NRC-09-0080, Engineering Calculation No. ENG-003, Revision 0, Calculation of EF1 Building Surface Dcgls.

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Engineering Calculation No. ENG-003, Revision 0, Calculation of EF1 Building Surface Dcgls.
ML093640139
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 10/07/2008
From: Bisson J
Bartlett
To:
NRC/FSME
References
NRC-09-0080 ENG-003, Rev 0
Download: ML093640139 (16)
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T-738 P-002/004 F-134 OCT-07-2008 07:23PM FROM---3 .D2f~ -3 (5 W8A RT L ETT ENGINEERING CALCULATION Calculation Number: ENG-003 Revision Number: Q, 0.1 Calculation Title 9 Calculation of EFI1 Buildirng Surface DCGLs Italculation of EF I BulldinE Surface D Preparer: Reviewer: A,0,ovI: ject Manag.er Approval:

r or ouy rce i r or Quility Assorance Date Date Dite: --Bartlett.60 Industrial Park Road Plymouth, MA 02360 Bartlett Engineering.

ENG-003 Calculation of EFI Building Surface DCGLs .Rev. 0 1.0 PURPOSE.The purpose of this calculation is to develop building surface derived concentration guideline levels (DCGLs) for the Detroit Edison Company's (DTE) Enrico Fermi (EF) I nuclear power site.This calculation is part of the scope of work defined in DTE Contract No. 4400001090.

2.0 APPLICABILITY

This calculation addresses only the development of building surface DCGLs for the EF 1 site.

3.0 REFERENCES

, 3.1 Bartlett Engineering Procedure ENG-AP-02, Verification of Software Operability 3.2 User's Manual for RESRAD-Build Version 3.0, June 2003 (ANL/EAD/03-1) 3.3 Bartlett Engineering Calculation ENG-001, Sensitivity Analyses to Support EF1 Building Surface DCGLs 3.4 10 CFR Part 20, Subpart E, Radiological Criteria for License Termination 3.5 NUREG/CR-5512, Residual Radioactive Contamination from Decommissioning

  • Volume 1: Technical Basis for Translating Contamination Levels to Annual Total Effective Dose Equivalent, Oct. 1992 (PNL-7994)
  • Volume 3: Parameter Analysis, Draft Report for Comment, Oct. 1999 (SAND99-2148) 3.6 NUREG/CR-6697, Development of Probabilistic RESRAD 6. 0 and RESRAD-Build 3.0 Computer Codes, Nov. 2000 (ANL/EADiTM-98) 3.7 NUREG/CR-6755, Technical Basis for Calculating Radiation Doses for the Building Occupancy Scenario Using the Probabilistic RESRAD-Build 3 0 Code, Feb. 2002 (ANL/EADITM/02-1) 3.8 NUREG-1727, NMSS Decommissioning Standard Review Plan, Sept. 2000 3.9 Federal Guidance Report (FGR) 11, Limiting Values of Radionuclide Intake and Air Concentrations and Dose Conversion Factors for Inhalation, Submersion, and Ingestion, EPA, 1988 3.10 Federal Guidance Report (FGR) 12, External Exposure to Radionuclides in Air, Water, and Soil, EPA, 1993 Page 2 of 16 Bartlett Engineering.

ENG-003 Calculation of-EF1 Building Surface DCGLs Rev. 0 4.0 METHOD OF CALCULATION The operability of the RESRAD-Build code was verified on each computer used for code executions in accordance with Engineering procedure ENG-AP-02, Verification of Software Operability

[ref. 3.1]. The RESRAD-Build user's manual [ref. 3.2] provided guidance for code operation.

Version 3.4 of the RESRAD-Build code was used to calculate building surface DCGL values.The RESRAD-Build computer code is a pathway analysis model designed to evaluate the potential radiological dose incurred by an individual who works in a building contaminated with radioactive material.

The exposure scenario modeled in this calculation is the building occupancy scenario, which provides estimates of human radiation exposures to residual radioactivity on surfaces inside standing buildings and permits the determination of DCGLs for building surfaces.

The scenario considers five exposure pathways: (i) direct external exposure from the source (i.e., radioactive material -deposited on the floor, walls, and ceiling), (ii) external exposure from deposited material, (iii) external exposure due to air submersion, (iv) exposure'due to inhalation of airborne radioactive material, (v) ingestion of radioactive material directly from the sources and material deposited on the surfaces.Bartlett Engineering Calculation ENG-001 [ref. 3.3] documents the selection process and sensitivity analyses performed for these numerous parameters; this calculation incorporates those results. The sensitivity analyses performed for the building scenario input parameters identified three sensitive input parameters (i.e., parameters whose values greatly influence the calculated dose) for that scenario:

deposition velocity, resuspension rate, and time for source removal. All other input parameters for the building scenario were non-sensitive.

In order to support the development of building surface DCGLs, Bartlett Engineering Calculation ENG-001 [ref. 3.3] provided recommendations for reasonably conservative values for the 3 sensitive parameters:

2 5 th and 7 5 th percentiles of the input parameter distributions.

Use of 2 5 th and 7 5 th percentiles values provides assurance that the DCGL calculations take into account the uncertainties associated with these sensitive input parameters.

The input values used in this calculation are consistent with both the selected scenario and the results of the sensitivity analyses.RESRAD-Build version 3.4 code runs were performed for 25 radionuclides-of-concern for. the EF1 site. Because each radionuclide was entered at a concentration of 1.0 pCi/m 2 and RESRAD-Build code calculates the annual dose associated with that contamination level, the RESRAD-Build results (i.e., mrem/y per 1.0 pCi/m 2) were used as a dose conversion factor (DCF) to obtain building surface DCGL values that corresponded to 25 mrem/y, the NRC limit established in 10CFR20, Subpart E [ref. 3.4]. This was accomplished using the following conversions:

The NRC dose limit, 25_mrem/y, divided by the RESRAD-Build DCF, mrem/y per pCi/m 2 = the DCGL in units of pCi/m 2 corresponding to 25 mrem/y.The next step was to convert the 25-mrem/y DCGL values (in units of pCi/m 2) to practical values (in units of dpm/1 00cm 2) that would support decommissioning and final status survey activities:

25-mrem/y DCGL (in pCi/m 2) .(2.22 dpm/1 pCi) * (lm/1OOcm) 2 .100 = 25-mrem/y DCGL in units of dpm/1 00cm 2 Page 3 of 16 Bartlett Engineering.

ENG-003'Calculation of EF1 Building Surface DCGLs Rev. 0 5.0 ASSUMPTIONS AND INPUT 5.1 Assumptions Building Scenario description:

The RESRAD-Build code v3.4 was used to model (through use of input parameter values) the building occupancy scenario defined in NUREG/CR-5512, volume 1 [ref. 3.5]. Modeling of this scenario provides an estimate of human radiation exposure to residual radioactivity on surfaces inside standing buildings and permits the determination of DCGLs for building surfaces.Five exposure pathways are assumed active: (i) direct external exposure from the source (i.e., residual radioactive material on the floor, walls, and ceiling), (ii)external exposure from deposited airborne material, (iii) external exposure due to air submersion, (iv) exposure due to inhalation of airborne radioactive material, (v) ingestion of radioactive material directly from the sources and material deposited on the surfaces.The Building Occupancy scenario modeled for the EF1 site accounted for light to moderate decommissioning activities carried out inside EF1 site buildings through use of conservative input for breathing rate and inadvertent ingestion of surface contamination.

This approach produced reasonably conservative estimates of annual doses associated with contaminated building surfaces." Radionuclides-of-concern for the Fermi 1 site: Ag-108m, Am241, C-14, Mn-54, Co-60, Cm-242, Cm-243, Cs-134, Cs-137, Eu-152, Eu-154, Eu-155, Fe-55, H-3, Na-22, Nb-94, Ni-59, Ni-63, Pu-238, Pu239, Pu-240, Pu-241, Sb-1 25, Sr-90, and Tc-99.* The hypothetical worker performs light to moderate decommissioning activities inside the building for a full occupational year (assumed equivalent to 97.5 twenty-four hours days [ref.3.5]).

  • The room dimensions provided by DTE are representative of the rooms in the EF1 buildings (see Figure 1).5.2 Input* Table 1 (pages 9 through 15) summarizes the classification, prioritization, values and their bases for all input parameter.

Values from NUREG/CR-5512, volume 3 [ref. 3.5], NUEG/CR-6697

[ref. 3.6], NUREG/CR-6755

[ref. 3.7], or NUREG-1727

[ref. 3.8] were assigned for the following scenario-defined parameters:

o Exposure duration:

365.25 d o Indoor fraction:

0.267 (= 97.5 work d/y divided by 365.25 d/y)o Breathing rate: 45.6 m 3/d (= 24h x 1.9 m 3/h, a rate appropriate for moderate to heavy activity [ref. 3.6]).o Receptor location (center of room): 5.97m, 13.23m, 1.0m o Air exchange rate for room: 1.52 per h o Indirect ingestion rate: 1.1 E-04 m 2/h Page 4 of 16 Bartlett Engineering.

ENG-003 Calculation of EF1 Building Surface DCGLs Rev. 0 o Air fraction:

0.07 for all nuclides except H-3; 1.0 for H-3 o Removable fraction:

0.1 Site-specific information (i.e., room dimensions) was used as the basis in calculations (see section 6.0) of values for the following parameters:

o Room area o Room height o Receptor location o Location of center of source o Source length o Source area* 2 5 th or 7 5 th percentile values from Bartlett Engineering Calculation ENG-001 [ref.3.3] were used as input for the sensitive parameters:

deposition velocity, resuspension rate, and time for source removal. Table 2 shows these values.Table 2: Percentile values for sensitive input parameters (reproduction of Table 6 in Reference.

3.3)Percentile Value Parameter a 25th 50th 75th UD 1.51790E-05 8.52364E-05 4.78217E-04 DKSUS 6.70403E-10 1.79444E-08 4.87543E-07 RFO(1) 1.82493E+04 3.30569E+04 5.26952E+04 RFO(2) 1.82301E+04 3.32029E+04 5.27188E+04 RFO(3) 1.81302E+04 3.30489E+04 5.27756E+04 RFO(4) 1.82071E+04 3.30410E+04 5.27269E+04 RFO(5) 1.80948E+04 3.31085E+04 5.27132E+04 RFO(6) 1.82466E+04 3.30500E+04 5.26222E+04 a RFO(#) = source removal time (for source number), UD = deposition velocity, and DKSUS = resuspension rate Note: The parameter, time for source removal, was not identified as sensitive for Ag-1 08m sources number 2 and 4 and .Eu-1 54 source number 2 in the sensitivity analysis (see Table 5 in reference 3.3). Therefore, the distribution for this parameter from NUREG/CR-6697

[ref. 3.6] was used as input for Ag-108m sources 2 and 4 and Eu-1 54 source 2 in the RESRAD-Build runs.Page 5 of 16 Bartlett Engineering.

Calculation of EF1 Building Surface DCGLs ENG-003 Rev. 0 6.0 CALCULATIONS AND RESULTS 6.1 Room dimensions:

EF1 provided dimensions of a representative room, shown in Figure 1. Table 3 below shows the unit conversion for the room dimensions and the area associated with each source (i.e., floor, walls, and ceiling).Table 3: Representative Room Dimensions (Based on dimensions provided by DTE -see Figure 1)Source Recorded No. Description Dimension ft m m 2 1 floor 315.97 2 north wall 39'2" 39.17 11.94 *43.67 3 east wall 86' 10" 86.83 26.47 96.81 4 south wall 39'2" 39.17 11.94 43.67 5 west wall 86' 10" 86.83 26.47 96.81 6 ceiling 315.97 wall height 12' 12.00 3.66 total room area: 912.88 a Recorded room dimensions are shown in Figure 1.b Feet to meter conversion factor: 1 ft = 0.3048m.6.2 Direct ingestion rate (h-') is calculated from the indirect ingestion rate from NUREG/CR-6755

[ref. 3.7], 1.1 E-04 m 2/h, and the total source area, 912.88 M 2 , as follows: (1 .1 E-04 m 2/h)/(912.88 M 2) = 1.2E-07 h 1 6.3 Location of the center of source: The center of each source was determined based on the representative room dimensions.

The locations were determined as the mid-point of the dimension values for the X, Y, and Z-axes. Table 4 below presents the locations for the center of the sources.Table 4: Location of Center of Sources Source Source Location of Center of Source (m)No. Description X-axis Y-axis Z-axis 1 floor 5.97 13.23 .0.00 2 north wall 5.97 26.47 1.83 3 east wall 11.94 13.23 1.83 4 south wall 5.97 0.00 1.83 5 west wall 0.00 13.23 1.83 6 ceiling 5.97 13.23 3.66 6.4 RESRAD-Build v3.4 results: Table 1 (pages 9 through 15) summarizes the input used in each RESRAD-Build code execution.

6.4.1 Each of the radionuclides listed in section 5.1 was evaluated using an initial concentration of 1.0 pCi/m 2 in separate code executions.

6.4.2 The evaluation time (t) was set to ly.Page 6 of 16 Bartlett Engineering.

Calculation of EFI Building Surface DCGLs ENG-003 Rev. 0 6.5 Table 5 summarizes the RESRAD-Build results by radionuclide.

Table 5: RESRAD-Build Results RESRAD-Build RESRAD-Build results: DCF DCGL 2 Sy DCGLW Nuclide File Name (mrem/y per 1 pCi/m 2) (pCi/m 2) (dpm/1OOcm 2)Ag-108m RESBMCAg108mDCGL.rpt 3.12E-05 8.01 E+05 1.78E+04 Am-241 RESRADB_Am241_DCGL.rpt 1.10E-04 2.27E+05 5.05E+03 C-14 RESRADBC14_DCGL.rpt 5.51E-08 4.54E+08 1.01 E+07 Cm-242 RESRADBCm242_DCGL.rpt 1.81 E-06 1.38E+07 3.07E+05 Cm-243 RESRADBCm243_DCGL.rpt 7.70E-05 3.25E+05 7.21 E+03 Co-60 RESRADBCo60_DCGL.rpt 5.18E-05 4.83E405 1.07E+04 Cs-134 RESRADB_Cs134_DCGL.rpt 3.19E-05 7.84E+05 1.74E+04 Cs-137 RESRADB_Cs137_DCGL.rpt 1.42E-05 1.76E+06 3.91E+04 Eu-152 RESRADBEu152_DCGL.rpt 2.58E-05 9.69E+05 2.15E+04 Eu-154 RESBMCEu1554_DCGL.rpt 2.73E-05 9.16E+05 2.03E+04 Eu-155 RESRADB_Eu155_DCGL.rpt 1.53E-06 1.63E+07 3.63E+05 Fe-55 RESRADBFe55_DCGL.rpt 1.37E-08 1.82E+09 4.05E+07 H-3 RESRADBH3_DCGL.rpt 1.92E-09 1.30E+10 2.89E+08 Mn-54 RESRADBMn54_DCGL.rpt 1.32E-05 1.89E+06 4.20E+04 Na22 RESRADBNa22_DCGL.rpt 4.38E-05 5.71 E+05 1.27E+04 Nb-94 RESRADBNb94_DCGL.rpt 3.63E-05 6.89E+05 1.53E+04 Ni-59 RESRADB_Ni59_DCGL.rpt 9.30E-07 2.69E+07 5.97E+05 Ni-63 RESRADBNi63_DCGL.rpt 1.54E-08 1.62E+09 3.60E+07 Pu-238 RESRADBPu238_DCGL.rpt 9.75E-05 2.56E+05 5.69E+03 Pu-239 RESRADBPu239_DCGL.rpt 1.11 E-04 2.25E+05 5.00E+03 Pu-240 RESRADBPu240_DCGL.rpt 1.11 E-04 2.25E+05 5.00E+03 Pu-241 RESRADBPu241_DCGL.rpt 2.08E-06 1.20E+07 2.67E+05 Sb-125 RESRADBSb125_DCGL.rpt 9.33E-06 2.68E+06 5.95E+04 Sr-90 RESRADBSr9O0DCGL.rpt 4.03E-06 6.20E+06 1.38E+05 Tc-99 RESRADB Tc99 DCGL.rpt 4.01 E-08 6.23E+08 1.38E+07 6.5.1 Column 3 presents the annual dose associated with a concentration of 1.0 pCi/m 2 as calculated using the RESRAD-Build code. These results were used as radionuclide-specific conversion factors (CF) with units of mrem/y per pCi/m 2.For each radionuclide, DCGL values corresponding to the NRC 25 mrem/y dose limit (designated as DCGL 2 5 y) were calculated as follows: (25 mrem/y) divided by the radionuclide-specific CF = DCGL 2 5 y (pCi/m 2)The resulting DCGL 2 5 y values are shown in column 4 of Table 5.The following hand calculations verify the operation of the spreadsheet:

Ag-1 08m: (25 mrem/y)/(3.12E-05 mrem/y per pCi/m 2)= 8.01 3E+05 pCi/m 2 Page 7 of 16 Bartlett Engineering.

Calculation of EFI Building Surface DCGLs ENG-003 Rev. 0 Pu-238: (25 mrem/y)/(9.757E-05 mrem/y per pCi/m 2)= 2.564E+05 pCi/m 2 6.5.2 Column 5 of Table 5 presents the conversions of the DCGL 2 5 y values to practical values with units of dpm/1OOcm 2 (designated in Table 5 as DCGLW). These DCGLw values would support decommissioning and final status surveys at the EF1 site.DCGL 2 5 y, pCi/mi 2.(2.22 dpm/1 pCi) .(1 m/1 00cm)2 _ 100 = DCGLw, dpm/1 00cm 2 The following hand calculations verify the operation of the spreadsheet:

C-14: (4.54E+08)(2.22)(1

/10000)(100)

= 1.007E+07 dpm/1 00cm 2 Cs-1 37: (1.76E+06)(2.22)(1/10000)(100)

= 3.907E+04 dpm/1OOcm 2 6.6 For practical application, the DCGLW values were rounded to 2 significant digits.Table 6 presents the rounded DCGLw values.Table 6: Building Surface DCGLw Values by Radionuclide Building Surface Building Surface Building Surface DCGLw DCGLw DCGL,, Nuclide (dpm/1OOcm

2) Nuclide (dpm/1OOcm
2) Nuclide (dpm/1OOcm 2)Ag-108m 1.8E+04 Eu-154 2.OE+04 Pu-238 5.7E+03 Arn-241 5.OE+03 Eu-155 3.6E+05 Pu-239 5.OE+03 C-14 1.OE+07 Fe-55 4.1 E+07 Pu-240 5.OE+03 Cm-242 3.1E+05. H-3 2.9E+8 Pu-241 2.7E+05 Cm-243 7.2E+03 Mn-54 4.2E+04 Sb-1 25 5.9E+04 Co-60 1.1E+04 Na-22 1.3E+04 Sr-90 1.4E+05 Cs-134 1.7E+04 Nb-94 1.5E+04 Tc-99 1.4E+07 Cs-137 3.9E+04 Ni-59 6.OE+05 Eu-1 52 2.2E+04 Ni-63 3.6E+07 Page 8 of 16 Bartlett Engineering.

Calculation of EFI Building Surface DCGLs ENG-003 Rev. 0 Table 1: Input Parameter Values for Building Surface DCGLs Parameter Typea Nuclide Treatmentb Value/Distribution Value Reference Source Exposure Duration (d) B All D 365.25 NUREG/CR-5512, Vol.3,section 5.2.1 Indoor Fraction B All D 0.267 NUREG/CR-5512, Vol.3,section 5.2.2.9 Evaluation Time (y) P All 1 Use of 1 y provides doses at t=Oy and tWly.Number of Rooms P All D 1 NUREG/CR-5512 Cm-242 D 1.5179E-05 25th percentile value Deposition Velocity (m/s) P Pu-241 D 1.5179E-05 25 h percentile value All Others D 4.78217E-04 7 5 1h percentile value Cm-242 D 4.87543E-07 7 5 th percentile value Resuspension Rate (s") P Pu-241 D 4.87543E-07 7 5'h percentile value All Others D 6.70403E-10 2 5 th percentile value NUREG/CR-6697, Att. C, sec. 7.4 and Air Exchange Rate for Room (h') B All 0 1.52 NUREG/CR-6755, sec. 3.2 Room Area (m 2) P All D 315.97 Site-specific data Room Height (m) P All D 3.66 Site-specific data Time Fraction B All D 1 NUREG/CR-5512 Inhalation rate for moderate to heavy a 3 activities

-NUREG/CR-6697, Attachment Inhalation Rate (m/d) M All 0 45.6 C, section 5.1; NUREG/CR-5512, vol. 3, section 5.3.4 Indirect Ingestion Rate (m 2/h) B All D 0.00011 NUREG/CR6755, A.3.3, Table A.12 Receptor Location B All D 5.97, 13.23, 1 NUREG/CR-5512; site-specific room dimensions Shielding Thickness (cm) P All D 0Site-specific model-no shielding assumed RESRAD-B'uild default value for concrete Shielding Density (g/cm 3) P All D 2.4-nousdiDCLcllaos-not used in DCGL calculations Shielding Material P All D concrete Default input -not used in DCGL calculations Number of Sources P All 6 Modeling for representative room External Dose Conversion Factor, M All D RESRAD-Build FGR12 (mrem/y per pCi/cm 2) M _A__ default Air Submersion Dose Conversion RESRAD-Build FGR12 Factor, (mrem/y per pCi/m 3) M All D default Inhalation Dose Conversion Factor, M All D RESRAD-Build FGR11 (mrem/pCi) default Ingestionl Dose Conversion Factor, M All D RESRAD-Build FGR11 (mrem/pCi) default Source 1: Floor Type P All area NUREG/CR-5512 Direction P All I Z NUREG/CR-5512 Location of Center of Source: x,y,z P All D 5.97, 13.23, 0 Site-Specific Modeling (m)Source length X-axis (m) P All D 11.94 Site-Specific Modeling Source length Y-axis (m) P All D 26.47 Site-Specific Modeling Area (m 2) P All D --- Source length inputs used H-3 1.0 Air Fraction B All D 0.0 NUREG/CR-6697, Att. C Section 8.6 All others 0.07 Direct Ingestion (h') B All D 1.2E-7 NUREG/CR6755, A.3.3 Removable Fraction P All D 0.1 NUREG-1727, Table C.7.1; NUREG/CR-l F o 6755, section 3.5 Page 9 of 16 Bartlett Engineering.

Calculation of EF1 Building Surface DCGLs ENG-003 Rev. 0 Table 1: Input Parameter Values for Building Surface DCGLs Parameter Typea Nuclide Treatmentb Value/Distribution Value Reference Source Time for Source Removal (d) p Ag-108m D 52,695.2 75m percentile value Am-241 0 18,249.3 2 5 Th percentile value C-14 D 52,695.2 7 5 Th percentile value Co-60 D 52,695.2 7 5 Th percentile value Cm-242 D 18,249.3 2 5 Th percentile value Cm-243 D 18,249.3 2 5 Th percentile value Cs-134 D 52,695.2 7 5 Th percentile value Cs-137 D 52,695.2 7 5 Th percentile value Eu-1 52 D 52,695.2 7 5 Th percentile value Eu-1 54 D 52,695.2 7 5 Th percentile value Eu-1 55 D 52,695.2 7 5 Th percentile value Fe-55 D 52,695.2 7 5 Th percentile value H-3 D 18,249.3 2 5 Th percentile value Mn-54 D 52,695.2 7 5 Th percentile value Na_22 D 52,695.2 7 5 Th percentile value Nb-94 D 52,695.2 7 5 Th percentile value Ni-59 D 18,249.3 2 5 Th percentile value Ni-63 D 18,249.3 2 5 Th percentile value Pu-238 D 18,249.3 2 5 Th percentile value Pu-239 D 18,249.3 2 5 Th percentile value Pu-240 D 18,249.3 2 5 Th percentile value Pu-241 D 18,249.3 2 5 Th percentile value Sb-1 25 D 52,695.2 7 5 Th percentile value Sr-90 D 52,695.2 7 5 Th percentile value Tc-99 D 52,695.2 7 5 Th percentile value Radionuclide Concentration (pCi/m 2) P All D 1.0 Source 2: North Wall Type P 3 Area NUREG/CR-5512 Direction P 3- Y NUREG/CR-5512 Location of Center of Source: x,y,z P 3 D 5.97, 26.47, 1.83 Site-Specific Modeling (m)Source length X-axis (m). P 2 D 11.94 Site-Specific Modeling Source length Z-axis (m) P 2 D 3.66 Site- Specific Modeling Area (M 2) P 2 D --- Source length inputs used Air Fraction B H-3 D 1.0 NUREG/CR-6697, Att. C Section 8.6_____________________All others 0.07 _ _______________

Direct Ingestion (h-1) B 2 D 1.2E-7 NUREG/CR6755, A.3.3 R emovable Fraction P 1 D 0.1 NUREG-1727, Table C.7.1; NUREG/CR-n 1 D 06755, section 3.5 Page 10 of 16 Bartlett Engineering.

, Calculation of EF I Building Surface DCGLs ENG-003 Rev. 0 Table 1: InPUt Parameter Values for Buildino Surface DCGLs Parameter Typea Nuclide Treatmentb Value/Distribution Value Reference Source Time for Source Removal (d) P Ag-1 08m S Triangular 0 NUREG/CR-6755, Section 3.6;NUREG/CR-6697, Art.C, 8.8 Am-241 D 18,230.1 2 5 Th percentile value C-14 D 52,718.8 7 5 Th percentile value Co-60 D 52,718.8 7 5 Th percentile value Cm-242 D 18,230.1 2 5 Th percentile value Cm-243 D 18,230.1 2 5 Th percentile value Cs-134 D 52,718.8 7 5 Th percentile value Cs-137 D 52,718.8 7 5 Th percentile value Eu-1 52 D 52,718.8 75Th percentile value Eu-154 S Triangularc NUREG/CR-6755, Section 3.6;NUREG/CR-6697, Att.C, 8.8 Eu-155 D 18,230.1 2 5 Th percentile value Fe-55 D 52,718.8 7 5 TTh percentile value H-3 D 18,230.1 2 5 Th percentile value Mn-54 D 52,718.8 7 5 Th percentile value Na_22 D 52,718.8 7 5 Th percentile value Nb-94 D 18,230.1 2 5 Th percentile value Ni-59 D 18,230.1 2 5 Th percentile value Ni-63 D 18,230.1 2 5Th percentile value Pu-238 D 18,230.1 2 5 Th percentile value Pu-239 D 18,230.1 2 5 Th percentile value Pu-240 D 18,230.1 2 5 Th percentile value Pu-241 D 18,230.1 2 5 Th percentile value Sb-1 25 D 52,718.8 7 5 Th percentile value Sr-90 D 52,718.8 7 5 Th percentile value Tc-99 D 52,718.8 7 5 Th percentile value Radionuclide Concentration (pCi/m 2) P 2 D 1.0 Source 3: East Wall Type P 3 Area NUREG/CR-5512 Direction P 3 X NUREG/CR-5512 Location of Center of Source: x,y,z P 3 D 11.94, 13.23, 1.83 Site-Specific Modeling (m)Source length Y-axis (m) P 2 D 26.47 Site-Specific Modeling Source length Z-axis (m) P 2 D 3.66 Site-Specific Modeling Area (M 2) P 2 D --- Source length inputs used Air Fraction B H-3 D 1.0 NUREG/CR-6697, Att. C Section 8.6___rFraction_

B All others 0.07 Direct Ingestion (h-1) B 2 D 1.2E-7 NUREG/CR6755, A.3.3 Removable Fracti on P 1 D 0.1 NUREG-1727, Table C.7.1; NUREG/CR-b F6755, section 3.5 Page 11 of 16 Bartlett Engineering.

Calculation of EFI1 Building Surface DCGLs ENG-003 Rev. 0 Table 1: Input Parameter Values for Building Surface DCGLs Parameter Typea Nuclide Treatmentb Value/Distribution Value Reference Source Time for Source Removal (d) p Ag-108m D 52,775.6 7 5 t percentile value Am-241 D 18,130.2 2 5 Th percentile value C-1 4 D 52,775.6 7 5 Th percentile value Co-60 D 52,775.6 7 5 Th percentile value Cm-242 D 18,130.2 2 5 Th percentile value Cm-243 D 18,130.2 2 5 Th percentile value Cs-1 34 D 52,775.6 7 5 Th percentile value Cs-1 37 D 52,775.6 7 5 Th percentile value Eu-1 52 D 52,775.6 7 5 Th percentile value Eu-1 54 D 52,775.6 7 5 Th percentile value Eu-155 D 52,775.6 7 5 Th percentile value Fe-55 D 52,775.6 7 5 Th percentile value H-3 D 18,130.2 2 5 Th percentile value Mn-54 D 52,775.6 7 5 Th percentile value Na_22 D 52,775.6 7 5 Th percentile value Nb-94 D 52,775.6 7 5 Th percentile value Ni-59 D 18,130.2 2 5 Th percentile value Ni-63 D 18,130.2 2 5 Th percentile value Pu-238 D 18,130.2 25TI percentie value Pu-239 D 18,130.2 2 5 Th percentile value Pu-240 D 18,130.2 2 5 Th percentile value Pu-241 D 18,130.2 2 5 Th percentile value Sb-1 25 D 52,775.6 7 5 Th percentile value Sr-90 D 52,775.6 7 5 Th percentile value Tc-99 D 52,775.6 7 5 Th percentile value Radionuclide Concentration (pCi/m 2) P 2 D 1.0 Source 4: South Wall Type P 3 area NUREG/CR-5512 Direction P 3 Y NUREG/CR-5512 Location of Center of Source: x,y,z p 3 D 5.97, 0, 1.83 Site-Specific Modeling (m)Source length X-axis (m) P 2 D 11.94 Site-Specific Modeling Source length Z-axis (m) P 2 D 3.66 Site-Specific Modeling Area (M 2) P 2 D --- Source length inputs used Air Fraction B H-3NUREG/CR-6697, A. C Section 8.6 All others 0.07 Direct Ingestion (h-1) B 2 D 1.2E-7 NUREG/CR6755, A.3.3 Removable Fraction 1 D 0.1 NUREG-1727, Table C.7.1; NUREG/CR-FP 1 06755, section 3.5 Page 12 of 16 Bartlett Engineering.

Calculation of EF1 Building Surface DCGLs ENG-003 Rev. 0 Table 1: Input Parameter Values for Building Surface DCGLs Parameter Typea Nuclide Treatmentb Value/Distribution Value Reference Source Time for Source Removal (d) p Ag-108m S Triangularc NUREG/CR-6755, Section 3.6;NUREG/CR-6697, Att.C, sec 8.8 Am-241 D 18,207.1 2 5 Th percentile value C-14 D 52,726.9 7 5"Th percentile value Co-60 D 52,726.9 7 5 Th percentile value Cm-242 D 18,207.1 2 5 Th percentile value Cm-243 D 18,207.1 2 5 Th percentile value Cs-134 D 52,726.9 7 5 Th percentile value Cs-137 D 52,726.9 7 5 Th percentile value Eu-152 D 18,207.1 2 5 Th percentile value Eu-154 D 18,207.1 2 5 th percentile value Eu-155 D 18,207.1 2 5 Th percentile value Fe-55 D 52,726.9 7 5 Th percentile value H-3 D 18,207.1 2 5 Th percentile value Mn-54 D 52,726.9 7 5 Th percentile value Na-22 D 52,726.9 7 5 Th percentile value Nb-94 D 18,207.1 2 5 Th percentile value Ni-59 D 18,207.1 2 5 Th percentile value Ni-63 D 18,207.1 2 5 Th percentile value Pu-238 D 18,207.1 2 5 Th percentile value Pu-239 D 18,207.1 2 5 Th percentile value Pu-240 D 18,207.1 2 5 Th percentile value Pu-241 D 18,207.1 2 5 Th percentile value Sb-125 D 52,726.9 7 5 Th percentile value Sr-90 D 52,726.9 7 5 Th percentile value Tc-99 D 52,726.9 7 5"Th percentile value Radionuclide Concentration (pCi/m 2) P 2 D 1.0 Source 5: West Wall Type P 3 area NUREG/CR-5512 Direction P 3 X NUREG/CR-5512 Location of Center of Source: x,y,z P 3 D 0, 13.23, 1.83 Site-Specific Modeling (m)Source length Y-axis (m) P 2 D 26.47 Site-Specific Modeling Source length Z-axis (m) P 2 D 3.66 Site-Specific Modeling Area (Mi 2) P 2 D --- Source length inputs used* i rcinB H-3 01.0 Air Fraction B l oH3 D 0.07 NUREG/CR-6697, Att. C Section 8.6 Direct Ingestion (hW) B 2 D 1.2E-7., NUREG/CR6755, A.3.3 Removable Fraction P 1D 0.1 NUREG-1727, Table C.7.1; NUREG/CR-Rt6755, section 3.5 Page 13 of 16 I Bartlett Engineering.

Calculation of EFI Building Surface DCGLs ENG-003 Rev. 0 Table 1: Input Parameter Values for Building Surface DCGLs Parameter Typea Nuclide Treatmentb Value/Distribution Value Reference Source Time for Source Removal (d) p Ag-1 08m D 52,713.2 75" percentile value Am-241 D 18,094.8 2 5 Th percentile value C-14 D 52,713.2 7 5 Th percentile value Co-60 D 52,713.2 7 5 Th percentile value Cm-242 D 18,094.8 2 5 Th percentile value Cm-243 D 18,094.8 2 5 Th percentile value Cs-134 D 52,713.2 7 5 T percentile value Cs-137 D 52,713.2 7 5 Th percentile value Eu-152 D 52,713.2 75 T percentile value Eu-1 54 D 52,713.2 7 5 th percentile value Eu-1 55 D 52,713.2 7 5 Th percentile value Fe-55 D 52,713.2 7 5 Th percentile value H-3 D 18,094.8 2 5 Th percentile value Mn-54 D 52,713.2 7 5 Th percentile value Na-22 D 52,713.2 7 5 Th percentile value Nb-94 D 52,713.2 7 5 Th percentile value Ni-59 D 18,094.8 2 5 T percentile value Ni-63 D 18,094.8 2 5 Th percentile value Pu-238 D 18,094.8 2 5 Th percentile value Pu-239 D 18,094.8 2 5 Th percentile value Pu-240 D 18,094.8 2 5 Th percentile value Pu-241 D 18,094.8 2 5 Th percentile value Sb-1 25 D 52,713.2 7 5 Th percentile value Sr-90 D 52,713.2 7 5 Th percentile value Tc-99 D 52,713.2 7 5 Th percentile value Radionuclide Concentration (pCi/m 2) 2 D 1.0 Source 6: Ceiling Type P 3 area NUREG/CR-5512 Direction P 3 Z NUREG/CR-5512 Location of Center of Source: x,y,z 3 D 5.97, 13.23, 3.66 Site-Specific Modeling Source length X-axis (m) P 2 D 11.94 Site-Specific Modeling Source length Y-axis (m) P 2 D 26.47 Site-Specific Modeling Area (M 2) P 2 D --- Source length inputs used Air Fraction B H-3 1.0 NUREG/CR-6697, Att. C Section 8.6 (p._irFraction_

All others 0.07 8-14 and 8-15)Direct Ingestion (W 1) B 2 D 1.2E-7 NUREG/CR6755, A.3.3 Removable Fraction 1 D 0.1 NUREG-1727, Table C.7.1; NUREG/CR-iP 1 6755, section 3.5 Page 14 of 16 Bartlett Engineering.

Calculation of EF1 Building Surface DCGLs ENG-003 Rev. 0 Table 1: Input Parameter Values for Building Surface DCGLs Parameter Typea Nuclide I Treatmentb I Value/Distribution Value Reference Source Time for Source Removal (d)P Ag-108m Am-241 C-14 Co-54 Cm-242 Cm-243 Cs-134 Cs-137 Eu-152 Eu-154 Eu-155 Fe-55 H-3 Mn-54 Na-22 Nb-94 Ni-59 Ni-63 Pu-238 Pu-239 Pu-240 Pu-241 Sb-125 Sr-90 Tc-99 52,622.2 18,246.6 52,622.2 52,622.2 18,246.6 18,246.6 52,622.2 52,622.2 52,622.2 52,622.2 52,622.2 52,622.2 18,246.6 52,622.2 52,622.2 52,622.2 18,246.6 18,246.6 18,246.6 18,246.6 18,246.6 18,246.6 52,622.2 52,622.2 52,622.2 75 n percentile value 25Th percentile value 75 percentile value 7 5 Th percentile value 2 5 Th percentile value 2 5 Th percentile value 75Th percentile value 75 percentile value 75Th percentile value 75th percentile value 7 5 Th percentile value 7 5 Th percentile value 25Th percentile value 7 5 Th percentile value 75Th percentile value 75 percentile value 25Th percentile value 25 percentile value 2 5 Th percentile value 2 5 Th percentile value 2 5 Th percentile value 2 5 Th percentile value 75Th percentile value 75 percentile value 75Th percentile value Radionuclide Concentration (pCi/m 2) I P 1 2 D 1.0 1 a p physical, B = behavioral, M = metabolic; (see NUREG/CR-6697, Attachment B, Table 4.)b D = deterministic c Triangular with defining values for distribution:

minimum = 1,000, maximum = 100,000, and most likely = 10,000.Page 15 of 16 I Bartlett Engineering.

Calculation of EFI Building Surface DCGLs ENG-003 Rev. 0 Figure 1: Dimensions of EF 1 Representative Room Hei5J IN t IC I ' //'i" Lis I I T I I Page 16 of 16

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