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| number = ML15344A390
| number = ML15344A390
| issue date = 12/18/2014
| issue date = 12/18/2014
| title = Zion, Units 1 and 2 - TSD-14-004, Revision 1, Brookhaven National Laboratory: Recommended Values for the Distribution of Coefficient (Kd) to Be Used in Dose Assessments for Decommissioning the Zion Nuclear Power Plant
| title = TSD-14-004, Revision 1, Brookhaven National Laboratory: Recommended Values for the Distribution of Coefficient (Kd) to Be Used in Dose Assessments for Decommissioning the Zion Nuclear Power Plant
| author name = Fauver D, Sullivan T, Yetter R P
| author name = Fauver D, Sullivan T, Yetter R
| author affiliation = ZionSolutions, LLC
| author affiliation = ZionSolutions, LLC
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:RECOMMENDED VALUES FOR THE DISTRIBUTION COEFFICIENT (KD) TO BE USED IN DOSE ASSESSMENTS FOR DECOMMISSIONING THE ZION NUCLEAR POWER PLANT Terry Sullivan
{{#Wiki_filter:TSD 14-004 Revision 1 Page 1 of 15


Informal Report
TSD 14-004 Revision 1 Summary of Changes in this Revision:
* Rev. 1 -Changed Eu distribution coefficient values.
Page 2 of 15


Environmental & Climate Sciences Department Brookhaven National Laboratory P.O. Box 5000 Upton, NY 11973-5000 www.bnl.gov  
TSD 14-004 Revision 1 BNL-105442-2014-IR-R1 RECOMMENDED VALUES FOR THE DISTRIBUTION COEFFICIENT (KD) TO BE USED IN DOSE ASSESSMENTS FOR DECOMMISSIONING THE ZION NUCLEAR POWER PLANT Terry Sullivan September 24, 2014 Revision 1 Informal Report Biological, Environmental & Climate Sciences Department Brookhaven National Laboratory P.O. Box 5000 Upton, NY 11973-5000 www.bnl.gov Notice: This manuscript has been authored by employees of Brookhaven Science Associates, LLC under Contract No. DE-AC02-98CH10886 with the U.S. Department of Energy. The publisher by accepting the manuscript for publication acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes.
Page 3 of 15


Notice: This manuscript has been authored by employees of Brookhaven Science Associates, LLC under Contract No. DE
TSD 14-004 Revision 1 DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or any third partys use or the results of such use of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights.
-AC02-98CH10886 with the U.S. Department of Energy. The publisher by accepting the manuscript for publication acknowledges that the United States Government retains a non
Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof or its contractors or subcontractors. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.
-exclusive, paid
Page 4 of 15
-up, irrevocable, world
-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes.


DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or any third partys use or the results of such use of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights.
TSD 14-004 Revision 1 Table of Contents
Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof or its contractors or subcontractors. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. 
: 1. Introduction ................................................................................................................................ 1
: 2. Approach .................................................................................................................................... 2
: 3. Data ............................................................................................................................................. 2
Concrete Environment Kd values ............................................................................................... 4
: 4. Discussion .................................................................................................................................. 6
: 5. Recommended Values ................................................................................................................ 7
References ....................................................................................................................................... 9
List of Tables Table 1. Potential Radionuclides of Concern at the Zion Power Plant .......................................... 1
Table 2 Site-specific Kd values (ml/g) for the Zion Nuclear Power Station .................................. 3
Table 3 Literature soil Kd values for radionuclides of concern at Zion. ........................................ 4
Table 4 Preferred distribution coefficients (Kd ml/g) for cement concrete environments (Table 5.1 Krupka, 1998). .......................................................................................................................... 6
Table 5 Recommended Kd values to be used in the basement fill model. ..................................... 8
Page 5 of 15


Table of Contents
TSD 14-004 Revision 1
: 1. Introduction ................................................................................................................................
: 1. Introduction ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated. The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled. The remaining u n d e r g r o u n d structures will contain low amounts of residual licensed radioactive material. An important component of the decommissioning process is the demonstration that any remaining activity will not cause a hypothetical individual to receive a dose in excess of 25 mrem/y as specified in 10CFR20 Subpart E.
1!2. Approach ....................................................................................................................................
2!3. Data .............................................................................................................................................
2!Concrete Environment Kd values ...............................................................................................
4!4. Discussion ..................................................................................................................................
6!5. Recommended Values ................................................................................................................
7!References .......................................................................................................................................
9! List of Tables Table 1. Potential Radionuclides of Concern at the Zion Power Plant ..........................................
1!Table 2  Site
-specific K d values (ml/g) for the Zion Nucle ar Power Station ..................................
3!Table 3  Literature soil K d values for radionuclides of concern at Zion. ........................................
4!Table 4  Preferred distribution coefficients (K d ml/g) for cement concrete environments (Table 5.1 Krupka, 1998). ..........................................................................................................................
6!Table 5  Recommended K d values to be used in the basement fill model. .....................................
8!
1  1. Introduction ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated.
The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled. The remaining underground structures will contain low amounts of residual licensed radioactive material. An important component of the decommissioning process is the demonstration that any remaining activity will not cause a hypothetical individual to receive a dose in excess of 25 mrem/y as specified in 10CFR 20 Subpart E.
The compliance assessment requires prediction of the release and transport of contaminants to the hypothetical individual. Characterization studies by ZionSolutions have identified the following nuclides as being of potential concern (Table 1).
The compliance assessment requires prediction of the release and transport of contaminants to the hypothetical individual. Characterization studies by ZionSolutions have identified the following nuclides as being of potential concern (Table 1).
Table 1. Potential Radionuclides of Concern at the Zion Power Plant
Table 1. Potential Radionuclides of Concern at the Zion Power Plant Radionuclides   Radionuclides   Radionuclides   Radionuclides   Radionuclides   Radionuclides
!"#$%&'()$#*+
H-3           Co-60         Tc-99         Cs-137       Eu-155       Pu-241
,!"#$%&'()$#*+
C-14         Ni-63         Ag-108m       Pm-147       Np-237       Am-241
,!"#$%&'()$#*+
Fe-55         Sr-90         Sb-125         Eu-152       Pu-238       Am-243
,!"#$%&'()$#*+
Ni-59         Nb-94         Cs-134         Eu-154       Pu-239/240   Cm-243/244
,!"#$%&'()$#*+
A key parameter in this assessment is the distribution coefficient (Kd) which is a measure of the amount of the radionuclide that will sorb to the solid media (soil or backfill) in the subsurface environment. The exposure pathway of concern is the groundwater. Groundwater concentration has an inverse relationship with Kd. Thus a lower value of Kd will provide higher groundwater concentrations and a more conservative prediction of dose. BNL (Yim, 2012, Milian, 2014) has conducted site-specific measurements on using local groundwater and samples of site soils and potential backfill materials to assess the Kd value for the contaminants with the expected highest residual concentration (Fe-55, Co-60, Ni-63, Sr-90, and Cs-137) for ZionSolutions. However, there are several other radioactive contaminants (Table 1) that may be present at lower levels that will still require assessment to demonstrate that dose limits are not exceeded. This document reviews the existing literature to recommend a value for Kd when site-specific numbers are not available.
,!"#$%&'()$#*+
Literature values for Kd show that sorption strongly depends on the contacting media and the geochemical conditions. The backfill selected for disposal will therefore play a huge role in determining the choice of the Kd value. A final decision has not been made on the backfill material at the Zion Power Plant. Materials under consideration include:
,"#$!%&#'(!)*#++!%,#-$.!!"#$%%&/0#12-!%#-2!34#'$!!"#$%&'(/5#-2.!36#1$.!75#12-!89#::!;<#+(!;=#-1:!>0#-:1!/0#1$?!75#12$!34#:+!3=#+2!%,#-$2!>0#-:2!/0#1$+@12(!%5#12$@122! A key parameter in this assessment is the distribution coefficient (K d) which is a measure of the amount of the radionuclide that will sorb to the solid media (soil or backfill) in the subsurface environment. The exposure pathway of concern is the groundwater. Groundwater concentration has an inverse relationship with K
* Crushed concrete demolition debris
: d. Thus a lower value of K d will provide higher groundwater concentrations and a more conservative prediction of dose. BNL (Yim, 2012, Milian, 2014) has conducted site-specific measurements on using local groundwater and samples of site soils and potential backfill materials to assess the K d value for the contaminants with the expected highest residual concentration (Fe-55, Co-60, Ni-63, Sr-90, and Cs-137) for ZionSolutions. However, there are several other radioactive contaminants (Table 1) that may be present at lower levels that will still require assessment to demonstrate that dose limits are not exceeded. This document reviews the existing literature to recommend a value for K d when site-specific numbers are not available.  
* Crushed cinder block
* Flowable grout
* Local sand 1
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Literature values for K d show that sorption strongly depends on the contacting media and the geochemical conditions. The backfill selected for disposal will therefore play a huge role in determining the choice of the K d value. A final decision has not been made on the backfill material at the Zion Power Plant. Materials under consideration include:
TSD 14-004 Revision 1 The concrete and cinder block would be obtained from the building materials removed to three feet below grade and would be free from residual radioactive contamination. Combinations of the above materials are also under consideration.
&#xa5; Crushed concrete demolition debris
The first three materials are alkaline and will cause the pH to rise substantially above the local ambient conditions. Based on testing at BNL with materials supplied by ZionSolutions, the pH will initially increase to 10 or 11 for the cementitious materials and grout. Eventually, as the alkali is consumed by buffering reactions the pH will decrease. This is expected to take a minimum of several hundred years depending on the flow rate and buffering capacity of the surrounding soils. Several studies have found that pH is a key geochemical factor in controlling sorption. For this reason consideration must be given to the likely high pH conditions when selecting the Kd value to be used in modeling if a mixture of backfills is used.
&#xa5; Crushed cinder block
: 2. Approach The objective of selecting a Kd value is to choose a value that is reasonably conservative with respect to projected groundwater dose (radionuclide concentrations). This requires a value that is likely to provide a lower bound for Kd. The value for Kd strongly depends on the solid media that contacts the groundwater thus site-specific values are the most representative of actual conditions.
&#xa5; Flowable grout
For radionuclides with site-specific data the media with the lowest measured Kd was selected to provide this lower bound. For radionuclides without site-specific data the literature was reviewed to determine the range of Kd values typically found in soils and found in cementitious (high pH) environments. These Kds will be used for initial DUST-MS runs to determine groundwater concentrations at potential well locations. Depending upon the outcome they may be further refined with more site specific or literature data.
&#xa5; Local sand 2  The concrete and cinder block would be obtained from the building materials removed to three feet below grade and would be free from residual radioactive contamination. Combinations of the above materials are also under consideration.
Baes and Sharp (Baes and Sharp 1983) were among the first to show that the Kd value for Cs and Sr is log-normally distributed in soils. They applied a log-normal distribution to all elements and this approach is widely used (Sheppard and Thibault, 1990; NRC, 1990). Sheppard and Thibault extended the concept of log-normal distribution to apply to a soil type (sand, loam, clay or organic). This concept is used in this report to determine the 25th percentile value for Kd in soils. The use of the 25th percentile value has been performed in other decommissioning studies at Fermi (Dionne, 2009) and Humboldt Bay (Besson, 2013).
The first three materials are alkaline and will cause the pH to rise substantially above the local ambient conditions.
: 3. Data Three types of data are used for the selection of an appropriate Kd for the backfill region at the Zion Nuclear Power Plant. These include site-specific values using local groundwater and soil or concrete samples from the site; literature values for soil environments; and literature values for concrete environments.
Based on testing at BNL with materials supplied by ZionSolutions, the pH will initially increase to 10 or 11 for the cementitious materials and grout. Eventually, as the alkali is consumed by buffering reactions the pH will decrease. This is expected to take a minimum of several hundred years depending on the flow rate and buffering capacity of the surrounding soils. Several studies have found that pH is a key geochemical factor in controlling sorption. For this reason consideration must be given to the likely high pH conditions when selecting the Kd value to be used in modeling if a mixture of backfills is used.
Site-specific Kd data:
: 2. Approach The objective of selecting a K d value is to choose a value that is reasonably conservative with respect to projected groundwater dose (radionuclide concentrations). This requires a value that is likely to provide a lower bound for K
Kd measurements were performed for ZionSolutions using site-specific groundwater and soil samples (clay, silt, native sand, and disturbed sand - native sand that was excavated during 2
: d. The value for K d strongly depends on the solid media that contacts the groundwater thus site-specific values are the most representative of actual  
Page 7 of 15


conditions.
TSD 14-004 Revision 1 construction of the plant and backfilled around the plant) for six nuclides. Additionally potential backfill materials including two concrete samples (one from the Containment Building and one from the Crib House), two Cinder Block samples from the site, and one low density grout were tested using site-specific groundwater. The elements measured included Fe, Co, Ni, Sr and Cs.
For radionuclides with site-specific data the media with the lowest measured K d was selected to provide this lower bound. For radionuclides without site-specific data the literature was reviewed to determine the range of K d values typically found in soils and found in cementitious (high pH) environments. These Kds will be used for initial DUST-MS runs to determine groundwater concentrations at potential well locations. Depending upon the outcome they may be further refined with more site specific or literature data.
Table 2 presents the results of these measurements. Note isotopes of Cs and Ni found in Table 1 are also presented in Table 2 as isotopes will have the same chemical sorption properties.
Baes and Sharp (Baes and Sharp 1983) were among the first to show that the Kd value for Cs and Sr is log-normally distributed in soils. They applied a log-normal distribution to all elements and this approach is widely used (Sheppard and Thibault, 1990; NRC, 1990). Sheppard and Thibault extended the concept of log-normal distribution to apply to a soil type (sand, loam, clay or organic). This concept is used in this report to determine the 25 th percentile value for K d in soils. The use of the 25 th percentile value has been performed in other decommissioning studies at Fermi (Dionne, 2009) and Humboldt Bay (Besson, 2013).
Table 2 Site-specific Kd values (ml/g) for the Zion Nuclear Power Station Site       Site         Site
: 3. Data  Three types of data are used for the selection of an appropriate Kd for the backfill region at the Zion Nuclear Power Plant.
Site           Site           Site                           Specific   Specific   Specific
These include site-specific values using local groundwater and soil or concrete samples from the site; literature values for soil environments; and literature values for concrete environments.
Site       Specific       Specific       Specific   Site Specific       Crib       Cinder       Low
Site-specific K d data:
Specific         Silt       Disturbed       Native   Containment           House       Block       Density
K d measurements were performed for ZionSolutions using site-specific groundwater and soil samples (clay, silt, native sand, and disturbed sand  native sand that was excavated during 3  construction of the plant and backfilled around the plant) for six nuclides. Additionally potential backfill materials including two concrete samples (one from the Containment Building and one from the Crib House), two Cinder Block samples from the site, and one low density grout were tested using site-specific groundwater. The elements measured included Fe, Co, Ni, Sr and Cs. Table 2 presents the results of these measurements. Note isotopes of Cs and Ni found in Table 1 are also presented in Table 2 as isotopes will have the same chemical sorption properties.
Silt Kd1   Clay1 Kd   Sand Kd1   Sand Kd1   Concrete1 Kd   Concrete1     Kd2       Grout Kd2
Table 2 Site-specific K d values (ml/g) for the Zion Nuclear Power Station
Radionuclide   ml/g             ml/g         ml/g           ml/g           ml/g           Kd ml/g   ml/g       ml/g
!"#$%&'()$#*
Fe-55           8061         17288         2857           5579         16546           17288                
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im, 2012 2 Milian, 2014 Literature values for Kd in soil environments Numerous measurements of K d have been reported in the literature. Key compilations of this data include those by Baes and Sharp (Baes, 1983); Sheppard and Thibault (Sheppard, 1990), Yu (Yu, 1993), the U.S. Nuclear Regulatory Commission (NRC, 2000); and the International Atomic Energy Agency (IAEA, 2010). All of these documents provide statistical parameters to estimate the distribution. Literature values for K d in soil media from selected sources are presented in Table 3. The first two columns are mean values for K d presented in (Yu, 1993 and IAEA 2012). For conservatism the 25 th percentile in the distribution from the reports (Sheppard, 1990 and NRC, 2000) are also reported in the Table 3. For the Sheppard data the log-normal distribution of the data for sand was used except for Nb-94 and Sb-125 which are the geometrics means because standard deviations were not provided in the Sheppard data. Other soil types were not included because sand, in most cases, has the lowest K d and the surrounding soil at Zion is primarily sand.
Ni-59             75           136           331             62           3438             8361       177         4,569
4  Table 3 Literature soil K d values for radionuclides of concern at Zion.
Co-60           1161         1161         1161           1161           1161             1161       223         1941
!"#$%&'()$#*
Ni-63             75           136           331             62           3438             8361       177         4,569
,DE'F,2GGHI,-"&#, 1#, ,3)45 , DJKLK,@M2MI , ,N":)*+,2@F,2O,-"&#,%9,K)),-%$)+,3)45, ,D;!6F,@MMMI
Sr-90           2.3           5.7           3.4             2.3           10.4             18.5       23.5       11.8
,@P.Q,R*9(*&.$)*,3)45
Cs-134           527         3011           635             615             85             45         249         303
,D-Q*//"9#F, 2GGMI ,-"&#,,@P.Q,R*9(*&.$)*
Cs-137           527         3011           635             615             85             45         249         303
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he predictions at the 25 th percent level of the distribution for the NRC and Sheppard reports are similar. This is because the NRC data set for the distribution is based on, but not limited to the Sheppard data set.
1 Yim, 2012 2
Concrete Environment K d values The chemistry of the water will change from an initial value of greater than 11 down to the ambient pH in a crushed concrete environment. The convention of Bradbury and Sarott (1995) describing the three types of chemical environments that all cements progress through is used to understand the data. The following description of the environments has been abbreviated from the initial work by Krupka (Krupka, 1998)
Milian, 2014 Literature values for Kd in soil environments Numerous measurements of Kd have been reported in the literature. Key compilations of this data include those by Baes and Sharp (Baes, 1983); Sheppard and Thibault (Sheppard, 1990), Yu (Yu, 1993), the U.S. Nuclear Regulatory Commission (NRC, 2000); and the International Atomic Energy Agency (IAEA, 2010). All of these documents provide statistical parameters to estimate the distribution. Literature values for Kd in soil media from selected sources are presented in Table 3. The first two columns are mean values for Kd presented in (Yu, 1993 and IAEA 2012). For conservatism the 25th percentile in the distribution from the reports (Sheppard, 1990 and NRC, 2000) are also reported in the Table 3. For the Sheppard data the log-normal distribution of the data for sand was used except for Nb-94 and Sb-125 which are the geometrics means because standard deviations were not provided in the Sheppard data. Other soil types were not included because sand, in most cases, has the lowest Kd and the surrounding soil at Zion is primarily sand.
3 Page 8 of 15


5  &#xa5;    Environment I  This environment occurs immediately after the cement hardens and is wetted by infiltrating wate r  The cement pore water is characterize d as having a high pH of >12.5, high ionic strength, and high concentration s of potassium and sodium resulting from the dissolution of alkali impurities in the clinker phases.
TSD 14-004 Revision 1 Table 3 Literature soil Kd values for radionuclides of concern at Zion.
Hydration is still continuing during Environment I with the formation of C-S-H (Calcium- Silicate  Hydrate) and portlandite [
(Yu, 1993) Sand             (IAEA 2010)                                                     (Sheppard, 1990)
Ca(OH)2]    The composition of the cement pore fluid is at equilibrium with portlandite during this time. Based on the modeling estimates this environment may last for the first 100 to 10,000 years. Environment II  During this period, the soluble salts of the alkali metals are all dissolved    The pH of the cement pore water is controlled at a value of about 12.5 by the solubility  of portlandite.
Kd       Tables 12, 14 Sand or All       (NRC, 2000)               Sand 25th
The C-S-H and portlandite are the major solid phases present  Environment II may last for a long time    Its duration depends on how much water percolates through the system to dissolve all the slightly soluble portlandite    T his environment may last from 100-10,000 years to 1,000-100,000 years. Environment III The concentration of portlandite has been reduced to such an extent by this period that the solubility of C-S-H now controls the pH of the cement pore fluid  The C-S-H starts to dissolve incongruently with a continual decrease in pH  At the end of this evolution, Environment III can be conceptualize d as leaving only silica (SiO 2) as the solubility control for the pore fluid pH.
Radionuclide           ml/g                         Soils ml/g               25th Percentile ml/g   Percentile ml/g
For the sake of simplicity, the final end point of Environment III can be considered somewhat analo gous to the geochemical conditions of the "normal" ambient soil environment.
H-3                                                 1                                 0.0431                   0.051
The important point of this discussion is that the cement will control the pH for hundreds to thousands of years. Thus, if cementitious materials are used for backfill material, a high pH environment will prevail and K d values are likely to be similar to those found in cement based materials.  
C-14                     5                                                               1.24                     1.76
Fe-55                 220                           320                                     34.3                     39
Ni-59                 400                           140                                     160                     148
Co-60                   60                           640                                     42.9                     9.2
Ni-63                 400                           140                                     160                     148
Sr-90                   15                               22                                   7.49                     4.6
Nb-94                 160                           170                                     44.6                     164
Tc-99                 0.1                           0.23                                   0.0618                     0.04
Ag-108m                 90                                                               52.6                     27
Sb-125                 45                               17                                   43.4                     45
Cs-134                 280                           530                                     92.5                     51
Cs-137                 280                           530                                     93.4                     51
Pm-147                                           450                                     94.8                      
Eu-152                                                                             96.2                      
Eu-154                                                                             95.2                      
Eu-155                                                                             95.8                      
Np-237                   5                               35                                   3.75                     1.30
Pu-238                 550                           400                                     268                     174
Pu-239/240             550                           400                                     267.5                     174
Pu-241                 550                           400                                     268                     174
Am-241               1900                           1000                                     177                     333
Am-243               1900                           1000                                     178                     333
Cm-243/244           4000                           9300                                     1990                     891
The predictions at the 25th percent level of the distribution for the NRC and Sheppard reports are similar. This is because the NRC data set for the distribution is based on, but not limited to the Sheppard data set.
Concrete Environment Kd values The chemistry of the water will change from an initial value of greater than 11 down to the ambient pH in a crushed concrete environment. The convention of Bradbury and Sarott (1995) describing the three types of chemical environments that all cements progress through is used to understand the data. The following description of the environments has been abbreviated from the initial work by Krupka (Krupka, 1998) 4 Page 9 of 15


6  Table 4 Preferred distribution coefficients (K d ml/g) for cement concrete environments (Table 5.1 Krupka, 1998).
TSD 14-004 Revision 1
Environment I Environment II Environment III Oxidizing Conditions Reducing Condition s  Oxidizing Conditions Reducing Condition s  Oxidizing Conditions Reducing Condition s      Radionuclide K d (ml/g) Am 5000 5000 5000 5000 500 500 C 500 500 100 100 10 10 Cl 5 5 1 1 0 0 I 10 10 5 5 1 1 Lanthanides 5000 5000 5000 5000 500 500 Ni 100 100 100 100 10 10 Nb 1000 1000 1000 1000 100 100 Np 2000 5000 2000 5000 200 500 Pu 5000 5000 5000 5000 500 500 Ra 100 100 100 100 100 100 Sr 1 1 3 3 3 5 Tc 0 1000 0 1000 0 100 Th 5000 5000 5000 5000 500 500 U 1000 1000   1000 1000   100 100   The above table does not include Cs or Eu, two nuclides of potential concern at Zion. Cs is known to have low sorption on cements. This is due in part to competition for sorption sites with other ions (Na and K) that are released by the leaching from the concrete. Bradbury and Sarott (Bradbury 1995) provided K d estimates for Cs as 2 to 20 ml/g with the low value in Environment I. This is lower than the site-specific value for Cs at Zion. They also provided estimates for Eu (5000 to 1000 ml/g) with Environment III with the lowest K d and Cm (5000 to 1000 ml/g) with Environment III providing the least sorption (Bradbury, 1995). A recent study (Felipe-Sotello, 2012) measured Kd values for Eu at 66000 ml/g.
* Environment I This environment occurs immediately after the cement hardens and is wetted by infiltrating water The cement pore water is characterized as having a high pH of >12.5, high ionic strength, and high concentrations of potassium and sodium resulting from the dissolution of alkali impurities in the clinker phases. Hydration is still continuing during Environment I with the formation of C-S-H (Calcium- Silicate -
Other values for distribution coefficients in cementitious materials are provided in (Kaplan, 2008).  
Hydrate) and portlandite [Ca(OH)2]        The composition of the cement pore fluid is at equilibrium with portlandite during this time. Based on the modeling estimates this environment may last for the first 100 to 10,000 years.
Environment II During this period, the soluble salts of the alkali metals are all dissolved The pH of the cement pore water is controlled at a value of about 12.5 by the solubility of portlandite. The C-S-H and portlandite are the major solid phases present Environment II may last for a long time Its duration depends on how much water percolates through the system to dissolve all the slightly soluble portlandite        This environment may last from 100-10,000 years to 1,000-100,000 years.
Environment III The concentration of portlandite has been reduced to such an extent by this period that the solubility of C-S-H now controls the pH of the cement pore fluid The C-S-H starts to dissolve incongruently with a continual decrease in pH At the end of this evolution, Environment III can be conceptualized as leaving only silica (SiO2) as the solubility control for the pore fluid pH. For the sake of simplicity, the final end point of Environment III can be considered somewhat analogous to the geochemical conditions of the "normal" ambient soil environment.
The important point of this discussion is that the cement will control the pH for hundreds to thousands of years. Thus, if cementitious materials are used for backfill material, a high pH environment will prevail and Kd values are likely to be similar to those found in cement based materials.
5 Page 10 of 15
 
TSD 14-004 Revision 1 Table 4 Preferred distribution coefficients (Kd ml/g) for cement concrete environments (Table 5.1 Krupka, 1998).
Environment I               Environment II               Environment III Oxidizing     Reducing       Oxidizing     Reducing         Oxidizing   Reducing Conditions    Conditions      Conditions  Conditions      Conditions  Conditions Radionuclide                                           Kd (ml/g)
Am                   5000           5000           5000         5000             500           500 C                     500           500             100         100               10           10 Cl                       5             5                 1           1               0           0 I                       10           10                 5           5               1           1 Lanthanides         5000           5000           5000         5000             500           500 Ni                     100           100             100         100               10           10 Nb                   1000           1000           1000         1000             100           100 Np                   2000           5000           2000         5000             200           500 Pu                   5000           5000           5000         5000             500           500 Ra                     100           100             100         100             100           100 Sr                       1             1                 3           3               3           5 Tc                       0         1000                 0       1000                 0         100 Th                   5000           5000           5000         5000             500           500 U                   1000           1000           1000         1000             100           100 The above table does not include Cs or Eu, two nuclides of potential concern at Zion. Cs is known to have low sorption on cements. This is due in part to competition for sorption sites with other ions (Na and K) that are released by the leaching from the concrete. Bradbury and Sarott (Bradbury 1995) provided Kd estimates for Cs as 2 to 20 ml/g with the low value in Environment I. This is lower than the site-specific value for Cs at Zion. They also provided estimates for Eu (5000 to 1000 ml/g) with Environment III with the lowest Kd and Cm (5000 to 1000 ml/g) with Environment III providing the least sorption (Bradbury, 1995). A recent study (Felipe-Sotello, 2012) measured Kd values for Eu at 66000 ml/g. Other values for distribution coefficients in cementitious materials are provided in (Kaplan, 2008).
: 4. Discussion Site-specific values are the most representative of the conditions that will occur at Zion after decommissioning and they will be recommended for use in groundwater dose assessment.
: 4. Discussion Site-specific values are the most representative of the conditions that will occur at Zion after decommissioning and they will be recommended for use in groundwater dose assessment.
Although a final determination of the backfill material has not been made, it is likely that the backfill will contain a substantial amount of cementitious material. Examining the representative K d values for soils (Table 3) and cementitious systems (Table 4) it is clear that with the exception of Cs the cement K d values are greater than for soil systems. The K d value selected is meant to provide a conservative assessment of dose to the groundwater pathway. For this reason, with the exception of H and Tc literature soil K d values will be recommended for the assessment when site-specific values are not available. To increase the degree of confidence 7  that a conservative value has been selected the 25 th percentile K d from either the NRC or Sheppard reports will be used. For Tc the sand K d in Table 3 is less than 0.1. The cementitious oxidizing conditions K d is zero in Table 4. The soil K d is rounded to zero to ensure conservatism.
Although a final determination of the backfill material has not been made, it is likely that the backfill will contain a substantial amount of cementitious material. Examining the representative Kd values for soils (Table 3) and cementitious systems (Table 4) it is clear that with the exception of Cs the cement Kd values are greater than for soil systems. The Kd value selected is meant to provide a conservative assessment of dose to the groundwater pathway. For this reason, with the exception of H and Tc literature soil Kd values will be recommended for the assessment when site-specific values are not available. To increase the degree of confidence 6
The same will be done for the Table 3 H K d as a conservative assumption.
Page 11 of 15
For one nuclide, Sb-125, the IAEA median value was lower than the 25 th percentile value on the NRC distribution. No standard deviation was reported in the Sheppard data. For this reason, the IAEA value is recommended as the appropriate value for screening calculations for Sb-125.


The Eu isotopes all have slightly different K d values in Table 3. These values are from NRC, 2000 and are calculated values for the 25 th percentile based on a mean value and standard deviation. One would expect isotopes to have the same sorption characteristics. It is likely that this is round-off error in determining the 25 th percentile. For this reason the minimum value for all three isotopes will be selected as the reference value.
TSD 14-004 Revision 1 that a conservative value has been selected the 25th percentile Kd from either the NRC or Sheppard reports will be used. For Tc the sand Kd in Table 3 is less than 0.1. The cementitious oxidizing conditions Kd is zero in Table 4. The soil Kd is rounded to zero to ensure conservatism.
The recommended values for the basement fill model are either site-specific or values measured in soil. The K d values in a cement environment for elements other tan Cs, Tc and H are expected to be higher based on existing data. Thus, they should be appropriate for outside of the buildings in the surrounding soil with the exception of H, Tc and Cs. Depending on the buffering capacity of the soil, time, and distance from the building, the chemical environment of the groundwater exiting the building may control the sorption of Cs. For this reason, the site-specific Kd for Cs in the cement environment should be used in the surrounding soils to provide a conservative estimate of groundwater concentration for dose assessment.
The same will be done for the Table 3 H Kd as a conservative assumption.
: 5. Recommended Values
For one nuclide, Sb-125, the IAEA median value was lower than the 25th percentile value on the NRC distribution. No standard deviation was reported in the Sheppard data. For this reason, the IAEA value is recommended as the appropriate value for screening calculations for Sb-125.
The Eu isotopes all have slightly different Kd values in Table 3. These values are from NRC, 2000 and are calculated values for the 25th percentile based on a mean value and standard deviation. One would expect isotopes to have the same sorption characteristics. It is likely that this is round-off error in determining the 25th percentile. For this reason the minimum value for all three isotopes will be selected as the reference value.
The recommended values for the basement fill model are either site-specific or values measured in soil. The Kd values in a cement environment for elements other tan Cs, Tc and H are expected to be higher based on existing data. Thus, they should be appropriate for outside of the buildings in the surrounding soil with the exception of H, Tc and Cs. Depending on the buffering capacity of the soil, time, and distance from the building, the chemical environment of the groundwater exiting the building may control the sorption of Cs. For this reason, the site-specific Kd for Cs in the cement environment should be used in the surrounding soils to provide a conservative estimate of groundwater concentration for dose assessment.
: 5. Recommended Values The values in Table 5 are the minimum values found in any test for the site-specific case and the minimum values found from the reports cited in Table 3. These values are appropriate for maximizing the groundwater concentration and thereby predicted dose. For intruder scenarios or scenarios where the backfill is used as gardening soils, a higher value of Kd would be recommended for maximizing the predicted dose in those cases.
7 Page 12 of 15


The values in Table 5 are the minimum values found in any test for the site-specific case and the minimum values found from the reports cited in Table 3. These values are appropriate for maximizing the groundwater concentration and thereby predicted dose. For intruder scenarios or scenarios where the backfill is used as gardening soils, a higher value of K d would be recommended for maximizing the predicted dose in those cases. 
TSD 14-004 Revision 1 Table 5 Recommended Kd values to be used in the basement fill model.
Recommended
                  Half Life   Basement Fill
Radionuclide   (years)   Kd ml/g                   Reference1
2 H-3         1.24E+01                             0 C-14         5.73E+03                         1.2      NRC, 2000 Fe-55       2.70E+00                   2857          Site-Specific Ni-59       7.50E+04                         62      Site Specific Co-60       5.27E+00                       223      Site Specific Ni-63       9.60E+01                         62      Site Specific Sr-90       2.91E+01                         2.3      Site Specific Nb-94       2.03E+04                         45      NRC, 2000 2
Tc-99       2.13E+05                             0 Ag-108m     1.27E+02                         27      Sheppard, 1990 Sb-125       2.77E+00                         17      IAEA, 2010 Cs-134       2.06E+00                         45      Site Specific Cs-137       3.00E+01                         45      Site Specific Pm-147       2.62E+00                         95      NRC, 2000 3
Eu-152       1.33E+01                       95 NRC, 2000 Eu-154       8.80E+00                         95 NRC, 2000 Eu-155       4.96E+00                         95 NRC, 2000 Np-237       2.14E+06                             1 Sheppard, 1990 Pu-238       8.77E+01                       174 Sheppard, 1990 Pu-239/240   2.41E+04                       174 Sheppard, 1990 Pu-241       1.44E+01                       174 Sheppard, 1990 Am-241       4.32E+02                       177 NRC, 2000 Am-243       7.38E+03                       177 NRC, 2000 Cm-243/244   2.85E+01                       891 Sheppard, 1990 1
Values from NRC, 2000 or Sheppard, 1990 are the 25th percentile values on the cumulative distribution function.
2 25th percentile value was less than 0.1 and was rounded down to 0.
3 25th percentile value was less listed as 96 in Table 3. It was changed to 95 to make it consistent with other Eu isotopes.
8 Page 13 of 15


8  Table 5  Recommended K d values to be used in the basement fill model.
TSD 14-004 Revision 1 References Baes, C.F., and R.D. Sharp, (1983). A proposal for Estimation of Sol Leaching and Leaching Constants for Use in Assessment Models, J. Environ. Qual., Vol. 12, No. 1, 1983. Pp 17-28.
!"#$%&'()$#*
Besson, J.W. (2013). Humboldt Bay Power Plant License Termination Plan Revision 0 Chapter 6 Compliance with the Radiological Criteria May 2013, ENG-HB-003, Rev 0. Bartlett, Plymouth, MA.
, ,=")0,A$0*,D7*"9+I ,!*(%33*&#*#,>"+*3*&.,T$)),
Dionne, B.J., (2009). Calculation of Enrico Fermi 1 Derived Concentration Guideline Levels for Soil, ENG 004, Rev 1., Bartlett, Plymouth, MA Environmental Protection Agency, (2004). Understanding Variation in Partition Coefficient, Kd Values, United States Office of Air and Radiation EPA 402-R-04-002C, Vol 1 - 3.
1#,3)45 ,!*0*9*&(*2 ,"#$!-B12>D(-!0 2 %#-2!:B.$>D($!1.2 NRC, 2000 89#::!1B.(>D((!2857 Site-Specific 34#:+!.B:(>D(2!62 Site Specific
Felipe-Sotelo, M., Hinchliff, J., Evans, N., Warwick, P. and Read, D. (2012). Sorption of radionuclides to a cementitious backfill material under near-field conditions, Mineralogical Magazine, December 2012, Vol. 76(8), pp. 3401-3410.
%&#'(!:B1.>D((!223 Site Specific 34#'$!+B'(>D(-!62 Site Specific
International Atomic Energy Agency (IAEA, 2010). handbook of Parameter Values for the Prediction of Radionuclide Transfer in Terrestrial and Freshwater Environments, Technical Report Series No. 472., International Atomic Energy Agency, Vienna, Austria.
;<#+(!1B+->D(-!2.3 Site Specific 3=#+2!1B($>D(2!45 NRC, 2000
Kaplan, D.J. Roberts, K., Coates, J., Sigegried, M., and Serkiz, S., 2008.Saltstone and concrete interactions with radionuclides sorption (Kd), desorption, and reduction capacity measurements, SRNS-STI-2008-00045, Savannah River National laboratory, Savannah River, SC.
)*#++!1B-$>D(:!0 2 7C#-(?5!-B1.>D(1!27 Sheppard, 1990
Kay, J.A. (2004). Yankee Nuclear Plant Station License Termination Plan, Yankee Atomic Electric Company, MA.
;=#-1:!1B..>D((!17 IAEA, 2010
Krupka, K. M. and R. J. Serne. (1998). Effects on Radionuclide Concentrations by Cement/Ground-Water Interactions in Support of Performance Assessment of Low-Level Radioactive Waste Disposal Facilities. NUREG/CR-6377 (PNNL-11408), Pacific Northwest, National Laboratory, Richland, Washington.
%,#-$2!1B('>D((!45 Site Specific
Milian, L., T. Sullivan (2014). Sorption (Kd) measurements on Cinder Block and Grout in Support of Dose Assessments for Zion Nuclear Station Decommissioning, Brookhaven National Laboratory Report to ZionSolutions, April 2014 (Draft).
%,#-$.!$B((>D(-!45 Site Specific
Ochs, M., Pointeau, I. and Giffaut, E. (2006). Caesium sorption by hydrated cement as a function of degradation state: Experiments and modelling. Waste Management, 26, 725_732.
/5#-2.!1B'1>D((!95 NRC, 2000
Sheppard, M. and Thibault, D.H., 1990. Default Soil Solid/Liquid Partition Coefficients, Kds, For Four Major Soil types: A Compendium, Health Physics, Vol. 59, No. 4, pp. 471-481, Oct, 1990.
>0#-:1!-B$$>D(-!95 3 NRC, 2000
9 Page 14 of 15
>0#-:2!?B?(>D((!95 NRC, 2000
!"#$%%&2B+'>D((!95 NRC, 2000 36#1$.!1B-2>D('!1 Sheppard, 1990
/0#1$?!?B..>D(-!174 Sheppard, 1990
/0#1$+@12(!1B2->D(2!174 Sheppard, 1990
/0#12-!-B22>D(-!174 Sheppard, 1990 75#12-!2B$1>D(1!177 NRC, 2000 75#12$!.B$?>D($!177 NRC, 2000
%5#12$@122!1B?:>D(-!891 Sheppard, 1990 1 Values from NRC, 2000 or Sheppard, 1990 are the 25th percentile values on the cumulative distribution function.
2  25 th percentile value was less than 0.1 and was rounded down to 0.
3  25 th percentile value was less listed as 96 in Table 3. It was changed to 95 to make it consistent with other Eu isotopes.


9  References Baes, C.F., and R.D. Sharp, (1983). A proposal for Estimation of Sol Leaching and Leaching Constants for Use in Assessment Models, J. Environ. Qual., Vol. 12, No. 1, 1983. Pp 17-28.  
TSD 14-004 Revision 1 U.S. Nuclear Regulatory Commission, (NRC, 2000). Development of Probabilistic RESRAD 6.0 and RESRADBUILD 3.0 Computer Codes, NUREG/CR-6697, U.S. Nuclear Regulatory Commission, December 2000.
U.S. Department of Energy West Valley Demonstration Project, (DOE, 2009). Phase 1 Decommissioning Plan for the West Valley Demonstration, Appendix C Rev 2., Department of Energy.
Yim, S.P, T.M. Sullivan, and L. Milian, Sorption (Kd) measurements in Support of Dose Assessments for Zion Nuclear Station Decommissioning, Brookhaven National Laboratory Report to ZionSolutions, December 12, 2012.
Yu, C., Loureiro, C., Cheng, J.-J., Jones, Y.Y., Wang, Y.P. Chia, and E. Faillace, (1993). Data Collection Handbook to Support Modeling the Impacts of Radioactive Material in Soil, ANL/EAIS-8, Argonne National Laboratory, Argonne, IL.
10 Page 15 of 15


Besson, J.W.
TSD 14-004 Revision 1 Page 1 of 15
(2013). Humboldt Bay Power Plant License Termination Plan Revision 0 Chapter 6 Compliance with the Radiological Criteria May 2013, ENG-HB-003, Rev 0.
Bartlett, Plymouth, MA.


Dionne, B.J., (2009). Calculation of Enrico Fermi 1 Derived Concentration Guideline Levels for Soil, ENG 004, Rev 1., Bartlett, Plymouth, MA Environmental Protection Agency, (2004).
TSD 14-004 Revision 1 Summary of Changes in this Revision:
Understanding Variation in Partition Coefficient, Kd Values , United States Office of Air and Radiation EPA 402-R-04-002C, Vol 1  3.
* Rev. 1 -Changed Eu distribution coefficient values.
Felipe-Sotelo, M., Hinchliff, J., Evans, N., Warwick, P. and Read, D. (2012).
Page 2 of 15
Sorption of radionuclides to a cementitious backfill material under near-field conditions, Mineralogical Magazine, December 2012, Vol. 76(8), pp. 34013410.
International Atomic Energy Agency  (IAEA, 2010). handbook of Parameter Values for the Prediction of Radionuclide Transfer in Terrestrial and Freshwater Environments, Technical Report Series No. 472., International Atomic Energy Agency, Vienna, Austria.


Kaplan, D.J. Roberts, K., Coates, J., Sigegried, M., and Serkiz, S., 2008.
TSD 14-004 Revision 1 BNL-105442-2014-IR-R1 RECOMMENDED VALUES FOR THE DISTRIBUTION COEFFICIENT (KD) TO BE USED IN DOSE ASSESSMENTS FOR DECOMMISSIONING THE ZION NUCLEAR POWER PLANT Terry Sullivan September 24, 2014 Revision 1 Informal Report Biological, Environmental & Climate Sciences Department Brookhaven National Laboratory P.O. Box 5000 Upton, NY 11973-5000 www.bnl.gov Notice: This manuscript has been authored by employees of Brookhaven Science Associates, LLC under Contract No. DE-AC02-98CH10886 with the U.S. Department of Energy. The publisher by accepting the manuscript for publication acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes.
Saltstone and concrete interactions with radionuclides sorption (K d), desorption, and reduction capacity measurements
Page 3 of 15
, SRNS-STI-2008-00045, Savannah River National laboratory, Savannah River, SC. Kay, J.A. (2004).
Yankee Nuclear Plant Station License Termination Plan, Yankee Atomic Electric Company, MA.
Krupka, K. M. and R. J. Serne. (1998).
Effects on Radionuclide Concentrations by Cement/Ground-Water Interactions in Support of Performance Assessment of Low-Level Radioactive Waste Disposal Facilities. NUREG/CR-6377 (PNNL-11408), Pacific Northwest, National Laboratory, Richland, Washington.
Milian, L., T. Sullivan (2014). Sorption (K d) measurements on Cinder Block and Grout in Support of Dose Assessments for Zion Nuclear Station Decommissioning , Brookhaven National Laboratory Report to ZionSolutions, April 2014 (Draft).


Ochs, M., Pointeau, I. and Giffaut, E. (2006).
TSD 14-004 Revision 1 DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or any third partys use or the results of such use of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights.
Caesium sorption by hydrated cement as a function of degradation state: Experiments and modelling. Waste Management, 26, 725_732.
Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof or its contractors or subcontractors. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.
Sheppard, M. and Thibault, D.H., 1990. Default Soil Solid/Liquid Partition Coefficients, K d s, For Four Major Soil types:  A Compendium, Health Physics, Vol. 59, No. 4, pp. 471
Page 4 of 15
-481, Oct, 1990.
10  U.S. Nuclear Regulatory Commission, (NRC, 2000).
Development of Probabilistic RESRAD 6.0 and RESRADBUILD 3.0 Computer Codes, NUREG/CR-6697, U.S. Nuclear Regulatory Commission, December 2000.
U.S. Department of Energy West Valley Demonstration Project, (DOE, 2009
). Phase 1 Decommissioning Plan for the West Valley Demonstration, Appendix C Rev 2.,
Department of Energy. Yim, S.P, T.M. Sullivan, and L. Milian, Sorption (Kd) measurements in Support of Dose Assessments for Zion Nuclear Station Decommissioning
, Brookhaven National Laboratory Report to ZionSolutions, December 12, 2012.
Yu, C., Loureiro, C., Cheng, J.
-J., Jones, Y.Y., Wang, Y.P. Chia, and E. Faillace, (1993).
Data Collection Ha ndbook to Support Modeling the Impacts of Radioactive Material in Soil,  ANL/EAIS-8, Argonne National Laboratory, Argonne, IL. 


RECOMMENDED VALUES FOR THE DISTRIBUTION COEFFICIENT (KD) TO BE USED IN DOSE ASSESSMENTS FOR DECOMMISSIONING THE ZION NUCLEAR POWER PLANT Terry Sullivan
TSD 14-004 Revision 1 Table of Contents
: 1. Introduction ................................................................................................................................ 1
: 2. Approach .................................................................................................................................... 2
: 3. Data ............................................................................................................................................. 2
Concrete Environment Kd values ............................................................................................... 4
: 4. Discussion .................................................................................................................................. 6
: 5. Recommended Values ................................................................................................................ 7
References ....................................................................................................................................... 9
List of Tables Table 1. Potential Radionuclides of Concern at the Zion Power Plant .......................................... 1
Table 2 Site-specific Kd values (ml/g) for the Zion Nuclear Power Station .................................. 3
Table 3 Literature soil Kd values for radionuclides of concern at Zion. ........................................ 4
Table 4 Preferred distribution coefficients (Kd ml/g) for cement concrete environments (Table 5.1 Krupka, 1998). .......................................................................................................................... 6
Table 5 Recommended Kd values to be used in the basement fill model. ..................................... 8
Page 5 of 15


Informal Report
TSD 14-004 Revision 1
 
: 1. Introduction ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated. The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled. The remaining u n d e r g r o u n d structures will contain low amounts of residual licensed radioactive material. An important component of the decommissioning process is the demonstration that any remaining activity will not cause a hypothetical individual to receive a dose in excess of 25 mrem/y as specified in 10CFR20 Subpart E.
Environmental & Climate Sciences Department Brookhaven National Laboratory P.O. Box 5000 Upton, NY 11973-5000 www.bnl.gov
The compliance assessment requires prediction of the release and transport of contaminants to the hypothetical individual. Characterization studies by ZionSolutions have identified the following nuclides as being of potential concern (Table 1).
 
Table 1. Potential Radionuclides of Concern at the Zion Power Plant Radionuclides   Radionuclides   Radionuclides   Radionuclides   Radionuclides   Radionuclides
Notice: This manuscript has been authored by employees of Brookhaven Science Associates, LLC under Contract No. DE
H-3           Co-60         Tc-99         Cs-137       Eu-155       Pu-241
-AC02-98CH10886 with the U.S. Department of Energy. The publisher by accepting the manuscript for publication acknowledges that the United States Government retains a non
C-14         Ni-63         Ag-108m       Pm-147       Np-237       Am-241
-exclusive, paid
Fe-55         Sr-90         Sb-125         Eu-152       Pu-238       Am-243
-up, irrevocable, world
Ni-59         Nb-94         Cs-134         Eu-154       Pu-239/240   Cm-243/244
-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes.
A key parameter in this assessment is the distribution coefficient (Kd) which is a measure of the amount of the radionuclide that will sorb to the solid media (soil or backfill) in the subsurface environment. The exposure pathway of concern is the groundwater. Groundwater concentration has an inverse relationship with Kd. Thus a lower value of Kd will provide higher groundwater concentrations and a more conservative prediction of dose. BNL (Yim, 2012, Milian, 2014) has conducted site-specific measurements on using local groundwater and samples of site soils and potential backfill materials to assess the Kd value for the contaminants with the expected highest residual concentration (Fe-55, Co-60, Ni-63, Sr-90, and Cs-137) for ZionSolutions. However, there are several other radioactive contaminants (Table 1) that may be present at lower levels that will still require assessment to demonstrate that dose limits are not exceeded. This document reviews the existing literature to recommend a value for Kd when site-specific numbers are not available.
 
Literature values for Kd show that sorption strongly depends on the contacting media and the geochemical conditions. The backfill selected for disposal will therefore play a huge role in determining the choice of the Kd value. A final decision has not been made on the backfill material at the Zion Power Plant. Materials under consideration include:
DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or any third partys use or the results of such use of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights.
* Crushed concrete demolition debris
Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof or its contractors or subcontractors. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.
* Crushed cinder block
* Flowable grout
* Local sand 1
Page 6 of 15


Table of Contents
TSD 14-004 Revision 1 The concrete and cinder block would be obtained from the building materials removed to three feet below grade and would be free from residual radioactive contamination. Combinations of the above materials are also under consideration.
: 1. Introduction ................................................................................................................................
The first three materials are alkaline and will cause the pH to rise substantially above the local ambient conditions. Based on testing at BNL with materials supplied by ZionSolutions, the pH will initially increase to 10 or 11 for the cementitious materials and grout. Eventually, as the alkali is consumed by buffering reactions the pH will decrease. This is expected to take a minimum of several hundred years depending on the flow rate and buffering capacity of the surrounding soils. Several studies have found that pH is a key geochemical factor in controlling sorption. For this reason consideration must be given to the likely high pH conditions when selecting the Kd value to be used in modeling if a mixture of backfills is used.
1!2. Approach ....................................................................................................................................
: 2. Approach The objective of selecting a Kd value is to choose a value that is reasonably conservative with respect to projected groundwater dose (radionuclide concentrations). This requires a value that is likely to provide a lower bound for Kd. The value for Kd strongly depends on the solid media that contacts the groundwater thus site-specific values are the most representative of actual conditions.
2!3. Data .............................................................................................................................................
For radionuclides with site-specific data the media with the lowest measured Kd was selected to provide this lower bound. For radionuclides without site-specific data the literature was reviewed to determine the range of Kd values typically found in soils and found in cementitious (high pH) environments. These Kds will be used for initial DUST-MS runs to determine groundwater concentrations at potential well locations. Depending upon the outcome they may be further refined with more site specific or literature data.
2!Concrete Environment Kd values ...............................................................................................
Baes and Sharp (Baes and Sharp 1983) were among the first to show that the Kd value for Cs and Sr is log-normally distributed in soils. They applied a log-normal distribution to all elements and this approach is widely used (Sheppard and Thibault, 1990; NRC, 1990). Sheppard and Thibault extended the concept of log-normal distribution to apply to a soil type (sand, loam, clay or organic). This concept is used in this report to determine the 25th percentile value for Kd in soils. The use of the 25th percentile value has been performed in other decommissioning studies at Fermi (Dionne, 2009) and Humboldt Bay (Besson, 2013).
4!4. Discussion ..................................................................................................................................
: 3. Data Three types of data are used for the selection of an appropriate Kd for the backfill region at the Zion Nuclear Power Plant. These include site-specific values using local groundwater and soil or concrete samples from the site; literature values for soil environments; and literature values for concrete environments.
6!5. Recommended Values ................................................................................................................
Site-specific Kd data:
7!References .......................................................................................................................................
Kd measurements were performed for ZionSolutions using site-specific groundwater and soil samples (clay, silt, native sand, and disturbed sand - native sand that was excavated during 2
9! List of Tables Table 1. Potential Radionuclides of Concern at the Zion Power Plant ..........................................
Page 7 of 15
1!Table 2  Site
-specific K d values (ml/g) for the Zion Nucle ar Power Station ..................................
3!Table 3  Literature soil K d values for radionuclides of concern at Zion. ........................................
4!Table 4  Preferred distribution coefficients (K d ml/g) for cement concrete environments (Table 5.1 Krupka, 1998). ..........................................................................................................................
6!Table 5  Recommended K d values to be used in the basement fill model. .....................................
8!
1  1. Introduction ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated.
The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled. The remaining underground structures will contain low amounts of residual licensed radioactive material. An important component of the decommissioning process is the demonstration that any remaining activity will not cause a hypothetical individual to receive a dose in excess of 25 mrem/y as specified in 10CFR 20 Subpart E.
The compliance assessment requires prediction of the release and transport of contaminants to the hypothetical individual. Characterization studies by ZionSolutions have identified the following nuclides as being of potential concern (Table 1).
Table 1. Potential Radionuclides of Concern at the Zion Power Plant
!"#$%&'()$#*+
,!"#$%&'()$#*+
,!"#$%&'()$#*+
,!"#$%&'()$#*+
,!"#$%&'()$#*+
,!"#$%&'()$#*+
,"#$!%&#'(!)*#++!%,#-$.!!"#$%%&/0#12-!%#-2!34#'$!!"#$%&'(/5#-2.!36#1$.!75#12-!89#::!;<#+(!;=#-1:!>0#-:1!/0#1$?!75#12$!34#:+!3=#+2!%,#-$2!>0#-:2!/0#1$+@12(!%5#12$@122! A key parameter in this assessment is the distribution coefficient (K d) which is a measure of the amount of the radionuclide that will sorb to the solid media (soil or backfill) in the subsurface environment. The exposure pathway of concern is the groundwater. Groundwater concentration has an inverse relationship with K
: d. Thus a lower value of K d will provide higher groundwater concentrations and a more conservative prediction of dose. BNL (Yim, 2012, Milian, 2014) has conducted site-specific measurements on using local groundwater and samples of site soils and potential backfill materials to assess the K d value for the contaminants with the expected highest residual concentration (Fe-55, Co-60, Ni-63, Sr-90, and Cs-137) for ZionSolutions. However, there are several other radioactive contaminants (Table 1) that may be present at lower levels that will still require assessment to demonstrate that dose limits are not exceeded. This document reviews the existing literature to recommend a value for K d when site-specific numbers are not available. 


Literature values for K d show that sorption strongly depends on the contacting media and the geochemical conditions. The backfill selected for disposal will therefore play a huge role in determining the choice of the K d value. A final decision has not been made on the backfill material at the Zion Power Plant. Materials under consideration include:
TSD 14-004 Revision 1 construction of the plant and backfilled around the plant) for six nuclides. Additionally potential backfill materials including two concrete samples (one from the Containment Building and one from the Crib House), two Cinder Block samples from the site, and one low density grout were tested using site-specific groundwater. The elements measured included Fe, Co, Ni, Sr and Cs.
&#xa5; Crushed concrete demolition debris
Table 2 presents the results of these measurements. Note isotopes of Cs and Ni found in Table 1 are also presented in Table 2 as isotopes will have the same chemical sorption properties.
&#xa5; Crushed cinder block
Table 2 Site-specific Kd values (ml/g) for the Zion Nuclear Power Station Site       Site         Site
&#xa5; Flowable grout
Site           Site           Site                           Specific   Specific   Specific
&#xa5; Local sand 2  The concrete and cinder block would be obtained from the building materials removed to three feet below grade and would be free from residual radioactive contamination. Combinations of the above materials are also under consideration.
Site       Specific       Specific       Specific   Site Specific       Crib       Cinder       Low
The first three materials are alkaline and will cause the pH to rise substantially above the local ambient conditions.
Specific         Silt       Disturbed       Native   Containment           House       Block       Density
Based on testing at BNL with materials supplied by ZionSolutions, the pH will initially increase to 10 or 11 for the cementitious materials and grout. Eventually, as the alkali is consumed by buffering reactions the pH will decrease. This is expected to take a minimum of several hundred years depending on the flow rate and buffering capacity of the surrounding soils. Several studies have found that pH is a key geochemical factor in controlling sorption. For this reason consideration must be given to the likely high pH conditions when selecting the Kd value to be used in modeling if a mixture of backfills is used.
Silt Kd1   Clay1 Kd   Sand Kd1   Sand Kd1   Concrete1 Kd   Concrete1     Kd2       Grout Kd2
: 2. Approach  The objective of selecting a K d value is to choose a value that is reasonably conservative with respect to projected groundwater dose (radionuclide concentrations). This requires a value that is likely to provide a lower bound for K
Radionuclide   ml/g             ml/g         ml/g           ml/g           ml/g           Kd ml/g   ml/g       ml/g
: d. The value for K d strongly depends on the solid media that contacts the groundwater thus site-specific values are the most representative of actual
Fe-55           8061         17288         2857           5579         16546           17288                
Ni-59             75           136           331             62           3438             8361       177         4,569
Co-60           1161         1161         1161           1161           1161             1161       223         1941
Ni-63             75           136           331             62           3438             8361       177         4,569
Sr-90           2.3           5.7           3.4             2.3           10.4             18.5       23.5       11.8
Cs-134           527         3011           635             615             85             45         249         303
Cs-137           527         3011           635             615             85             45         249         303
1 Yim, 2012 2
Milian, 2014 Literature values for Kd in soil environments Numerous measurements of Kd have been reported in the literature. Key compilations of this data include those by Baes and Sharp (Baes, 1983); Sheppard and Thibault (Sheppard, 1990), Yu (Yu, 1993), the U.S. Nuclear Regulatory Commission (NRC, 2000); and the International Atomic Energy Agency (IAEA, 2010). All of these documents provide statistical parameters to estimate the distribution. Literature values for Kd in soil media from selected sources are presented in Table 3. The first two columns are mean values for Kd presented in (Yu, 1993 and IAEA 2012). For conservatism the 25th percentile in the distribution from the reports (Sheppard, 1990 and NRC, 2000) are also reported in the Table 3. For the Sheppard data the log-normal distribution of the data for sand was used except for Nb-94 and Sb-125 which are the geometrics means because standard deviations were not provided in the Sheppard data. Other soil types were not included because sand, in most cases, has the lowest Kd and the surrounding soil at Zion is primarily sand.
3 Page 8 of 15


conditions.
TSD 14-004 Revision 1 Table 3 Literature soil Kd values for radionuclides of concern at Zion.
For radionuclides with site-specific data the media with the lowest measured K d was selected to provide this lower bound. For radionuclides without site-specific data the literature was reviewed to determine the range of K d values typically found in soils and found in cementitious (high pH) environments. These Kds will be used for initial DUST-MS runs to determine groundwater concentrations at potential well locations. Depending upon the outcome they may be further refined with more site specific or literature data.
(Yu, 1993) Sand             (IAEA 2010)                                                     (Sheppard, 1990)
Baes and Sharp (Baes and Sharp 1983) were among the first to show that the Kd value for Cs and Sr is log-normally distributed in soils. They applied a log-normal distribution to all elements and this approach is widely used (Sheppard and Thibault, 1990; NRC, 1990). Sheppard and Thibault extended the concept of log-normal distribution to apply to a soil type (sand, loam, clay or organic). This concept is used in this report to determine the 25 th percentile value for K d in soils. The use of the 25 th percentile value has been performed in other decommissioning studies at Fermi (Dionne, 2009) and Humboldt Bay (Besson, 2013).
Kd       Tables 12, 14 Sand or All       (NRC, 2000)               Sand 25th
: 3. Data  Three types of data are used for the selection of an appropriate Kd for the backfill region at the Zion Nuclear Power Plant.
Radionuclide           ml/g                         Soils ml/g               25th Percentile ml/g   Percentile ml/g
These include site-specific values using local groundwater and soil or concrete samples from the site; literature values for soil environments; and literature values for concrete environments.
H-3                                                 1                                 0.0431                   0.051
Site-specific K d data:
C-14                     5                                                               1.24                     1.76
K d measurements were performed for ZionSolutions using site-specific groundwater and soil samples (clay, silt, native sand, and disturbed sand  native sand that was excavated during 3  construction of the plant and backfilled around the plant) for six nuclides. Additionally potential backfill materials including two concrete samples (one from the Containment Building and one from the Crib House), two Cinder Block samples from the site, and one low density grout were tested using site-specific groundwater. The elements measured included Fe, Co, Ni, Sr and Cs. Table 2 presents the results of these measurements. Note isotopes of Cs and Ni found in Table 1 are also presented in Table 2 as isotopes will have the same chemical sorption properties.
Fe-55                 220                           320                                     34.3                     39
Table 2  Site-specific K d values (ml/g) for the Zion Nuclear Power Station
Ni-59                 400                           140                                     160                     148
!"#$%&'()$#*
Co-60                   60                           640                                     42.9                     9.2
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im, 2012 2 Milian, 2014 Literature values for Kd in soil environments Numerous measurements of K d have been reported in the literature. Key compilations of this data include those by Baes and Sharp (Baes, 1983); Sheppard and Thibault (Sheppard, 1990), Yu (Yu, 1993), the U.S. Nuclear Regulatory Commission (NRC, 2000); and the International Atomic Energy Agency (IAEA, 2010). All of these documents provide statistical parameters to estimate the distribution. Literature values for K d in soil media from selected sources are presented in Table 3. The first two columns are mean values for K d presented in (Yu, 1993 and IAEA 2012). For conservatism the 25 th percentile in the distribution from the reports (Sheppard, 1990 and NRC, 2000) are also reported in the Table 3. For the Sheppard data the log-normal distribution of the data for sand was used except for Nb-94 and Sb-125 which are the geometrics means because standard deviations were not provided in the Sheppard data. Other soil types were not included because sand, in most cases, has the lowest K d and the surrounding soil at Zion is primarily sand.
Ni-63                 400                           140                                     160                     148
4  Table 3  Literature soil K d values for radionuclides of concern at Zion.
Sr-90                   15                               22                                   7.49                     4.6
!"#$%&'()$#*
Nb-94                 160                           170                                     44.6                     164
,DE'F,2GGHI,-"&#, 1#, ,3)45 , DJKLK,@M2MI , ,N":)*+,2@F,2O,-"&#,%9,K)),-%$)+,3)45, ,D;!6F,@MMMI
Tc-99                 0.1                           0.23                                   0.0618                     0.04
,@P.Q,R*9(*&.$)*,3)45
Ag-108m                 90                                                               52.6                     27
,D-Q*//"9#F, 2GGMI ,-"&#,,@P.Q,R*9(*&.$)*
Sb-125                 45                               17                                   43.4                     45
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he predictions at the 25 th percent level of the distribution for the NRC and Sheppard reports are similar. This is because the NRC data set for the distribution is based on, but not limited to the Sheppard data set.
Cs-134                 280                           530                                     92.5                     51
Concrete Environment K d values The chemistry of the water will change from an initial value of greater than 11 down to the ambient pH in a crushed concrete environment. The convention of Bradbury and Sarott (1995) describing the three types of chemical environments that all cements progress through is used to understand the data. The following description of the environments has been abbreviated from the initial work by Krupka (Krupka, 1998)  
Cs-137                 280                           530                                     93.4                     51
Pm-147                                           450                                     94.8                      
Eu-152                                                                             96.2                      
Eu-154                                                                             95.2                      
Eu-155                                                                             95.8                      
Np-237                   5                               35                                   3.75                     1.30
Pu-238                 550                           400                                     268                     174
Pu-239/240             550                           400                                     267.5                     174
Pu-241                 550                           400                                     268                     174
Am-241               1900                           1000                                     177                     333
Am-243               1900                           1000                                     178                     333
Cm-243/244           4000                           9300                                     1990                     891
The predictions at the 25th percent level of the distribution for the NRC and Sheppard reports are similar. This is because the NRC data set for the distribution is based on, but not limited to the Sheppard data set.
Concrete Environment Kd values The chemistry of the water will change from an initial value of greater than 11 down to the ambient pH in a crushed concrete environment. The convention of Bradbury and Sarott (1995) describing the three types of chemical environments that all cements progress through is used to understand the data. The following description of the environments has been abbreviated from the initial work by Krupka (Krupka, 1998) 4 Page 9 of 15


5  &#xa5;    Environment I   This environment occurs immediately after the cement hardens and is wetted by infiltrating wate r  The cement pore water is characterize d as having a high pH of >12.5, high ionic strength, and high concentration s of potassium and sodium resulting from the dissolution of alkali impurities in the clinker phases.
TSD 14-004 Revision 1
Hydration is still continuing during Environment I with the formation of C-S-H (Calcium- Silicate Hydrate) and portlandite [
* Environment I This environment occurs immediately after the cement hardens and is wetted by infiltrating water The cement pore water is characterized as having a high pH of >12.5, high ionic strength, and high concentrations of potassium and sodium resulting from the dissolution of alkali impurities in the clinker phases. Hydration is still continuing during Environment I with the formation of C-S-H (Calcium- Silicate -
Ca(OH)2]     The composition of the cement pore fluid is at equilibrium with portlandite during this time. Based on the modeling estimates this environment may last for the first 100 to 10,000 years. Environment II   During this period, the soluble salts of the alkali metals are all dissolved   The pH of the cement pore water is controlled at a value of about 12.5 by the solubility of portlandite.
Hydrate) and portlandite [Ca(OH)2]         The composition of the cement pore fluid is at equilibrium with portlandite during this time. Based on the modeling estimates this environment may last for the first 100 to 10,000 years.
The C-S-H and portlandite are the major solid phases present   Environment II may last for a long time   Its duration depends on how much water percolates through the system to dissolve all the slightly soluble portlandite   T his environment may last from 100-10,000 years to 1,000-100,000 years. Environment III The concentration of portlandite has been reduced to such an extent by this period that the solubility of C-S-H now controls the pH of the cement pore fluid   The C-S-H starts to dissolve incongruently with a continual decrease in pH   At the end of this evolution, Environment III can be conceptualize d as leaving only silica (SiO 2) as the solubility control for the pore fluid pH.
Environment II During this period, the soluble salts of the alkali metals are all dissolved The pH of the cement pore water is controlled at a value of about 12.5 by the solubility of portlandite. The C-S-H and portlandite are the major solid phases present Environment II may last for a long time Its duration depends on how much water percolates through the system to dissolve all the slightly soluble portlandite         This environment may last from 100-10,000 years to 1,000-100,000 years.
For the sake of simplicity, the final end point of Environment III can be considered somewhat analo gous to the geochemical conditions of the "normal" ambient soil environment.
Environment III The concentration of portlandite has been reduced to such an extent by this period that the solubility of C-S-H now controls the pH of the cement pore fluid The C-S-H starts to dissolve incongruently with a continual decrease in pH At the end of this evolution, Environment III can be conceptualized as leaving only silica (SiO2) as the solubility control for the pore fluid pH. For the sake of simplicity, the final end point of Environment III can be considered somewhat analogous to the geochemical conditions of the "normal" ambient soil environment.
The important point of this discussion is that the cement will control the pH for hundreds to thousands of years. Thus, if cementitious materials are used for backfill material, a high pH environment will prevail and K d values are likely to be similar to those found in cement based materials.  
The important point of this discussion is that the cement will control the pH for hundreds to thousands of years. Thus, if cementitious materials are used for backfill material, a high pH environment will prevail and Kd values are likely to be similar to those found in cement based materials.
5 Page 10 of 15


6  Table 4 Preferred distribution coefficients (K d ml/g) for cement concrete environments (Table 5.1 Krupka, 1998).
TSD 14-004 Revision 1 Table 4 Preferred distribution coefficients (Kd ml/g) for cement concrete environments (Table 5.1 Krupka, 1998).
Environment I Environment II Environment III Oxidizing Conditions Reducing Condition s  Oxidizing Conditions Reducing Condition s  Oxidizing Conditions Reducing Condition s      Radionuclide K d (ml/g) Am 5000 5000 5000 5000 500 500 C 500 500 100 100 10 10 Cl 5 5 1 1 0 0 I 10 10 5 5 1 1 Lanthanides 5000 5000 5000 5000 500 500 Ni 100 100 100 100 10 10 Nb 1000 1000 1000 1000 100 100 Np 2000 5000 2000 5000 200 500 Pu 5000 5000 5000 5000 500 500 Ra 100 100 100 100 100 100 Sr 1 1 3 3 3 5 Tc 0 1000 0 1000 0 100 Th 5000 5000 5000 5000 500 500 U 1000 1000   1000 1000   100 100   The above table does not include Cs or Eu, two nuclides of potential concern at Zion. Cs is known to have low sorption on cements. This is due in part to competition for sorption sites with other ions (Na and K) that are released by the leaching from the concrete. Bradbury and Sarott (Bradbury 1995) provided K d estimates for Cs as 2 to 20 ml/g with the low value in Environment I. This is lower than the site-specific value for Cs at Zion. They also provided estimates for Eu (5000 to 1000 ml/g) with Environment III with the lowest K d and Cm (5000 to 1000 ml/g) with Environment III providing the least sorption (Bradbury, 1995). A recent study (Felipe-Sotello, 2012) measured Kd values for Eu at 66000 ml/g.
Environment I               Environment II               Environment III Oxidizing     Reducing       Oxidizing     Reducing         Oxidizing   Reducing Conditions    Conditions      Conditions  Conditions      Conditions  Conditions Radionuclide                                           Kd (ml/g)
Other values for distribution coefficients in cementitious materials are provided in (Kaplan, 2008).  
Am                   5000           5000           5000         5000             500           500 C                     500           500             100         100               10           10 Cl                       5             5                 1           1               0           0 I                       10           10                 5           5               1           1 Lanthanides         5000           5000           5000         5000             500           500 Ni                     100           100             100         100               10           10 Nb                   1000           1000           1000         1000             100           100 Np                   2000           5000           2000         5000             200           500 Pu                   5000           5000           5000         5000             500           500 Ra                     100           100             100         100             100           100 Sr                       1             1                 3           3               3           5 Tc                       0         1000                 0       1000                 0         100 Th                   5000           5000           5000         5000             500           500 U                   1000           1000           1000         1000             100           100 The above table does not include Cs or Eu, two nuclides of potential concern at Zion. Cs is known to have low sorption on cements. This is due in part to competition for sorption sites with other ions (Na and K) that are released by the leaching from the concrete. Bradbury and Sarott (Bradbury 1995) provided Kd estimates for Cs as 2 to 20 ml/g with the low value in Environment I. This is lower than the site-specific value for Cs at Zion. They also provided estimates for Eu (5000 to 1000 ml/g) with Environment III with the lowest Kd and Cm (5000 to 1000 ml/g) with Environment III providing the least sorption (Bradbury, 1995). A recent study (Felipe-Sotello, 2012) measured Kd values for Eu at 66000 ml/g. Other values for distribution coefficients in cementitious materials are provided in (Kaplan, 2008).
: 4. Discussion Site-specific values are the most representative of the conditions that will occur at Zion after decommissioning and they will be recommended for use in groundwater dose assessment.
: 4. Discussion Site-specific values are the most representative of the conditions that will occur at Zion after decommissioning and they will be recommended for use in groundwater dose assessment.
Although a final determination of the backfill material has not been made, it is likely that the backfill will contain a substantial amount of cementitious material. Examining the representative K d values for soils (Table 3) and cementitious systems (Table 4) it is clear that with the exception of Cs the cement K d values are greater than for soil systems. The K d value selected is meant to provide a conservative assessment of dose to the groundwater pathway. For this reason, with the exception of H and Tc literature soil K d values will be recommended for the assessment when site-specific values are not available. To increase the degree of confidence 7  that a conservative value has been selected the 25 th percentile K d from either the NRC or Sheppard reports will be used. For Tc the sand K d in Table 3 is less than 0.1. The cementitious oxidizing conditions K d is zero in Table 4. The soil K d is rounded to zero to ensure conservatism.
Although a final determination of the backfill material has not been made, it is likely that the backfill will contain a substantial amount of cementitious material. Examining the representative Kd values for soils (Table 3) and cementitious systems (Table 4) it is clear that with the exception of Cs the cement Kd values are greater than for soil systems. The Kd value selected is meant to provide a conservative assessment of dose to the groundwater pathway. For this reason, with the exception of H and Tc literature soil Kd values will be recommended for the assessment when site-specific values are not available. To increase the degree of confidence 6
The same will be done for the Table 3 H K d as a conservative assumption.
Page 11 of 15
For one nuclide, Sb-125, the IAEA median value was lower than the 25 th percentile value on the NRC distribution. No standard deviation was reported in the Sheppard data. For this reason, the IAEA value is recommended as the appropriate value for screening calculations for Sb-125.
 
The Eu isotopes all have slightly different K d values in Table 3. These values are from NRC, 2000 and are calculated values for the 25 th percentile based on a mean value and standard deviation. One would expect isotopes to have the same sorption characteristics. It is likely that this is round-off error in determining the 25 th percentile. For this reason the minimum value for all three isotopes will be selected as the reference value.
The recommended values for the basement fill model are either site-specific or values measured in soil. The K d values in a cement environment for elements other tan Cs, Tc and H are expected to be higher based on existing data. Thus, they should be appropriate for outside of the buildings in the surrounding soil with the exception of H, Tc and Cs. Depending on the buffering capacity of the soil, time, and distance from the building, the chemical environment of the groundwater exiting the building may control the sorption of Cs. For this reason, the site-specific Kd for Cs in the cement environment should be used in the surrounding soils to provide a conservative estimate of groundwater concentration for dose assessment. 
: 5. Recommended Values
 
The values in Table 5 are the minimum values found in any test for the site-specific case and the minimum values found from the reports cited in Table 3. These values are appropriate for maximizing the groundwater concentration and thereby predicted dose. For intruder scenarios or scenarios where the backfill is used as gardening soils, a higher value of K d would be recommended for maximizing the predicted dose in those cases. 
 
8  Table 5  Recommended K d values to be used in the basement fill model.
!"#$%&'()$#*
, ,=")0,A$0*,D7*"9+I ,!*(%33*&#*#,>"+*3*&.,T$)),
1#,3)45 ,!*0*9*&(*2 ,"#$!-B12>D(-!0 2 %#-2!:B.$>D($!1.2 NRC, 2000 89#::!1B.(>D((!2857 Site-Specific 34#:+!.B:(>D(2!62 Site Specific
%&#'(!:B1.>D((!223 Site Specific 34#'$!+B'(>D(-!62 Site Specific
;<#+(!1B+->D(-!2.3 Site Specific 3=#+2!1B($>D(2!45 NRC, 2000
)*#++!1B-$>D(:!0 2 7C#-(?5!-B1.>D(1!27 Sheppard, 1990
;=#-1:!1B..>D((!17 IAEA, 2010
%,#-$2!1B('>D((!45 Site Specific
%,#-$.!$B((>D(-!45 Site Specific
/5#-2.!1B'1>D((!95 NRC, 2000
>0#-:1!-B$$>D(-!95 3 NRC, 2000
>0#-:2!?B?(>D((!95 NRC, 2000
!"#$%%&2B+'>D((!95 NRC, 2000 36#1$.!1B-2>D('!1 Sheppard, 1990
/0#1$?!?B..>D(-!174 Sheppard, 1990
/0#1$+@12(!1B2->D(2!174 Sheppard, 1990
/0#12-!-B22>D(-!174 Sheppard, 1990 75#12-!2B$1>D(1!177 NRC, 2000 75#12$!.B$?>D($!177 NRC, 2000
%5#12$@122!1B?:>D(-!891 Sheppard, 1990 1 Values from NRC, 2000 or Sheppard, 1990 are the 25th percentile values on the cumulative distribution function.
2  25 th percentile value was less than 0.1 and was rounded down to 0.
3  25 th percentile value was less listed as 96 in Table 3. It was changed to 95 to make it consistent with other Eu isotopes.
 
9  References Baes, C.F., and R.D. Sharp, (1983). A proposal for Estimation of Sol Leaching and Leaching Constants for Use in Assessment Models, J. Environ. Qual., Vol. 12, No. 1, 1983. Pp 17-28.


Besson, J.W.
TSD 14-004 Revision 1 that a conservative value has been selected the 25th percentile Kd from either the NRC or Sheppard reports will be used. For Tc the sand Kd in Table 3 is less than 0.1. The cementitious oxidizing conditions Kd is zero in Table 4. The soil Kd is rounded to zero to ensure conservatism.
(2013). Humboldt Bay Power Plant License Termination Plan Revision 0 Chapter 6 Compliance with the Radiological Criteria May 2013, ENG-HB-003, Rev 0.
The same will be done for the Table 3 H Kd as a conservative assumption.
Bartlett, Plymouth, MA.
For one nuclide, Sb-125, the IAEA median value was lower than the 25th percentile value on the NRC distribution. No standard deviation was reported in the Sheppard data. For this reason, the IAEA value is recommended as the appropriate value for screening calculations for Sb-125.
The Eu isotopes all have slightly different Kd values in Table 3. These values are from NRC, 2000 and are calculated values for the 25th percentile based on a mean value and standard deviation. One would expect isotopes to have the same sorption characteristics. It is likely that this is round-off error in determining the 25th percentile. For this reason the minimum value for all three isotopes will be selected as the reference value.
The recommended values for the basement fill model are either site-specific or values measured in soil. The Kd values in a cement environment for elements other tan Cs, Tc and H are expected to be higher based on existing data. Thus, they should be appropriate for outside of the buildings in the surrounding soil with the exception of H, Tc and Cs. Depending on the buffering capacity of the soil, time, and distance from the building, the chemical environment of the groundwater exiting the building may control the sorption of Cs. For this reason, the site-specific Kd for Cs in the cement environment should be used in the surrounding soils to provide a conservative estimate of groundwater concentration for dose assessment.
: 5. Recommended Values The values in Table 5 are the minimum values found in any test for the site-specific case and the minimum values found from the reports cited in Table 3. These values are appropriate for maximizing the groundwater concentration and thereby predicted dose. For intruder scenarios or scenarios where the backfill is used as gardening soils, a higher value of Kd would be recommended for maximizing the predicted dose in those cases.
7 Page 12 of 15


Dionne, B.J., (2009). Calculation of Enrico Fermi 1 Derived Concentration Guideline Levels for Soil, ENG 004, Rev 1., Bartlett, Plymouth, MA Environmental Protection Agency, (2004).
TSD 14-004 Revision 1 Table 5 Recommended Kd values to be used in the basement fill model.
Understanding Variation in Partition Coefficient, Kd Values , United States Office of Air and Radiation EPA 402-R-04-002C, Vol 1  3.
Recommended
Felipe-Sotelo, M., Hinchliff, J., Evans, N., Warwick, P. and Read, D. (2012).
                  Half Life   Basement Fill
Sorption of radionuclides to a cementitious backfill material under near-field conditions, Mineralogical Magazine, December 2012, Vol. 76(8), pp. 34013410.
Radionuclide   (years)   Kd ml/g                   Reference1
International Atomic Energy Agency  (IAEA, 2010). handbook of Parameter Values for the Prediction of Radionuclide Transfer in Terrestrial and Freshwater Environments, Technical Report Series No. 472., International Atomic Energy Agency, Vienna, Austria.
2 H-3         1.24E+01                             0 C-14         5.73E+03                         1.2      NRC, 2000 Fe-55       2.70E+00                   2857          Site-Specific Ni-59       7.50E+04                         62      Site Specific Co-60       5.27E+00                       223      Site Specific Ni-63       9.60E+01                         62      Site Specific Sr-90       2.91E+01                         2.3      Site Specific Nb-94       2.03E+04                         45      NRC, 2000 2
Tc-99       2.13E+05                             0 Ag-108m     1.27E+02                         27      Sheppard, 1990 Sb-125       2.77E+00                         17      IAEA, 2010 Cs-134       2.06E+00                         45      Site Specific Cs-137       3.00E+01                         45      Site Specific Pm-147       2.62E+00                         95      NRC, 2000 3
Eu-152       1.33E+01                       95 NRC, 2000 Eu-154       8.80E+00                         95 NRC, 2000 Eu-155       4.96E+00                         95 NRC, 2000 Np-237       2.14E+06                             1 Sheppard, 1990 Pu-238       8.77E+01                       174 Sheppard, 1990 Pu-239/240   2.41E+04                       174 Sheppard, 1990 Pu-241       1.44E+01                       174 Sheppard, 1990 Am-241       4.32E+02                       177 NRC, 2000 Am-243       7.38E+03                       177 NRC, 2000 Cm-243/244   2.85E+01                       891 Sheppard, 1990 1
Values from NRC, 2000 or Sheppard, 1990 are the 25th percentile values on the cumulative distribution function.
2 25th percentile value was less than 0.1 and was rounded down to 0.
3 25th percentile value was less listed as 96 in Table 3. It was changed to 95 to make it consistent with other Eu isotopes.
8 Page 13 of 15


Kaplan, D.J. Roberts, K., Coates, J., Sigegried, M., and Serkiz, S., 2008.
TSD 14-004 Revision 1 References Baes, C.F., and R.D. Sharp, (1983). A proposal for Estimation of Sol Leaching and Leaching Constants for Use in Assessment Models, J. Environ. Qual., Vol. 12, No. 1, 1983. Pp 17-28.
Saltstone and concrete interactions with radionuclides sorption (K d), desorption, and reduction capacity measurements
Besson, J.W. (2013). Humboldt Bay Power Plant License Termination Plan Revision 0 Chapter 6 Compliance with the Radiological Criteria May 2013, ENG-HB-003, Rev 0. Bartlett, Plymouth, MA.
, SRNS-STI-2008-00045, Savannah River National laboratory, Savannah River, SC. Kay, J.A. (2004).
Dionne, B.J., (2009). Calculation of Enrico Fermi 1 Derived Concentration Guideline Levels for Soil, ENG 004, Rev 1., Bartlett, Plymouth, MA Environmental Protection Agency, (2004). Understanding Variation in Partition Coefficient, Kd Values, United States Office of Air and Radiation EPA 402-R-04-002C, Vol 1 - 3.
Yankee Nuclear Plant Station License Termination Plan, Yankee Atomic Electric Company, MA.
Felipe-Sotelo, M., Hinchliff, J., Evans, N., Warwick, P. and Read, D. (2012). Sorption of radionuclides to a cementitious backfill material under near-field conditions, Mineralogical Magazine, December 2012, Vol. 76(8), pp. 3401-3410.
Krupka, K. M. and R. J. Serne. (1998).
International Atomic Energy Agency (IAEA, 2010). handbook of Parameter Values for the Prediction of Radionuclide Transfer in Terrestrial and Freshwater Environments, Technical Report Series No. 472., International Atomic Energy Agency, Vienna, Austria.
Effects on Radionuclide Concentrations by Cement/Ground-Water Interactions in Support of Performance Assessment of Low-Level Radioactive Waste Disposal Facilities. NUREG/CR-6377 (PNNL-11408), Pacific Northwest, National Laboratory, Richland, Washington.
Kaplan, D.J. Roberts, K., Coates, J., Sigegried, M., and Serkiz, S., 2008.Saltstone and concrete interactions with radionuclides sorption (Kd), desorption, and reduction capacity measurements, SRNS-STI-2008-00045, Savannah River National laboratory, Savannah River, SC.
Milian, L., T. Sullivan (2014). Sorption (K d) measurements on Cinder Block and Grout in Support of Dose Assessments for Zion Nuclear Station Decommissioning , Brookhaven National Laboratory Report to ZionSolutions, April 2014 (Draft).
Kay, J.A. (2004). Yankee Nuclear Plant Station License Termination Plan, Yankee Atomic Electric Company, MA.
Krupka, K. M. and R. J. Serne. (1998). Effects on Radionuclide Concentrations by Cement/Ground-Water Interactions in Support of Performance Assessment of Low-Level Radioactive Waste Disposal Facilities. NUREG/CR-6377 (PNNL-11408), Pacific Northwest, National Laboratory, Richland, Washington.
Milian, L., T. Sullivan (2014). Sorption (Kd) measurements on Cinder Block and Grout in Support of Dose Assessments for Zion Nuclear Station Decommissioning, Brookhaven National Laboratory Report to ZionSolutions, April 2014 (Draft).
Ochs, M., Pointeau, I. and Giffaut, E. (2006). Caesium sorption by hydrated cement as a function of degradation state: Experiments and modelling. Waste Management, 26, 725_732.
Sheppard, M. and Thibault, D.H., 1990. Default Soil Solid/Liquid Partition Coefficients, Kds, For Four Major Soil types: A Compendium, Health Physics, Vol. 59, No. 4, pp. 471-481, Oct, 1990.
9 Page 14 of 15


Ochs, M., Pointeau, I. and Giffaut, E. (2006).
TSD 14-004 Revision 1 U.S. Nuclear Regulatory Commission, (NRC, 2000). Development of Probabilistic RESRAD 6.0 and RESRADBUILD 3.0 Computer Codes, NUREG/CR-6697, U.S. Nuclear Regulatory Commission, December 2000.
Caesium sorption by hydrated cement as a function of degradation state: Experiments and modelling. Waste Management, 26, 725_732.
U.S. Department of Energy West Valley Demonstration Project, (DOE, 2009). Phase 1 Decommissioning Plan for the West Valley Demonstration, Appendix C Rev 2., Department of Energy.
Sheppard, M. and Thibault, D.H., 1990. Default Soil Solid/Liquid Partition Coefficients, K d s, For Four Major Soil types:  A Compendium, Health Physics, Vol. 59, No. 4, pp. 471
Yim, S.P, T.M. Sullivan, and L. Milian, Sorption (Kd) measurements in Support of Dose Assessments for Zion Nuclear Station Decommissioning, Brookhaven National Laboratory Report to ZionSolutions, December 12, 2012.
-481, Oct, 1990.
Yu, C., Loureiro, C., Cheng, J.-J., Jones, Y.Y., Wang, Y.P. Chia, and E. Faillace, (1993). Data Collection Handbook to Support Modeling the Impacts of Radioactive Material in Soil, ANL/EAIS-8, Argonne National Laboratory, Argonne, IL.
10  U.S. Nuclear Regulatory Commission, (NRC, 2000).
10 Page 15 of 15}}
Development of Probabilistic RESRAD 6.0 and RESRADBUILD 3.0 Computer Codes, NUREG/CR-6697, U.S. Nuclear Regulatory Commission, December 2000.
U.S. Department of Energy West Valley Demonstration Project, (DOE, 2009
). Phase 1 Decommissioning Plan for the West Valley Demonstration, Appendix C Rev 2.,
Department of Energy. Yim, S.P, T.M. Sullivan, and L. Milian, Sorption (Kd) measurements in Support of Dose Assessments for Zion Nuclear Station Decommissioning
, Brookhaven National Laboratory Report to ZionSolutions, December 12, 2012.
Yu, C., Loureiro, C., Cheng, J.
-J., Jones, Y.Y., Wang, Y.P. Chia, and E. Faillace, (1993).
Data Collection Ha ndbook to Support Modeling the Impacts of Radioactive Material in Soil, ANL/EAIS-8, Argonne National Laboratory, Argonne, IL.}}

Latest revision as of 03:28, 31 October 2019

TSD-14-004, Revision 1, Brookhaven National Laboratory: Recommended Values for the Distribution of Coefficient (Kd) to Be Used in Dose Assessments for Decommissioning the Zion Nuclear Power Plant
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TSD 14-004 Revision 1 Page 1 of 15

TSD 14-004 Revision 1 Summary of Changes in this Revision:

  • Rev. 1 -Changed Eu distribution coefficient values.

Page 2 of 15

TSD 14-004 Revision 1 BNL-105442-2014-IR-R1 RECOMMENDED VALUES FOR THE DISTRIBUTION COEFFICIENT (KD) TO BE USED IN DOSE ASSESSMENTS FOR DECOMMISSIONING THE ZION NUCLEAR POWER PLANT Terry Sullivan September 24, 2014 Revision 1 Informal Report Biological, Environmental & Climate Sciences Department Brookhaven National Laboratory P.O. Box 5000 Upton, NY 11973-5000 www.bnl.gov Notice: This manuscript has been authored by employees of Brookhaven Science Associates, LLC under Contract No. DE-AC02-98CH10886 with the U.S. Department of Energy. The publisher by accepting the manuscript for publication acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes.

Page 3 of 15

TSD 14-004 Revision 1 DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or any third partys use or the results of such use of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights.

Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof or its contractors or subcontractors. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

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TSD 14-004 Revision 1 Table of Contents

1. Introduction ................................................................................................................................ 1
2. Approach .................................................................................................................................... 2
3. Data ............................................................................................................................................. 2

Concrete Environment Kd values ............................................................................................... 4

4. Discussion .................................................................................................................................. 6
5. Recommended Values ................................................................................................................ 7

References ....................................................................................................................................... 9

List of Tables Table 1. Potential Radionuclides of Concern at the Zion Power Plant .......................................... 1

Table 2 Site-specific Kd values (ml/g) for the Zion Nuclear Power Station .................................. 3

Table 3 Literature soil Kd values for radionuclides of concern at Zion. ........................................ 4

Table 4 Preferred distribution coefficients (Kd ml/g) for cement concrete environments (Table 5.1 Krupka, 1998). .......................................................................................................................... 6

Table 5 Recommended Kd values to be used in the basement fill model. ..................................... 8

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TSD 14-004 Revision 1

1. Introduction ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated. The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled. The remaining u n d e r g r o u n d structures will contain low amounts of residual licensed radioactive material. An important component of the decommissioning process is the demonstration that any remaining activity will not cause a hypothetical individual to receive a dose in excess of 25 mrem/y as specified in 10CFR20 Subpart E.

The compliance assessment requires prediction of the release and transport of contaminants to the hypothetical individual. Characterization studies by ZionSolutions have identified the following nuclides as being of potential concern (Table 1).

Table 1. Potential Radionuclides of Concern at the Zion Power Plant Radionuclides Radionuclides Radionuclides Radionuclides Radionuclides Radionuclides

H-3 Co-60 Tc-99 Cs-137 Eu-155 Pu-241

C-14 Ni-63 Ag-108m Pm-147 Np-237 Am-241

Fe-55 Sr-90 Sb-125 Eu-152 Pu-238 Am-243

Ni-59 Nb-94 Cs-134 Eu-154 Pu-239/240 Cm-243/244

A key parameter in this assessment is the distribution coefficient (Kd) which is a measure of the amount of the radionuclide that will sorb to the solid media (soil or backfill) in the subsurface environment. The exposure pathway of concern is the groundwater. Groundwater concentration has an inverse relationship with Kd. Thus a lower value of Kd will provide higher groundwater concentrations and a more conservative prediction of dose. BNL (Yim, 2012, Milian, 2014) has conducted site-specific measurements on using local groundwater and samples of site soils and potential backfill materials to assess the Kd value for the contaminants with the expected highest residual concentration (Fe-55, Co-60, Ni-63, Sr-90, and Cs-137) for ZionSolutions. However, there are several other radioactive contaminants (Table 1) that may be present at lower levels that will still require assessment to demonstrate that dose limits are not exceeded. This document reviews the existing literature to recommend a value for Kd when site-specific numbers are not available.

Literature values for Kd show that sorption strongly depends on the contacting media and the geochemical conditions. The backfill selected for disposal will therefore play a huge role in determining the choice of the Kd value. A final decision has not been made on the backfill material at the Zion Power Plant. Materials under consideration include:

  • Crushed concrete demolition debris
  • Crushed cinder block
  • Local sand 1

Page 6 of 15

TSD 14-004 Revision 1 The concrete and cinder block would be obtained from the building materials removed to three feet below grade and would be free from residual radioactive contamination. Combinations of the above materials are also under consideration.

The first three materials are alkaline and will cause the pH to rise substantially above the local ambient conditions. Based on testing at BNL with materials supplied by ZionSolutions, the pH will initially increase to 10 or 11 for the cementitious materials and grout. Eventually, as the alkali is consumed by buffering reactions the pH will decrease. This is expected to take a minimum of several hundred years depending on the flow rate and buffering capacity of the surrounding soils. Several studies have found that pH is a key geochemical factor in controlling sorption. For this reason consideration must be given to the likely high pH conditions when selecting the Kd value to be used in modeling if a mixture of backfills is used.

2. Approach The objective of selecting a Kd value is to choose a value that is reasonably conservative with respect to projected groundwater dose (radionuclide concentrations). This requires a value that is likely to provide a lower bound for Kd. The value for Kd strongly depends on the solid media that contacts the groundwater thus site-specific values are the most representative of actual conditions.

For radionuclides with site-specific data the media with the lowest measured Kd was selected to provide this lower bound. For radionuclides without site-specific data the literature was reviewed to determine the range of Kd values typically found in soils and found in cementitious (high pH) environments. These Kds will be used for initial DUST-MS runs to determine groundwater concentrations at potential well locations. Depending upon the outcome they may be further refined with more site specific or literature data.

Baes and Sharp (Baes and Sharp 1983) were among the first to show that the Kd value for Cs and Sr is log-normally distributed in soils. They applied a log-normal distribution to all elements and this approach is widely used (Sheppard and Thibault, 1990; NRC, 1990). Sheppard and Thibault extended the concept of log-normal distribution to apply to a soil type (sand, loam, clay or organic). This concept is used in this report to determine the 25th percentile value for Kd in soils. The use of the 25th percentile value has been performed in other decommissioning studies at Fermi (Dionne, 2009) and Humboldt Bay (Besson, 2013).

3. Data Three types of data are used for the selection of an appropriate Kd for the backfill region at the Zion Nuclear Power Plant. These include site-specific values using local groundwater and soil or concrete samples from the site; literature values for soil environments; and literature values for concrete environments.

Site-specific Kd data:

Kd measurements were performed for ZionSolutions using site-specific groundwater and soil samples (clay, silt, native sand, and disturbed sand - native sand that was excavated during 2

Page 7 of 15

TSD 14-004 Revision 1 construction of the plant and backfilled around the plant) for six nuclides. Additionally potential backfill materials including two concrete samples (one from the Containment Building and one from the Crib House), two Cinder Block samples from the site, and one low density grout were tested using site-specific groundwater. The elements measured included Fe, Co, Ni, Sr and Cs.

Table 2 presents the results of these measurements. Note isotopes of Cs and Ni found in Table 1 are also presented in Table 2 as isotopes will have the same chemical sorption properties.

Table 2 Site-specific Kd values (ml/g) for the Zion Nuclear Power Station Site Site Site

Site Site Site Specific Specific Specific

Site Specific Specific Specific Site Specific Crib Cinder Low

Specific Silt Disturbed Native Containment House Block Density

Silt Kd1 Clay1 Kd Sand Kd1 Sand Kd1 Concrete1 Kd Concrete1 Kd2 Grout Kd2

Radionuclide ml/g ml/g ml/g ml/g ml/g Kd ml/g ml/g ml/g

Fe-55 8061 17288 2857 5579 16546 17288

Ni-59 75 136 331 62 3438 8361 177 4,569

Co-60 1161 1161 1161 1161 1161 1161 223 1941

Ni-63 75 136 331 62 3438 8361 177 4,569

Sr-90 2.3 5.7 3.4 2.3 10.4 18.5 23.5 11.8

Cs-134 527 3011 635 615 85 45 249 303

Cs-137 527 3011 635 615 85 45 249 303

1 Yim, 2012 2

Milian, 2014 Literature values for Kd in soil environments Numerous measurements of Kd have been reported in the literature. Key compilations of this data include those by Baes and Sharp (Baes, 1983); Sheppard and Thibault (Sheppard, 1990), Yu (Yu, 1993), the U.S. Nuclear Regulatory Commission (NRC, 2000); and the International Atomic Energy Agency (IAEA, 2010). All of these documents provide statistical parameters to estimate the distribution. Literature values for Kd in soil media from selected sources are presented in Table 3. The first two columns are mean values for Kd presented in (Yu, 1993 and IAEA 2012). For conservatism the 25th percentile in the distribution from the reports (Sheppard, 1990 and NRC, 2000) are also reported in the Table 3. For the Sheppard data the log-normal distribution of the data for sand was used except for Nb-94 and Sb-125 which are the geometrics means because standard deviations were not provided in the Sheppard data. Other soil types were not included because sand, in most cases, has the lowest Kd and the surrounding soil at Zion is primarily sand.

3 Page 8 of 15

TSD 14-004 Revision 1 Table 3 Literature soil Kd values for radionuclides of concern at Zion.

(Yu, 1993) Sand (IAEA 2010) (Sheppard, 1990)

Kd Tables 12, 14 Sand or All (NRC, 2000) Sand 25th

Radionuclide ml/g Soils ml/g 25th Percentile ml/g Percentile ml/g

H-3 1 0.0431 0.051

C-14 5 1.24 1.76

Fe-55 220 320 34.3 39

Ni-59 400 140 160 148

Co-60 60 640 42.9 9.2

Ni-63 400 140 160 148

Sr-90 15 22 7.49 4.6

Nb-94 160 170 44.6 164

Tc-99 0.1 0.23 0.0618 0.04

Ag-108m 90 52.6 27

Sb-125 45 17 43.4 45

Cs-134 280 530 92.5 51

Cs-137 280 530 93.4 51

Pm-147 450 94.8

Eu-152 96.2

Eu-154 95.2

Eu-155 95.8

Np-237 5 35 3.75 1.30

Pu-238 550 400 268 174

Pu-239/240 550 400 267.5 174

Pu-241 550 400 268 174

Am-241 1900 1000 177 333

Am-243 1900 1000 178 333

Cm-243/244 4000 9300 1990 891

The predictions at the 25th percent level of the distribution for the NRC and Sheppard reports are similar. This is because the NRC data set for the distribution is based on, but not limited to the Sheppard data set.

Concrete Environment Kd values The chemistry of the water will change from an initial value of greater than 11 down to the ambient pH in a crushed concrete environment. The convention of Bradbury and Sarott (1995) describing the three types of chemical environments that all cements progress through is used to understand the data. The following description of the environments has been abbreviated from the initial work by Krupka (Krupka, 1998) 4 Page 9 of 15

TSD 14-004 Revision 1

  • Environment I This environment occurs immediately after the cement hardens and is wetted by infiltrating water The cement pore water is characterized as having a high pH of >12.5, high ionic strength, and high concentrations of potassium and sodium resulting from the dissolution of alkali impurities in the clinker phases. Hydration is still continuing during Environment I with the formation of C-S-H (Calcium- Silicate -

Hydrate) and portlandite [Ca(OH)2] The composition of the cement pore fluid is at equilibrium with portlandite during this time. Based on the modeling estimates this environment may last for the first 100 to 10,000 years.

Environment II During this period, the soluble salts of the alkali metals are all dissolved The pH of the cement pore water is controlled at a value of about 12.5 by the solubility of portlandite. The C-S-H and portlandite are the major solid phases present Environment II may last for a long time Its duration depends on how much water percolates through the system to dissolve all the slightly soluble portlandite This environment may last from 100-10,000 years to 1,000-100,000 years.

Environment III The concentration of portlandite has been reduced to such an extent by this period that the solubility of C-S-H now controls the pH of the cement pore fluid The C-S-H starts to dissolve incongruently with a continual decrease in pH At the end of this evolution, Environment III can be conceptualized as leaving only silica (SiO2) as the solubility control for the pore fluid pH. For the sake of simplicity, the final end point of Environment III can be considered somewhat analogous to the geochemical conditions of the "normal" ambient soil environment.

The important point of this discussion is that the cement will control the pH for hundreds to thousands of years. Thus, if cementitious materials are used for backfill material, a high pH environment will prevail and Kd values are likely to be similar to those found in cement based materials.

5 Page 10 of 15

TSD 14-004 Revision 1 Table 4 Preferred distribution coefficients (Kd ml/g) for cement concrete environments (Table 5.1 Krupka, 1998).

Environment I Environment II Environment III Oxidizing Reducing Oxidizing Reducing Oxidizing Reducing Conditions Conditions Conditions Conditions Conditions Conditions Radionuclide Kd (ml/g)

Am 5000 5000 5000 5000 500 500 C 500 500 100 100 10 10 Cl 5 5 1 1 0 0 I 10 10 5 5 1 1 Lanthanides 5000 5000 5000 5000 500 500 Ni 100 100 100 100 10 10 Nb 1000 1000 1000 1000 100 100 Np 2000 5000 2000 5000 200 500 Pu 5000 5000 5000 5000 500 500 Ra 100 100 100 100 100 100 Sr 1 1 3 3 3 5 Tc 0 1000 0 1000 0 100 Th 5000 5000 5000 5000 500 500 U 1000 1000 1000 1000 100 100 The above table does not include Cs or Eu, two nuclides of potential concern at Zion. Cs is known to have low sorption on cements. This is due in part to competition for sorption sites with other ions (Na and K) that are released by the leaching from the concrete. Bradbury and Sarott (Bradbury 1995) provided Kd estimates for Cs as 2 to 20 ml/g with the low value in Environment I. This is lower than the site-specific value for Cs at Zion. They also provided estimates for Eu (5000 to 1000 ml/g) with Environment III with the lowest Kd and Cm (5000 to 1000 ml/g) with Environment III providing the least sorption (Bradbury, 1995). A recent study (Felipe-Sotello, 2012) measured Kd values for Eu at 66000 ml/g. Other values for distribution coefficients in cementitious materials are provided in (Kaplan, 2008).

4. Discussion Site-specific values are the most representative of the conditions that will occur at Zion after decommissioning and they will be recommended for use in groundwater dose assessment.

Although a final determination of the backfill material has not been made, it is likely that the backfill will contain a substantial amount of cementitious material. Examining the representative Kd values for soils (Table 3) and cementitious systems (Table 4) it is clear that with the exception of Cs the cement Kd values are greater than for soil systems. The Kd value selected is meant to provide a conservative assessment of dose to the groundwater pathway. For this reason, with the exception of H and Tc literature soil Kd values will be recommended for the assessment when site-specific values are not available. To increase the degree of confidence 6

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TSD 14-004 Revision 1 that a conservative value has been selected the 25th percentile Kd from either the NRC or Sheppard reports will be used. For Tc the sand Kd in Table 3 is less than 0.1. The cementitious oxidizing conditions Kd is zero in Table 4. The soil Kd is rounded to zero to ensure conservatism.

The same will be done for the Table 3 H Kd as a conservative assumption.

For one nuclide, Sb-125, the IAEA median value was lower than the 25th percentile value on the NRC distribution. No standard deviation was reported in the Sheppard data. For this reason, the IAEA value is recommended as the appropriate value for screening calculations for Sb-125.

The Eu isotopes all have slightly different Kd values in Table 3. These values are from NRC, 2000 and are calculated values for the 25th percentile based on a mean value and standard deviation. One would expect isotopes to have the same sorption characteristics. It is likely that this is round-off error in determining the 25th percentile. For this reason the minimum value for all three isotopes will be selected as the reference value.

The recommended values for the basement fill model are either site-specific or values measured in soil. The Kd values in a cement environment for elements other tan Cs, Tc and H are expected to be higher based on existing data. Thus, they should be appropriate for outside of the buildings in the surrounding soil with the exception of H, Tc and Cs. Depending on the buffering capacity of the soil, time, and distance from the building, the chemical environment of the groundwater exiting the building may control the sorption of Cs. For this reason, the site-specific Kd for Cs in the cement environment should be used in the surrounding soils to provide a conservative estimate of groundwater concentration for dose assessment.

5. Recommended Values The values in Table 5 are the minimum values found in any test for the site-specific case and the minimum values found from the reports cited in Table 3. These values are appropriate for maximizing the groundwater concentration and thereby predicted dose. For intruder scenarios or scenarios where the backfill is used as gardening soils, a higher value of Kd would be recommended for maximizing the predicted dose in those cases.

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TSD 14-004 Revision 1 Table 5 Recommended Kd values to be used in the basement fill model.

Recommended

Half Life Basement Fill

Radionuclide (years) Kd ml/g Reference1

2 H-3 1.24E+01 0 C-14 5.73E+03 1.2 NRC, 2000 Fe-55 2.70E+00 2857 Site-Specific Ni-59 7.50E+04 62 Site Specific Co-60 5.27E+00 223 Site Specific Ni-63 9.60E+01 62 Site Specific Sr-90 2.91E+01 2.3 Site Specific Nb-94 2.03E+04 45 NRC, 2000 2

Tc-99 2.13E+05 0 Ag-108m 1.27E+02 27 Sheppard, 1990 Sb-125 2.77E+00 17 IAEA, 2010 Cs-134 2.06E+00 45 Site Specific Cs-137 3.00E+01 45 Site Specific Pm-147 2.62E+00 95 NRC, 2000 3

Eu-152 1.33E+01 95 NRC, 2000 Eu-154 8.80E+00 95 NRC, 2000 Eu-155 4.96E+00 95 NRC, 2000 Np-237 2.14E+06 1 Sheppard, 1990 Pu-238 8.77E+01 174 Sheppard, 1990 Pu-239/240 2.41E+04 174 Sheppard, 1990 Pu-241 1.44E+01 174 Sheppard, 1990 Am-241 4.32E+02 177 NRC, 2000 Am-243 7.38E+03 177 NRC, 2000 Cm-243/244 2.85E+01 891 Sheppard, 1990 1

Values from NRC, 2000 or Sheppard, 1990 are the 25th percentile values on the cumulative distribution function.

2 25th percentile value was less than 0.1 and was rounded down to 0.

3 25th percentile value was less listed as 96 in Table 3. It was changed to 95 to make it consistent with other Eu isotopes.

8 Page 13 of 15

TSD 14-004 Revision 1 References Baes, C.F., and R.D. Sharp, (1983). A proposal for Estimation of Sol Leaching and Leaching Constants for Use in Assessment Models, J. Environ. Qual., Vol. 12, No. 1, 1983. Pp 17-28.

Besson, J.W. (2013). Humboldt Bay Power Plant License Termination Plan Revision 0 Chapter 6 Compliance with the Radiological Criteria May 2013, ENG-HB-003, Rev 0. Bartlett, Plymouth, MA.

Dionne, B.J., (2009). Calculation of Enrico Fermi 1 Derived Concentration Guideline Levels for Soil, ENG 004, Rev 1., Bartlett, Plymouth, MA Environmental Protection Agency, (2004). Understanding Variation in Partition Coefficient, Kd Values, United States Office of Air and Radiation EPA 402-R-04-002C, Vol 1 - 3.

Felipe-Sotelo, M., Hinchliff, J., Evans, N., Warwick, P. and Read, D. (2012). Sorption of radionuclides to a cementitious backfill material under near-field conditions, Mineralogical Magazine, December 2012, Vol. 76(8), pp. 3401-3410.

International Atomic Energy Agency (IAEA, 2010). handbook of Parameter Values for the Prediction of Radionuclide Transfer in Terrestrial and Freshwater Environments, Technical Report Series No. 472., International Atomic Energy Agency, Vienna, Austria.

Kaplan, D.J. Roberts, K., Coates, J., Sigegried, M., and Serkiz, S., 2008.Saltstone and concrete interactions with radionuclides sorption (Kd), desorption, and reduction capacity measurements, SRNS-STI-2008-00045, Savannah River National laboratory, Savannah River, SC.

Kay, J.A. (2004). Yankee Nuclear Plant Station License Termination Plan, Yankee Atomic Electric Company, MA.

Krupka, K. M. and R. J. Serne. (1998). Effects on Radionuclide Concentrations by Cement/Ground-Water Interactions in Support of Performance Assessment of Low-Level Radioactive Waste Disposal Facilities. NUREG/CR-6377 (PNNL-11408), Pacific Northwest, National Laboratory, Richland, Washington.

Milian, L., T. Sullivan (2014). Sorption (Kd) measurements on Cinder Block and Grout in Support of Dose Assessments for Zion Nuclear Station Decommissioning, Brookhaven National Laboratory Report to ZionSolutions, April 2014 (Draft).

Ochs, M., Pointeau, I. and Giffaut, E. (2006). Caesium sorption by hydrated cement as a function of degradation state: Experiments and modelling. Waste Management, 26, 725_732.

Sheppard, M. and Thibault, D.H., 1990. Default Soil Solid/Liquid Partition Coefficients, Kds, For Four Major Soil types: A Compendium, Health Physics, Vol. 59, No. 4, pp. 471-481, Oct, 1990.

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TSD 14-004 Revision 1 U.S. Nuclear Regulatory Commission, (NRC, 2000). Development of Probabilistic RESRAD 6.0 and RESRADBUILD 3.0 Computer Codes, NUREG/CR-6697, U.S. Nuclear Regulatory Commission, December 2000.

U.S. Department of Energy West Valley Demonstration Project, (DOE, 2009). Phase 1 Decommissioning Plan for the West Valley Demonstration, Appendix C Rev 2., Department of Energy.

Yim, S.P, T.M. Sullivan, and L. Milian, Sorption (Kd) measurements in Support of Dose Assessments for Zion Nuclear Station Decommissioning, Brookhaven National Laboratory Report to ZionSolutions, December 12, 2012.

Yu, C., Loureiro, C., Cheng, J.-J., Jones, Y.Y., Wang, Y.P. Chia, and E. Faillace, (1993). Data Collection Handbook to Support Modeling the Impacts of Radioactive Material in Soil, ANL/EAIS-8, Argonne National Laboratory, Argonne, IL.

10 Page 15 of 15

TSD 14-004 Revision 1 Page 1 of 15

TSD 14-004 Revision 1 Summary of Changes in this Revision:

  • Rev. 1 -Changed Eu distribution coefficient values.

Page 2 of 15

TSD 14-004 Revision 1 BNL-105442-2014-IR-R1 RECOMMENDED VALUES FOR THE DISTRIBUTION COEFFICIENT (KD) TO BE USED IN DOSE ASSESSMENTS FOR DECOMMISSIONING THE ZION NUCLEAR POWER PLANT Terry Sullivan September 24, 2014 Revision 1 Informal Report Biological, Environmental & Climate Sciences Department Brookhaven National Laboratory P.O. Box 5000 Upton, NY 11973-5000 www.bnl.gov Notice: This manuscript has been authored by employees of Brookhaven Science Associates, LLC under Contract No. DE-AC02-98CH10886 with the U.S. Department of Energy. The publisher by accepting the manuscript for publication acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes.

Page 3 of 15

TSD 14-004 Revision 1 DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or any third partys use or the results of such use of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights.

Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof or its contractors or subcontractors. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

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TSD 14-004 Revision 1 Table of Contents

1. Introduction ................................................................................................................................ 1
2. Approach .................................................................................................................................... 2
3. Data ............................................................................................................................................. 2

Concrete Environment Kd values ............................................................................................... 4

4. Discussion .................................................................................................................................. 6
5. Recommended Values ................................................................................................................ 7

References ....................................................................................................................................... 9

List of Tables Table 1. Potential Radionuclides of Concern at the Zion Power Plant .......................................... 1

Table 2 Site-specific Kd values (ml/g) for the Zion Nuclear Power Station .................................. 3

Table 3 Literature soil Kd values for radionuclides of concern at Zion. ........................................ 4

Table 4 Preferred distribution coefficients (Kd ml/g) for cement concrete environments (Table 5.1 Krupka, 1998). .......................................................................................................................... 6

Table 5 Recommended Kd values to be used in the basement fill model. ..................................... 8

Page 5 of 15

TSD 14-004 Revision 1

1. Introduction ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated. The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled. The remaining u n d e r g r o u n d structures will contain low amounts of residual licensed radioactive material. An important component of the decommissioning process is the demonstration that any remaining activity will not cause a hypothetical individual to receive a dose in excess of 25 mrem/y as specified in 10CFR20 Subpart E.

The compliance assessment requires prediction of the release and transport of contaminants to the hypothetical individual. Characterization studies by ZionSolutions have identified the following nuclides as being of potential concern (Table 1).

Table 1. Potential Radionuclides of Concern at the Zion Power Plant Radionuclides Radionuclides Radionuclides Radionuclides Radionuclides Radionuclides

H-3 Co-60 Tc-99 Cs-137 Eu-155 Pu-241

C-14 Ni-63 Ag-108m Pm-147 Np-237 Am-241

Fe-55 Sr-90 Sb-125 Eu-152 Pu-238 Am-243

Ni-59 Nb-94 Cs-134 Eu-154 Pu-239/240 Cm-243/244

A key parameter in this assessment is the distribution coefficient (Kd) which is a measure of the amount of the radionuclide that will sorb to the solid media (soil or backfill) in the subsurface environment. The exposure pathway of concern is the groundwater. Groundwater concentration has an inverse relationship with Kd. Thus a lower value of Kd will provide higher groundwater concentrations and a more conservative prediction of dose. BNL (Yim, 2012, Milian, 2014) has conducted site-specific measurements on using local groundwater and samples of site soils and potential backfill materials to assess the Kd value for the contaminants with the expected highest residual concentration (Fe-55, Co-60, Ni-63, Sr-90, and Cs-137) for ZionSolutions. However, there are several other radioactive contaminants (Table 1) that may be present at lower levels that will still require assessment to demonstrate that dose limits are not exceeded. This document reviews the existing literature to recommend a value for Kd when site-specific numbers are not available.

Literature values for Kd show that sorption strongly depends on the contacting media and the geochemical conditions. The backfill selected for disposal will therefore play a huge role in determining the choice of the Kd value. A final decision has not been made on the backfill material at the Zion Power Plant. Materials under consideration include:

  • Crushed concrete demolition debris
  • Crushed cinder block
  • Local sand 1

Page 6 of 15

TSD 14-004 Revision 1 The concrete and cinder block would be obtained from the building materials removed to three feet below grade and would be free from residual radioactive contamination. Combinations of the above materials are also under consideration.

The first three materials are alkaline and will cause the pH to rise substantially above the local ambient conditions. Based on testing at BNL with materials supplied by ZionSolutions, the pH will initially increase to 10 or 11 for the cementitious materials and grout. Eventually, as the alkali is consumed by buffering reactions the pH will decrease. This is expected to take a minimum of several hundred years depending on the flow rate and buffering capacity of the surrounding soils. Several studies have found that pH is a key geochemical factor in controlling sorption. For this reason consideration must be given to the likely high pH conditions when selecting the Kd value to be used in modeling if a mixture of backfills is used.

2. Approach The objective of selecting a Kd value is to choose a value that is reasonably conservative with respect to projected groundwater dose (radionuclide concentrations). This requires a value that is likely to provide a lower bound for Kd. The value for Kd strongly depends on the solid media that contacts the groundwater thus site-specific values are the most representative of actual conditions.

For radionuclides with site-specific data the media with the lowest measured Kd was selected to provide this lower bound. For radionuclides without site-specific data the literature was reviewed to determine the range of Kd values typically found in soils and found in cementitious (high pH) environments. These Kds will be used for initial DUST-MS runs to determine groundwater concentrations at potential well locations. Depending upon the outcome they may be further refined with more site specific or literature data.

Baes and Sharp (Baes and Sharp 1983) were among the first to show that the Kd value for Cs and Sr is log-normally distributed in soils. They applied a log-normal distribution to all elements and this approach is widely used (Sheppard and Thibault, 1990; NRC, 1990). Sheppard and Thibault extended the concept of log-normal distribution to apply to a soil type (sand, loam, clay or organic). This concept is used in this report to determine the 25th percentile value for Kd in soils. The use of the 25th percentile value has been performed in other decommissioning studies at Fermi (Dionne, 2009) and Humboldt Bay (Besson, 2013).

3. Data Three types of data are used for the selection of an appropriate Kd for the backfill region at the Zion Nuclear Power Plant. These include site-specific values using local groundwater and soil or concrete samples from the site; literature values for soil environments; and literature values for concrete environments.

Site-specific Kd data:

Kd measurements were performed for ZionSolutions using site-specific groundwater and soil samples (clay, silt, native sand, and disturbed sand - native sand that was excavated during 2

Page 7 of 15

TSD 14-004 Revision 1 construction of the plant and backfilled around the plant) for six nuclides. Additionally potential backfill materials including two concrete samples (one from the Containment Building and one from the Crib House), two Cinder Block samples from the site, and one low density grout were tested using site-specific groundwater. The elements measured included Fe, Co, Ni, Sr and Cs.

Table 2 presents the results of these measurements. Note isotopes of Cs and Ni found in Table 1 are also presented in Table 2 as isotopes will have the same chemical sorption properties.

Table 2 Site-specific Kd values (ml/g) for the Zion Nuclear Power Station Site Site Site

Site Site Site Specific Specific Specific

Site Specific Specific Specific Site Specific Crib Cinder Low

Specific Silt Disturbed Native Containment House Block Density

Silt Kd1 Clay1 Kd Sand Kd1 Sand Kd1 Concrete1 Kd Concrete1 Kd2 Grout Kd2

Radionuclide ml/g ml/g ml/g ml/g ml/g Kd ml/g ml/g ml/g

Fe-55 8061 17288 2857 5579 16546 17288

Ni-59 75 136 331 62 3438 8361 177 4,569

Co-60 1161 1161 1161 1161 1161 1161 223 1941

Ni-63 75 136 331 62 3438 8361 177 4,569

Sr-90 2.3 5.7 3.4 2.3 10.4 18.5 23.5 11.8

Cs-134 527 3011 635 615 85 45 249 303

Cs-137 527 3011 635 615 85 45 249 303

1 Yim, 2012 2

Milian, 2014 Literature values for Kd in soil environments Numerous measurements of Kd have been reported in the literature. Key compilations of this data include those by Baes and Sharp (Baes, 1983); Sheppard and Thibault (Sheppard, 1990), Yu (Yu, 1993), the U.S. Nuclear Regulatory Commission (NRC, 2000); and the International Atomic Energy Agency (IAEA, 2010). All of these documents provide statistical parameters to estimate the distribution. Literature values for Kd in soil media from selected sources are presented in Table 3. The first two columns are mean values for Kd presented in (Yu, 1993 and IAEA 2012). For conservatism the 25th percentile in the distribution from the reports (Sheppard, 1990 and NRC, 2000) are also reported in the Table 3. For the Sheppard data the log-normal distribution of the data for sand was used except for Nb-94 and Sb-125 which are the geometrics means because standard deviations were not provided in the Sheppard data. Other soil types were not included because sand, in most cases, has the lowest Kd and the surrounding soil at Zion is primarily sand.

3 Page 8 of 15

TSD 14-004 Revision 1 Table 3 Literature soil Kd values for radionuclides of concern at Zion.

(Yu, 1993) Sand (IAEA 2010) (Sheppard, 1990)

Kd Tables 12, 14 Sand or All (NRC, 2000) Sand 25th

Radionuclide ml/g Soils ml/g 25th Percentile ml/g Percentile ml/g

H-3 1 0.0431 0.051

C-14 5 1.24 1.76

Fe-55 220 320 34.3 39

Ni-59 400 140 160 148

Co-60 60 640 42.9 9.2

Ni-63 400 140 160 148

Sr-90 15 22 7.49 4.6

Nb-94 160 170 44.6 164

Tc-99 0.1 0.23 0.0618 0.04

Ag-108m 90 52.6 27

Sb-125 45 17 43.4 45

Cs-134 280 530 92.5 51

Cs-137 280 530 93.4 51

Pm-147 450 94.8

Eu-152 96.2

Eu-154 95.2

Eu-155 95.8

Np-237 5 35 3.75 1.30

Pu-238 550 400 268 174

Pu-239/240 550 400 267.5 174

Pu-241 550 400 268 174

Am-241 1900 1000 177 333

Am-243 1900 1000 178 333

Cm-243/244 4000 9300 1990 891

The predictions at the 25th percent level of the distribution for the NRC and Sheppard reports are similar. This is because the NRC data set for the distribution is based on, but not limited to the Sheppard data set.

Concrete Environment Kd values The chemistry of the water will change from an initial value of greater than 11 down to the ambient pH in a crushed concrete environment. The convention of Bradbury and Sarott (1995) describing the three types of chemical environments that all cements progress through is used to understand the data. The following description of the environments has been abbreviated from the initial work by Krupka (Krupka, 1998) 4 Page 9 of 15

TSD 14-004 Revision 1

  • Environment I This environment occurs immediately after the cement hardens and is wetted by infiltrating water The cement pore water is characterized as having a high pH of >12.5, high ionic strength, and high concentrations of potassium and sodium resulting from the dissolution of alkali impurities in the clinker phases. Hydration is still continuing during Environment I with the formation of C-S-H (Calcium- Silicate -

Hydrate) and portlandite [Ca(OH)2] The composition of the cement pore fluid is at equilibrium with portlandite during this time. Based on the modeling estimates this environment may last for the first 100 to 10,000 years.

Environment II During this period, the soluble salts of the alkali metals are all dissolved The pH of the cement pore water is controlled at a value of about 12.5 by the solubility of portlandite. The C-S-H and portlandite are the major solid phases present Environment II may last for a long time Its duration depends on how much water percolates through the system to dissolve all the slightly soluble portlandite This environment may last from 100-10,000 years to 1,000-100,000 years.

Environment III The concentration of portlandite has been reduced to such an extent by this period that the solubility of C-S-H now controls the pH of the cement pore fluid The C-S-H starts to dissolve incongruently with a continual decrease in pH At the end of this evolution, Environment III can be conceptualized as leaving only silica (SiO2) as the solubility control for the pore fluid pH. For the sake of simplicity, the final end point of Environment III can be considered somewhat analogous to the geochemical conditions of the "normal" ambient soil environment.

The important point of this discussion is that the cement will control the pH for hundreds to thousands of years. Thus, if cementitious materials are used for backfill material, a high pH environment will prevail and Kd values are likely to be similar to those found in cement based materials.

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TSD 14-004 Revision 1 Table 4 Preferred distribution coefficients (Kd ml/g) for cement concrete environments (Table 5.1 Krupka, 1998).

Environment I Environment II Environment III Oxidizing Reducing Oxidizing Reducing Oxidizing Reducing Conditions Conditions Conditions Conditions Conditions Conditions Radionuclide Kd (ml/g)

Am 5000 5000 5000 5000 500 500 C 500 500 100 100 10 10 Cl 5 5 1 1 0 0 I 10 10 5 5 1 1 Lanthanides 5000 5000 5000 5000 500 500 Ni 100 100 100 100 10 10 Nb 1000 1000 1000 1000 100 100 Np 2000 5000 2000 5000 200 500 Pu 5000 5000 5000 5000 500 500 Ra 100 100 100 100 100 100 Sr 1 1 3 3 3 5 Tc 0 1000 0 1000 0 100 Th 5000 5000 5000 5000 500 500 U 1000 1000 1000 1000 100 100 The above table does not include Cs or Eu, two nuclides of potential concern at Zion. Cs is known to have low sorption on cements. This is due in part to competition for sorption sites with other ions (Na and K) that are released by the leaching from the concrete. Bradbury and Sarott (Bradbury 1995) provided Kd estimates for Cs as 2 to 20 ml/g with the low value in Environment I. This is lower than the site-specific value for Cs at Zion. They also provided estimates for Eu (5000 to 1000 ml/g) with Environment III with the lowest Kd and Cm (5000 to 1000 ml/g) with Environment III providing the least sorption (Bradbury, 1995). A recent study (Felipe-Sotello, 2012) measured Kd values for Eu at 66000 ml/g. Other values for distribution coefficients in cementitious materials are provided in (Kaplan, 2008).

4. Discussion Site-specific values are the most representative of the conditions that will occur at Zion after decommissioning and they will be recommended for use in groundwater dose assessment.

Although a final determination of the backfill material has not been made, it is likely that the backfill will contain a substantial amount of cementitious material. Examining the representative Kd values for soils (Table 3) and cementitious systems (Table 4) it is clear that with the exception of Cs the cement Kd values are greater than for soil systems. The Kd value selected is meant to provide a conservative assessment of dose to the groundwater pathway. For this reason, with the exception of H and Tc literature soil Kd values will be recommended for the assessment when site-specific values are not available. To increase the degree of confidence 6

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TSD 14-004 Revision 1 that a conservative value has been selected the 25th percentile Kd from either the NRC or Sheppard reports will be used. For Tc the sand Kd in Table 3 is less than 0.1. The cementitious oxidizing conditions Kd is zero in Table 4. The soil Kd is rounded to zero to ensure conservatism.

The same will be done for the Table 3 H Kd as a conservative assumption.

For one nuclide, Sb-125, the IAEA median value was lower than the 25th percentile value on the NRC distribution. No standard deviation was reported in the Sheppard data. For this reason, the IAEA value is recommended as the appropriate value for screening calculations for Sb-125.

The Eu isotopes all have slightly different Kd values in Table 3. These values are from NRC, 2000 and are calculated values for the 25th percentile based on a mean value and standard deviation. One would expect isotopes to have the same sorption characteristics. It is likely that this is round-off error in determining the 25th percentile. For this reason the minimum value for all three isotopes will be selected as the reference value.

The recommended values for the basement fill model are either site-specific or values measured in soil. The Kd values in a cement environment for elements other tan Cs, Tc and H are expected to be higher based on existing data. Thus, they should be appropriate for outside of the buildings in the surrounding soil with the exception of H, Tc and Cs. Depending on the buffering capacity of the soil, time, and distance from the building, the chemical environment of the groundwater exiting the building may control the sorption of Cs. For this reason, the site-specific Kd for Cs in the cement environment should be used in the surrounding soils to provide a conservative estimate of groundwater concentration for dose assessment.

5. Recommended Values The values in Table 5 are the minimum values found in any test for the site-specific case and the minimum values found from the reports cited in Table 3. These values are appropriate for maximizing the groundwater concentration and thereby predicted dose. For intruder scenarios or scenarios where the backfill is used as gardening soils, a higher value of Kd would be recommended for maximizing the predicted dose in those cases.

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TSD 14-004 Revision 1 Table 5 Recommended Kd values to be used in the basement fill model.

Recommended

Half Life Basement Fill

Radionuclide (years) Kd ml/g Reference1

2 H-3 1.24E+01 0 C-14 5.73E+03 1.2 NRC, 2000 Fe-55 2.70E+00 2857 Site-Specific Ni-59 7.50E+04 62 Site Specific Co-60 5.27E+00 223 Site Specific Ni-63 9.60E+01 62 Site Specific Sr-90 2.91E+01 2.3 Site Specific Nb-94 2.03E+04 45 NRC, 2000 2

Tc-99 2.13E+05 0 Ag-108m 1.27E+02 27 Sheppard, 1990 Sb-125 2.77E+00 17 IAEA, 2010 Cs-134 2.06E+00 45 Site Specific Cs-137 3.00E+01 45 Site Specific Pm-147 2.62E+00 95 NRC, 2000 3

Eu-152 1.33E+01 95 NRC, 2000 Eu-154 8.80E+00 95 NRC, 2000 Eu-155 4.96E+00 95 NRC, 2000 Np-237 2.14E+06 1 Sheppard, 1990 Pu-238 8.77E+01 174 Sheppard, 1990 Pu-239/240 2.41E+04 174 Sheppard, 1990 Pu-241 1.44E+01 174 Sheppard, 1990 Am-241 4.32E+02 177 NRC, 2000 Am-243 7.38E+03 177 NRC, 2000 Cm-243/244 2.85E+01 891 Sheppard, 1990 1

Values from NRC, 2000 or Sheppard, 1990 are the 25th percentile values on the cumulative distribution function.

2 25th percentile value was less than 0.1 and was rounded down to 0.

3 25th percentile value was less listed as 96 in Table 3. It was changed to 95 to make it consistent with other Eu isotopes.

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TSD 14-004 Revision 1 References Baes, C.F., and R.D. Sharp, (1983). A proposal for Estimation of Sol Leaching and Leaching Constants for Use in Assessment Models, J. Environ. Qual., Vol. 12, No. 1, 1983. Pp 17-28.

Besson, J.W. (2013). Humboldt Bay Power Plant License Termination Plan Revision 0 Chapter 6 Compliance with the Radiological Criteria May 2013, ENG-HB-003, Rev 0. Bartlett, Plymouth, MA.

Dionne, B.J., (2009). Calculation of Enrico Fermi 1 Derived Concentration Guideline Levels for Soil, ENG 004, Rev 1., Bartlett, Plymouth, MA Environmental Protection Agency, (2004). Understanding Variation in Partition Coefficient, Kd Values, United States Office of Air and Radiation EPA 402-R-04-002C, Vol 1 - 3.

Felipe-Sotelo, M., Hinchliff, J., Evans, N., Warwick, P. and Read, D. (2012). Sorption of radionuclides to a cementitious backfill material under near-field conditions, Mineralogical Magazine, December 2012, Vol. 76(8), pp. 3401-3410.

International Atomic Energy Agency (IAEA, 2010). handbook of Parameter Values for the Prediction of Radionuclide Transfer in Terrestrial and Freshwater Environments, Technical Report Series No. 472., International Atomic Energy Agency, Vienna, Austria.

Kaplan, D.J. Roberts, K., Coates, J., Sigegried, M., and Serkiz, S., 2008.Saltstone and concrete interactions with radionuclides sorption (Kd), desorption, and reduction capacity measurements, SRNS-STI-2008-00045, Savannah River National laboratory, Savannah River, SC.

Kay, J.A. (2004). Yankee Nuclear Plant Station License Termination Plan, Yankee Atomic Electric Company, MA.

Krupka, K. M. and R. J. Serne. (1998). Effects on Radionuclide Concentrations by Cement/Ground-Water Interactions in Support of Performance Assessment of Low-Level Radioactive Waste Disposal Facilities. NUREG/CR-6377 (PNNL-11408), Pacific Northwest, National Laboratory, Richland, Washington.

Milian, L., T. Sullivan (2014). Sorption (Kd) measurements on Cinder Block and Grout in Support of Dose Assessments for Zion Nuclear Station Decommissioning, Brookhaven National Laboratory Report to ZionSolutions, April 2014 (Draft).

Ochs, M., Pointeau, I. and Giffaut, E. (2006). Caesium sorption by hydrated cement as a function of degradation state: Experiments and modelling. Waste Management, 26, 725_732.

Sheppard, M. and Thibault, D.H., 1990. Default Soil Solid/Liquid Partition Coefficients, Kds, For Four Major Soil types: A Compendium, Health Physics, Vol. 59, No. 4, pp. 471-481, Oct, 1990.

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TSD 14-004 Revision 1 U.S. Nuclear Regulatory Commission, (NRC, 2000). Development of Probabilistic RESRAD 6.0 and RESRADBUILD 3.0 Computer Codes, NUREG/CR-6697, U.S. Nuclear Regulatory Commission, December 2000.

U.S. Department of Energy West Valley Demonstration Project, (DOE, 2009). Phase 1 Decommissioning Plan for the West Valley Demonstration, Appendix C Rev 2., Department of Energy.

Yim, S.P, T.M. Sullivan, and L. Milian, Sorption (Kd) measurements in Support of Dose Assessments for Zion Nuclear Station Decommissioning, Brookhaven National Laboratory Report to ZionSolutions, December 12, 2012.

Yu, C., Loureiro, C., Cheng, J.-J., Jones, Y.Y., Wang, Y.P. Chia, and E. Faillace, (1993). Data Collection Handbook to Support Modeling the Impacts of Radioactive Material in Soil, ANL/EAIS-8, Argonne National Laboratory, Argonne, IL.

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