NRC-09-0080, Engineering Calculation No. ENG-001, Revision 2, Sensitivity Analyses to Support EF1 Building Surface Dcgls.

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Engineering Calculation No. ENG-001, Revision 2, Sensitivity Analyses to Support EF1 Building Surface Dcgls.
ML093640137
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Site: Fermi DTE Energy icon.png
Issue date: 01/27/2009
From: Bisson J
Bartlett
To:
NRC/FSME
References
NRC-09-0080 ENG-001, Rev 2
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4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 A A A A A A A A A A A A (-J BARTLETT ENGINEERING CALCULATION Calculation Number: ENG-O01 Revision Number: 2 e: Sensitivity Analyses to SuDuort EF1 Building Calculation Titl Surface DCGLs Preparer:

.Reviewer:

.Approval:

6-VA C 3---Corpo0e Project Manager Approval: Director of Quality Assurance Date /Z¢2, Date b qlvp Date (-x1-Date: /-,7- 0, Bartlett.60 Industrial Park Road Plymouth, MA 02360 Bartlett Engineering.

ENG-001 Sensitivity Analyses to Support EF1 Building Surface DCGLs Rev. 2 1.0 PURPOSE The purpose of this calculation is to determine which of the input parameters for the building occupancy scenario have a significant impact on the calculated dose (i.e., those parameters whose values greatly influence the calculated dose; aka, "sensitive" input parameters).

The results of this calculation will support the development of building surface derived concentration guideline levels (DCGLs) for the Detroit Edison Company's (DTE) Enrico Fermi (EF) 1 nuclear power site, located in Newport, Michigan. -This calculation is a deliverable product specified in the scope of work section in Contract No. 4400001090.

Revision 2 of this calculation corrects typographical errors in Table 1.2.0 APPLICABILITY This calculation addresses only the sensitivity analysis for input parameters for the building occupancy scenario as defined for the DTE EF 1 site.

3.0 REFERENCES

3.1 Procedure ENG-AP-02, Verification of Software Operability 3.2 User's Manual for RESRAD-Build i'ersion 3.0, June 2003 (ANL/EAD/03-1) 3.3 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) 3.4 NUREG/CR-6697, Development of Probabilistic RESRAD 6.0 and RESRAD-Build 3.0 Computer Codes, Nov. 2000 (ANL/EADiTM-98) 3.5 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/EAD/TM/02-1) 3.6 NUREG-1 727, NMSS Decommissioning Standard Review Plan, Sept. 2000 3.7 NUREG/CR-6676, Probabilistic Dose Analysis Using Parameter Distributions Develop5ed for RESRAD and RESRAD-Build Codes, May 2000 (ANL/EAD/TM-89) 3.8 NUREG/CR-6692, Probabilistic Modules for the RESRAD and RESRAD-Build Computer Codes, Nov. 2000 (ANL/EAD/TM-91) 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 Bartlett Engineering.

ENG-001 Sensitivity Analyses to Support EF1 Building Surface DCGLs Rev. 2 4.0 METHOD OF CALCULATION The operability of the RESRAD-Build code was verified on each computer use for code executions in accordance with the Bartlett 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.

The sensitivity analyses for the building scenario input parameters was performed using Version 3.4 of the RESRAD-Build computer code, which was developed by Argonne National Laboratory under the sponsorship of the U.S. Department of Energy and other federal agencies.

The code requires input for numerous parameters in order to calculate the dose via various exposure pathways to a hypothetical individual working in a building contaminated with radioactive material.

The probabilistic modules in RESRAD-Build permit the user to perform a sensitivity analysis to identify those parameters that have the greatest impact on dose. In addition, the probabilistic modules-allow the evaluation of dose as a function of parameter distributions.

Verification of the RESRAD-Build code is documented in the RESRAD-Build user's manual [ref.3.2] and testing for the probabilistic codes is discussed in NUREG/CR-6697

[ref. 3.4].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 exposure pathways considered are (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.The approach taken in this calculation consists of two primary phases: the selection of input parameter values and performing RESRAD-Build runs. The first phase involves classifying and prioritizing the RESRAD-Build input parameters.

The selection process is based on guidance provided in NUREG/CR-6676

[ref 3.7], NUREG/CR-6697

[ref. 3.4], NUREG/CR-6692

[ref. 3.8], and NUREG/CR-6755

[ref. 3.5]. Figure 1 provides a flow diagram for the parameter selection process.Classification, prioritization, and treatment of input parameters:

Parameters were classified as behavioral, metabolic, or physical parameters consistent to the classifications found in NUREG/CR-6697

[ref. 3.4]. Behavioral parameters depend on the behavior of the receptor and the scenario definition.

Metabolic parameters are independent of the defined scenario, and represent the metabolic characteristics of the receptor.

Physical parameters are those parameters that would not change if the receptor changed.Following the classification process, parameters were assigned priority rankings.

Priority 1 parameters are high priority; Priority 2 parameters are medium priority; and Priority 3 parameters are low priority.

NUREG/CR-6697

[ref. 3.4] provides prioritization rankings for input parameters.

Those rankings were adopted in this calculation.

The priority of a given parameter is based on: Page 3 Bartlett Engineering.

ENG-001 Sensitivity Analyses to Support EF1 Building Surface DCGLs Rev. 2* the relevance of the parameter in dose calculations,* the variability of the dose because of changes in the parameter value,* the parameter type,. and* the availability of parameter-specific data.Input parameters were treated as either deterministic (a single value is assigned) or stochastic (a probability distribution is assigned).

Treatment depended on parameter type, availability of site-specific data, and the relevance of the parameter in the dose calculations.

  • Behavioral and metabolic parameters were treated as deterministic and the assigned values were from NUREG/CR05512, volume 3 [ref. 3.3], NUREG/OR-6697 [ref. 3.4], NUREG/CR-6755

[ref. 3.5], or the RESRAD-Build default library.Parameters for which site-specific data are available were treated as de-terministic.

  • Physical parameters for which site-specific data are unavailable were assigned values based on priority.

Priority 1 and 2 physical parameters were treated stochastic and assigned probability distributions from NREG/CR-5512, volume 3[ref. 3.3], NUREG/CR-6697

[ref. 3.4], NUREG/CR-6755

[ref. 3.5], or assigned a deterministic value from NUREG/CR-5512, volume 3 [ref. 3.3], NUREG/CR-6697

[ref.3.4], or NUREG/CR-6755

[ref. 3.5]. Priority 3 physical parameters were treated as deterministic and were assigned values from NUREG/CR-5512, volume 3 [ref. 3.3], NUREG/CR-6697

[ref.3.4], NUREG/CR-6755

[ref. 3.5], or the RESRAD-Build default library.Following the parameter selection process, RESRAD-Build input files were developed based on the results of the parameter selection process and a parameter sensitivity analysis was performed for each radionuclide of concern. Input correlations were applied based on guidance in NUREG/CR-6676

[ref. 3.7].The RESRAD-Build Probabilistic Output Report provides regression and correlation coefficients for the average doses at the user defined evaluation times. The Partial Rank Correlation Coefficient (PRCC) has been used to identify sensitive parameters with the limit set at 0.1.NUREG/CR-6692

[ref. 3.8] and NUREG/CR-6697

[ref. 3.4] recommend the use of the PRCC for cases where a non-linear relationship and widely disparate scales exists between the input and output. The guidance further recommends the use of the PRCC if strong correlations exist between input parameters.

The criterion for sensitivity used .in this calculation was a PRCC value with an absolute value greater than 0.1. In addition, PRCC values that are greater than zero (positive value) or less than zero (negative value) identify whether sensitive parameters are positively or negatively correlated to dose, respectively.

Therefore, 7 5 th values were determined for sensitive parameters that had positive PRCC values and 2 5 th values were determined for sensitive parameters that had negative PRCC values. These 2 5 th and 7 5 th percentile values are proposed as reasonably conservative input for the DCGL calculation for the EF1 site.The 2 5 th and 7 5 th percentile values were obtained using the following method: 1. Open the RESRAD-Build

"*.buo" file generated during from the sensitivity run using the "View Interactive Output" button on the RESRAD-Build navigator.

2. Click the "Results" tab in the interactive output window.3. Click on the "Graphics" tab.Page 4 Bartlett Engineering.

ENG-001 Sensitivity Analyses to Support EF1 Building Surface DCGLs Rev. 2 4. Select "input vector" by scrolling through the choices under the "Primary Object" prompt.5. Select the desired parameter by scrolling through the choices under the "Input Parameter" prompt.6. Right click on the cumulative probability graph and select "Edit Chart Data." 7. Scroll down until the desired fraction (i.e., 0.25 or 0.75) is visible in column C2.The corresponding value in column C1 is the percentile value.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 ofýhuman 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., 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.Twenty-five client-identified radionuclides are assumed as radionuclides-of-concern for the Fermi 1 site: Ag-1 08m, Am241, C-14, Co-60, Cm-242, Cm-243, Cs-1 34, Cs-1 37, Eu-152, Eu-154, Eu-155, Fe-55, H-3, Mn-54, Na-22, Nb-94, Ni-59, Ni-63, Pu-238, Pu239, Pu-240, Pu-241, Sb-125, Sr-90, and Tc-99.The hypothetical worker is assumed to perform activities inside the building for a full occupational year.Figure 2 provides an illustration of the representative room for the EF1 site (dimensions provided by DTE). For modeling purposes, a rectangular room (39 ft, 2 in by 86 ft, 10 in)with 12-ft walls was assumed. This modeled room included 6 area sources (i.e. floor, 4 walls, and ceiling).5.2 Table 1 summarizes the classification, prioritization, values and their bases for all input parameter.

Values from NUREG/CR-5512, volume 3 [ref. 3.3], NUEG/CR-6697

[ref. 3.4], NUREG/CR-6755

[ref. 3.5], or NUREG-1727

[ref.3.6]

were assigned for the following scenario-defined parameters:

  • Exposure duration:

365.25 d* Indoor fraction:

0.267 (= 97.5 work d/y divided by 365.25 d/y)* Inhalation rate: 33.6 m 3/d (=1.4 m 3/h

  • 24 h/d)" Receptor location (center of room): 5.97m, 13.23m, 1.0m* Air exchange rate for room: 1.52 per h Page 5 Bartlett Engineering.

ENG-001 Sensitivity Analyses to Support EF1 Building Surface DCGLs Rev. 2* Indirect ingestion rate: 1.1 E-04 m 2/h* -Air fraction:

0.07 for all nuclides except H-3; 1.0 for H-3* 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: " Room area" Room height" Receptor location* Location of center of source* Source length* Source area Statistical distributions from NUREG/CR-6755

[ref. 3.5] provided input for:* deposition velocity," resuspension rate, and" time for source removal.An input correlation of 0.9 between the deposition velocity and the resuspension rate was applied based on guidance in NUREG/CR-6676

[ref. 3.7]. In addition, because the sources are assumed constructed of the same material and subject to the same environment, an input correlation of 0.9 was applied for the time for source removal between sources.6.0 CALCULATIONS AND RESULTS 6.1 Room dimensions:

EF1 staff provided dimensions of a representative room, shown in Figure 2. Table 2 shows the unit conversion for the room dimensions and the area associated with each source (i.e., floor, walls, and ceiling).6.2 Direct ingestion rate (h 1) is calculated from the indirect ingestion rate from NUREG/CR-6755

[ref. 3.5], 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 hW 6.3 Using the dimensions for the east and south walls (86 ft, 10 in and 39 ft, 2 in, respectively) and a wall height of 12 ft (see Figure 2), the locations of the centers of the sources were determined as the mid-point on the X, Y, and Z-axes. Table 3 presents the locations for the center of the sources.,6.4 RESRAD-Build v3.4 results: Table 1 summarizes the input used in each RESRAD-Build code execution.

6.4.1 Each of the radionuclides listed in section 5.1 was evaluated in separate code executions.

Page 6 Bartlett Engineering.

ENG-001 Sensitivity Analyses to Support EF1 Building Surface DCGLs Rev. 2 6.4.2 Use of an evaluation time (t) of ly produces dose results for t = Oy and t =ly. For all radionuclides, t = Oy was the time of maximum dose, as demonstrated by lower doses at t =. ly. For some radionuclides, several evaluation' times were included in the code runs to confirm the decreasing dose pattern indicated by the t = 0y and t = ly doses. Table 4 shows the maximum doses calculated at various times.6.5 PRCC values were reviewed against the sensitivity criterion (i.e., I PRCCI >0.1).For each of the 25 radionuclides, deposition velocity, the resuspension rate, and the time for source removal were identified as sensitive input parameters.

Table 5 summarizes the sensitive parameters by radionuclide.

6.6 The 2 5 th and 7 5 th percentile values for sensitive input parameters were obtained through use of the interactive output in the RESRAD-Build code. Table 6 presents these values.6.6.1 A comparison of the 2 5 th and 7 5 th percentiles values obtained from the RESRAD-Build code to the distributions given in NUREG/CR-6697

[ref.3.4] indicates that the 2 5 th and' 7 5 th percentile values are reasonably conservative.

Table 6 includes this comparison.

7.0 CONCLUSION

7.1 Deposition velocity, resuspension rate, and time for source removal are sensitive input parameters to the building occupancy scenario for each of the 25 radionuclides-of concern.7.2 The 2 5 th and 7 5 th percentile values for sensitive input parameters have been determined from the parameter distributions and found to be reasonably conservative when compared with the distributions from NUREG/CR-6697

[ref. 3.4].7.3 The 2 5 th and 7 5 th percentile values for sensitive input parameters are recommended for use as input for building surfaces DCGLs for the EFR site.Page 7 Bartlett Engineering.

Sensitivity Analyses to Support EF1 Building Surface DCGLs ENG-001 Rev. 2 Table 1 Input Parameter Values for Sensitivity Analysis Treat- Value or Value/Distribution Parameter Typea Priorityb mentc Distribution Reference Source Distribution's Statistical Parametersd 1 2 3 4 Exposure Duration (d) B 3 D 365.25 NUREG/CR-5512, NR` NR NR NR ExposureDuration_(d)_

B 3 D 365.25 Vol.3,section 5.2.1 Indoor Fraction B 2 D 0.267 NUREG/CR-5512, NR NR NR NR Vol.3,section 5.2.2.9 Evaluation Time (y) P 3 D 1 or multiple (e.g., T=1 corresponds to 1,10, 50, 100) dose over the is' year NR NR NR NR Number of Rooms P 3 D 1 NUREG/CR-5512 NR NR NR NR NUREG/CR-6755, Deposition Velocity (m/s) P 2 5 Loguniform Section 3.3; 2.70E-06 2.70E-03 -NUREG/CR-6697, Att.C, section 7.5 NUREG/CR-6755, Resuspension Rate (s1) 1 Loguhiform Section 3.1; 2.5E-1 1 1.35E-5 -NUREG/CR-6697, Att.C, section 7.2 NUREG/CR-6697, Att.AirExchange Rate for Room hB 2 D 1.52 C, section 7.4 and NR NR NR NR R (h-) NUREG/CR-6755, section 3.2 Room Area (M 2) P 2 D 315.97 Site-specific data NR NR NR NR Room Height (m) P 2 D 3.66 Site-specific data NR NR NR NR Time Fraction B 3 D 1 NUREG/CR-5512 NR NR NR NR NUREG/CR-6697; Inhalation Rate (m 3/d) M 2 D 33.6 NUREG/CR-5512, vol. NR NR NR NR 3, section 5.3.4 Indirect Ingestion Rate (M2/h) B 2 D 0.00011 NUREG/CR6755, NR NR NR NR A.3.3, Table A.12 NUREG/CR-5512; Receptor Location B 3 D 5.97, 13.23, 1 center of room based NR NR NR NR on site-specific room dimensions Shielding Thickness (cm) P 2 D 0 Site-specific model-no NR NR NR NR I _ _ __ I_ _ _shielding assumed I II Page 8 Bartlett Engineering.

Sensitivity Analyses to Support EF1 Building Surface DCGLs ENG-001 Rev. 2 Table 1 Input Parameter Values for Sensitivity Analysis Treat- Value or Value/Distribution Parameter Typea Priorityb

-mentc Distribution Reference Source Distribution's Statistical Parametersd 1 .2 3 4 Shielding Density P 1 0 Site-specific model-no NR NR NR NR Shieldin Density(g/cm

3) P _1_D_0 shielding assumed Shielding Material P 3 D None Site-specific model-no NR NR NR NR ShieldingMaterialP_3 D None shielding assumed Site-specific modeling Number of Sources P 3 D 6 (includes floor, 4 walls, plus ceiling)External Dose Conversion Factor, RESRAD-Build FGR12 (mrem/y per pCi/cm 2) M 3 D default Air Submersion Dose Conversion M 3 D RESRAD-Build FGR12 Factor, (mrem/y per pCi/m 3) default Inhalation Dose Conversion Factor, M D RESRAD-Build FGR1 1 (mrem/pCi) default Ingestionl Dose Conversion Factor, M D RESRAD-Build FGR1 1 (mrem/pCi) default Type P 3 D area NUREG/CR-5512 Direction P 3 D Z NUREG/CR-5512 Location of Center of Source: x,y,z (m) P 3 D 5.97, 13.23, 0 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 315.97 Site-Specific Modeling NUREG/CR-6697, Att.Air Fraction for H-3 B 2 D 1.0 C Section 8.6 Air Fraction (all nuclides other than H-3) B 2 D 0.07 NUREG/CR-6697, Att.____________________________

_______ _____________

C Section 8.6 _ __ ____Direct Ingestion (h-') B 2 D 1.2E-7 NUREG/CR6755, A.3.3 NUREG-1 727, Table Removable Fraction P 1 D 0.1 C.7.1; NUREG/CR-6755, section 3.5 NUREG/CR-6755, Time for Source Removal (d) P 2 Triangular NUREG/CR-6697, 1,000 100,00 10,000 Att.C, 8.8 Page 9 Bartlett Engineering.

Sensitivity Analyses to Support EF1 Building Surface DCGLs ENG-001 Rev. 2 Table 1 Input Parameter Values for Sensitivitv Analysis Treat- Value or Value/Distribution Parameter Typea Prioritybi mentc Distribution Reference Source Distribution's Statistical Parametersd

.1 2 .3 4 Radionuclide Concentration (pCi/m2) P 2 D 1.0 ---Type P 3 D Area NUREG/CR-5512 Direction P 3 D Y NUREG/CR-5512 Location of Center of Source: x,y,z (m) P 3 D 5.97, 26.47, 1.83 Site-Specific Modeling 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 43.67 Site-Specific Modeling Air Fraction for H-3 B 2 D 1.0 NUREG/CR-6697, Att.C, Section 8.6 NUREG/CR-6697, Att.Air Fraction (all nuclides other than H-3) B 2 D 0.07 C, Section 8.6 Direct Ingestion (h-1) B 2 D 1.2E-7 NUREG/CR6755, A.3.3 NUREG-1727, Table Removable Fraction P 1 D 0.1 C.7.1; NUREG/CR-6755, section 3.5 NUREG/CR-6755, Time for Source Removal (d) P Triangular Section 3.6; 1,000 100,000 10,000 NUREG/CR-6697, Att.C, 8.8 Radionuclide Concentration (pCi/m 2) P 2 D 1.0 Type P 3 D Area NUREG/CR-5512 Direction P 3 D X NUREG/CR-5512 Location of Center of Source: x,y,z (m) P 3 D 11.94, 13.23, 1.83 Site-Specific Modeling 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 96.81 Site-Specific Modeling Air Fraction for H-3 B 2 D 1.0 NUREG/CR-6697, Att.C Section 8.6 NUREG/CR-6697, Att.Air Fraction (all nuclides other than H-3) B 2 D 0.07 C Section 8.6 Direct Ingestion (h-1) B 2 D 1.2E-7 NUREG/CR6755, A.3.3 Page 10 Bartlett Engineering.

Sensitivity Analyses to Support EF1 Building Surface DCGLs ENG-001 Rev. 2 Table 1 Input Parameter Values for Sensitivity Analysis Treat- Value or Value/Distribution Parameter Type' Priorityb mentc Distribution Reference Source Distribution's Statistical Parametersd 1 2 3 4 NUREG-1727, Table Removable Fraction P 1 D 0.1 C.7.1; NUREG/CR-6755, section 3.5 NUREG/CR-6755, Section 3.6; 1,0 .1000 000 Time for Source Removal (d) P 2 S Triangular NUREGiCR-6697, 1,000 .100,000 10,000 Att.C, 8.8 Radionuclide Concentration (pCi/m 2) P 2 D 1.0 1 -Type P 3 D area NUREG/CR-5512 Direction P 3 D Y NUREG/CR-5512 Location of Center of Source: x,y,z,(m)

P 3 D 5.97, 0, 1.83 Site-Specific Modeling 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 43.67 Site-Specific Modeling NUREG/CR-6697, Att.Air Fraction for H-3 B 21.0 C Section 8.6 Air Fraction (all nuclides other than H-3) B 2 D 0.07 NUREG/CR-6697, Aft.C Section 8.6 Direct Ingestion (h-1) B 2 D 1.2E-7 NUREG/CR6755, A.3.3 NUREG-1727, Table Removable Fraction P 1 D 0.1 C.7.1; NUREG/CR-6755, section 3.5 NUREG/CR-6755, Time for Source Removal (d) P 2 5 Triangular Section 3.6; 1,000 100,000 10,000 NUREG/CR-6697, Att.C, 8.8 Radionuclide Concentration (pCi/m 2) P 2 D 1.0 --Type P 3 D area NUREG/CR-5512 Direction P 3 D X NUREG/CR-5512 Location of Center of Source: x,y,z (m) P 3 D 0, 13.23, 1.83 Site-Specific Modeling Source lengthY-axis (m) P 2 D 26.47 Site-Specific Modeling Source length Z-axis (m) P 2 D 3.66 Site-Specific Modeling Area (i 2) P -2 D 96.81 Site-Specific Modeling Page 11 Bartlett Engineering.

Sensitivity Analyses to Support EF1 Building Surface DCGLs ENG-001 Rev. 2 Table 1 Input Parameter Values for Sensitivity Analysis Treat- Value or Value/Distribution Parameter Type' Priorityb mentc Distribution Reference Source Distribution's Statistical Parametersd 1 2 3 4 Air Fraction for H-3 B 2 D 1.0 NUREG/CR-6697, Att.C Section 8.6 Air Fraction (all nuclides other than H-3) B 2 D 0.07 NUREG/CR-6697, Att.C Section 8.6 Direct Ingestion (h-1). B 2 D 1.2E-7 NUREG/CR6755, A.3.3 NUREG-1727, Table Removable Fraction P 1 D 0.1 C.7.1; NUREG/CR-6755, section 3.5 NUREG/CR-6755, Time for Source Removal (d) P 2 S Triangular Section 3.6; 1,000 100,000 10,000 NUREG/CR-6697, 100 10001,0 Att.C, 8.8 Radionuclide

'Concentration (pCi/m 2) P 2 D 1.0 Type P 3 D area NUREG/CR-5512 Direction P 3 D Z NUREG/CR-5512 Location of Center of Source: x,y,z (m) P, 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 (inM) P 2 D 315.97 Site-Specific Modeling Air Fraction for H-3 BD 1.0 NUREG/CR-6697, Att.C Section 8.6 NUREG/CR-6697, Att.Air Fraction (all nuclides other than H-3) B 2 D 0.07 C Section 8.6 _ _Att Direct Ingestion (h 1) B 2 D 1.2E-7 NUREG/CR6755, A.3.3 NUREG-1 727, Table Removable Fraction P 1 D 0.1 C.7.1; NUREG/CR-6755, section 3.5 NUREG/CR-6755, Time for Source Removal (d) P 2 S Triangular SectionR36, 1,000 100,000 10,000 NUREG/CR-6697, 100 10001,0_______) Att.C, 8.8 Radionuclide Concentration (pCi/2) 2 D 1.0 -Page 12 Bartlett Engineering.

ENG-001 Sensitivity Analyses to Support EF1 Building Surface DCGLs Rev. 2 Table 1 notes: a p = physical, B = behavioral, M = metabolic; (see NUREG/CR-6697, Attachment B, Table 4.)b 1 high-priority parameter, 2 = medium-priority parameter, 3 low-priority parameter (see NUREG/CR-6697, Attachment B, Table 4.1)c D = deterministic, S = stochastic d Distribution Statistical Parameters:

Loguniform:

1= minimum, 2 maximum Triangular:

1 = minimum, 2 = maximum, 3 = most likely e NR = none recommended Additional Sensitivity Analysis Data: Random Seed = 1000 Number of Observations

= 300 Number of repetitions

= 1 Input Rank Correlation Coefficients:

Resuspension Rate and Deposition Velocity =0.9 Time for source removal (correlation set between sources) = 0.9 Page 13 Bartlett Engineering.

Sensitivity Analyses to Support EF1 Building Surface DCGLs ENG-001 Rev. 2 Table 2: Representative Room Dimensions Source Recorded No. Description Dimension' ft mb m2 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 dimensions for east and south walls of b Feet to meter conversion factor: 1 ft = 0.3048m.representative room (see Figure 2).Table 3: 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 Page 14 Bartlett Engineering.

Sensitivity Analyses to Support EF1 Building Surface DCGLs ENG-001 Rev. 2 Table 4: Maximum Dose At Evaluation Times RESRAD-Build Maximum dose (mrem) at evaluation time: Nuclide File Name Oy ly loy 5 0y 1OOy 200y Ag-108m RESBMCAg108mSA 1.97E-05 1.95E-05 1.85E-05 1.65E-05 1.09E-05 6.05E-06 Am-241 RESBMC_Am241 SA 1.70E-04 1.57E-04 9.12E-05 7.21E-05 5.11E-05 1.71E-05 C-14 RESBMC_C14SA 5.96E-08 5.44E-08 5.19E-08 4.33E-08 3.27E-08 1.20E-08 Cm-242 RESBMC_Cm242 SA 3.04E-06 5.99E-07 2.64E-13 --- 0.OOE+00 ---Cm-243 RESBMC_Cm243 SA 1.18E-04 1.07E-04 5.14E-05 --- 3.85E-06 ---00-60 RESBMC_Co60 SA 5.18E-05 4.54E-05 ............

Cs-134 RESBMC_Cs134 SA 3.19E-05 2.28E-05 --- ---.....Cs-137 RESBMC_Cs137SA 1.42E-05 1.38E-05 1.12E-05 4.30E-06 1.31E-06 ---Eu-152 RESBMC_Eu152 SA 2.58E-05 2.45E-05 ---........

Eu-154 RESBMCEu154 SA 2.73E-05 2.52E-05 --- --- -Eu-155 RESBMCEu155SA 1.53E-06 1.33E-06 --- ---.....Fe-55 RESBMCFe55SA 1.37E-08 1.06E-08 1.01E-09 2.94E-14 5.93E-20 1.52E-31 H-3 RESBMC_H3SA 3.32E-09 2.97E-09 8.86E-10 7.88E-11 3.65E-12 4.98E-15 Mn-54 RESBMC Mn54 SA 1.32E-05 5.86E-06 3.99E-09 3.37E-23 ---Na22 RESBMC_Na22 SA 4.38E-05 3.35E-05 3.03E-06 6.97E-1 1 Nb-94 RESBMCNb94 SA 3.64E-05 3.62E-05 3.61 E-05 --- ---.. .Ni-59 RESBMCNi59SA 6.30E-09 5.71E-09 5.18E-09 4.34E-09 3.29E-09 1.19E-09 Ni-63 RESBMCNi63 SA 1.68E-08 1.50E-08 1.32E-08 8.27E-09 4.37E-09 7.68E-10 Pu-238 RESBMC_Pu238 SA 1.49E-04 1.36E-04 7.43E-05 4.56E-05 2.35E-05 4.11E-06 Pu-239 RESBMCPu239 SA 1.64E-04 1.53E-04 --- ---.....Pu-240 RESBMCPu240SA 1.64E-04 1.52E-04 8.92E-05 7.48E-05 5.69E-05 2.17E-05 Pu-241 RESBMC_Pu241 SA 3.01 E-06 2.92E-06 2.26E-06 2.38E-06 1.76E-06 6.06E-07 Sb-125 RESBMCSB125 SA 9.33E-06 7.26E-06 --- --- ---.Sr-90 RESBMCSr90 SA 4.36E-06 3.89E-06 3.03E-06 9.86E-07 ---Tc-99 RESBMC Tc99 SA 4.42E-08 4.OOE-08 3.78E-08 3.20E-08 ---* Dose at 30 years.Page 15 Bartlett Engineering.

Sensitivity Analyses to Support EF1 Building Surface DCGLs ENG-001 Rev. 2 Table 5: PRCC Values Radionuclide PRCC values in descendin rank order (RESRAD-Build output file name) RFOa (source #) UDb (source #) DKSUSc (source #)Ag-108m 0.82 (1) 0.61 (2) -0.77 (2, 4)(RESBMCAg108m SA) 0.69 (6) 0.59 (4) -0.53 (6)0.38 (5) 0.46 (6) -0.50 (1)0.35 (3) 0.45 (1) -0.46 (5)0.39 (5) -0.44 (3)0.34 (3)Am-241 -1.00 (1, 2, 3, 4, 5, 6) 0.49 (2, 3) -0.63 (3)(RESBMCAm241 SA) 0.46 (1) -0.62 (2)0.43 .(6) -0.59 (1)0.42 (4, 5) -0.58 (4, 6)-0.57.(5)C-14 0.53 (3) 0.43 (1,3,4, 5) -0.65 (4)(RESBMCC14 SA) 0.50 (2) 0.42(2,6)

-0.64 (1,2, 3, 5, 6)0.49 (5)0.48 (4,6)0.47(1)Co-60 0.73 (4) 0.54 (4) -0.55 (2, 4)(RESBMCCo60 SA) 0.72 (2, 5) 0.52 (2) -0.30 (5)0.70(1,3) 0.28(5). -0.20(3)0.43 (6) .0.21(3) -0.18 (6)0.15(6)Cm-242 -0.99 (1, 2, 5) -0.60 (2, 5) 0.55 (2)(RESBMCCm242 SA) -0.98 (3, 4, 6) -0.58 (1, 3, 6)" 0.54 (5)-0.56 (4) ,.0.52 (1,3)0.50 (6)0.49 (4)Cm-243 -1.00 ( 1,2, 3, 4, 5, 6) 0.36 (3) -0.40 (3)(RESBMCCm243 SA) 0.30(2, 5) -0.34 (5)0.25 (1) -0.30 (2)0.23 (6) -0.26 (1,4)0.22 (4) -0.25 (6)Cs-134 0.90 (2, 4) 0.41 (2, 4) -0.41 (4)(RESBMCCs-134 SA) 0.70 (3) 0.15 (3) -0.40 (2)0.69(5) 0.12(5) -0.17(3)0.51 (1) -0.11 (5)0.32 (6)Cs-137 0.85 (1) 0.54 (3) -0.58 (5)(RESBMCCs137 SA) 0.80 (6) 0.53 (5) --0.57 (3, 4)0.77 (3, 5) 0.52 (4) -0.54 (2)0.71 (2) 0.49 (2) -0.50 (6)0.69 (4) 0.47 (6) -0.49 (1)0.45(1)Eu-1 52 0.81 (6) 0.51 (4) -0.54 (4)(RESBMCEu152 SA) 0.67 (1) 0.42 (2) -0.51 (2)0.44 (5) 0.38 (6) -0.40 (6)0.43 (3) 0.26 (3, 5) -0.30 (5)0.25 (2) -0.26 (3)-0.13 (4) -0.11 (1)Page 16 Bartlett Engineering.

Sensitivity Analyses to Support EF1 Building Surface DCGLs ENG-001 Rev. 2 Table 5: PRCC Values Radionuclide PRCC values in descending rank order (RESRAD-Build output file name) RFOa (source #) UDb (source #) DKSUS' (source #)Eu-154 0.86 (6) 0.67 (4) -0.71 (4)(RESBMCEul 54 SA) 0.56 (3) 0.40 (6) -0.44 (2)0.52 (5) 0.39 (2) -0.40 (6)0.36 (1) 0.32 (5) -0.35 (5)-0.15(4) 0.24(3) -0.26(3)Eu-155 0.89 (1) 0.49 (5) -0.50 (5)(RESBMC_Eu155 SA) 0.70 (6) 0.39 (3) -0.40 (3)0.45 (3) 0.23 (6) -0.25 (6)0.44(5) 0.16(4) -0.15(1)-0.71 (2) 0.15(1,2)

-0.14(2,4)

-0.70 (4)Fe-55 0.98 (4) 0.59 (4, 6) -0.58 (4, 6)(RESBMC_Fe55 SA) 0.97 (1, 2, 6) 0.57 (2) -0.57 (2)0.91 (3, 5) 0.53 (1) -0.52 (1)0.40 (3) -0.39 (3)0.36 (5) -0.38 (5)H-3 -0.74 (5) 0.67 (1, 2) -0.73 (1,5)(RESBMCH3 SA) -0.71 (2) 0.66 (3, 4, 5) -0.72 (2, 3, 4)-0.70 (4, 6) 0.65 (6) -0.71 (6)-0.69 (1)-0.68 (3)Mn-54 0.93(5) 0.16(3) -0.16(2)(RESBMC_Mn54 SA) 0.92(1,3) 0.15 (2) -0.13 (5)0.78(6) 0.14(4) -0.12(3,4) 0.67(2) 0.12(5) -0.11 (6)0.60 (4)Na-22 0.80 (2) 0.46 (2) -0.44 (2)(RESBMC_Na22 SA) 0.77 (4) 0.38 (4) -0.37 (4)0.73(3) 0.18(3) -0.17(5)0.71 (5) 0.16(5) -0.16(3)0.66 (1)0.40 (6)Nb-94 0.52(1) 0.50(4) -0.76(4)(RESBMC_Nb94 SA) 0.27 (6) 0.48 (2) -0.73 (2)0.21 (5) 0.37 (5) -0.59 (5)0.18 (3) 0.35 (3) -0.57 (3)-0.43 (2) 0.25 (1) -0.37 (1)-0.49 (4) 0.24 (6) -0.34 (6)Ni-59 -0.72 (5) 0.48 (5) -0.74 (5)(RESBMCNi59 SA) -0.71 (4) 0.47 (1, 2, 3) -0.73 (2, 3, 4)i -0.70 (2) 0.46 (4) -0.72 (1)-0.69 (1, 6) 0.43 (6) -0.70 (6)-0.66 (3)Ni-63 -0.70 (2; 4) 0.65 (2, 4) -0.79 (4)(RESBMCNi63 SA) -0.69 (1) 0.64 (1) -0.78 (1,2)-0.67 (6) 0.62 (6) -0.77 (6)-0.66 (5) 0.56 (5) -0.70 (5)-0.59 (3) 0.53 (3) -0.69 (3)Page 17 Bartlett Engineering.

Sensitivity Analyses to Support EF1 Building Surface DCGLs ENG-001 Rev. 2 Table 5: PRCC Values Radionuclide PRCC values in descending rank order (RESRAD-Build output file name) RFOa (source #) UDb (source #) DKSUSc (source #)Pu-238 -0192(6) 0.17 (1, 2, 3, 4, 5, 6) -0.15 (1,2, 3, 4, 5, 6)(RESBMC_Pu238 SA) -0.91 (1)-0.58 (5)-0.57 (3)-0.41 (2)-0.26 (4)Pu-239 -1.00 (1, 2, 3, 4, 5, 6) 0.41 (2) -0.60 (2, 3)(RESBMC_Pu239 SA) 0.39 (3) -0.57 (5)0.37(1) -0.56(1)0.36 (5) -0.55 (4)0.34 (4) -0.54 (6)0.33 (6)Pu-240 -1.00 (1,2, 3, 4, 5, 6) 0.42 (2) -0.61 (2,3)(RESBMC_Pu240 SA) 0.41 (3) -0.57 (4, 5)0.37 (5) -0.55 (1,6)0.36(1,4)0.35 (6)Pu-241 -1.00 (1, 2, 3, 4, 5, 6) -0.37 (4) 0.38 (4)(RESBMC_Pu241 SA) -0.33 (1) 0.34 (1)-0.31 (6) 0.32 (6)-0.29 (5) 0.31 (2)-0.27 (2, 3) 0.28 (5)0.26 (3)Sb-125 0.88(1) 0.54(2) -0.52 (2)(RESBMCSb125 SA) 0.87 (5) 0.51 (4) -0.49 (4)0.86(2) 0.19 (3, 5, 6) -0.19(6)0.85 (3) -0.18 (3, 5)0.83 (4)0.76 (6)Sr-90 0.31 (2, 4, 6) 0.66 (3) -0.76 (3, 5)(RESBMCSr90 SA) 0.29 (3) 0.65 (5) -0.73 (2, 4, 6)0.28 (5) 0.63 (2, 4, 6) -0.71 (1)0.25(1) 0.60(1)Tc-99 0.41 (3) 0.47 (5) -0.72 (4, 5, 6)(RESBMCTc99 SA) 0.36 (5) 0.46 (3, 4, 6) -0.71 (3)0.34 (2, 6) 0.44 (1) -0.70 (1)0.33(1) 0.42(2) -0.69(2)0.26 (4)a RFO(#) = source removal time (for source number)b UD = deposition velocity c DKSUS = resuspension rate Page 18 Bartlett Engineering.

Sensitivity Analyses to Support EF1 Building Surface DCGLs ENG-001 Rev. 2 Table 6: 2 5 th and 7 5 th Percentile Values for Sensitive Parameters Note: The 2 5 th and 7 5 th percentile values are the same for a given number of observations.

Therefore, because 300 observations were used in the sensitivity analysis for each radionuclide, the 2 5 th and 7 5 th percentile values are the same for each radionuclide.

Percentile Value NUREG/CR-6697

[ref. 3.41 Distribution Parameter' 25th th 75th Minimum Median Maximum UD 1.51790E-05 8.52364E-05 4.78217E-04 2.7xl 0-6 8.5xl 0-5 2.7xl 0-3 DKSUS 6.70403 E- 10 1.79444E-08 4.87543E-07 2.8xl 0 1' 4.9xl0-8 1.4xl 0-5 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 b RFO(4) 1.82071E+04 3.30410E+04 5.27269E+04 1,000 10,000 100,000 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.b Most likely Value.Page 19 Bartlett Engineering.

Sensitivity Analyses to Support EF1 Building Surface DCGLs ENG-001 Rev. 2 Figure 1: Parameter Selection Process Input parameter value Complete sensitivity analysis Using RESRAD-Build 3.4 Classify parameter as"Sensitive" or "Non-sensitive" 1~"Sensitive" if IPRCCI > 0.1"Non-sensitive" if IPRCCI < 0.1 Assign site-specific value, median value or distribution 4'TEDE positively correlated to parameter if PRCC > 0+Assign site-specific value or distribution, or 75h percentile TEDE negatively correlated to parameter if PRCC < 0 iAssign site-specific value or distribution, or 25" percentile Input paramete~r value for DCGL Page 20 Input parameter value for DCGL Bartlett Engineering.

ENG-001 Sensitivity Analyses to Support EFI Building Surface DCGLs Rev. 2 Figure 2: Dimensions of EF1 Representative Room , /q 3 C 7;:&Lis 3eV ~" Page 21

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