 1.51E-05 1.68E-05 Np-237 0.00E+00 0.00E+00

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 35 of 54 AB/TB/RWPB Other Wall/Floor Nuclide ROC? Mix Fraction Dose Fraction Sum 1.00E+00 ROC 9.87E-01 IC Dose 1.25E-02 Table 31: Relative Dose Fractions, RDFi,k, AB/TB/RWPB Mix Fraction, Using 75th Percentiles of the Averages, Embedded Pipe DCGL Scenarios*

971' Embedded 989' Embedded 990' Embedded AB/TB/RWPB Pipe Pipe Dose Pipe Dose Nuclide ROC? Mix Fraction Dose Fraction Fraction Fraction H-3 2.76E-02 9.06E-03 9.06E-03 9.06E-03 C-14 Y 4.43E-02 2.26E-01 2.26E-01 2.26E-01 Fe-55 1.42E-03 4.11E-06 4.11E-06 4.11E-06 Co-58 4.54E-14 2.62E-15 2.62E-15 2.62E-15 Ni-59 1.82E-03 7.02E-05 7.02E-05 7.02E-05 Ni-63 2.55E-01 1.96E-02 1.96E-02 1.96E-02 Co-60 Y 6.99E-03 1.04E-02 1.04E-02 1.04E-02 Tc-99 4.68E-04 4.75E-03 4.75E-03 4.75E-03 Sr-90 Y 2.79E-03 9.88E-02 9.88E-02 9.88E-02 Sb-125 1.81E-04 1.09E-04 1.09E-04 1.09E-04 Cs-134 1.16E-04 1.40E-04 1.40E-04 1.40E-04 Cs-137 Y 6.55E-01 6.26E-01 6.26E-01 6.26E-01 Ce-144 3.38E-06 1.43E-07 1.43E-07 1.43E-07 Eu-152 Y 5.09E-04 4.30E-05 4.30E-05 4.30E-05 Eu-154 6.67E-05 8.18E-06 8.18E-06 8.18E-06 Eu-155 1.69E-04 3.22E-06 3.22E-06 3.22E-06 Pu-238 3.69E-05 9.09E-04 9.09E-04 9.09E-04 Pu-239/240 3.01E-05 1.09E-03 1.09E-03 1.09E-03 Pu-241 3.19E-03 1.71E-03 1.71E-03 1.71E-03 Am-241 1.02E-04 1.66E-03 1.66E-03 1.66E-03 Cm-243/244 1.07E-05 5.61E-05 5.61E-05 5.61E-05 Np-237 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sum 1.00E+00 1.00E+00 1.00E+00 ROC 9.61E-01 9.61E-01 9.61E-01 IC Dose 3.91E-02 3.91E-02 3.91E-02

• The dose fractions for the Embedded Pipe scenarios differ slightly but round to the same number.

Table 32: Relative Dose Fractions, RDFi,k, AB/TB/RWPB Mix Fraction, Using 75th Percentiles of the Nuclide Ratios to Cs-137, Embedded Pipe DCGL Scenarios*

AB/TB/RWPB 971' Embedded Pipe 989' Embedded Pipe 990' Embedded Pipe Nuclide ROC? Mix Fraction Dose Fraction Dose Fraction Dose Fraction H-3 2.52E-02 8.76E-03 8.76E-03 8.76E-03 C-14 Y 5.14E-02 2.77E-01 2.77E-01 2.77E-01 Fe-55 2.33E-03 7.14E-06 7.14E-06 7.14E-06 Co-58 7.00E-14 4.26E-15 4.26E-15 4.26E-15 Ni-59 2.48E-03 1.01E-04 1.01E-04 1.01E-04 Ni-63 3.43E-01 2.78E-02 2.78E-02 2.78E-02 Co-60 Y 1.15E-02 1.81E-02 1.81E-02 1.81E-02 Tc-99 5.23E-04 5.61E-03 5.61E-03 5.61E-03 Sr-90 Y 2.51E-03 9.38E-02 9.38E-02 9.38E-02 Sb-125 1.65E-04 1.05E-04 1.05E-04 1.05E-04 Cs-134 1.67E-04 2.13E-04 2.13E-04 2.13E-04 Cs-137 Y 5.55E-01 5.61E-01 5.61E-01 5.61E-01 Ce-144 3.36E-06 1.51E-07 1.51E-07 1.51E-07 Eu-152 Y 7.15E-04 6.38E-05 6.38E-05 6.38E-05 Eu-154 1.13E-04 1.46E-05 1.46E-05 1.46E-05

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 36 of 54 AB/TB/RWPB 971' Embedded Pipe 989' Embedded Pipe 990' Embedded Pipe Nuclide ROC? Mix Fraction Dose Fraction Dose Fraction Dose Fraction Eu-155 2.72E-04 5.50E-06 5.50E-06 5.50E-06 Pu-238 3.01E-05 7.86E-04 7.86E-04 7.86E-04 Pu-239/240 2.47E-05 9.42E-04 9.42E-04 9.42E-04 Pu-241 4.77E-03 2.70E-03 2.70E-03 2.70E-03 Am-241 1.32E-04 2.28E-03 2.28E-03 2.28E-03 Cm-243/244 1.51E-05 8.36E-05 8.36E-05 8.36E-05 Np-237 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sum 1.00E+00 1.00E+00 1.00E+00 ROC 9.51E-01 9.51E-01 9.51E-01 IC Dose 4.94E-02 4.94E-02 4.94E-02

• The dose fractions for the Embedded Pipe scenarios differ slightly but round to the same number.

Table 33: Relative Dose Fractions, RDFi,k, AB/TB/RWPB Mix Fraction, Using 75th Percentiles of the Averages, Soil, Buried Pipe, & Fill Material DCGL Scenarios AB/TB/RWPB Soil 0.15 m Dose Soil 1.0 m Dose Buried Pipe Fill Material Nuclide ROC? Mix Fraction Fraction Fraction Dose Fraction Dose Fraction H-3 2.76E-02 4.57E-05 3.38E-04 1.09E-04 3.12E-03 C-14 Y 4.43E-02 1.46E-02 4.61E-02 2.00E-03 6.05E-02 Fe-55 1.42E-03 7.67E-07 7.10E-07 1.53E-07 1.62E-06 Co-58 4.54E-14 2.47E-14 1.54E-14 2.78E-14 1.95E-15 Ni-59 1.82E-03 3.19E-06 8.38E-06 1.63E-06 3.00E-05 Ni-63 2.55E-01 1.23E-03 3.22E-03 6.25E-04 1.15E-02 Co-60 Y 6.99E-03 3.48E-02 2.40E-02 3.89E-02 7.75E-03 Tc-99 4.68E-04 6.82E-05 3.22E-04 1.28E-04 1.70E-03 Sr-90 2.79E-03 4.97E-03 1.71E-02 7.91E-03 6.18E-02 Sb-125 1.81E-04 1.35E-04 8.19E-05 1.53E-04 4.35E-05 Cs-134 1.16E-04 3.58E-04 2.91E-04 3.78E-04 1.90E-04 Cs-137 Y 6.55E-01 9.42E-01 9.08E-01 9.48E-01 8.51E-01 Ce-144 3.38E-06 2.43E-07 1.55E-07 2.77E-07 6.47E-08 Eu-152 Y 5.09E-04 1.14E-03 6.97E-04 1.28E-03 1.63E-05 Eu-154 6.67E-05 1.60E-04 9.87E-05 1.80E-04 3.11E-06 Eu-155 1.69E-04 1.08E-05 5.91E-06 1.21E-05 1.22E-06 Pu-238 3.69E-05 4.16E-06 1.11E-05 1.03E-05 3.39E-04 Pu-239/240 3.01E-05 3.78E-06 1.00E-05 9.32E-06 3.08E-04 Pu-241 3.19E-03 1.11E-05 3.25E-05 2.56E-05 6.30E-04 Am-241 1.02E-04 1.43E-05 3.53E-05 3.07E-05 6.40E-04 Cm-243/244 1.07E-05 3.14E-06 3.72E-06 4.43E-06 2.35E-05 Np-237 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sum 1.00E+00 1.00E+00 1.00E+00 1.00E+00 ROC 9.93E-01 9.78E-01 9.90E-01 9.20E-01 IC Dose 7.02E-03 2.16E-02 9.58E-03 8.04E-02 Table 34: Relative Dose Fractions, RDFi,k, AB/TB/RWPB Mix Fraction, Using 75th Percentiles of the Nuclide Ratios to Cs-137, Soil, Buried Pipe & Fill Material DCGL Scenarios AB/TB/RWPB Soil 0.15 m Dose Soil 1.0 m Dose Buried Pipe Fill Material Dose Nuclide ROC? Mix Fraction Fraction Fraction Dose Fraction Fraction H-3 2.52E-02 4.73E-05 3.50E-04 1.13E-04 3.23E-03 C-14 Y 5.14E-02 1.92E-02 6.05E-02 2.64E-03 7.96E-02 Fe-55 2.33E-03 1.43E-06 1.32E-06 2.86E-07 3.01E-06 Co-58 7.00E-14 4.32E-14 2.69E-14 4.87E-14 3.40E-15 Ni-59 2.48E-03 4.92E-06 1.29E-05 2.51E-06 4.62E-05 Ni-63 3.43E-01 1.86E-03 4.88E-03 9.52E-04 1.75E-02 Co-60 Y 1.15E-02 6.49E-02 4.47E-02 7.27E-02 1.44E-02 Tc-99 5.23E-04 8.64E-05 4.07E-04 1.62E-04 2.15E-03 Sr-90 2.51E-03 5.06E-03 1.74E-02 8.05E-03 6.28E-02

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 37 of 54 AB/TB/RWPB Soil 0.15 m Dose Soil 1.0 m Dose Buried Pipe Fill Material Dose Nuclide ROC? Mix Fraction Fraction Fraction Dose Fraction Fraction Sb-125 1.65E-04 1.39E-04 8.43E-05 1.58E-04 4.49E-05 Cs-134 1.67E-04 5.83E-04 4.73E-04 6.16E-04 3.10E-04 Cs-137 Y 5.55E-01 9.06E-01 8.70E-01 9.12E-01 8.17E-01 Ce-144 3.36E-06 2.75E-07 1.74E-07 3.13E-07 7.30E-08 Eu-152 Y 7.15E-04 1.81E-03 1.11E-03 2.04E-03 2.60E-05 Eu-154 1.13E-04 3.07E-04 1.88E-04 3.45E-04 5.95E-06 Eu-155 2.72E-04 1.98E-05 1.08E-05 2.22E-05 2.24E-06 Pu-238 3.01E-05 3.86E-06 1.02E-05 9.52E-06 3.14E-04 Pu-239/240 2.47E-05 3.51E-06 9.31E-06 8.67E-06 2.86E-04 Pu-241 4.77E-03 1.89E-05 5.50E-05 4.34E-05 1.07E-03 Am-241 1.32E-04 2.11E-05 5.19E-05 4.53E-05 9.41E-04 Cm-243/244 1.51E-05 5.01E-06 5.91E-06 7.08E-06 3.75E-05 Np-237 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sum 1.00E+00 1.00E+00 1.00E+00 1.00E+00 ROC 9.92E-01 9.76E-01 9.89E-01 9.11E-01 IC Dose 8.17E-03 2.39E-02 1.05E-02 8.88E-02 Table 35: Relative Dose Fractions, RDFi,k, Containment Mix Fraction, Using 75th Percentiles of the Averages, LLBP Scenarios R/D Concrete R/D Steel CB Mix Dose Dose Nuclide ROC? Fraction Fraction Fraction H-3 9.72E-02 1.71E-04 1.86E-04 C-14 Y 6.28E-01 1.01E-02 1.07E-02 Fe-55 8.86E-05 1.26E-11 1.04E-11 Co-58 3.56E-14 3.15E-60 2.65E-60 Ni-59 4.12E-04 1.23E-07 1.02E-07 Ni-63 3.98E-02 9.34E-06 8.17E-06 Co-60 Y 3.70E-03 2.83E-03 1.95E-03 Tc-99 2.87E-04 2.49E-04 2.49E-04 Sr-90 Y 3.70E-04 3.72E-05 5.90E-05 Sb-125 5.11E-05 1.66E-07 1.07E-07 Cs-134 4.86E-05 4.64E-08 4.74E-08 Cs-137 Y 2.26E-01 9.79E-01 9.80E-01 Ce-144 1.61E-06 3.04E-18 2.20E-18 Eu-152 Y 2.09E-03 7.59E-03 5.11E-03 Eu-154 1.21E-04 2.19E-04 1.33E-04 Eu-155 3.54E-05 2.31E-07 1.28E-07 Pu-238 1.39E-05 4.33E-05 1.82E-04 Pu-239/240 1.40E-05 6.05E-05 2.50E-04 Pu-241 1.75E-03 3.57E-05 1.23E-04 Am-241 3.32E-05 2.74E-06 8.06E-04 Cm-243/244 1.27E-05 2.65E-05 1.10E-04 Np-237 6.29E-07 9.42E-05 1.06E-04 Sum 1.00E+00 1.00E+00 ROC 9.99E-01 9.98E-01 IC Dose 9.12E-04 2.15E-03 Table 36: Relative Dose Fractions, RDFi,k, Containment Mix Fraction, Using 75th Percentiles of the Nuclide Ratios to Cs-137, LLBP Scenarios R/D Concrete R/D Steel Dose Nuclide ROC? CB Mix Fraction Dose Fraction Fraction H-3 8.70E-02 5.32E-04 5.83E-04 C-14 Y 8.27E-01 4.64E-02 4.93E-02

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 38 of 54 R/D Concrete R/D Steel Dose Nuclide ROC? CB Mix Fraction Dose Fraction Fraction Fe-55 1.43E-05 6.74E-12 5.58E-12 Co-58 1.47E-14 4.55E-60 3.85E-60 Ni-59 1.53E-04 1.60E-07 1.32E-07 Ni-63 1.76E-02 1.44E-05 1.27E-05 Co-60 Y 1.67E-03 4.45E-03 3.07E-03 Tc-99 3.41E-04 1.03E-03 1.04E-03 Sr-90 2.59E-04 9.07E-05 1.45E-04 Sb-125 1.89E-05 2.14E-07 1.38E-07 Cs-134 2.08E-05 6.94E-08 7.12E-08 Cs-137 Y 6.01E-02 9.08E-01 9.13E-01 Ce-144 1.52E-06 9.96E-18 7.25E-18 Eu-152 Y 2.95E-03 3.75E-02 2.54E-02 Eu-154 1.44E-04 9.11E-04 5.53E-04 Eu-155 4.09E-05 9.34E-07 5.17E-07 Pu-238 5.66E-06 6.13E-05 2.59E-04 Pu-239/240 1.06E-05 1.60E-04 6.65E-04 Pu-241 2.91E-03 2.08E-04 7.18E-04 Am-241 4.78E-05 1.38E-05 4.06E-03 Cm-243/244 1.27E-05 9.24E-05 3.83E-04 Np-237 1.24E-06 6.48E-04 7.31E-04 Sum 1.00E+00 1.00E+00 ROC 9.96E-01 9.91E-01 IC Dose 3.67E-03 9.01E-03 Table 37: Relative Dose Fractions, RDFi,k, AB/TB/RWPB Mix Fraction, Using 75th Percentiles of the Averages, LLBP Scenarios*

R/D AB EP 4.03 AB EP 18.81 TB EP 9.4 in Concrete R/D Steel AB/TB/RWPB in ID Dose in ID Dose ID Dose Dose Dose Nuclide ROC? Mix Fraction Fraction Fraction Fraction Fraction Fraction H-3 2.76E-02 2.33E-07 2.33E-07 2.33E-07 1.70E-05 1.85E-05 C-14 Y 4.43E-02 3.08E-06 3.08E-06 3.08E-06 2.50E-04 2.64E-04 Fe-55 1.42E-03 1.33E-12 1.33E-12 1.33E-12 6.76E-11 5.56E-11 Co-58 4.54E-14 5.45E-61 5.45E-61 5.45E-61 1.41E-60 1.19E-60 Ni-59 1.82E-03 2.72E-08 2.72E-08 2.72E-08 1.92E-07 1.58E-07 Ni-63 2.55E-01 8.40E-06 8.40E-06 8.40E-06 2.11E-05 1.84E-05 Co-60 Y 6.99E-03 1.69E-03 1.69E-03 1.69E-03 1.87E-03 1.29E-03 Tc-99 4.68E-04 2.86E-06 2.86E-06 2.86E-06 1.42E-04 1.42E-04 Sr-90 Y 2.79E-03 1.05E-04 1.05E-04 1.05E-04 9.85E-05 1.56E-04 Sb-125 1.81E-04 2.00E-07 2.00E-07 2.00E-07 2.07E-07 1.33E-07 Cs-134 1.16E-04 3.51E-08 3.51E-08 3.51E-08 3.90E-08 3.97E-08 Cs-137 Y 6.55E-01 9.98E-01 9.98E-01 9.98E-01 9.97E-01 9.96E-01 Ce-144 3.38E-06 1.63E-18 1.63E-18 1.63E-18 2.23E-18 1.62E-18 Eu-152 Y 5.09E-04 6.30E-04 6.30E-04 6.30E-04 6.52E-04 4.38E-04 Eu-154 6.67E-05 3.94E-05 3.94E-05 3.94E-05 4.26E-05 2.57E-05 Eu-155 1.69E-04 5.20E-07 5.20E-07 5.20E-07 3.88E-07 2.13E-07 Pu-238 3.69E-05 6.56E-07 6.56E-07 6.56E-07 4.03E-05 1.69E-04 Pu-239/240 3.01E-05 7.49E-07 7.49E-07 7.49E-07 4.58E-05 1.89E-04 Pu-241 3.19E-03 1.59E-06 1.59E-06 1.59E-06 2.29E-05 7.87E-05 Am-241 1.02E-04 7.81E-06 7.81E-06 7.81E-06 2.95E-06 8.66E-04 Cm-243/244 1.07E-05 3.28E-06 3.28E-06 3.28E-06 7.87E-06 3.24E-05 Np-237 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sum 1.00E+00 1.00E+00 1.00E+00 1.00E+00 1.00E+00 ROC 1.00E+00 1.00E+00 1.00E+00 1.00E+00 9.98E-01 IC Dose 6.57E-05 6.57E-05 6.57E-05 3.44E-04 1.54E-03

• The dose fractions for the Embedded Pipe scenarios differ slightly but round to the same number.

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 39 of 54 Table 38: Relative Dose Fractions, RDFi,k, AB/TB/RWPB Mix Fraction, Using 75th Percentiles of the Nuclide Ratios to Cs-137, LLBP Scenarios*

AB EP 4.03 in AB EP 18.81 in TB EP 9.4 in R/D R/D Steel AB/TB/RWPB ID Dose ID Dose ID Dose Concrete Dose Nuclide ROC? Mix Fraction Fraction Fraction Fraction Fraction Fraction H-3 2.52E-02 2.51E-07 2.51E-07 2.51E-07 1.83E-05 1.99E-05 C-14 Y 5.14E-02 4.21E-06 4.21E-06 4.21E-06 3.42E-04 3.61E-04 Fe-55 2.33E-03 2.57E-12 2.57E-12 2.57E-12 1.31E-10 1.07E-10 Co-58 7.00E-14 9.89E-61 9.89E-61 9.89E-61 2.56E-60 2.15E-60 Ni-59 2.48E-03 4.35E-08 4.35E-08 4.35E-08 3.06E-07 2.52E-07 Ni-63 3.43E-01 1.33E-05 1.33E-05 1.33E-05 3.32E-05 2.90E-05 Co-60 Y 1.15E-02 3.28E-03 3.28E-03 3.28E-03 3.63E-03 2.49E-03 Tc-99 5.23E-04 3.77E-06 3.77E-06 3.77E-06 1.87E-04 1.87E-04 Sr-90 Y 2.51E-03 1.11E-04 1.11E-04 1.11E-04 1.04E-04 1.65E-04 Sb-125 1.65E-04 2.14E-07 2.14E-07 2.14E-07 2.22E-07 1.42E-07 Cs-134 1.67E-04 5.93E-08 5.93E-08 5.93E-08 6.59E-08 6.72E-08 Cs-137 Y 5.55E-01 9.95E-01 9.95E-01 9.95E-01 9.94E-01 9.94E-01 Ce-144 3.36E-06 1.91E-18 1.91E-18 1.91E-18 2.62E-18 1.89E-18 Eu-152 Y 7.15E-04 1.04E-03 1.04E-03 1.04E-03 1.08E-03 7.23E-04 Eu-154 1.13E-04 7.82E-05 7.82E-05 7.82E-05 8.46E-05 5.10E-05 Eu-155 2.72E-04 9.88E-07 9.88E-07 9.88E-07 7.37E-07 4.05E-07 Pu-238 3.01E-05 6.31E-07 6.31E-07 6.31E-07 3.87E-05 1.62E-04 Pu-239/240 2.47E-05 7.23E-07 7.23E-07 7.23E-07 4.42E-05 1.82E-04 Pu-241 4.77E-03 2.79E-06 2.79E-06 2.79E-06 4.03E-05 1.39E-04 Am-241 1.32E-04 1.19E-05 1.19E-05 1.19E-05 4.51E-06 1.32E-03 Cm-243/244 1.51E-05 5.44E-06 5.44E-06 5.44E-06 1.30E-05 5.37E-05 Np-237 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sum 1.00E+00 1.00E+00 1.00E+00 1.00E+00 1.00E+00 ROC 1.00E+00 1.00E+00 1.00E+00 1.00E+00 9.98E-01 IC Dose 1.18E-04 1.18E-04 1.18E-04 4.65E-04 2.15E-03

• The dose fractions for the Embedded Pipe scenarios differ slightly but round to the same number.

In addition to the RDFs for each nuclide and population, Table 25 through Table 38 show the relative doses for the ROC and IC nuclides as ROC Fractional Dose and IC Fractional Dose, respectively. A summary of each location/scenario ROCs are provided in Table 39.

Table 39: Summary of ROC Lists Location/Scenario ROC List CB Walls and Floors C-14, Co-60, Sr-90, Cs-137, Eu-152 Soil (CB Mix), Backfill Material, Buried Pipe C-14, Co-60, Cs-137, Eu-152 Other Floors/Walls C-14, Co-60, Sr-90, Cs-137, Eu-152 AB/TB Embedded Pipes C-14, Co-60, Sr-90, Cs-137, Eu-152 AB/TB, RWPB Soil, Backfill Material, Buried Pipe C-14, Co-60, Cs-137, Eu-152 The evaluation shows that the IC dose fraction ranges from approximately 0.28% to 8.88% of the total dose depending on the source and the method used for determining the fractions. The highest value for

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 40 of 54 the IC dose fraction is from the AB/TB/RWPB mix fraction for the Backfill Material scenario using the 75 th percentiles of the nuclide ratios to Cs-137 statistical method.

The evaluations of the LLBP Scenarios shows that the relative doses for these scenarios for the IC nuclides are very small. The highest LLBP IC dose fraction being 0.90%. The highest value for the IC dose fraction is from the Steel Recycling/Disposal scenario in the CB using 75 th percentiles of the nuclide ratios to Cs-137.

6.3 Selection of Overall Nuclide Fraction To support FSS activities, a single radionuclide mix is desired for each potential source-term rather than a set of values as has been used in Sections 5.1 and 6.2 representing three statistical/mathematical methods. Evaluation of the three statistical methods, shows that the two methods involving the use of the 75th percentiles result in very similar results, particularly the IC dose fractions.

Using the 75th percentile provides sufficient overall conservatism in the development of the radionuclide mixtures. We do recognize that a higher percentile value will provide a different mixture profile, but such an approach would give undo weight to outliers of the sample populations. In addition, there is prior precedence in using the 75th percentile, particularly in the parameter selection process for dose modeling to support DCGL calculations and that this approach also results in satisfactory conservatism.

This approach was previously used in the development of the La Crosse Boiling Water Reactor (LACBWR) radionuclide mixtures as documented in Energy Solutions Technical Support Document RS-TD-313196-001 Radionuclides of Concern During LACBWR Decommissioning [17.].

For consistency and simplicity, we have chosen the 75th percentile of the Cs-137 fractions to represent the overall nuclide mix for the Containment Building sample population and the AB/TB/RWPB sample population as reproduced in Section 5.2. Table 40 shows the final radionuclide mixture fractions which have been selected for each mixture evaluated. These were the radionuclide mix fractions for the nuclides used to calculate the DCGLS and for the determination of ROCs and IC to dose.

Table 40: Final Radionuclide Mixtures for FCS Nuclide CB Mix AB/TB/RWPB Mix H-3 8.70E-02 2.52E-02 C-14 8.27E-01 5.14E-02 Fe-55 1.43E-05 2.33E-03 Co-58 1.47E-14 7.00E-14 Ni-59 1.53E-04 2.48E-03 Ni-63 1.76E-02 3.43E-01 Co-60 1.67E-03 1.15E-02 Tc-99 3.41E-04 5.23E-04 Sr-90 2.59E-04 2.51E-03 Sb-125 1.89E-05 1.65E-04 Cs-134 2.08E-05 1.67E-04 Cs-137 6.01E-02 5.55E-01 Ce-144 1.52E-06 3.36E-06 Eu-152 2.95E-03 7.15E-04 Eu-154 1.44E-04 1.13E-04 Eu-155 4.09E-05 2.72E-04

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 41 of 54 Nuclide CB Mix AB/TB/RWPB Mix Pu-238 5.66E-06 3.01E-05 Pu-239/240 1.06E-05 2.47E-05 Pu-241 2.91E-03 4.77E-03 Am-241 4.78E-05 1.32E-04 Cm-243/244 1.27E-05 1.51E-05 Np-237 1.24E-06 0.00E+00 6.4 ROC Mixture Fractions In order to support gross gamma measurements during characterization and final status surveys, an ROC mixture for gamma emitting radionuclides can be used to calculate the sensitivity of gross gamma detectors for a specific mixture. This determination begins with the re-normalized ROC fractions listed in Table 40 for the ROCs identified in Section 5.2. These fractions are provided in, Table 41 including the HTD radionuclides.

Table 41: ROC Mixture Fraction AB/TB/RWPB CB CB Fill AB/TB/RWPB CB Soil & Wall/Floor & AB/TB/RWPB Wall/Floor Material Soils & Buried Nuclide BP Mix Embedded Fill Material Mix Mix Pipe Mix Fraction Pipe Mix Mix Fraction Fraction Fraction Fraction Fraction C-14 9.27E-01 9.27E-01 9.27E-01 8.27E-02 8.30E-02 8.30E-02 Co-60 1.87E-03 1.87E-03 1.87E-03 1.85E-02 1.86E-02 1.86E-02 Sr-90 2.91E-04 0.00E+00 0.00E+00 4.04E-03 0.00E+00 0.00E+00 Cs-137 6.74E-02 6.74E-02 6.74E-02 8.94E-01 8.97E-01 8.97E-01 Eu-152 3.31E-03 3.31E-03 3.31E-03 1.15E-03 1.16E-03 1.16E-03 Using the data in Table 41, the ROC mixture fraction for only the gamma emitters is re-normalized against the total gamma ROC activity and shown in Table 42.

Table 42: Gamma ROC Mixture Fractions AB/TB/RWPB CB CB Fill AB/TB/RWPB CB Soil & Wall/Floor & AB/TB/RWPB Wall/Floor Material Soils & Buried Nuclide BP Mix Embedded Fill Material Mix Mix Pipe Mix Fraction Pipe Mix Mix Fraction Fraction Fraction Fraction Fraction Co-60 2.58E-02 2.58E-02 2.58E-02 2.03E-02 2.03E-02 2.03E-02 Cs-137 9.29E-01 9.29E-01 9.29E-01 9.78E-01 9.78E-01 9.78E-01 Eu-152 4.56E-02 4.56E-02 4.56E-02 1.26E-03 1.26E-03 1.26E-03 6.5 Surrogate Ratios From the data provided in sections 6.1, 6.2, 6.3 and 6.4, it is evident that Cs-137 is the predominant ROC gamma-emitting radionuclide. Co-60 and Eu-152 are also gamma emitting ROCs are present, but at much lower fractions than Cs-137. Also, C-14, and Sr-90 are identified as ROCs while also being HTD radionuclides.

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 42 of 54 Cs-137 was selected as the most appropriate gamma emitter for the surrogate relationship for both Sr-90 and C-14. This was based on the high percentage of Cs-137 (93-98%) and the low percentage of Co-60 (2.0-2.5%). Due to the high abundance of C-14 in the mix fractions (83% in the CB and 5% in the AB/TB/RWPB) the resulting surrogate ratio to Co-60 would have been impractical to use during additional characterization, remediation, and final status surveys. Due to instrument sensitivities and the high C-14/Co-60 ratios, it would not be possible to meet the required scan MDCs.

The ratio of HTDs to gamma emitters is required to develop a surrogate relationship as defined in MARSSIM. The concentration of HTDs can be inferred from the concentration of a gamma emitter in cases where samples are not subject to HTD analysis during FSS activities. Tables 42 and 43 show the decayed concentrations, MDCs and the Cs-137 ratios for each HTD ROC in each mixture fraction. As shown by an ND notation, there are some instances where HTDs and/or gamma emitters were not detected. These tables show the decayed reported activity if detected, and if not detected, the decayed MDC is used.

For the samples where neither nuclide was detected, the ratio of the MDCs was not used since this is merely a ratio of the detectability of the two nuclides for that specific sample and has no relationship to the activity ratio.

Of the 57 samples, 43 of the Sr-90, 55 of the C-14 and 56 of the Cs-137 results were greater than MDC.

One sample was non-detectable for both Sr-90 and Cs-137 and one sample was non-detectable for both C-14 and Cs-137.

Table 43: Sr-90 and Cs-137 Decayed Reported Concentrations, MDCs and Ratios Sr-90 Cs-137 Sr-90 Cs-137 Concentration Concentration Sr-90/Cs-Decayed Sr-90 Decayed Cs-137 Using Using 137 Ratio Reported Decayed Reported Decayed Reported or Reported or Using Concentrations MDCs Concentrations MDCs MDC Values MDC Values Reported or Sample ID Building (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) MDC Values 1100X-1-CJ-FCV1-005 CB 5.29E+00 2.32E-01 4.19E+03 1.78E+01 5.29E+00 4.19E+03 1.26E-03 1100X-1-CJ-WCV1-003 CB 8.53E+00 1.62E+00 1.37E+03 1.64E+02 8.53E+00 1.37E+03 6.24E-03 1100X-1-CJ-WCV1-004 CB 8.43E+00 5.30E-01 4.59E+03 1.44E+01 8.43E+00 4.59E+03 1.84E-03 1200X-1-CJ-FCV1-001 CB 6.02E-01 7.70E-02 1.07E+02 1.95E+00 6.02E-01 1.07E+02 5.64E-03 1200X-1-CJ-FCV1-002 CB 1.87E+00 1.38E-01 4.02E+02 5.19E+00 1.87E+00 4.02E+02 4.65E-03 1200X-1-CJ-FCV1-003 CB 3.67E+00 1.84E-01 9.20E+02 5.49E+00 3.67E+00 9.20E+02 3.99E-03 1200X-1-CJ-FCV1-010 CB 4.33E-01 6.33E-02 3.02E+02 3.47E+00 4.33E-01 3.02E+02 1.43E-03 1200X-1-CJ-FCV1-018 CB 3.85E-01 6.19E-02 2.15E+02 2.94E+00 3.85E-01 2.15E+02 1.79E-03 1200X-1-CJ-FCV1-023 CB 1.47E+01 3.53E-01 5.07E+03 1.36E+01 1.47E+01 5.07E+03 2.89E-03 1200X-1-CJ-FCV1-025 CB 1.78E+00 1.21E-01 8.21E+02 5.36E+00 1.78E+00 8.21E+02 2.16E-03 1200X-1-CJ-FCV1-027 CB 8.96E-01 9.30E-02 3.84E+03 1.20E+01 8.96E-01 3.84E+03 2.33E-04 1200X-1-CJ-WCV1-005 CB 9.13E-02 5.41E-02 8.04E+01 1.81E+00 9.13E-02 8.04E+01 1.14E-03 1200X-1-CJ-WCV1-006 CB 3.46E-01 2.29E-01 3.57E+01 4.34E+00 3.46E-01 3.57E+01 9.69E-03

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 43 of 54 Sr-90 Cs-137 Sr-90 Cs-137 Concentration Concentration Sr-90/Cs-Decayed Sr-90 Decayed Cs-137 Using Using 137 Ratio Reported Decayed Reported Decayed Reported or Reported or Using Concentrations MDCs Concentrations MDCs MDC Values MDC Values Reported or Sample ID Building (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) MDC Values 1200X-1-CJ-WCV1-008 CB 1.11E-01 1.49E-01 1.10E+01 1.08E+00 1.49E-01 1.10E+01 1.35E-02 1200X-1-CJ-WCV1-009 CB 6.97E-02 7.22E-02 2.55E+02 3.38E+00 7.22E-02 2.55E+02 2.83E-04 1200X-1-CJ-WCV1-011 CB 1.52E-01 1.40E-01 7.89E+01 7.42E+00 1.52E-01 7.89E+01 1.92E-03 1200X-1-CJ-WCV1-012 CB 2.47E-01 2.05E-01 4.53E+01 4.36E+00 2.47E-01 4.53E+01 5.45E-03 1200X-1-CJ-WCV1-015 CB 1.19E-01 2.04E-01 2.03E+01 2.23E+00 2.04E-01 2.03E+01 1.01E-02 1200X-1-CJ-WCV1-028 CB -7.76E-02 1.34E-01 1.29E+02 1.11E+01 1.34E-01 1.29E+02 1.04E-03 1200X-1-CJ-WCV1-029 CB 1.41E-02 1.85E-01 1.22E+01 1.45E+00 1.85E-01 1.22E+01 1.52E-02 1300X-1-CJ-FCV1-003 CB 4.34E-01 7.36E-02 4.60E+03 1.25E+01 4.34E-01 4.60E+03 9.45E-05 1300X-1-CJ-FCV1-005 CB 7.05E-02 1.53E-01 8.14E+01 8.70E+00 1.53E-01 8.14E+01 1.88E-03 1300X-1-CJ-FCV1-006 CB 2.07E-01 5.19E-02 7.56E+02 5.50E+00 2.07E-01 7.56E+02 2.73E-04 1300X-1-CJ-FCV1-008 CB 1.22E+00 1.08E-01 1.08E+03 6.89E+00 1.22E+00 1.08E+03 1.13E-03 1300X-1-CJ-WCV1-007 CB 1.89E-01 2.09E-01 5.26E+01 4.60E+00 2.09E-01 5.26E+01 3.96E-03 1400X-1-CJ-FCV1-002 CB 8.75E+00 3.41E-01 2.39E+03 9.59E+00 8.75E+00 2.39E+03 3.66E-03 1400X-1-CJ-FCV1-021 CB -2.04E-02 9.18E-02 7.83E+01 1.39E+00 9.18E-02 7.83E+01 1.17E-03 2100X-1-CJ-FCV1-001 AB 3.37E+00 7.15E-01 4.19E+02 4.68E+01 3.37E+00 4.19E+02 8.04E-03 2100X-1-CJ-FCV1-003 AB 7.31E-01 2.47E-01 2.47E+02 2.80E+01 7.31E-01 2.47E+02 2.96E-03 2100X-1-CJ-FCV1-005 AB 1.34E+00 3.77E-01 6.00E+02 4.94E+01 1.34E+00 6.00E+02 2.23E-03 2100X-1-CJ-FCV1-006 AB 3.76E-01 6.63E-02 9.76E+01 2.31E+00 3.76E-01 9.76E+01 3.85E-03 2100X-1-CJ-FCV1-011 AB 1.69E-01 5.33E-02 5.15E+01 1.33E+00 1.69E-01 5.15E+01 3.28E-03 2100X-1-CJ-FCV1-014 AB 2.10E-01 5.75E-02 1.14E+02 2.53E+00 2.10E-01 1.14E+02 1.84E-03 2200X-1-CJ-FCV1-006 AB 4.68E-02 1.94E-01 5.67E+02 4.94E+01 1.94E-01 5.67E+02 3.42E-04 2200X-1-CJ-FCV1-008 AB 1.47E+00 1.21E-01 1.04E+03 5.11E+00 1.47E+00 1.04E+03 1.41E-03 2200X-1-CJ-FCV1-010 AB 1.13E+00 9.77E-02 2.87E+02 3.78E+00 1.13E+00 2.87E+02 3.94E-03 2200X-1-CJ-FCV1-020 AB 6.53E+00 2.46E-01 1.04E+04 1.49E+01 6.53E+00 1.04E+04 6.26E-04 2200X-1-CJ-FCV1-021 AB 7.96E-01 2.93E-01 3.75E+02 3.95E+01 7.96E-01 3.75E+02 2.12E-03 2200X-1-CJ-FCV1-022 AB 1.51E+01 3.37E-01 1.60E+04 1.96E+01 1.51E+01 1.60E+04 9.45E-04 2200X-1-CJ-FCV1-026 AB 1.91E+01 3.92E-01 1.81E+04 2.52E+01 1.91E+01 1.81E+04 1.05E-03 2200X-1-CJ-FCV1-030 AB 1.11E+01 2.08E+00 2.42E+02 2.80E+01 1.11E+01 2.42E+02 4.61E-02 2200X-1-CJ-FCV1-031 AB 1.00E+00 9.09E-02 3.36E+02 2.68E+00 1.00E+00 3.36E+02 2.98E-03 2200X-1-CJ-FCV1-035 AB 1.50E+00 1.10E-01 7.22E+02 4.08E+00 1.50E+00 7.22E+02 2.08E-03 2200X-1-CJ-FCV1-038 AB 2.43E+00 5.73E-01 1.12E+02 1.10E+01 2.43E+00 1.12E+02 2.17E-02 2200X-1-CJ-FCV1-039 AB 4.49E+00 9.29E-01 1.20E+02 1.08E+01 4.49E+00 1.20E+02 3.74E-02 2200X-1-CJ-WCV1-009 AB -3.37E-02 4.17E-02 3.27E+01 1.12E+00 4.17E-02 3.27E+01 1.28E-03 2300X-1-CJ-FCV1-001 AB 1.54E+01 3.54E-01 6.48E+03 1.21E+01 1.54E+01 6.48E+03 2.37E-03 2300X-1-CJ-FCV1-002 AB 2.01E+01 4.12E-01 8.99E+03 1.40E+01 2.01E+01 8.99E+03 2.24E-03 2300X-1-CJ-FCV1-003 AB 1.04E+01 1.98E+00 5.10E+03 6.03E+02 1.04E+01 5.10E+03 2.05E-03

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 44 of 54 Sr-90 Cs-137 Sr-90 Cs-137 Concentration Concentration Sr-90/Cs-Decayed Sr-90 Decayed Cs-137 Using Using 137 Ratio Reported Decayed Reported Decayed Reported or Reported or Using Concentrations MDCs Concentrations MDCs MDC Values MDC Values Reported or Sample ID Building (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) MDC Values 2300X-1-CJ-FCV1-005 AB 5.50E+00 2.17E-01 3.09E+03 7.85E+00 5.50E+00 3.09E+03 1.78E-03 2300X-1-CJ-FCV1-007 AB 3.15E+00 3.20E-01 6.68E+02 5.04E+00 3.15E+00 6.68E+02 4.71E-03 2300X-1-CJ-FCV1-010 AB 1.67E-01 2.06E-01 4.60E+01 6.10E+00 2.06E-01 4.60E+01 4.47E-03 2600X-1-CJ-FCV1-002 AB 4.65E-02 4.66E-02 5.80E+01 1.53E+00 4.66E-02 5.80E+01 8.03E-04 3100X-3-CJ-FCV1-006 TB 9.00E-02 7.25E-02 3.03E-01 1.02E-01 9.00E-02 3.03E-01 2.97E-01 3100X-3-CJ-FCV1-014 TB 5.42E-02 5.85E-02 1.32E-01 1.81E-01 ND ND Not Used 4100X-1-CJ-FCV1-004 RWPB -2.87E-02 5.55E-02 5.86E+00 3.99E-01 5.55E-02 5.86E+00 9.46E-03 4100X-1-CJ-FCV1-005 RWPB 1.11E+00 9.09E-02 2.88E+00 3.11E-01 1.11E+00 2.88E+00 3.87E-01 Table 44: C-14 and Cs-137 Decayed Reported Concentrations, MDCs and Ratios C-14 Cs-137 C-14/Cs-137 Cs-137 Concentration Concentration Ratio Using C-14 Decayed C-14 Decayed Cs-137 Using Using Reported Reported Decayed Reported Decayed Reported or Reported or Concentrations Concentrations MDCs Concentrations MDCs MDC Values MDC Values or MDC Values Sample ID Building (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) 1100X-1-CJ-FCV1-005 CB 1.56E+03 1.26E+01 4.19E+03 1.78E+01 1.56E+03 4.19E+03 3.72E-01 1100X-1-CJ-WCV1-003 CB 2.06E+03 1.60E+02 1.37E+03 1.64E+02 2.06E+03 1.37E+03 1.51E+00 1100X-1-CJ-WCV1-004 CB 1.06E+03 1.06E+01 4.59E+03 1.44E+01 1.06E+03 4.59E+03 2.31E-01 1200X-1-CJ-FCV1-001 CB 1.53E+03 1.26E+01 1.07E+02 1.95E+00 1.53E+03 1.07E+02 1.43E+01 1200X-1-CJ-FCV1-002 CB 2.67E+03 1.64E+01 4.02E+02 5.19E+00 2.67E+03 4.02E+02 6.63E+00 1200X-1-CJ-FCV1-003 CB 1.99E+03 1.45E+01 9.20E+02 5.49E+00 1.99E+03 9.20E+02 2.16E+00 1200X-1-CJ-FCV1-010 CB 1.45E+02 4.29E+00 3.02E+02 3.47E+00 1.45E+02 3.02E+02 4.80E-01 1200X-1-CJ-FCV1-018 CB 1.59E+03 1.28E+01 2.15E+02 2.94E+00 1.59E+03 2.15E+02 7.39E+00 1200X-1-CJ-FCV1-023 CB 8.08E+01 3.21E+00 5.07E+03 1.36E+01 8.08E+01 5.07E+03 1.59E-02 1200X-1-CJ-FCV1-025 CB 2.70E+03 1.63E+01 8.21E+02 5.36E+00 2.70E+03 8.21E+02 3.29E+00 1200X-1-CJ-FCV1-027 CB 1.62E+03 1.23E+01 3.84E+03 1.20E+01 1.62E+03 3.84E+03 4.21E-01 1200X-1-CJ-WCV1-005 CB 7.18E+02 8.48E+00 8.04E+01 1.81E+00 7.18E+02 8.04E+01 8.94E+00 1200X-1-CJ-WCV1-006 CB 4.47E+03 3.46E+02 3.57E+01 4.34E+00 4.47E+03 3.57E+01 1.25E+02 1200X-1-CJ-WCV1-008 CB 4.69E+02 3.65E+01 1.10E+01 1.08E+00 4.69E+02 1.10E+01 4.25E+01 1200X-1-CJ-WCV1-009 CB 2.62E+03 1.58E+01 2.55E+02 3.38E+00 2.62E+03 2.55E+02 1.03E+01 1200X-1-CJ-WCV1-011 CB 5.63E+02 4.36E+01 7.89E+01 7.42E+00 5.63E+02 7.89E+01 7.13E+00

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 45 of 54 C-14 Cs-137 C-14/Cs-137 Cs-137 Concentration Concentration Ratio Using C-14 Decayed C-14 Decayed Cs-137 Using Using Reported Reported Decayed Reported Decayed Reported or Reported or Concentrations Concentrations MDCs Concentrations MDCs MDC Values MDC Values or MDC Values Sample ID Building (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) 1200X-1-CJ-WCV1-012 CB 3.54E+02 2.75E+01 4.53E+01 4.36E+00 3.54E+02 4.53E+01 7.81E+00 1200X-1-CJ-WCV1-015 CB 3.64E+02 2.83E+01 2.03E+01 2.23E+00 3.64E+02 2.03E+01 1.79E+01 1200X-1-CJ-WCV1-028 CB 2.52E+01 2.88E+00 1.29E+02 1.11E+01 2.52E+01 1.29E+02 1.96E-01 1200X-1-CJ-WCV1-029 CB 3.47E+02 2.70E+01 1.22E+01 1.45E+00 3.47E+02 1.22E+01 2.85E+01 1300X-1-CJ-FCV1-003 CB 1.41E+03 1.21E+01 4.60E+03 1.25E+01 1.41E+03 4.60E+03 3.06E-01 1300X-1-CJ-FCV1-005 CB 2.09E+03 1.62E+02 8.14E+01 8.70E+00 2.09E+03 8.14E+01 2.57E+01 1300X-1-CJ-FCV1-006 CB 1.72E+02 4.37E+00 7.56E+02 5.50E+00 1.72E+02 7.56E+02 2.27E-01 1300X-1-CJ-FCV1-008 CB 3.03E+02 5.74E+00 1.08E+03 6.89E+00 3.03E+02 1.08E+03 2.79E-01 1300X-1-CJ-WCV1-007 CB 6.94E+02 5.38E+01 5.26E+01 4.60E+00 6.94E+02 5.26E+01 1.32E+01 1400X-1-CJ-FCV1-002 CB 8.54E+03 3.19E+01 2.39E+03 9.59E+00 8.54E+03 2.39E+03 3.58E+00 1400X-1-CJ-FCV1-021 CB 2.07E+03 1.63E+01 7.83E+01 1.39E+00 2.07E+03 7.83E+01 2.64E+01 2100X-1-CJ-FCV1-001 AB 3.60E+00 1.96E+00 4.19E+02 4.68E+01 3.60E+00 4.19E+02 8.59E-03 2100X-1-CJ-FCV1-003 AB 8.38E+00 2.10E+00 2.47E+02 2.80E+01 8.38E+00 2.47E+02 3.40E-02 2100X-1-CJ-FCV1-005 AB 1.22E+01 2.27E+00 6.00E+02 4.94E+01 1.22E+01 6.00E+02 2.03E-02 2100X-1-CJ-FCV1-006 AB 2.87E+00 2.14E+00 9.76E+01 2.31E+00 2.87E+00 9.76E+01 2.94E-02 2100X-1-CJ-FCV1-011 AB 3.64E+00 2.26E+00 5.15E+01 1.33E+00 3.64E+00 5.15E+01 7.06E-02 2100X-1-CJ-FCV1-014 AB 7.84E+00 2.42E+00 1.14E+02 2.53E+00 7.84E+00 1.14E+02 6.89E-02 2200X-1-CJ-FCV1-006 AB 2.25E+01 2.73E+00 5.67E+02 4.94E+01 2.25E+01 5.67E+02 3.97E-02 2200X-1-CJ-FCV1-008 AB 2.38E+01 2.69E+00 1.04E+03 5.11E+00 2.38E+01 1.04E+03 2.28E-02 2200X-1-CJ-FCV1-010 AB 9.14E+00 2.36E+00 2.87E+02 3.78E+00 9.14E+00 2.87E+02 3.19E-02 2200X-1-CJ-FCV1-020 AB 1.99E+01 2.56E+00 1.04E+04 1.49E+01 1.99E+01 1.04E+04 1.90E-03 2200X-1-CJ-FCV1-021 AB 1.35E+01 2.29E+00 3.75E+02 3.95E+01 1.35E+01 3.75E+02 3.60E-02 2200X-1-CJ-FCV1-022 AB 2.28E+01 2.60E+00 1.60E+04 1.96E+01 2.28E+01 1.60E+04 1.42E-03 2200X-1-CJ-FCV1-026 AB 1.31E+01 2.44E+00 1.81E+04 2.52E+01 1.31E+01 1.81E+04 7.22E-04 2200X-1-CJ-FCV1-030 AB 9.57E+01 7.81E+00 2.42E+02 2.80E+01 9.57E+01 2.42E+02 3.96E-01 2200X-1-CJ-FCV1-031 AB 4.97E+00 2.17E+00 3.36E+02 2.68E+00 4.97E+00 3.36E+02 1.48E-02 2200X-1-CJ-FCV1-035 AB 1.93E+01 2.57E+00 7.22E+02 4.08E+00 1.93E+01 7.22E+02 2.67E-02 2200X-1-CJ-FCV1-038 AB 7.90E+00 2.08E+00 1.12E+02 1.10E+01 7.90E+00 1.12E+02 7.06E-02 2200X-1-CJ-FCV1-039 AB 1.18E+01 2.12E+00 1.20E+02 1.08E+01 1.18E+01 1.20E+02 9.83E-02 2200X-1-CJ-WCV1-009 AB 1.88E+01 2.43E+00 3.27E+01 1.12E+00 1.88E+01 3.27E+01 5.74E-01 2300X-1-CJ-FCV1-001 AB 7.98E+01 3.69E+00 6.48E+03 1.21E+01 7.98E+01 6.48E+03 1.23E-02 2300X-1-CJ-FCV1-002 AB 5.28E+01 3.28E+00 8.99E+03 1.40E+01 5.28E+01 8.99E+03 5.87E-03 2300X-1-CJ-FCV1-003 AB 1.38E+02 1.09E+01 5.10E+03 6.03E+02 1.38E+02 5.10E+03 2.71E-02 2300X-1-CJ-FCV1-005 AB 3.25E+01 2.83E+00 3.09E+03 7.85E+00 3.25E+01 3.09E+03 1.05E-02 2300X-1-CJ-FCV1-007 AB 5.02E+01 3.37E+00 6.68E+02 5.04E+00 5.02E+01 6.68E+02 7.51E-02 2300X-1-CJ-FCV1-010 AB 2.57E+00 1.92E+00 4.60E+01 6.10E+00 2.57E+00 4.60E+01 5.58E-02

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 46 of 54 C-14 Cs-137 C-14/Cs-137 Cs-137 Concentration Concentration Ratio Using C-14 Decayed C-14 Decayed Cs-137 Using Using Reported Reported Decayed Reported Decayed Reported or Reported or Concentrations Concentrations MDCs Concentrations MDCs MDC Values MDC Values or MDC Values Sample ID Building (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) 2600X-1-CJ-FCV1-002 AB 2.42E+01 2.66E+00 5.80E+01 1.53E+00 2.42E+01 5.80E+01 4.17E-01 3100X-3-CJ-FCV1-006 TB 3.26E+00 2.32E+00 3.03E-01 1.02E-01 3.26E+00 3.03E-01 1.08E+01 3100X-3-CJ-FCV1-014 TB 1.82E+00 2.15E+00 1.32E-01 1.81E-01 ND ND Not Used 4100X-1-CJ-FCV1-004 RWPB 8.04E+00 2.25E+00 5.86E+00 3.99E-01 8.04E+00 5.86E+00 1.37E+00 4100X-1-CJ-FCV1-005 RWPB 8.46E-01 2.09E+00 2.88E+00 3.11E-01 2.09E+00 2.88E+00 7.26E-01 For each set of ratios, the average, minimum, maximum, standard deviation, % coefficient of variation, 75th and 95th percentile of the ratios is shown for each sample population in Table 45 and Table 46.

To account for the variability and level of uncertainty in the data, the 95 th percentile values were selected for the final surrogate ratios. Using the 95 th percentile value along with the MDC substituted will provide reasonable conservatism during the final status surveys.

Table 45: Sr-90/Cs-137 Ratio Sr-90/Cs-137 Based on Reported or MDC Concentrations Parameter CB Sample AB/TB/RWPB Population Sample Population Average 3.80E-03 2.95E-02 Minimum 9.45E-05 3.42E-04 Maximum 1.52E-02 3.87E-01 Standard 4.03E-03 8.96E-02 Deviation

% Coefficient of 1.06E+00 303.37%

Variation 75th Percentile 5.05E-03 4.71E-03 95th Percentile 1.25E-02 1.97E-01 Table 46: C-14/Cs-137 Ratio C-14/Cs-137 Based on Reported or MDC Concentrations Parameter CB Sample AB/TB/RWPB Population Sample Population Average 1.31E+01 5.17E-01 Minimum 1.59E-02 7.22E-04 Maximum 1.25E+02 1.08E+01 Standard 2.49E+01 2.03E+00 Deviation

% Coefficient 189.27% 391.43%

of Variation 75th Percentile 1.38E+01 7.51E-02 95th Percentile 3.83E+01 1.11E+00

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 47 of 54 Cs-137 was selected as the most appropriate surrogate for Sr-90 and C-14.

Table 47: Cs-137 Surrogate Ratios Nuclide Ratioed to Mix Fraction Cs-137 Value CB C-14 38.3 AB/TB/RWPB C-14 1.11 CB Sr-90 0.0125 AB/TB/RWPB Sr-90 0.197 7

References:

[1.] U.S. Nuclear Regulatory Commission, Consolidated Decommissioning Guidance:

Decommissioning Process for Material Licensees, NUREG-1757 Volume 2, Revision 2, 2006.

[2.] U.S. Nuclear Regulatory Commission, Long-Lived Activation Products in Reactor Materials, Pacific Northwest Laboratory, NUREG/CR-3474,1984.

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

[4.] FC-18-002, Potential Radionuclides of Concern During the Decommissioning of Fort Calhoun Station, Fort Calhoun Station Technical Basis Document, 2018.

[5.] FC-20-007 Fort Calhoun Station Potential Radionuclides of Concern, Fort Calhoun Station Technical Basis Document, 2020.

[6.] FC-18-003 Evaluation of Cs-137 Global Fallout in Soils at Fort Calhoun Station, 2018.

[7.] Oak Ride Institute of Science and Education, Confirmatory Survey Summary and Results for the Non-Impacted Land Areas Associated with the Fort Calhoun Nuclear Generating Station, Blair, Nebraska, 2019.

[8.] Fort Calhoun Characterization Sample Plan, Survey Area 1000, 2019.

[9.] Fort Calhoun Characterization Sample Plan, Survey Area 2000, 2019.

[10.] Fort Calhoun Characterization Sample Plan, Survey Area 3000, 2019.

[11.] Fort Calhoun Characterization Sample Plan, Survey Area 4000, 2019.

[12.] ENRG078, WO No. 518752, Charleston, SC,: GEL Laboratories LLC, 2020

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 48 of 54

[13.] ENRG078, WO No. 499910, Charleston, SC,: GEL Laboratories LLC, 2020.

[14.] ENRG078, WO No. 499244, Charleston, SC: GEL Laboratories LLC, 2020.

[15.] ENRG078, WO No. 505229, Charleston, SC: GEL Laboratories LLC, 2020.

[16.] ENRG078, WO No. 539900, Charleston, SC: GEL Laboratories LLC, 2020.

[17.] RS-TD-313196-001 Radionuclides of Concern During LACBWR Decommissioning, Energy Solutions Technical Support Document, 2018.

8 Attachments:

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 49 of 54 8.1 Attachment 1: Decay Corrected Analytical Results for Concrete Samples, With Negative Value Reset to Zero Table 48: Sample Analytical Results, First Set of Radionuclides (pCi/g)

Sample ID H-3 C-14 Fe-55 Co-58 Ni-59 Ni-63 Co-60 Tc-99 1100X-1-CJ-FCV1-005 1.24E+03 1.56E+03 7.13E+02 0.00E+00 1.12E+01 1.00E+03 4.59E+02 4.51E-02 1100X-1-CJ-WCV1-003 5.75E+02 2.06E+03 8.46E+02 0.00E+00 0.00E+00 8.25E+02 4.18E+02 7.76E-01 1100X-1-CJ-WCV1-004 2.07E+03 1.06E+03 7.55E+02 1.29E-09 3.10E+01 2.25E+03 9.39E+02 2.56E+00 1200X-1-CJ-FCV1-001 5.45E+02 1.53E+03 0.00E+00 2.23E-11 7.12E-02 1.24E+02 2.01E+01 6.85E-01 1200X-1-CJ-FCV1-002 5.31E+02 2.67E+03 1.04E+00 0.00E+00 0.00E+00 5.19E+02 3.65E+01 4.11E-01 1200X-1-CJ-FCV1-003 5.10E+02 1.99E+03 0.00E+00 1.21E-12 2.23E+00 1.94E+02 1.76E+01 5.62E-01 1200X-1-CJ-FCV1-010 6.42E+02 1.45E+02 0.00E+00 0.00E+00 0.00E+00 1.35E+02 5.31E+00 4.07E-01 1200X-1-CJ-FCV1-018 6.21E+02 1.59E+03 1.19E+00 2.20E-12 0.00E+00 5.50E+01 7.62E-01 8.56E-02 1200X-1-CJ-FCV1-023 1.93E+02 8.08E+01 0.00E+00 1.37E-11 1.09E+01 1.08E+03 3.31E+01 2.09E-01 1200X-1-CJ-FCV1-025 4.81E+02 2.70E+03 0.00E+00 0.00E+00 2.31E-01 1.14E+02 5.10E+00 2.43E-01 1200X-1-CJ-FCV1-027 3.72E+02 1.62E+03 0.00E+00 2.61E-11 8.96E-01 9.55E+01 1.34E+01 0.00E+00 1200X-1-CJ-WCV1-005 2.32E+02 7.18E+02 0.00E+00 0.00E+00 4.68E-02 2.07E+01 1.02E+00 2.21E-01 1200X-1-CJ-WCV1-006 1.07E+01 4.47E+03 0.00E+00 2.51E-09 5.76E-01 3.50E+00 5.69E-01 0.00E+00 1200X-1-CJ-WCV1-008 3.30E+01 4.69E+02 0.00E+00 2.77E-08 1.10E+00 1.00E+01 1.01E+00 2.33E-01 1200X-1-CJ-WCV1-009 1.70E+02 2.62E+03 0.00E+00 1.85E-11 5.12E-01 1.03E+01 3.94E-01 6.60E-02 1200X-1-CJ-WCV1-011 3.42E+01 5.63E+02 0.00E+00 7.15E-09 0.00E+00 2.01E+00 1.31E-01 3.89E-01 1200X-1-CJ-WCV1-012 2.92E+01 3.54E+02 0.00E+00 2.35E-08 2.21E-01 1.49E+01 3.02E-01 2.04E+00 1200X-1-CJ-WCV1-015 2.82E+01 3.64E+02 0.00E+00 0.00E+00 0.00E+00 1.04E+00 2.94E-01 1.75E+00 1200X-1-CJ-WCV1-028 1.29E+01 2.52E+01 0.00E+00 9.43E-10 1.53E+00 4.94E+00 4.70E+00 8.34E+00 1200X-1-CJ-WCV1-029 1.83E+01 3.47E+02 0.00E+00 0.00E+00 0.00E+00 2.02E+00 2.27E-01 4.63E+00 1300X-1-CJ-FCV1-003 2.84E+02 1.41E+03 0.00E+00 0.00E+00 0.00E+00 1.40E+02 7.75E+00 4.44E-01 1300X-1-CJ-FCV1-005 5.63E+01 2.09E+03 0.00E+00 4.67E-09 3.27E-01 8.92E+00 1.11E+00 0.00E+00 1300X-1-CJ-FCV1-006 1.35E+02 1.72E+02 1.00E+00 6.11E-12 0.00E+00 3.38E+01 1.04E+00 0.00E+00 1300X-1-CJ-FCV1-008 5.61E+01 3.03E+02 5.15E-01 1.79E-11 1.69E+00 4.02E+01 1.29E+00 1.01E-01 1300X-1-CJ-WCV1-007 2.92E+01 6.94E+02 0.00E+00 0.00E+00 0.00E+00 5.44E+00 1.65E-01 2.53E+00 1400X-1-CJ-FCV1-002 2.65E+02 8.54E+03 0.00E+00 6.72E-13 2.03E+00 4.64E+01 1.43E+00 1.72E-01 1400X-1-CJ-FCV1-021 3.47E+02 2.07E+03 0.00E+00 0.00E+00 1.86E-01 6.08E+00 1.46E+00 1.76E-01 2100X-1-CJ-FCV1-001 2.40E+00 3.60E+00 0.00E+00 1.34E-08 1.87E+00 3.49E+02 5.01E-01 5.63E-01 2100X-1-CJ-FCV1-003 3.84E+00 8.38E+00 2.17E+00 2.01E-10 9.32E+00 1.16E+03 6.71E-01 8.08E-03 2100X-1-CJ-FCV1-005 1.41E+01 1.22E+01 0.00E+00 0.00E+00 0.00E+00 3.42E+01 4.72E-01 1.58E-01 2100X-1-CJ-FCV1-006 2.04E+01 2.87E+00 0.00E+00 5.22E-12 0.00E+00 3.09E+01 1.12E+00 1.14E-01 2100X-1-CJ-FCV1-011 4.82E+00 3.64E+00 0.00E+00 0.00E+00 4.02E-01 5.92E+01 1.78E+00 5.53E+00 2100X-1-CJ-FCV1-014 7.73E-01 7.84E+00 0.00E+00 0.00E+00 0.00E+00 4.59E+01 4.01E-01 2.60E+01 2200X-1-CJ-FCV1-006 1.65E+00 2.25E+01 0.00E+00 5.28E-09 8.01E-01 7.59E+01 4.10E-01 1.09E+01 2200X-1-CJ-FCV1-008 6.38E+01 2.38E+01 0.00E+00 7.99E-12 0.00E+00 9.04E+01 1.94E+01 0.00E+00 2200X-1-CJ-FCV1-010 1.26E+01 9.14E+00 0.00E+00 0.00E+00 0.00E+00 1.30E+02 4.11E+00 0.00E+00 2200X-1-CJ-FCV1-020 3.99E+01 1.99E+01 6.75E-01 1.70E-11 4.91E+00 1.35E+03 9.59E+00 1.61E+00 2200X-1-CJ-FCV1-021 2.01E+00 1.35E+01 0.00E+00 0.00E+00 0.00E+00 1.18E+02 3.49E-01 0.00E+00 2200X-1-CJ-FCV1-022 1.10E+01 2.28E+01 8.63E-02 0.00E+00 6.56E+00 6.13E+02 5.29E-01 0.00E+00 2200X-1-CJ-FCV1-026 1.15E+01 1.31E+01 1.15E-01 6.02E-12 0.00E+00 1.81E+02 0.00E+00 0.00E+00 2200X-1-CJ-FCV1-030 4.61E+01 9.57E+01 4.25E+00 0.00E+00 8.61E+00 7.44E+02 7.06E+01 0.00E+00 2200X-1-CJ-FCV1-031 1.64E+02 4.97E+00 1.54E+00 2.10E-12 2.37E+00 2.17E+02 2.95E+00 0.00E+00 2200X-1-CJ-FCV1-035 8.67E+00 1.93E+01 2.21E+00 3.70E-12 3.21E+00 3.87E+02 7.54E+00 0.00E+00 2200X-1-CJ-FCV1-038 1.90E+00 7.90E+00 0.00E+00 1.32E-08 4.79E-01 1.28E+02 2.34E+00 0.00E+00 2200X-1-CJ-FCV1-039 4.39E+00 1.18E+01 0.00E+00 0.00E+00 6.36E-01 1.47E+02 2.62E+00 0.00E+00 2200X-1-CJ-WCV1-009 4.23E+00 1.88E+01 0.00E+00 0.00E+00 1.08E+00 5.97E+00 1.84E-01 4.35E-01 2300X-1-CJ-FCV1-001 1.71E+00 7.98E+01 2.57E+00 0.00E+00 3.41E+00 3.00E+02 4.14E-01 0.00E+00 2300X-1-CJ-FCV1-002 9.56E+00 5.28E+01 2.46E-01 0.00E+00 6.57E+00 7.38E+02 3.45E+00 0.00E+00 2300X-1-CJ-FCV1-003 2.97E+00 1.38E+02 6.32E+00 0.00E+00 7.27E+00 9.18E+02 6.52E+01 1.36E-01 2300X-1-CJ-FCV1-005 3.77E+00 3.25E+01 4.22E+00 0.00E+00 4.10E+00 3.95E+02 1.15E+00 1.81E-01 2300X-1-CJ-FCV1-007 3.06E+01 5.02E+01 0.00E+00 6.72E-12 0.00E+00 5.44E+01 3.19E+00 0.00E+00 2300X-1-CJ-FCV1-010 0.00E+00 2.57E+00 1.60E+00 1.26E-07 0.00E+00 1.03E+01 1.02E+00 6.28E-01

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 50 of 54 Sample ID H-3 C-14 Fe-55 Co-58 Ni-59 Ni-63 Co-60 Tc-99 2600X-1-CJ-FCV1-002 9.98E+00 2.42E+01 0.00E+00 0.00E+00 0.00E+00 1.82E+01 7.94E-01 1.51E-01 3100X-3-CJ-FCV1-006 0.00E+00 3.26E+00 2.87E-01 9.13E-13 0.00E+00 0.00E+00 1.03E-02 0.00E+00 3100X-3-CJ-FCV1-014 0.00E+00 1.82E+00 3.41E-02 7.99E-13 0.00E+00 1.63E+00 2.28E-02 0.00E+00 4100X-1-CJ-FCV1-004 0.00E+00 8.04E+00 4.22E-01 0.00E+00 7.16E-01 1.77E+00 1.18E-01 0.00E+00 4100X-1-CJ-FCV1-005 0.00E+00 8.46E-01 6.12E-01 4.32E-13 1.65E-04 3.83E-01 2.57E-01 0.00E+00 Table 49: Sample Analytical Results, Second Set of Radionuclides (pCi/g)

Sample ID Sr-90 Sb-125 Cs-134 Cs-137 Ce-144 Eu-152 Eu-154 1100X-1-CJ-FCV1-005 5.29E+00 0.00E+00 1.42E+01 4.19E+03 0.00E+00 3.98E+03 3.64E+02 1100X-1-CJ-WCV1-003 8.53E+00 0.00E+00 1.78E+01 1.37E+03 2.26E-01 3.78E+03 3.46E+02 1100X-1-CJ-WCV1-004 8.43E+00 0.00E+00 1.19E+01 4.59E+03 0.00E+00 3.46E+03 3.29E+02 1200X-1-CJ-FCV1-001 6.02E-01 1.10E-01 1.18E-02 1.07E+02 8.79E-04 0.00E+00 2.68E-01 1200X-1-CJ-FCV1-002 1.87E+00 0.00E+00 4.73E-02 4.02E+02 0.00E+00 1.20E-01 0.00E+00 1200X-1-CJ-FCV1-003 3.67E+00 5.88E-02 1.27E-01 9.20E+02 6.53E-04 0.00E+00 2.93E-01 1200X-1-CJ-FCV1-010 4.33E-01 0.00E+00 7.03E-03 3.02E+02 2.32E-03 1.69E+00 1.01E-02 1200X-1-CJ-FCV1-018 3.85E-01 2.34E-01 1.77E-02 2.15E+02 0.00E+00 1.11E-02 0.00E+00 1200X-1-CJ-FCV1-023 1.47E+01 1.28E+00 4.16E-01 5.07E+03 8.18E-03 1.86E-01 8.22E-02 1200X-1-CJ-FCV1-025 1.78E+00 5.96E-01 4.41E-02 8.21E+02 4.87E-03 0.00E+00 0.00E+00 1200X-1-CJ-FCV1-027 8.96E-01 3.32E-01 3.94E-01 3.84E+03 0.00E+00 2.86E-01 0.00E+00 1200X-1-CJ-WCV1-005 9.13E-02 7.21E-02 3.89E-03 8.04E+01 2.58E-03 0.00E+00 1.66E-01 1200X-1-CJ-WCV1-006 3.46E-01 5.86E-04 1.30E-02 3.57E+01 6.56E-03 1.79E+00 7.34E-02 1200X-1-CJ-WCV1-008 1.11E-01 0.00E+00 2.54E-03 1.10E+01 9.21E-03 9.59E-01 8.77E-02 1200X-1-CJ-WCV1-009 6.97E-02 0.00E+00 6.29E-03 2.55E+02 0.00E+00 9.57E-01 1.43E-01 1200X-1-CJ-WCV1-011 1.52E-01 0.00E+00 1.51E-02 7.89E+01 1.12E-02 2.10E+00 1.33E-01 1200X-1-CJ-WCV1-012 2.47E-01 1.05E-01 1.06E-02 4.53E+01 3.77E-03 2.18E+00 1.05E-01 1200X-1-CJ-WCV1-015 1.19E-01 0.00E+00 1.40E-02 2.03E+01 2.20E-03 1.05E+00 2.18E-01 1200X-1-CJ-WCV1-028 0.00E+00 4.84E-02 6.00E-02 1.29E+02 0.00E+00 1.17E+00 3.01E-02 1200X-1-CJ-WCV1-029 1.41E-02 3.56E-02 2.37E-02 1.22E+01 0.00E+00 1.31E+00 3.01E-02 1300X-1-CJ-FCV1-003 4.34E-01 1.34E-01 4.33E-01 4.60E+03 0.00E+00 0.00E+00 4.32E-02 1300X-1-CJ-FCV1-005 7.05E-02 1.26E-02 2.68E-02 8.14E+01 1.50E-03 1.27E-01 5.79E-03 1300X-1-CJ-FCV1-006 2.07E-01 7.57E-02 9.91E-02 7.56E+02 2.89E-04 0.00E+00 0.00E+00 1300X-1-CJ-FCV1-008 1.22E+00 3.95E-02 6.30E-02 1.08E+03 3.77E-03 1.35E+00 2.04E-01 1300X-1-CJ-WCV1-007 1.89E-01 0.00E+00 1.52E-02 5.26E+01 0.00E+00 6.84E-01 0.00E+00 1400X-1-CJ-FCV1-002 8.75E+00 7.65E-02 2.43E-02 2.39E+03 6.31E-03 0.00E+00 1.85E-01 1400X-1-CJ-FCV1-021 0.00E+00 0.00E+00 0.00E+00 7.83E+01 0.00E+00 3.69E-01 5.78E-02 2100X-1-CJ-FCV1-001 3.37E+00 3.33E-02 1.09E-02 4.19E+02 0.00E+00 0.00E+00 5.88E-02 2100X-1-CJ-FCV1-003 7.31E-01 0.00E+00 1.52E-03 2.47E+02 0.00E+00 2.39E-01 7.73E-02 2100X-1-CJ-FCV1-005 1.34E+00 1.71E-01 2.19E-01 6.00E+02 2.33E-02 9.97E-01 0.00E+00 2100X-1-CJ-FCV1-006 3.76E-01 0.00E+00 1.30E-02 9.76E+01 4.34E-04 2.99E-01 5.03E-02 2100X-1-CJ-FCV1-011 1.69E-01 0.00E+00 1.50E-02 5.15E+01 0.00E+00 0.00E+00 2.44E-03 2100X-1-CJ-FCV1-014 2.10E-01 2.16E-02 8.96E-03 1.14E+02 2.54E-03 0.00E+00 0.00E+00 2200X-1-CJ-FCV1-006 4.68E-02 0.00E+00 2.97E-02 5.67E+02 0.00E+00 4.12E-01 4.20E-02 2200X-1-CJ-FCV1-008 1.47E+00 3.15E-01 1.50E-01 1.04E+03 2.32E-04 0.00E+00 1.10E-01 2200X-1-CJ-FCV1-010 1.13E+00 2.56E-01 0.00E+00 2.87E+02 0.00E+00 2.37E-01 0.00E+00 2200X-1-CJ-FCV1-020 6.53E+00 6.58E-01 2.70E+00 1.04E+04 2.01E-03 2.23E+00 3.46E-02 2200X-1-CJ-FCV1-021 7.96E-01 0.00E+00 0.00E+00 3.75E+02 2.47E-03 0.00E+00 0.00E+00 2200X-1-CJ-FCV1-022 1.51E+01 0.00E+00 2.68E-02 1.60E+04 0.00E+00 1.14E+00 0.00E+00 2200X-1-CJ-FCV1-026 1.91E+01 0.00E+00 2.31E-02 1.81E+04 1.10E-02 1.70E+00 0.00E+00 2200X-1-CJ-FCV1-030 1.11E+01 4.80E-01 1.52E-01 2.42E+02 0.00E+00 3.37E-01 0.00E+00 2200X-1-CJ-FCV1-031 1.00E+00 0.00E+00 2.22E-02 3.36E+02 1.40E-03 0.00E+00 4.58E-02 2200X-1-CJ-FCV1-035 1.50E+00 9.26E-02 1.91E-02 7.22E+02 4.03E-04 9.89E-02 3.93E-02 2200X-1-CJ-FCV1-038 2.43E+00 4.40E-02 4.98E-02 1.12E+02 8.48E-03 4.46E-02 0.00E+00 2200X-1-CJ-FCV1-039 4.49E+00 3.06E-02 1.35E-02 1.20E+02 0.00E+00 4.29E-01 9.23E-02 2200X-1-CJ-WCV1-009 0.00E+00 0.00E+00 9.94E-03 3.27E+01 0.00E+00 0.00E+00 0.00E+00 2300X-1-CJ-FCV1-001 1.54E+01 0.00E+00 0.00E+00 6.48E+03 1.00E-03 0.00E+00 3.93E-02 2300X-1-CJ-FCV1-002 2.01E+01 1.32E-01 2.14E-02 8.99E+03 0.00E+00 1.24E+00 4.24E-02 2300X-1-CJ-FCV1-003 1.04E+01 3.11E-01 0.00E+00 5.10E+03 0.00E+00 0.00E+00 2.35E-01 2300X-1-CJ-FCV1-005 5.50E+00 0.00E+00 8.34E-03 3.09E+03 9.93E-04 0.00E+00 0.00E+00

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 51 of 54 Sample ID Sr-90 Sb-125 Cs-134 Cs-137 Ce-144 Eu-152 Eu-154 2300X-1-CJ-FCV1-007 3.15E+00 2.15E-01 2.41E-01 6.68E+02 6.30E-03 3.88E-01 1.49E-01 2300X-1-CJ-FCV1-010 1.67E-01 0.00E+00 3.36E-02 4.60E+01 0.00E+00 4.19E-02 0.00E+00 2600X-1-CJ-FCV1-002 4.65E-02 2.43E-03 1.19E-02 5.80E+01 0.00E+00 6.45E-01 6.46E-02 3100X-3-CJ-FCV1-006 9.00E-02 8.86E-03 0.00E+00 3.03E-01 3.74E-04 5.75E-02 0.00E+00 3100X-3-CJ-FCV1-014 5.42E-02 2.31E-03 1.23E-02 1.32E-01 1.32E-03 0.00E+00 2.04E-01 4100X-1-CJ-FCV1-004 0.00E+00 0.00E+00 9.18E-03 5.86E+00 0.00E+00 4.95E-02 1.25E-01 4100X-1-CJ-FCV1-005 1.11E+00 2.75E-02 0.00E+00 2.88E+00 3.23E-04 6.16E-02 6.04E-02 Table 50: Sample Analytical Results, Third Set of Radionuclides (pCi/g)

Sample ID Eu-155 Pu-238 Pu-239/240 Pu-241 Am-241 Cm- Np-237 243/244 1100X-1-CJ-FCV1-005 7.03E+00 2.87E-01 1.23E+00 7.18E+00 4.02E-01 9.03E-02 NA 1100X-1-CJ-WCV1-003 5.85E+00 2.61E-01 1.11E+00 5.45E+00 3.46E-01 3.92E-02 5.18E-03 1100X-1-CJ-WCV1-004 2.76E+00 1.39E+00 1.72E+00 1.76E+01 2.70E+00 6.33E-01 NA 1200X-1-CJ-FCV1-001 7.53E-02 4.28E-02 0.00E+00 4.86E+00 9.95E-02 4.63E-03 NA 1200X-1-CJ-FCV1-002 0.00E+00 2.48E-01 8.37E-02 3.92E+00 5.33E-01 1.43E-01 NA 1200X-1-CJ-FCV1-003 0.00E+00 5.73E-02 4.92E-02 3.54E+00 1.40E-01 3.36E-02 NA 1200X-1-CJ-FCV1-010 1.81E-02 1.50E-02 0.00E+00 1.77E+00 5.70E-02 1.12E-02 NA 1200X-1-CJ-FCV1-018 0.00E+00 1.99E-02 0.00E+00 1.75E+00 3.07E-02 2.68E-03 NA 1200X-1-CJ-FCV1-023 0.00E+00 6.85E-01 3.98E-01 1.13E+01 1.08E+00 9.89E-02 NA 1200X-1-CJ-FCV1-025 0.00E+00 1.78E-03 1.01E-02 2.76E+00 4.32E-02 0.00E+00 NA 1200X-1-CJ-FCV1-027 0.00E+00 7.46E-03 1.07E-02 3.87E+00 5.58E-02 1.45E-03 NA 1200X-1-CJ-WCV1-005 7.72E-02 7.69E-03 0.00E+00 4.13E+00 6.38E-02 0.00E+00 NA 1200X-1-CJ-WCV1-006 1.40E-02 1.68E-03 5.19E-03 2.60E+00 6.43E-02 0.00E+00 0.00E+00 1200X-1-CJ-WCV1-008 0.00E+00 0.00E+00 0.00E+00 4.41E+00 9.80E-03 6.29E-03 0.00E+00 1200X-1-CJ-WCV1-009 0.00E+00 1.52E-02 0.00E+00 2.66E+00 6.27E-02 1.83E-02 NA 1200X-1-CJ-WCV1-011 3.77E-02 0.00E+00 8.11E-03 4.24E+00 6.28E-02 0.00E+00 4.09E-03 1200X-1-CJ-WCV1-012 0.00E+00 3.08E-03 1.43E-02 2.65E+00 0.00E+00 4.85E-02 0.00E+00 1200X-1-CJ-WCV1-015 0.00E+00 0.00E+00 1.42E-02 1.08E+00 1.74E-02 5.28E-03 0.00E+00 1200X-1-CJ-WCV1-028 1.43E-01 8.47E-03 0.00E+00 2.74E+00 0.00E+00 2.08E-02 0.00E+00 1200X-1-CJ-WCV1-029 1.29E-02 0.00E+00 0.00E+00 7.75E-01 9.28E-03 1.79E-02 6.14E-03 1300X-1-CJ-FCV1-003 2.55E-01 2.11E-02 1.13E-02 3.44E+00 4.58E-02 0.00E+00 NA 1300X-1-CJ-FCV1-005 4.47E-02 7.33E-03 5.57E-03 2.23E+00 7.57E-02 4.21E-02 2.14E-03 1300X-1-CJ-FCV1-006 0.00E+00 6.21E-03 6.53E-04 3.04E+00 3.26E-02 5.89E-03 NA 1300X-1-CJ-FCV1-008 3.57E-02 2.82E-02 2.31E-02 1.45E+00 7.27E-02 1.59E-03 NA 1300X-1-CJ-WCV1-007 7.25E-02 0.00E+00 6.29E-03 7.11E-01 0.00E+00 1.72E-02 0.00E+00 1400X-1-CJ-FCV1-002 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.40E-03 0.00E+00 NA 1400X-1-CJ-FCV1-021 5.12E-02 1.68E-02 4.34E-02 0.00E+00 8.43E-03 0.00E+00 NA 2100X-1-CJ-FCV1-001 0.00E+00 8.44E-03 3.42E-03 3.79E+00 5.32E-02 1.30E-01 0.00E+00 2100X-1-CJ-FCV1-003 1.45E-01 1.75E-01 7.39E-02 4.35E+00 1.91E-01 1.09E-01 0.00E+00 2100X-1-CJ-FCV1-005 3.36E-01 1.23E-02 2.68E-02 1.73E+00 0.00E+00 0.00E+00 0.00E+00 2100X-1-CJ-FCV1-006 3.47E-01 1.51E-02 0.00E+00 1.25E+00 2.62E-02 0.00E+00 NA 2100X-1-CJ-FCV1-011 0.00E+00 0.00E+00 0.00E+00 7.20E-02 0.00E+00 0.00E+00 NA 2100X-1-CJ-FCV1-014 4.45E-02 2.27E-02 0.00E+00 0.00E+00 0.00E+00 5.69E-04 NA 2200X-1-CJ-FCV1-006 2.97E-01 0.00E+00 0.00E+00 4.08E+00 0.00E+00 0.00E+00 0.00E+00 2200X-1-CJ-FCV1-008 0.00E+00 1.71E-03 1.35E-02 0.00E+00 1.42E-02 0.00E+00 NA 2200X-1-CJ-FCV1-010 1.82E-01 0.00E+00 1.25E-02 0.00E+00 0.00E+00 0.00E+00 NA 2200X-1-CJ-FCV1-020 0.00E+00 8.43E-03 1.40E-02 0.00E+00 1.71E-02 0.00E+00 NA 2200X-1-CJ-FCV1-021 0.00E+00 5.79E-03 3.66E-02 2.26E+00 0.00E+00 0.00E+00 2.87E-03 2200X-1-CJ-FCV1-022 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NA 2200X-1-CJ-FCV1-026 0.00E+00 3.94E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NA 2200X-1-CJ-FCV1-030 0.00E+00 1.14E-01 5.54E-02 3.29E+00 2.75E-01 1.99E-02 2.06E-03 2200X-1-CJ-FCV1-031 0.00E+00 0.00E+00 1.35E-02 0.00E+00 3.85E-03 1.10E-02 NA 2200X-1-CJ-FCV1-035 0.00E+00 3.90E-02 3.19E-02 0.00E+00 2.59E-02 4.15E-03 NA 2200X-1-CJ-FCV1-038 7.66E-02 4.73E-03 4.88E-03 6.44E+00 6.44E-02 6.35E-02 0.00E+00 2200X-1-CJ-FCV1-039 4.02E-03 1.92E-03 0.00E+00 3.13E+00 1.00E-03 0.00E+00 0.00E+00 2200X-1-CJ-WCV1-009 1.13E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NA 2300X-1-CJ-FCV1-001 6.22E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NA

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 52 of 54 Sample ID Eu-155 Pu-238 Pu-239/240 Pu-241 Am-241 Cm- Np-237 243/244 2300X-1-CJ-FCV1-002 0.00E+00 4.89E-01 3.29E-01 2.94E+00 9.26E-01 9.33E-02 NA 2300X-1-CJ-FCV1-003 8.78E-02 2.45E-01 1.10E-01 5.86E+00 7.45E-01 2.15E-01 0.00E+00 2300X-1-CJ-FCV1-005 0.00E+00 3.81E-03 0.00E+00 0.00E+00 4.66E-02 0.00E+00 NA 2300X-1-CJ-FCV1-007 0.00E+00 2.12E-02 3.24E-04 8.16E-01 2.56E-01 0.00E+00 NA 2300X-1-CJ-FCV1-010 0.00E+00 0.00E+00 2.75E-03 4.82E-01 1.84E-02 6.23E-09 0.00E+00 2600X-1-CJ-FCV1-002 3.47E-02 0.00E+00 1.39E-02 1.81E-01 2.53E-02 5.07E-03 NA 3100X-3-CJ-FCV1-006 0.00E+00 2.08E-02 6.94E-03 0.00E+00 0.00E+00 7.90E-03 NA 3100X-3-CJ-FCV1-014 2.19E-02 2.05E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NA 4100X-1-CJ-FCV1-004 0.00E+00 1.09E-02 1.15E-02 0.00E+00 0.00E+00 0.00E+00 NA 4100X-1-CJ-FCV1-005 0.00E+00 0.00E+00 0.00E+00 2.85E-01 6.37E-03 0.00E+00 NA

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 53 of 54 8.2 Attachment 2: Derived Concentration Guide Limits Table 51: DCGLs BFM Wall/Floor DCGL (No IC Dose Correction) Embedded Pipe DCGL Calculation Auxiliary Auxiliary Turbine Auxiliary, Floor Floor Floor Turbine, 971' 989' 990' Circulating elevation elevation elevation Buried Pipe Water LTP LTP LTP Soil Fill Excavation Tunnels, Contain- Chapter 6 Chapter 6 Chapter 6 0.15 m Soil 1.0 m Material Scenario Intake ment Equation Equation Equation DCGL, DCGL, DCGL, DCGL, Structure, Building, 6-14, 6-14, 6-14, Radionuclide pCi/g pCi/g pCi/g dpm/100cm2 pCi/m2 pCi/m2 pCi/m2 pCi/m2 pCi/m2 Am-241 1.402E+02 3.053E+01 3.115E+00 7.442E+05 4.168E+06 4.046E+06 4.90E+08 3.83E+08 2.63E+08 C-14 5.996E+01 1.019E+01 1.433E+01 3.596E+06 8.629E+06 8.559E+06 1.568E+09 1.224E+09 8.406E+08 Ce-144 2.746E+02 2.319E+02 1.023E+03 1.430E+06 2.553E+08 5.922E+07 1.886E+11 1.473E+11 1.011E+11 Cm-243 6.747E+01 3.060E+01 8.928E+00 3.511E+05 1.003E+07 7.082E+06 1.528E+09 1.193E+09 8.192E+08 Cm-244 2.944E+02 5.766E+01 8.928E+00 1.548E+06 1.369E+07 1.330E+07 1.528E+09 1.193E+09 8.192E+08 Co-58 3.631E+01 3.128E+01 1.117E+01 1.898E+05 3.916E+07 8.058E+06 1.912E+09 1.493E+09 1.025E+09 Co-60 3.970E+00 3.086E+00 4.575E+02 2.103E+04 3.578E+06 8.640E+05 1.390E+11 1.085E+11 7.452E+10 Cs-134 6.424E+00 4.237E+00 1.767E+01 3.670E+04 4.396E+06 1.345E+06 5.366E+09 4.190E+09 2.877E+09 Cs-137 1.374E+01 7.656E+00 1.197E+01 8.432E+04 7.265E+06 2.749E+06 6.648E+09 5.191E+09 3.564E+09 Eu-152 8.857E+00 7.748E+00 1.508E+01 4.610E+04 1.013E+07 1.983E+06 8.371E+09 6.537E+09 4.487E+09 Eu-154 8.220E+00 7.168E+00 6.108E+02 4.282E+04 9.336E+06 1.839E+06 9.484E+10 7.406E+10 5.084E+10 Eu-155 3.081E+02 3.027E+02 4.200E+02 1.611E+06 3.619E+08 6.791E+07 6.519E+10 5.090E+10 3.495E+10 Fe-55 3.660E+04 2.122E+04 2.703E+03 1.341E+09 1.384E+10 6.308E+09 4.193E+11 3.274E+11 2.248E+11 H-3 1.195E+04 8.655E+02 1.716E+04 5.409E+07 2.208E+08 2.254E+08 2.764E+12 2.158E+12 1.482E+12 Ni-59 1.128E+04 2.307E+03 1.733E+02 2.400E+08 1.219E+09 1.122E+09 2.436E+10 1.902E+10 1.306E+10 Ni-63 4.120E+03 8.424E+02 1.190E+03 8.763E+07 4.451E+08 4.098E+08 2.075E+11 1.620E+11 1.112E+11 Np-237 4.723E+00 7.619E-01 4.345E+02 3.955E+04 7.808E+04 7.831E+04 1.043E+11 8.146E+10 5.593E+10 Pu-238 1.752E+02 3.536E+01 5.655E-02 9.576E+05 2.976E+06 2.939E+06 6.148E+06 4.801E+06 3.296E+06 Pu-239 1.578E+02 3.184E+01 2.131E+00 8.624E+05 2.681E+06 2.647E+06 3.246E+08 2.534E+08 1.740E+08 Pu-240 1.578E+02 3.185E+01 1.919E+00 8.630E+05 2.681E+06 2.647E+06 2.221E+08 1.734E+08 1.190E+08 Pu-241 5.666E+03 1.040E+03 1.919E+00 3.018E+07 1.310E+08 1.298E+08 2.221E+08 1.734E+08 1.190E+08 Sb-125 2.662E+01 2.348E+01 1.919E+00 1.382E+05 2.475E+07 5.694E+06 2.399E+08 1.874E+08 1.286E+08 Sr-90 1.111E+01 1.731E+00 9.916E+01 8.093E+04 8.666E+05 8.903E+05 1.493E+10 1.166E+10 8.002E+09 Tc-99 1.356E+02 1.542E+01 8.165E+01 5.938E+05 5.900E+06 6.084E+06 1.328E+10 1.037E+10 7.119E+09

Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan RSCS TSD 21-043 Page 54 of 54 8.3 Attachment 3: LLBP Scenario Concentrations that Result in 25 mrem Table 52: LLBP Scenario Concentrations that Result in 25 mrem Embedded Pipe LLBP Drilling Spoils Concentration Scenario Recycle/Disposal LLBP Scenario Radionuclide AB EP 4.03 in ID AB EP 18.81 in ID TB EP 9.4 in ID Concrete Steel (pCi/m2 per 25 (pCi/m2 per 25 (pCi/m2 per 25 (pCi/m2 per 25 (pCi/m2 per 25 mrem/yr) mrem/yr) mrem/yr) mrem/yr) mrem/yr)

Am-241 4.065E+10 8.191E+10 1.743E+10 3.223E+10 7.542E+06 C-14 4.492E+13 9.051E+13 1.926E+13 1.654E+11 1.076E+10 Ce-144 6.468E+21 1.303E+22 2.773E+21 1.414E+21 1.343E+20 Cm-243 1.020E+10 2.055E+10 4.372E+09 1.274E+09 2.123E+07 Cm-244 6.993E+11 1.409E+12 2.998E+11 3.328E+09 4.095E+07 Co-58 2.603E+56 5.246E+56 1.116E+56 3.007E+55 2.460E+54 Co-60 1.289E+10 2.598E+10 5.528E+09 3.489E+09 3.489E+08 Cs-134 1.035E+13 2.085E+13 4.437E+12 2.787E+12 1.879E+11 Cs-137 2.051E+09 4.133E+09 8.793E+08 6.142E+08 4.222E+07 Eu-152 2.526E+09 5.091E+09 1.083E+09 7.305E+08 7.475E+07 Eu-154 5.292E+09 1.066E+10 2.269E+09 1.464E+09 1.668E+08 Eu-155 1.013E+12 2.042E+12 4.344E+11 4.062E+11 5.077E+10 Fe-55 3.334E+18 6.718E+18 1.429E+18 1.963E+16 1.640E+15 H-3 3.698E+14 7.452E+14 1.585E+14 1.516E+12 9.573E+10 Ni-59 2.091E+14 4.214E+14 8.965E+13 8.893E+12 7.427E+11 Ni-63 9.493E+13 1.913E+14 4.070E+13 1.134E+13 8.926E+11 Np-237 2.540E+09 5.118E+09 1.089E+09 1.778E+07 1.090E+06 Pu-238 1.757E+11 3.541E+11 7.535E+10 8.563E+08 1.404E+07 Pu-239 1.257E+11 2.532E+11 5.388E+10 6.148E+08 1.025E+07 Pu-240 1.266E+11 2.550E+11 5.426E+10 6.162E+08 1.027E+07 Pu-241 6.277E+12 1.265E+13 2.691E+12 1.301E+11 2.602E+09 Sb-125 2.834E+12 5.710E+12 1.215E+12 8.189E+11 8.773E+10 Sr-90 8.303E+10 1.673E+11 3.560E+10 2.653E+10 1.150E+09 Tc-99 5.104E+11 1.028E+12 2.188E+11 3.072E+09 2.112E+08