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Remediation Work Plan 1110-PP-001 Rev. 0 Prepared for: Cardinal Health PET Cyclotron Facility St Louis, MO August 2016 Prepared by: 9111 Cross Park Drive, Suite D200 Knoxville, TN 37923 800.563.7497
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Page 1: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

Remediation Work Plan 1110-PP-001 Rev. 0

Prepared for:

Cardinal Health PET Cyclotron Facility St Louis, MO

August 2016

Prepared by:

9111 Cross Park Drive, Suite D200 Knoxville, TN 37923

800.563.7497

Page 2: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

1110-PP-001, Rev. 0 August 2016

Remediation Work Plan, Cardinal Health PET Cyclotron Facility, St Louis, MO

RECORD OF REVISIONS

Change Number

Date Description of Change Approval

0 9/12/16 Initial Distribution

APPROVALS Prepared By ________________________________________ ____9/12/16__ Tom Hansen III Date Approved By ________________________________________ ____9/12/2016_ Timothy Pratt Date Review and Approval ________________________________________ ______________ Cardinal Health Date

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Remediation Work Plan, Cardinal Health PET Cyclotron Facility, St Louis, MO

Table of Contents 1. PURPOSE ............................................................................................................................. 1

2. FACILITY OPERATING HISTORY ............................................................................................ 1

3. FACILITY DESCRIPTION ........................................................................................................ 2

4. RADIOLOGICAL STATUS OF FACILITY .................................................................................. 3

5. RELEASE CRITERION AND DOSE MODELING ....................................................................... 6 5.1. Structure DCGLs for Activated Areas ............................................................................. 6 5.2. Surface DCGLs for Non-Activated Areas ........................................................................ 8 6. PLANNED DECOMMISSIONING ACTIVITIES ......................................................................... 9 6.1. Characterization ............................................................................................................10 6.2. Remediation ..................................................................................................................13 6.3. Air Sampling and Concrete Dust Control .......................................................................13 6.4. Survey and Removal of Clean Concrete Debris .............................................................14

7. PROJECT MANAGEMENT AND ORGANIZATION ................................................................ 14 7.1. Project Manager (PM) ...................................................................................................14 7.2. Field Personnel .............................................................................................................15 7.3. Coordination of Efforts ...................................................................................................16 8. HEALTH AND SAFETY PROGRAM DURING DECOMMISSIONING ...................................... 16

9. SURVEY INSTRUMENTATION ............................................................................................ 17 9.1. Instrument Calibration ...................................................................................................17 9.2. Daily Response Checks ................................................................................................17 9.3. Determination of Counting Times and Minimum Detectable Concentrations ..................17 9.3.1. Static Counting ....................................................................................................17 9.3.2. Ratemeter Scanning ............................................................................................18 9.3.3. Gamma Scans .....................................................................................................18 9.3.4. Removable Contamination Measurement Counting .............................................21 9.4. Counting Uncertainty .....................................................................................................21 9.5. Instrumentation Specifications .......................................................................................22 9.6. Background Determination ............................................................................................23

10. RADIOACTIVE WASTE MANAGEMENT PROGRAM ............................................................ 23 10.1. Waste Characterization .................................................................................................23 10.2. Waste Shipment ............................................................................................................23 11. QUALITY ASSURANCE PROGRAM...................................................................................... 23

12. FACILITY RADIATION SURVEYS .......................................................................................... 25 12.1. Data Quality Objectives .................................................................................................25 12.2. Area Classification .........................................................................................................26 12.3. Survey Unit Identification ...............................................................................................27 12.4. Surface Scans ...............................................................................................................28 12.5. Determining the Number of Sample Locations ...............................................................28 12.5.1. Number of Gross Beta/Gamma Total Surface Activity Measurements .................29 12.5.2. Number of Volumetric NaI Measurement Locations .............................................29 12.6. Determination of Sampling Locations ............................................................................30 12.7. Total Surface Activity Measurements ............................................................................31 12.8. Gamma Radiation Measurements .................................................................................31 12.9. Removable Contamination Measurements ....................................................................32 12.10. Volumetric Core Samples ..............................................................................................32 12.11. Survey Investigation Levels for Non-Activated Surfaces ................................................32 12.12. Survey Investigation Levels for Potentially Activated Structures ....................................32

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Remediation Work Plan, Cardinal Health PET Cyclotron Facility, St Louis, MO

12.13. Survey Documentation ..................................................................................................33 12.14. Data Validation ..............................................................................................................33

13. EVALUATING SURVEY RESULTS ......................................................................................... 34

14. FINAL REPORT ................................................................................................................... 34

15. REFERENCES ...................................................................................................................... 35

Attachments Attachment 1: Laboratory Sample Analysis Reports for Cyclotron Room Characterization Attachment 2: RESRAD-BUILD DCGLactivation Modeling for Radionuclides of Concern Attachment 3: RESRAD-BUILD DCGLsurface Modeling for Radionuclides of Concern Attachment 4: MicroShield MDC Model Abbreviations and Acronyms ALARA As Low As Reasonably Achievable Ameriphysics Ameriphysics, LLC CFR Code of Federal Regulations cpm counts per minute DAC Derived Air Concentration DCGL Derived Concentration Guideline Level dpm disintegration per minute DQO Data Quality Objective ICRP International Commission on Radiological Protection LBGR Lower Bound of the Gray Region MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDC Minimum Detectable Concentration MO DOH Missouri Department of Health NaI Sodium Iodide NIST National Institute of Standards and Technology NRC Nuclear Regulatory Commission PET Positron Emission Tomography QAPP Quality Assurance Project Plan TEDE Total Effective Dose Equivalent

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1. PURPOSE The purpose of this Remediation Work Plan (Plan) is to provide the concise work instructions necessary to decommission the Cardinal Health PET Manufacturing Facility located at 10718 Trenton Avenue, St Louis, MO. Cardinal Health has contracted Ameriphysics, LLC (Ameriphysics) via Rowe Transfer Inc. to perform the decommissioning and survey activities described in this Plan. All work will be accomplished using Ameriphysics’ Nuclear Regulatory Commission (NRC) radioactive material license. Activities necessary to accomplish decommissioning include radiological characterization, remediation where residual volumetric contamination exceeds release criterion, transportation of resultant wastes for disposal, and final status surveying to demonstrate compliance with the NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “Consolidated NMSS Decommissioning Guidance” and NUREG-1575, “Multi-Agency Radiation Survey and Site Investigation Manual” (MARSSIM), and provides the approach, methods, and techniques for the radiological decommissioning of the facility. These methods ensure technically defensible data are generated to aid in determining compliance with the release criterion for unrestricted use specified in 10 CFR 20 Subpart E, Section 20.1402, Radiological criteria for unrestricted use. 2. FACILITY OPERATING HISTORY The Cardinal Health PET Manufacturing facility on Trenton Avenue is currently licensed by the NRC for possession and storage of radioactive materials with the intent to decommission. The current license amendment was issued on January 14, 2016. The facility was previously licensed under the same Radioactive Materials License number for the production, packaging, and distribution of manufactured radiopharmaceuticals and for possession and storage of radioactive materials incident to the manufacture of radiopharmaceuticals by use of a cyclotron. This facility was opened by Syncor Advanced Isotopes in 2001 and the site was registered with the Missouri Department of Health (MO DOH) for accelerator-produced materials under registration IRM-141. Following Cardinal Health’s acquisition of Syncor, the MO DOH updated this registration with the Cardinal Health name. Cardinal Health then applied for a Radioactive Materials License with the NRC in 2011 as a result of the NRC implementing jurisdiction over accelerator-produced materials under the Energy Policy Act of 2005. This license was granted on December 27, 2011 under the current license number. The cyclotron at this facility is a General Electric PETtrace 8, which primarily produced F-18 to be used in radiopharmaceuticals for Positron Emission Tomography (PET) scans. The cyclotron typically operated at an energy of 16.5 MeV. The cyclotron is encased in a concrete vault which shielded the machine in all six primary directions.

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This cyclotron primarily used O-18 as its target material, generating F-18 and neutrons through a (p,n) reaction; these neutrons create the potential for activation of the surrounding materials, primarily the cyclotron vault and the cyclotron itself. The cyclotron and components were shipped to Michigan State University on 8/24/2016. All remaining wastes were shipped for processing and disposal on 9/7/2016. 3. FACILITY DESCRIPTION The site is located in an industrial park at 10718 Trenton Ave., St Louis, MO. Figure 3-1 provides a satellite view of the Cardinal Health PET Manufacturing facility location. The footprint of the facility is outlined in blue. The map was obtained online from Google maps. Figure 3-2 provides the floor plan of the facility with the Restricted Area outlined with bold lines.

Figure 3-1– Location of Cardinal Health PET Manufacturing Facility

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Figure 3-2– Layout of the Cardinal Health St louis, MO Facility

4. RADIOLOGICAL STATUS OF FACILITY The site produced F-18 as a result of normal operations. This radionuclide has a very short half-life (110 minutes), and since the site has not operated since August 14, 2015, any residual F-18 has decayed. The reaction that produces F-18, 18O(p,n)18F, also produces neutrons that can cause building materials in the cyclotron room to become activated, primarily concrete and steel. The cool down period has allowed very short-lived radionuclides to decay; however, the radionuclides in Table 4-1 may be present in the floor, wall, and ceiling of the cyclotron vault.

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Since the PETtrace cyclotron was shielded by a concrete vault, there is very little likelihood that any other surfaces in the facility have been activated. The concentration varies according to proximity to the beam and interferences that cause losses.

Table 4-1: Potential Radiological Contaminants

Atomic Number Element Radionuclide(s)

3 Tritium 3H

11 Sodium 22Na

21 Scandium 46Sc

24 Chromium 51Cr

25 Manganese 54Mn

26 Iron 55Fe, 59Fe

27 Cobalt 56Co, 57Co, 58Co, 60Co

30 Zinc 65Zn

41 Niobium 95Nb

47 Silver 108mAg, 110mAg

48 Cadmium 109Cd

51 Antimony 124Sb

55 Cesium 134Cs

63 Europium 152Eu, 154Eu, 155Eu

Radionuclides of concern from Table 4-1 and certain properties of their decay from ICRP Publication 107, “Nuclear Decay Data for Dosimetric Calculations”, are presented in Table 4-2.

Table 4-2: Radionuclides of Concern and Properties of Decay

Nuclide Half-Life1 Daughter

Decay Mode2 Fraction

Energy Emitted (MeV/transformation)

Alpha Electron Photon Total

H-3 12.32 y

He-3 B-

1.00 - 0.005 - 0.0057

Na-22 2.6019 y

22Ne EC, B+ 1.00

- 0.1941 2.1926 2.3866

Sc-46 83.79 d

46Ti B-

1.00 - 0.1121 2.0096 2.1217

Cr-51 27.7025 d

51V EC

1.00 - 0.0038 0.0329 0.0367

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Nuclide Half-Life1 Daughter

Decay Mode2 Fraction

Energy Emitted (MeV/transformation)

Alpha Electron Photon Total

Mn-54 313.12 d

54Cr 54Fe

EC, B+, B- 1.00

2.90E-06 - 0.0042 0.8360 0.8402

Fe-55 2.737 y Mn-55

EC 1.00

0.0042 0.0017 0.0058

Fe-59 44.495 d

59Co B-

1.00 - 0.1179 1.1883 1.3062

Co-56 77.23 d

56Fe EC, B+ 1.00

- 0.1198 3.6404 3.7602

Co-57 271.74 d

57Fe EC

1.00 - 0.0186 0.1252 0.1439

Co-58 70.86 d

58Fe EC, B+ 1.00

- 0.0340 0.9749 1.0089

Co-60 05.2713 y

60Ni B-

1.00 - 0.0969 2.5038 2.6007

Zn-65 244.06 d

65Cu EC, B+ 1.00

- 0.0069 0.5819 0.5888

Nb-95 34.991 d

95Mo B-

1.00 - 0.0446 0.7645 0.8091

Ag-108m 418 y 108Ag 108Pd

EC, IT 8.70E-02 9.13E-01

- 0.0159 1.6209 1.6368

Ag-110m 249.76 d

110Ag 110Cd

B-, IT 1.36E-02 9.86E-01

- 0.0758 2.7606 2.8363

Cd-109 461.4 d

109Ag EC

1.00 - 0.0827 0.0265 0.1092

Sb-124 60.20 d

124Te B-

1.00 - 0.3831 1.8531 2.2362

Cs-134 2.0648 y

134Ba 134Xe

B-, EC 1.00

3.00E-06 - 0.1639 1.5551 1.7190

Eu-152 13.537 y

152Gd 152Sm

EC, B+, B- 2.79E-01 7.21E-01

- 0.1286 1.1759 1.3045

Eu-154 8.593 y

154Gd 154Sm

B-, EC 9.998E-01 2.000E-04

- 0.2730 1.2493 1.5223

Eu-155 4.7611 y

155Gd B-

1.00 - 0.0647 0.0612 0.1259

1 Key to half-life: d is days and y is years 2 Key to decay mode: B- is beta minus, B+ is beta plus, EC is electron capture

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All daughter nuclides are stable, with the exception of Ag-108, Ag-110 and Gd-152. Activity contributions from these daughters are considered negligible as Ag-108 is formed by isomeric transition in only 8.7% of Ag-108m transformations, Ag-110 is formed by isomeric transition in only 1.36% of Ag-110m transformations, and Gd-152 has a very long half-life, 1.08E+14 years. Radiation emitted is beta and gamma; however, it is important to consider that atoms undergoing decay are trapped within the volume of the materials and surfaces. According to the Radiological Health Handbook, the maximum range of a 1 MeV beta particle is less than 1/10th of an inch in lead, copper, iron, aluminum, and concrete. At 0.1 MeV, the maximum range is less than 1/100th of an inch. Unlike betas and other charged particles that exhibit finite ranges, gammas cannot be completely attenuated. Rather, the intensity of the radiation is reduced by increasingly thicker absorbers. Consequently, gamma radiation is the radiation of concern except in instances where surface contamination is a concern. 5. RELEASE CRITERION AND DOSE MODELING Radiological requirements for license termination are described Title 10 of the Code of Federal Regulations, Part 20, Subpart E, Radiological Criteria for License Termination, which states that a site will be considered acceptable for unrestricted release if the residual radioactivity that is distinguishable from background radiation results in a total effective dose equivalent (TEDE) to an average member of the critical group that does not exceed 25 millirem per year (mrem/y), and the residual radioactivity has been reduced to levels that are as low as reasonably achievable (ALARA). The release criterion is dose-based and cannot be measured directly. Consequently, MARSSIM uses the term derived concentration guideline value (DCGL) to describe radionuclide-specific surface or volume residual radioactivity levels that corresponds to the release criterion. This project requires DCGLs for volumetrically activated structures (DCGLactivation) and non-activated surfaces that could have been potentially surface contaminated by the transfer of contamination from materials moved and stored in these areas (DCGLsurface). Dose modeling software, RESRAD-BUILD (Argonne National Laboratory), V3.50, October 30, 2009, was used to establish DCGLs in both instances. 5.1. Structure DCGLs for Activated Areas The RESRAD-BUILD code was run using the code’s default parameters to determine the maximum dose in mrem per year to an individual from 1 pCi/g of each of the listed nuclides distributed volumetrically throughout a material. Values for DCGLactivation were determined by dividing the release criterion, 25 mrem/yr, by the code’s outputs. The RESRAD-BUILD output reports are included in Attachment 2. The dose per pCi/g values returned by the code and the corresponding DCGLactivation are provided in Table 5-1.

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Table 5-1: DCGLactivation for Concrete Structures

Radionuclide mrem/yr

pCi/g DCGL (pCi/g)

Ag-108m 3.06E+00 8.17E+00

Ag-110m 3.38E+00 7.40E+00

Cd-109 3.14E-03 7.96E+03

Co-56 1.23E+00 2.03E+01

Co-57 9.51E-02 2.63E+02

Co-58 1.72E-02 1.45E+03

Co-60 4.62E+00 5.41E+00

Cr-51 6.11E-03 4.09E+03

Cs-134 2.54E+00 9.84E+00

Eu-152 2.12E+00 1.18E+01

Eu-154 2.28E+00 1.10E+01

Eu-155 4.53E-02 5.52E+02

Fe-55 1.16E-08 2.15E+09

Fe-59 9.26E-03 2.70E+03

H-3 9.67E-03 2.59E+03

Mn-54 1.11E+00 2.25E+01

Na-22 3.76E+00 6.65E+00

Nb-95 1.10E-01 2.27E+02

Sb-124 4.13E-03 6.05E+03

Sc-46 1.46E-08 1.71E+09

Zn-65 7.12E-01 3.51E+01

Note that the “sum of fractions” rule applies. The instruments used for surface scans will not be able to discriminate between radionuclides; therefore, a gross activation DCGL (DCGLgross) is determined using the MARSSIM Equation 4-4:

n

ngross

DCGL

f

DCGL

f

DCGL

fDCGL

2

2

1

1

1

To determine DCGLgross, the data from characterization-sample location "Cyclotron Vault Floor (0-6 inch)" in section 6.1 was used to determine the activity fraction (fn). The activity contribution from each radionuclide was summed, and the activity fraction that each radionuclide contributes to the total activity was determined. The results were input into the following table, and MARSSIM Equation 4-4 was used to calculate the DCGLgross.

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Table 5-2: Volumetric DCGLgross Determination

Radionuclide Fraction of Total

(fn) DCGL (pCi/g)

Activity Fraction

(fn/DCGL)

Co-60 23.2% 5.41E+00 4.29E-02

Cs-134 2.8% 9.84E+00 2.88E-03

Eu-152 63.0% 1.18E+01 5.35E-02

Eu-154 6.4% 1.10E+01 5.87E-03

Mn-54 1.8% 2.25E+01 8.16E-04

Sc-46 1.2% 1.71E+09 6.75E-12

Zn-65 1.5% 3.51E+01 4.28E-04

Σfn/DCGL 1.06E-01

DCGLgross in pCi/g (1/Σfn/DCGL) 9.41E+00

Note that DCGLgross is applied only when making gross measurements. In instances where radionuclide-specific measurements are performed to demonstrate compliance with the release criterion, results will be compared against the radionuclide-specific DCGLs indicated in column 3 of Table 5-1. Sum of fractions will be observed, and the combined results may not exceed unity., Small localized hotspots that exceed the DCGL could still result in the survey unit, as a whole, meeting the release criterion. This would require the use of the elevated measurement comparison methodology discussed in MARSSIM sections 8.5.1 and 8.5.2. 5.2. Surface DCGLs for Non-Activated Areas The RESRAD-BUILD code was run using default parameters to determine surface DCGLs corresponding to the 25 mrem/yr year limit. The output reports are provided in Attachment 3 of this Plan. These surface DCGLs correspond to total contamination (fixed and removable). The default model assumes that 10% of the contamination is removable; consequently, a removable activity limit equal to 10% of the surface DCGL is implemented to confirm this important assumption. Table 5-3 shows the radionuclide specific surface DCGLs for this project.

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Table 5-3: DCGLsurface for Nuclides of Concern at 25 mrem/yr

Radionuclide DCGL

(dpm/100cm2)

Removable Activity Limit

(dpm/100cm2)

Ag-108m 2.8E+04 2.8E+03

Ag-110m 3.0E+04 3.0E+03

Cd-109 5.2E+05 5.2E+04

Co-56 7.4E+04 7.4E+03

Co-57 6.6E+05 6.6E+04

Co-58 2.0E+06 2.0E+05

Co-60 2.1E+04 2.1E+03

Cr-51 1.3E+07 1.3E+06

Cs-134 3.6E+04 3.6E+03

Eu-152 4.0E+04 4.0E+03

Eu-154 3.7E+04 3.7E+03

Eu-155 5.7E+05 5.7E+04

Fe-55 2.0E+07 2.0E+06

Fe-59 3.0E+06 3.0E+05

H-3 2.4E+08 2.4E+07

Mn-54 9.1E+04 9.1E+03

Na-22 2.7E+04 2.7E+03

Nb-95 6.8E+05 6.8E+04

Sb-124 1.7E+06 1.7E+05

Sc-46 1.6E+07 1.6E+06

Zn-65 1.4E+05 1.4E+04

The field instruments used to collect survey data are not equipped to distinguish between radionuclides. The measurements are analyzed for gross beta/gamma only. Therefore, measurements of surface activity are evaluated against the most limiting surface DCGL which is Co-60 at 21,000 dpm/100cm2 total activity. The removable activity measurements will be evaluated against 10% of the surface activity limit (i.e., 2,100 dpm/100cm2). 6. PLANNED DECOMMISSIONING ACTIVITIES This section describes the work activities that are necessary to accomplish decommissioning. Because all work will be conducted by Ameriphysics in accordance with Ameriphysics’ Radiological Control Procedure Manual, a detailed discussion of these activities is not provided unless otherwise specified.

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6.1. Characterization The extent to which the cyclotron room is impacted by long-lived radionuclides is typically evaluated following cyclotron removal. To aid in development of remediation planning and development of this Plan, a shielded 2-inch x 2-inch (2” x 2”) sodium iodide (NaI) detector was used to assess the site prior to removal of the cyclotron. Core samples were also performed to access the radionuclides of concern and the depth of activation in the concrete vault structure. A NaI background value of 3,527 cpm was determined by calculating the average of several one-minute static measurements from concrete surfaces outside of the cyclotron vault. A NaI scan survey was then performed inside the vault. It was immediately evident during the scan survey that the cyclotron and other components remaining in the room were significantly affecting background. However, the walls and floor nearest the cyclotron target assembly exhibited significantly higher count rates. So characterization was limited but somewhat possible using the NaI detector. Following NaI scan surveys, NaI detector one-minute static measurements were performed at multiple locations. The results of the one-minute NaI readings are provided in Figure 6-1.

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Figure 6-1: Radiological Investigation Areas

Core sampling was performed at five locations. These locations were chosen based on the NaI results and accessibility. The south wall was inaccessible so it was not sampled. The samples were analyzed off site via gamma spectroscopy by GEL Laboratories in Charleston, SC. The laboratory results are attached in their entirety in Attachment 1 and are summarized in

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Table 6-1.

Table 6-1: Summary of Cyclotron Room Sample Results

Nuclide

Sample Results (pCi/g)

Cyclotron Vault

Floor (0-6 inch)

Cyclotron Vault

Floor (6-15 inch)

Cyclotron Vault East Wall (0-6

inch)

Cyclotron Vault

West Wall (0-6 inch)

Cyclotron Vault

North Wall (0-6 inch)

Cyclotron Vault

Hallway (0-9 inch)

Antimony-124 ND ND ND ND ND ND

Cadmium-109 ND ND ND ND ND ND

Cesium-134 1.94 0.415 1.60 0.594 1.36 0.668

Chromium-51 ND ND ND ND ND ND

Cobalt-56 ND ND ND ND ND ND

Cobalt-57 ND ND ND ND ND ND

Cobalt-58 ND ND ND ND ND ND

Cobalt-60 15.9 3.93 9.95 4.26 7.94 3.93

Europium-152 43.2 11.6 26.4 11.2 24.0 13.7

Europium-154 4.41 0.959 3.43 1.16 2.52 1.31

Europium-155 ND ND ND ND ND ND

Iron-59 ND ND ND ND ND ND

Manganese-54 1.26 ND 2.44 ND 1.29 0.294

Niobium-95 ND ND ND ND ND ND

Scandium-46 0.792 0.249 0.673 0.294 0.564 0.258

Silver-108m ND ND ND ND ND ND

Silver-110m ND ND ND ND ND ND

Sodium-22 ND ND ND ND ND ND

Zinc-65 1.03 ND 2.25 1.04 2.19 0.851

Total Activity: 68.5 17.2 46.7 18.6 39.9 21.0

ND = Not Detected Following the characterization activities, additional information was located which indicated that additional radionuclides of concern (H-3 and Fe-55) were likely to be present at relatively low concentrations compared to their DCGLs. Following the removal of the cyclotron, additional samples were collected for H-3 and Fe-55 analysis. The analytical results did indicate the presence of these radionuclides. Tritium was detected up to 80.1 pCi/g and Fe-55 up to 358 pCi/g.

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6.2. Remediation Based on the characterization described in the previous section and Ameriphysics’ experience on similar projects, remediation is expected to be limited to approximately two feet of concrete and steel of the inner vault areas. Remediation of the vault will be performed using a hydraulic excavator with a hammer attachment and various handheld tools (e.g., chipping hammers, reciprocating saws, etc.). No decontamination of any other areas outside the vault is anticipated. Although the concrete within the vault is expected to be activated to a depth of approximately two feet, the entire vault will be removed as part of the project. An opening will be made on the north side of the building to allow access to the vault’s exterior north wall. Temporary doors will be installed at the opening to control access to the restricted area. Using the excavator, demolition of the vault will begin with the exterior of the north wall. This wall is approximately 5.5 feet thick. Since the wall is expected to be activated on the interior 2 feet, most of the concrete rubble created initially is expected to be clean (non-activated). This rubble/debris will be segregated and surveyed for free release (See section 6.4). Once the concrete is removed to the point of activation, all rubble will be managed as radioactive waste. Following the removal of the north wall, the opening will allow access to the interior of the vault. The interior walls and ceiling surfaces will be remediated until the activated concrete has been removed. The remaining wall and ceiling surfaces will be demolished and the rubble/debris will be surveyed for free release. After removal of the walls and ceiling, the activated floor concrete will be remediated. A final status survey of the remaining floor surfaces will be performed as described in Section 12. Because of the relatively small footprint of the facility, space is very limited for the demolition activities. Enclosures (e.g., temporary containment tents with HEPA filtration units) will be utilized, as necessary, to ensure that contamination is controlled and no releases to the public occur. 6.3. Air Sampling and Concrete Dust Control Air sampling will be performed during potential airborne radioactivity producing activities (i.e., activated concrete demolition). The sampling will include breathing zone, general area, and effluent sampling, as appropriate. If air samples indicate the presence of airborne radioactivity above 1 Derived Air Concentration (DAC) within the work area, work will be stopped and additional radiological controls will be implemented (e.g., additional misting, slower demolition, additional HEPA ventilation).

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If necessary, a temporary containment tent with local HEPA filtration will be constructed adjacent to the cyclotron vault on the exterior of the building to extend the work area. All radiological remediation operations will be performed within the building or within containment areas (other than final waste package loading on the transport vehicle). Misting and/or air filtration will be used to control dusts as necessary. Continuous air sampling will be performed outside the restricted area for effluent monitoring. These samples will be evaluated against the most restrictive radionuclide of concern (Eu-154 effluent limit = 3E-11 µCi/ml). 6.4. Survey and Removal of Clean Concrete Debris Clean concrete debris will be generated as a result of vault decommissioning activities. The concrete debris will be scan surveyed using a pancake GM detector and a 2” x 2” NaI detector using the typical operating parameters identified in Table 9-3. If no activity exceeding minimum detectable concentrations (MDC) from Table 9-3 is detected, the material will be placed in a segregated roll-off container for disposal/recycle as clean material. Removable contamination measurements will be performed during the process and analyzed using a Ludlum 3030E (or equivalent) dual alpha/beta wipe sample counter. The surveys will be documented and reviewed prior to release of the debris for disposal/recycle.

7. PROJECT MANAGEMENT AND ORGANIZATION The specific responsibilities and authority of management, safety and health, and other personnel on this site are detailed in the following paragraphs. One person may fill more than one role. 7.1. Project Manager (PM) The PM has responsibility and authority to direct all work operations. The PM coordinates safety and health functions, has the authority to oversee and monitor the performance of the Plan, and bears ultimate responsibility for the proper implementation of this Plan. The specific duties of the PM are:

• Managing the project and overseeing the technical and programmatic activities of the health and safety program;

• Ensuring that adequate health and safety systems (policies, plans, procedures, materials, etc.) are in place and operational;

• Assigning sufficient resources to maintain and implement the health and safety program;

• Ensuring effective emergency response;

• Serving as primary site liaison with public agencies and officials and site contractors;

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• Managing the safety and health functions on this site;

• Serving as the site’s point of contact for safety and health matters;

• Ensuring site monitoring, worker training, medical surveillance, and effective selection and use of personal protective equipment (PPE);

• Ensure the correct field execution of the Plan;

• Assessing site conditions for unsafe acts and conditions and providing corrective action;

• Maintaining effective safety and health records as described in this Plan; and

• Coordinating with the emergency response personnel and others as necessary for safety and health efforts.

7.2. Field Personnel Field personnel are responsible for complying with this Plan and other written work documents, using the proper PPE, reporting unsafe acts and conditions, and following the lines of authority established for this project site. Other, general responsibilities of all project personnel include:

• Maintaining complete, factual, detailed, and objective records;

• Safeguarding record materials, including, but not limited to, field notebooks, raw data sheets, and chain-of-custody forms;

• Taking all reasonable precautions to prevent injury to themselves and to their fellow employees;

• Being alert to potentially harmful situations;

• Performing only those tasks that they believe they can do safely and immediately reporting any accidents and/or unsafe conditions to the PM;

• Notifying the PM of any special medical conditions (i.e., allergies, contact lenses, diabetes, and medication use);

• Preventing spillage to the extent possible, and in the event spillage occurs, containing the spillage and notifying the PM (note: field personnel should not engage in spill containment or cleanup if conditions are not safe and if the cleanup cannot be accomplished with supplies available at the site);

• Avoiding splashing materials to the extent possible;

• Practicing good housekeeping by keeping the work area neat, clean, and orderly to the extent possible;

• Reporting all injuries - no matter how minor; and

• Ensuring that proper waste management procedures are followed.

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7.3. Coordination of Efforts The other contractors and subcontractors on this site who could be affected by the tasks and operations associated with the Plan are listed in Table 7-1 below.

Table 7-1: Other Site Contractors and Subcontractors

Company Function

Cardinal Health Client/Site Lessee

Rowe Transfer Prime Contractor

Ameriphysics Sub-Contractor to Rowe Transfer

All work shall be performed by Ameriphysics and Rowe Transfer, as contractors of Cardinal Health, under Ameriphysics’ radioactive material license. The following organizations will be participating to accomplish the work:

• Cardinal Health leases the facility and has contracted Ameriphysics via Rowe Transfer to perform the activities described in this Plan; therefore, Cardinal Health is responsible for ensuring that Ameriphysics fulfills the portion of the work for which they have been contracted. Cardinal Health is responsible for providing site access, removing interferences, identification and marking of utilities, and backfill/restoration.

• Rowe Transfer is the prime contractor that teams with Ameriphysics and is responsible for the cyclotron removal, packaging and loading activities associated with the project.

• Ameriphysics is responsible for collecting the data necessary to support a decision regarding the radiological condition of the facility. Ameriphysics’ PM shall be the person directly responsible for all onsite operations related to the project.

• The NRC is the organization responsible for providing the regulatory authority necessary to perform the work and release the facility. The NRC will provide regulatory oversight, as they determine appropriate, in various areas including health physics, quality assurance, and industrial health and safety. The NCR is responsible for reviewing the data presented by Ameriphysics and making the final decision regarding disposition of the site.

8. HEALTH AND SAFETY PROGRAM DURING DECOMMISSIONING Ameriphysics maintains a comprehensive health and safety program, and specific individual programs, that have been developed to assure compliance with federal, state, and local regulations.

Ameriphysics' Health and Safety Manual will be followed by all who are working under Ameriphysics' license for the duration of the project.

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9. SURVEY INSTRUMENTATION Based on potential contaminants, their associated radiations, and the types of residual contamination categories to be evaluated, the detection sensitivities of various instruments and techniques were evaluated for use. Instruments are evaluated for use during surface scans, direct measurements, and analysis of removable contamination wipes. 9.1. Instrument Calibration Laboratory and portable field instruments are calibrated at least annually with National Institute of Standards and Technology (NIST) traceable sources and to radiation emission types and energies that provide detection capabilities similar to the nuclides of concern. 9.2. Daily Response Checks For radiological instruments operated by Ameriphysics, a reference source is measured prior to use each day. The result is accurate if it falls within ±20% of originally determined values. This is consistent with the guidance in Section 6.5.4 of MARSSIM, Instrument Calibration. Background readings are taken as part of the daily response checks and compared with the acceptance range for instrument and site conditions determined during instrument set up in accordance with Ameriphysics Survey Instrument Procedure, RCP 4-3. If an instrument fails a response check, all data obtained with the instrument since the last satisfactory check is invalidated. 9.3. Determination of Counting Times and Minimum Detectable Concentrations Minimum counting times for background determinations and counting times for measurement of total and removable contamination are chosen to provide MDCs that meet the Data Quality Objectives (DQOs) specified in this Plan. MARSSIM equations relative to building surfaces are modified to convert to units of dpm/100 cm2. Count times and scanning rates are determined using the equations in the following sections. 9.3.1. Static Counting Static counting MDC at a 95% confidence level is calculated using the following equation, which is an expansion of NUREG-1507, “Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions”, Table 3.1 (Strom & Stansbury, 1992):

2100

)1(29.33

cm

AET

T

TTR

MDC

totalBS

B

BSBSB

static

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Where: MDCstatic = minimum detectable concentration level in dpm/100cm2 RB = background count rate in counts per minute (cpm) TS+B = sample count time in minutes TB = background count time in minutes Etotal = total detector efficiency for radionuclide emission of interest

(includes combination of the 2π instrument efficiency and surface efficiency)1

A = detector area in cm2 1. Surface efficiency applied will be in accordance with the recommended value of 0.25 for beta emitters <400keV

EMAX.

9.3.2. Ratemeter Scanning Scanning MDC at a 95% confidence level is calculated using the following equation which is a combination of MARSSIM equations 6-8, 6-9, and 6-10:

2100

60'

cm

AEp

ibd

MDC

tot

i

scan

Where: MDCscan = minimum detectable concentration level in dpm/100 cm2 d’ = desired performance variable (1.38) bi = background counts during the residence interval i = residence interval p = surveyor efficiency (0.5) Etot = total detector efficiency for radionuclide emission of interest

(includes combination of the instrument 2π efficiency and surface efficiency1)

A = detector probe area in cm2

1. Surface efficiency applied will be in accordance with the recommended value of 0.25 for beta emitters <400 keV EMAX.

9.3.3. Gamma Scans Surface scans are conducted with a shielded 2” x 2” NaI detector for each potentially volumetrically activated survey unit. The scan survey coverage requirements are discussed further in Section 12.4. Gamma scans will be conducted with a Ludlum 2221 survey instrument coupled to a Ludlum 44-10 NaI detector, or equivalent.

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The MDC for scans used to evaluate volumetric activity against the DCGLs is determined using the approach presented in Section 6 of NUREG-1507, “Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions”. Using this approach, the relationship between the surveyor minimum detectable count rate (MDCsurveyor) and the radionuclide concentration is determined in two steps. First, the relationship between the radionuclide concentration and exposure rate is determined; second, the relationship between the detector’s net count rate to net exposure rate (cpm per μR/h) is established. The method requires modeling (using MicroShield) of a small area of elevated activity as a cylindrical volume to determine the net exposure rate. The measurements will be taken at the average height of the NaI scintillation detector above the source during scanning. A model that conservatively estimates MDCsurveyor was developed. The following input parameters were used:

Areal dimension of the cylindrical hot spot: 0.25 m2 (radius of 28 cm) Depth of hot spot: 15 cm Dose point: 10 cm above surface Density of hot spot: 2.35 g/cm3

Note that this model reflects the exact conditions of the methodology presented in NUREG-1507, with the exception of density. In this instance, the MicroShield default density for concrete was used rather than soil. While DCGL development was based on activation in the first 30 cm of building material, a hot spot depth of 15 cm was determined to be appropriate for MDC calculation because it reflects the reasonable detection capabilities of the NaI detector. Nuclide activities were calculated by multiplying the activity concentrations of the highest sample by the mass of the modeled volume (86,777 grams). The modeling code performed the appropriate calculations and determined the total exposure rate, 50.4 μrem/hr, which accounts for buildup. The dose modeling report from MicroShield is included as Attachment 4. Additionally, Microshield provided the exposure rate for a number of gamma energies associated with the input source term. These data were used along with data for a 2” x 2” NaI detector from NUREG-1507, Table 6.3, to weight the cpm/μrem/hr value at each energy by the fractional exposure rate to estimate an overall cpm/μrem/hr value specific to the source term.

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Table 9-1: Weighted cpm/μrem/hr for 2” x 2” NaI

Energy (keV) Exposure

Rate (μrem/hr)

Exposure Rate Fraction

cpm/μrem/hr1

cpm/μrem/hr (weighted)

152 1.43E-02 2.83E-04 2.20E+03 6.22E-01

30 4.40E-05 8.73E-07 5.16E+03 4.51E-03

40 1.39E-01 2.75E-03 8.88E+03 2.44E+01

50 4.77E-02 9.45E-04 1.18E+04 1.12E+01

100 4.02E-01 7.98E-03 9.84E+03 7.85E+01

200 3.18E-01 6.31E-03 4.23E+03 2.67E+01

300 1.77E+00 3.51E-02 2.52E+03 8.85E+01

400 5.79E-01 1.15E-02 1.70E+03 1.95E+01

500 8.34E-02 1.65E-03 1.27E+03 2.10E+00

600 1.46E+00 2.90E-02 1.01E+03 2.93E+01

800 5.64E+00 1.12E-01 7.10E+02 7.94E+01

1000 1.94E+01 3.85E-01 5.40E+02 2.08E+02

1500 2.05E+01 4.07E-01 3.50E+02 1.43E+02

2000 8.90E-08 1.76E-09 2.60E+02 4.59E-07

Total: 5.04E+01 Total Weighted

cpm/μrem/hr: 7.11E+02

1 Values from NUREG-1507 Table 6.3. 2No value listed on table for 15 keV. The value for 20 keV used.

The scan MDC for a 2” x 2” NaI detector was calculated using the following inputs:

Scan rate of 0.5 meters per second provides an observation interval of approximately 1 second based on a hot spot diameter of 56 cm

Locally determined background is expected to be less than or equal to 3,527 cpm The desired level of surveyor performance, 95% correct detections and 60% false positive

rate, results in a d’ of 1.38 The surveyor efficiency (p) is assumed to be 0.5

Based on these inputs, MDCRsurveyor was calculated as follows: 1) Bi = (3,527 cpm) * (1 sec) * (1min/60 sec) = 58.78 counts 2) MDCR = (1.38) * sqrt(58.78) * (60 sec/1 min) = 635 cpm 3) MDCRsurveyor = 635 cpm/sqrt(0.5) = 898 cpm The corresponding Minimum Detectable Exposure Rate is determined by dividing the MDCRsurveyor by the weighted conversion factor determined in Table 9-1 (equation 6-18 of NUREG-1507): Minimum Detectable Exposure Rate = 898 cpm / 711 cpm/μrem/hr = 1.26 μrem/hr

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Finally, the radionuclide concentrations necessary to yield the minimum detectable exposure rate was calculated using equation 6-22 of NUREG-1507 as follows: Scan MDC = (68.5 pCi/g) * 1.26 μrem/hr / 50.4 μrem/hr = 1.71 pCi/g The MDC of the scan procedure – needed to detect an area of elevated activity at the limit determined by the area factor – is discussed in Section 5.5.2.4 of MARSSIM and calculated as follows: Scan MDC (required) = DCGL x Area Factor Areas smaller than the area for which the DCGL is calculated result in area factors greater than one. Because the most restrictive DCGL is 5.41 pCi/g (Co-60) and the Scan MDC is well less than 50% of this value, we can conclude that the Scan MDC is appropriate without calculating area factors. 9.3.4. Removable Contamination Measurement Counting Removable contamination measurement (smear) counting Minimum Detectable Concentration at a 95% confidence level is calculated using the following equation, which is NUREG-1507, “Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions”, Table 3.1 (Strom & Stansbury, 1992):

Et

t

ttB

MDCs

b

ssr

smear

)1(29.33

Where: MDCsmear = minimum detectable concentration level in dpm/smear Br = background count rate in counts per minute tb = background count time in minutes ts = sample count time in minutes E = 4π instrument efficiency for radionuclide emission of interest

9.4. Counting Uncertainty The counting uncertainty for both total and removable measurements is calculated using equation 6-15 from MARSSIM:

2 2

s b bR

s b b

C C

T T

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Where: σR = uncertainty Cs+b = gross counts of the sample Ts+b = Sample time (minutes) Cb = Gross background counts Tb = Background count time (minutes) 9.5. Instrumentation Specifications The instrumentation to be used for facility decommissioning surveys is summarized in the following tables. Table 9-2 lists the standard features of each instrument such as probe size and efficiency. Table 9-3 lists the typical operational parameters such as scan rate, count time, and the associated MDCs. Alternate or additional instrumentation with similar detection capabilities may be utilized as needed for survey requirements with the Ameriphysics’ Project Manager approval.

Table 9-2: Instrumentation Specifications

Detector Model

Detector Type Detector

Area Meter Model

Window Thickness

Typical Total Efficiency

Ludlum 43-93 Alpha/Beta Scintillation

100 cm2 Ludlum

2360 0.8

mg/cm2 8 % (99Tc) – Beta

Ludlum 43-10-1

Alpha/Beta Scintillation

100 cm2 Ludlum

3030 0.4

mg/cm2 18% – Beta

Ludlum 43-37 Alpha/Beta

Gas Proportional

584 cm2 Ludlum

2360 0.8

mg/cm2 8 % (99Tc) – Beta

Ludlum 44-10 Gamma

Scintillation 2” x 2”

NaI Ludlum

2221 N/A 640 cpm/uR/hr

Table 9-3: Typical Instrument Operating Parameters and Sensitivities

Measurement Type

Detector Model

Meter Model

Scan Rate

Count Time

Background

(cpm) MDC

(dpm/100cm2)1

Surface Scans 43-93 Ludlum

2360 3

cm/sec. N/A 400 2,442 – Beta

Total Surface Activity

43-93 Ludlum

2360 N/A

60 sec.

400 1,201 – Beta

Surface Scans 43-37 Ludlum

2360 3

cm/sec. N/A 700 859 – Beta

Gamma Scans 44-10 Ludlum

2221 0.5

m/sec. N/A 2,577 1.71 pCi/g

Removable Beta Activity

Ludlum 43-10-1

Ludlum 3030E

N/A 60

sec. 70 – Beta 223 – Beta

Note 1: Unless otherwise specified.

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9.6. Background Determination For surveys in areas that were not exposed to a neutron flux, gross beta/gamma total surface activity measurements are performed. The use of reference background areas or paired background comparisons is not necessary for the purposes of this Plan since the radionuclides of concern do not exist in background or they exist at very small fractions of the DCGLs. An ambient background measurement taken at waist level in the center of each survey unit will be used. The ambient background value will be subtracted from the applicable gross measurement count rates (in cpm) to determine the net measurement count rate. For areas that were exposed to a neutron flux (e.g., Cyclotron Room), 10 cm readings using a shielded 2” x 2” NaI detector will be collected on concrete surfaces outside the Cyclotron Room. 10. RADIOACTIVE WASTE MANAGEMENT PROGRAM Radioactive wastes generated as a result of decontamination will be transported to either a licensed radioactive materials processor or for direct disposal at a licensed radioactive materials disposal facility. 10.1. Waste Characterization Previously obtained sample results will be used to develop an "assayed" source representative of the mix of nuclides in the waste. Activities of the concrete wastes may be estimated using the sample results collected during the characterization multiplied by the weight of the wastes. The absolute amount is not required; only the relative quantities, in terms of total activity. If radioactive wastes exceeding the expected values from Table 5-1 are identified, waste material may be characterized using the MicroShield Infer Source tool in terms of radionuclide identification, total activity, and specific activity. 10.2. Waste Shipment Waste containers will be prepared, loaded, and manifested by personnel who have satisfied the training requirements of Title 49 of the Code of Federal Regulations (CFR) Part 172, Subpart H. Shipping papers will reflect Cardinal Health as the generator. 11. QUALITY ASSURANCE PROGRAM

Ameriphysics' Quality Assurance Program comprises the planned and systematic actions

necessary to provide adequate confidence that a system, component, or service achieves a level

of quality which meets or exceeds established requirements.

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In addition to the Ameriphysics Quality Assurance Program, a project specific Quality Assurance Project Plan (QAPP) will be prepared that presents the organization, objectives, functional activities, and specific quality assurance (QA), and quality control (QC) activities associated with the decommissioning of the cyclotron facility, in St Louis, Missouri. The QAPP will describe the specific protocols that will be followed for field measurements, instrument control and calibration, sampling, sample handling and storage, chain of custody, and laboratory analysis. The plan will present details regarding data quality objectives (DQOs) for the project, field and sample documentation, sample packaging and shipping, and laboratory analytical procedures. Ameriphysics will submit a project-specific Quality Assurance Project Plan (QAPP) utilizing the guidelines of MARSSIM Section 9. The QAPP will be reviewed and approved by Cardinal Health prior to commencing decommissioning. The QAPP will incorporate at a minimum, the following sections:

• Introduction

• Project Organization and Responsibilities

• On Site Organization for Measurements and Laboratory Analysis

o Subcontract Support

• Data Quality Objectives

o Specific Data Quality Objectives

• QC Measurements, Samples, Holding Times, Custody

o QC Measurements and Samples

o Chain of Custody (COC)

o Off Site Laboratory Custody Procedures

o Sample Numbering and Field Documentation

• Procedures

• On Site Laboratory and Field Instruments

• Calibration Procedures and Frequency

• Internal Quality Control Checks

o Instrument QC

o QC Samples

• Calculation of Data Quality Indicators

o Field Measurement Data

o Laboratory Data

• Corrective Actions

• Data Reduction, Validation, and Reporting

o Field Measurements and Sample Collection

o Contract Laboratory Services

o On Site Laboratory Results

o Data Validation

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• Preventative Maintenance Procedures

o Field Instruments and Equipment

o Laboratory Instruments

• Performance and System Audits

12. FACILITY RADIATION SURVEYS Final status surveys are performed to demonstrate that residual radioactivity in each survey unit satisfies the predetermined criteria for release for unrestricted use. The final status survey is designed using the DQO process. Final status surveys are conducted by performing required scan surveys, total direct surveys, and removable contamination measurements. All survey data is documented on survey maps and associated data information sheets. 12.1. Data Quality Objectives The process of designing a final status survey begins with development of DQOs. On the basis of these objectives and the known or anticipated radiological conditions at the site, the numbers and locations of measurement and sampling points used to demonstrate compliance with the release criterion are then determined. Finally, survey techniques appropriate to develop adequate data are selected and implemented. Survey results obtained in accordance with the MARSSIM guidelines are used to select between one condition of the environment (the null hypothesis, H0) and an alternative condition (the alternative hypothesis, Ha). The null hypothesis is treated like a baseline condition that is assumed to be true in the absence of strong evidence to the contrary. Acceptance or rejection of the null hypothesis depends upon whether or not the particular survey results are consistent with the hypothesis. A decision error occurs when the decision maker rejects the null hypothesis when it is true, or accepts the null hypothesis when it is false. These two types of decision errors are classified as Type I and Type II decision errors. A Type I decision error occurs when the null hypothesis is rejected when it is true, and is sometimes referred to as a false positive error. The probability of making a Type I decision error, or the level of significance, is denoted by alpha (α). Alpha reflects the amount of evidence the decision maker would like to see before abandoning the null hypothesis, and is also referred to as the size of the test. A Type II decision error occurs when the null hypothesis is accepted when it is false. This is sometimes referred to as a false negative error. The probability of making a Type II decision error

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is denoted by beta (β). The term (1- β) is the probability of rejecting the null hypothesis when it is false, and is also referred to as the power of the test. The null hypothesis for this project is that the residual radioactivity concentrations exceed the release criterion. Acceptable decision error probabilities for testing the hypothesis are set at α = 0.05 and β = 0.05. 12.2. Area Classification Classification is a critical step in the survey design process. Areas that have no reasonable potential for residual contamination do not need any level of survey coverage and are designated as non-impacted areas. These areas have no radiological impact from site operations. Impacted areas are areas that have some potential for containing residual radioactivity. They are subdivided into the following three classes:

• Class 1 areas: Areas that have, or had prior to remediation, a potential for radioactive contamination or known contamination. Examples of Class 1 areas include site areas previously subjected to remedial actions, locations where leaks or spills are known to have occurred, former burial or disposal sites, waste storage sites, and areas with contaminants in discrete solid pieces of material high specific activity.

• Class 2 areas: These areas have, or had prior to remediation, a potential for radioactive contamination or known contamination, but are not expected to exceed the DCGL. To justify changing an area's classification from Class 1 to Class 2, the existing data (from the historical site assessment, scoping surveys, or characterization surveys) should provide a high degree of confidence that no individual measurement would exceed the DCGL. Examples of areas that might be classified as Class 2 include locations where radioactive materials were present in an unsealed form, potentially contaminated transport routes, upper walls and ceilings of rooms subjected to airborne radioactivity, areas where low concentrations of radioactive materials were handled, and areas on the perimeter of former contamination control areas.

• Class 3 areas: Any impacted areas that are not expected to contain any residual radioactivity, or are expected to contain levels of residual radioactivity at a small fraction of the DCGL, based on site operating history and previous radiological surveys. Examples of areas that might be classified as Class 3 include buffer zones around Class 1 or Class 2 areas, and areas with very low potential for residual contamination but insufficient information to justify a non-impacted classification.

The working hypothesis of MARSSIM is that all impacted areas being evaluated for release have a potential for radioactive contamination above the DCGL. This initial assumption means that all areas are initially considered Class 1 areas unless some basis for reclassification as Class 2, Class 3 or non-impacted is provided. Consistent with this approach, Class 1 areas have the greatest

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potential for contamination and, therefore, receive the highest degree of survey effort, followed by Class 2 and then Class 3 areas. For the purposes of this Plan, the floors of the restricted area are classified as Class 1. The lower walls and support spaces making up the balance of the restricted area are classified as Class 2. The upper walls and ceilings of these spaces are classified as non-impacted unless during scan surveys of the lower walls, there is an indication that further investigation of the upper walls and ceilings is warranted. The floors in the non-restricted areas are classified as Class 3. 12.3. Survey Unit Identification A survey unit is a physical area consisting of structures or land areas of specified size and shape for which a separate decision is made as to whether or not that area exceeds the release criterion. As this decision is made as a result of the final status survey, the survey unit is the primary entity for demonstrating compliance with the release criterion. To facilitate survey design and ensure that the number of survey data points for a specific site is relatively uniformly distributed among areas of similar contamination potential, the site is divided into survey units that share a common history or other characteristics, or are naturally distinguishable from other portions of the site. A survey unit should not include areas that have different classifications. The survey unit’s characteristics should be generally consistent with exposure pathway modeling that is used to convert dose or risk into radionuclide concentrations. For indoor areas each room may be designated as a survey unit. Indoor areas may also be subdivided into several survey units of different classification, such as separating floors and lower walls from upper walls and ceilings (and other upper horizontal surfaces) or subdividing a large warehouse based on floor area. MARSSIM states that survey units should be limited in size based on classification, exposure pathway modeling assumptions, and site-specific conditions. MARSSIM also suggests size limitations, which for Class 1 structural surfaces is 100 m2 or less (floor area) and Class 2 structural surfaces 100 to 1,000 m2. Both Class 1 and Class 2 survey units are less than these size recommendations. MARSSIM does not have a suggested limit for class 3 survey units.

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Initial survey unit classification is as follows:

Table 12-1: Initial Survey Unit Classification

Survey Unit ID

Description Approximate Survey Area

(m2)

Initial Classification

SU 1 Cyclotron Room Floor (walls and ceiling to be removed)

72 Class 1 Impacted

SU 2-4 Restricted Area Floors 51, 99, & 59 Class 1 Impacted

SU 5 Restricted Area Walls (0-2

meters) 350 Class 2 Impacted

SU 6 Non-Restricted Area Floors 155 Class 3 Impacted

12.4. Surface Scans Scanning is used to identify locations within the survey unit that exceed the investigation level, which for this survey is the DCGL. These locations are marked and receive additional investigations to determine the concentration, area, and extent of the contamination. Scanning surveys are designed to detect small areas of elevated activity that are not detected by the measurements using the systematic pattern. For this reason, the measurement locations and the number of total surface activity measurements may need to be adjusted based on the sensitivity of the scanning technique. Scan surveys are performed for gross beta/gamma in all potentially contaminated areas that have no potential for volumetric activation. NaI scans are performed in potentially activated areas such as the remaining Cycloton Room floor. NaI scans are performed to meet the survey residence time of 1-second as discussed in Section 9.3.3. For the purposes of the final status survey, Class 1 survey units will receive a 100% scan survey of all accessible surfaces. Class 2 survey units will receive a minimum of 50% scan survey of all accessible surfaces. Class 3 areas will receive a minimum of 10% scan of all accessible surfaces. If elevated activity is detected during the scan surveys, then the location is marked and samples are taken to quantify the activity. The samples will consist of total and removable surface activity for non-activated areas or concrete samples for activated areas. Note that these measurements are evaluated on an individual basis and are in addition to the static measurements required by MARSSIM. 12.5. Determining the Number of Sample Locations For situations where the contaminant is not present in background, or is present at such a small fraction of the DCGL as to be considered insignificant, a background reference area is not necessary. Instead, the contaminant levels are compared directly with the DCGL value. A one-sample Sign test is used to statistically demonstrate compliance with the release criterion.

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The lower bound of the gray region (LBGR) is selected to be one-half the DCGL and is used as an arbitrary starting point for developing an acceptable survey design along with target values of 0.05 for α and β. The width of the gray region, equal to DCGL minus the LBGR, is a parameter that is central to the Sign test. This parameter is also referred to as the shift, Δ. The absolute size of the shift is actually of less importance than the relative shift, Δ/σ, where σ is an estimate of the standard deviation of the measured values in the survey unit. Values estimated for σ include both the real spatial variability in the quantity being measured and the precision of the chosen measurement system. The relative shift, Δ/σ, is an expression of the resolution of the measurements in units of measurement uncertainty. The importance of choosing appropriate values for σ must be emphasized. If the value is grossly underestimated, the number of data points will be too few to obtain the desired power level for the test and a resurvey may be recommended. Therefore, in the interest of conservatism a larger value is selected even though the number of data points determined is increased. Table 5.5 of MARSSIM provides the number of data points used to demonstrate compliance using the Sign test for selected values of α, β, and Δ/σ. The sample numbers on Table 5.5 of MARSSIM were calculated using the methodology presented in MARSSIM and increased by 20% to account for missing or unusable data. 12.5.1. Number of Gross Beta/Gamma Total Surface Activity Measurements Gross Beta/Gamma measurements consist of static measurements taken with Ludlum 43-93 or equivalent. These measurements will be taken in potentially non-activated contamination areas (areas outside the vault within the restricted area). Since an actual value for σ is not known, it is preliminarily assumed to be no more than 30 percent of the DCGL. This important assumption is confirmed by a post-survey analysis of σ. Using this estimate of σ, the relative shift is calculated using a LBGR of 50 percent of the DCGL (∆ = 1 x DCGL – 0.5 x DCGL). This calculation is shown below.

Relative shift = ∆

𝜎=

1 − 0.5

0.3= 1.6

The value extracted from the table using the expected site-specific parameters is 17 and represents the minimum number of measurements performed in each survey unit. 12.5.2. Number of Volumetric NaI Measurement Locations Volumetric measurements are to be taken with a NaI detector. These measurements are to be taken in potentially activated areas (i.e., footprint of the vault).

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Since an actual value for σ is not known, it is preliminarily assumed to be no more than 30 percent of the DCGL. This important assumption is confirmed by a post-survey analysis of σ. Using this estimate of σ, the relative shift is calculated using a LBGR of 50 percent of the DCGL (∆ = 1 x DCGL – 0.5 x DCGL). This calculation is shown below.

Relative shift = ∆

𝜎=

1 − 0.5

0.3= 1.6

The value extracted from the table using the expected site-specific parameters is 17 and represents the minimum number of measurements performed in each survey unit. The MDC of the scan procedure – needed to detect an area of elevated activity at the limit determined by the area factor – is discussed in Section 5.5.2.4 of MARSSIM3 and calculated as follows:

Scan MDC (required) = (𝐷𝐶𝐺𝐿𝑊) × (𝐴𝑟𝑒𝑎 𝐹𝑎𝑐𝑡𝑜𝑟) Area factors are determined by taking the ratio of the dose per unit concentration generated by RESRAD-BUILD for the area specified in Section 5.2 to the dose generated by the largest unsampled area. The surface area of the largest area is approximately 72 square meters. When 18 samples are spaced using the procedure specified in section 5.1, the distance between sampling locations is 2 meters. The area encompassed by a square sampling pattern of two meters is four square meters. The actual Scan MDC, 1.71 pCi/g (see Section 9.3.3), is below the most limiting DCGL of 5.41 pCi/g (based on Co-60) which would be much less than a determined elevated measurement (DCGLEMC) for a four square meter unsampled area. As a result, no additional sampling points are necessary for assessment of small areas of elevated activity in the cyclotron activation areas. 12.6. Determination of Sampling Locations Class 1 and Class 2 survey units are sampled using a random start, systematic grid system. After determining the number of samples needed in the survey unit, sample spacing is determined from MARSSIM equation 5-8:

grid squarea for n

AL

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Where: L = sample spacing interval A = the survey unit area n = number of samples needed in the survey unit

Maps are generated of the survey unit’s permanent surfaces included in the statistical tests (floors, walls, ceilings, fixed cabinetry, etc.) and folded out in a 2-dimensional view. A random starting point is determined using computer-generated random numbers coinciding with the x and y coordinates of the total survey unit. A grid is plotted across the survey unit surfaces based on the random start point and the determined sample spacing. A measurement location is plotted at each intersection of the grid plot. In addition to the survey locations identified for statistical evaluations and elevated measurement comparisons, data may be obtained from judgmental locations that are selected due to unusual appearance, location relative to contamination areas, high potential for residual activity, general supplemental information, etc. Data points selected based on professional judgment are not included with the data points from the systematic grid for statistical evaluations; instead they are compared individually with the established DCGLs and conditions. Measurement locations selected based on professional judgment violates the assumption of unbiased measurements used to develop the statistical tests described by MARSSIM. 12.7. Total Surface Activity Measurements Direct surveys (static measurements) are performed on building surfaces to the extent practical in impacted areas utilizing instrumentation of the best geometry based on the surface at the survey location. Additionally, locations of elevated activity identified and marked during the scan survey require total activity measurements. Total surface contamination measurements for gross beta are taken at statistically determined sample locations. Scaler count times are based on achieving detection sensitivity below the DCGL. 12.8. Gamma Radiation Measurements In the potentially activated areas, one-minute static gamma measurements will be collected at each of the determined sample locations using the shielded 2” x 2” NaI detector (see Sections 12.5.2 and 12.6). The measurements will be collected at a similar geometry as the scan surveys (10 cm from the applicable surface). Additional judgmental locations will be collected at any locations exhibiting elevated count rates identified during the scan surveys.

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12.9. Removable Contamination Measurements Removable contamination measurements (smears) are collected on building surfaces and structures at each sample location (surface and activation areas) to determine the potential removable contamination. For each sample, an area of approximately 100 cm2 is wiped. 12.10. Volumetric Core Samples Core-sampling will be performed at each of the determined sample locations in potentially activated areas (see sections 12.5.2 and 12.6). The samples will be obtained to a depth of 15 cm. Sample custody will be maintained at all times. Additional judgmental locations will be collected at locations exhibiting elevated count rates identified during the scan surveys. The samples will be sent to an off-site laboratory for gamma spectroscopy analysis. The laboratory will report the radionuclides identified in Table 4-1 and all other true positive results. Analysis for the hard-to-detect radionuclides (H-3 and Fe-55) will only be performed on 10% of the total number of samples. These will be selected based on the highest 2” x 2” NaI detector readings determined during scan surveys. An average distribution will be determined to ratio the hard-to-detect radionuclides into the sample results for the remaining samples. 12.11. Survey Investigation Levels for Non-Activated Surfaces Investigation levels are used to flag locations that require special attention and further investigation to ensure areas are properly classified and adequate surveys are performed. These locations are marked and receive additional investigations to determine the concentration, area, and extent of the contamination. The survey investigation levels for each type of measurement are listed by classification in Table 12-2.

Table 12-2: Survey Investigation Levels for Non-Activated Surfaces

Survey Unit Classification

Flag Direct Measurement Result When:

Flag Scanning Measurement Result When:

Flag Removable Measurement Result

When:

Class 1 >75% of DCGL >75% of DCGL >1,000 dpm/100cm2

Class 2 >50% of DCGL >50% of DCGL >1,000 dpm/100cm2

Class 3 >10% of DCGL >10% of DCGL >500 dpm/100cm2

12.12. Survey Investigation Levels for Potentially Activated Structures To determine investigation and action levels for activated concrete, some calculations must be performed to correlate the 2” x 2” NaI detector readings in cpm to the activity in pCi/g. The investigation level triggers the need to collect volumetric samples and send for laboratory analysis. The action level triggers the need for additional remediation. The investigation level and the action level are 75% of the DCGLgross and 90% of the DCGLgross, respectively. To determine the

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corresponding values in cpm for the 2” x 2” NaI detector, the following calculations are performed. The sample results from the 0-6-inch core sample from the cyclotron vault floor had a total activity of 68.5 pCi/g. From the Microshield model, based on this sample, we would have an exposure rate of 50.4 µRem/hr. This results in 0.74 µRem/hr per pCi/g. 50.4 µRem/hr / 68.5 pCi/g = 0.74 µrem/hr per pCi/g We then calculate the expected exposure rate from the surface containing activity at the DCGLgross of 9.41 pCi/g. from Table 5-2. 9.41 pCi/g x 0.74 µrem/hr per pCi/g = 6.96 µrem/hr The cpm value for the 2” x 2” NaI detector that corresponds to the exposure rate of 6.96 µrem/hr is calculated by multiplying by the total weighted cpm/μrem/hr from Table 9-1. 6.96 µrem/hr x 711 cpm/μrem/hr = 4,949 cpm The investigation level at 75% of this value is 3,712 cpm above background. The action level at 90% of this value is 4,454 cpm above bacground. 12.13. Survey Documentation A survey package is developed for each survey unit and may contain the following:

• Survey instruction sheets • General survey requirements • Instrument requirements with associated MDCs, count times and scan rates • Survey maps • Overview maps detailing survey locations and placement methodology • Survey sub-unit maps with additional sample location information, as needed • Survey data sheets • Signature of data collector and reviewer

12.14. Data Validation Field data is reviewed and validated to ensure:

• Completeness of forms and that the type of survey was correctly assigned to the survey unit. • The MDCs for measurements meet the established data quality objectives; independent calculations are performed for a representative sample of data sheets and survey areas.

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• Instrument calibrations and daily functional checks were performed accurately and at the required frequency.

13. EVALUATING SURVEY RESULTS In addition to simply comparing the data against the release criteria, basic statistical quantities are calculated for the data obtained from the survey units. First, the average of the data set and the standard deviation are calculated. The average of the data is compared to the DCGL to get a preliminary indication of the survey unit status. Where remediation is inadequate, this comparison may readily reveal that a survey unit contains excess residual radioactivity - even before applying statistical tests. For example, if every measurement in the survey unit is below the DCGL, the survey unit clearly meets the release criterion. The value of the sample standard deviation is especially important. If the value is too large compared to that assumed during the survey design, this may indicate an insufficient number of samples were collected to achieve the desired power of the statistical test. The median is the middle value of the data set when the number of data points is odd, and is the average of the two middle values when the number of data points is even. Thus 50% of the data points are above the median, and 50% are below the median. Large differences between the average and the median are an early indication of skewness in the data. Ideally, the difference between the average and the mean should be a small fraction of the sample standard deviation. Examining the minimum, maximum, and range of the data may provide additional useful information. The range should not be unusually large. When there are 30 or fewer data points, values of the range much larger than about 4 to 5 standard deviations are considered unusual. For larger data sets the range might be wider. 14. FINAL REPORT A Final Report summarizing decommissioning activities performed at the facility will be prepared and submitted to Cardinal Health for their review and submittal to the NRC. The Final Report will include:

• Introduction

• Radionuclides of Concern

• Facility Description

• FSS Objectives

• FSS Procedures

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• Data Interpretation

• Findings and Results

• Comparison of Results with Guidelines

• Conclusions

Supporting appendices/attachments will also be provided, as required. Discussions therein may include the number of samples and measurements collected, maps and drawings illustrating findings and the locations of samples/measurements, statistical evaluations and other comparisons to guidelines, descriptions of field changes and anomalous results, conclusions based on specific and overall finding of the investigation, and other relevant information as required to demonstrate compliance with this plan and overall project objectives. 15. REFERENCES 1. NUREG-1575, “Multi-Agency Radiation Survey and Site Investigation Manual” (MARSSIM) 2. NUREG-1505, “A Nonparametric Statistical Methodology for the Design and Analysis of Final Decommissioning Surveys" 3. NUREG-1507, “Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions” 4. NUREG-1757, Volume 1 “Consolidated NMSS Decommissioning Guidance,” Appendix B 5. NUREG-1757, Volume 2 “Consolidated NMSS Decommissioning Guidance” 6. ICRP Publication 107, “Nuclear Decay Data for Dosimetric Calculations” 7. 10 CFR 20 Subpart E, “Radiological Criteria for License Termination” 8. Ameriphysics Radiological Control Procedure Manual and associated Procedures. 9. Handbook of Health Physics and Radiological Health, Third Edition.

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Attachment 1 Laboratory Sample Analysis Reports for Cyclotron Room Characterization

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June 01, 2016 Mr. Paul Jones Ameriphysics, LLC 911 Cross Park Dr. Knoxville, Tennessee 37923 Re: Ameriphysics, LLC Work Order: 398210 Dear Mr. Jones:

GEL Laboratories, LLC (GEL) appreciates the opportunity to provide the enclosed analytical results for thesample(s) we received on May 26, 2016. This original data report has been prepared and reviewed in accordancewith GEL’s standard operating procedures.

Our policy is to provide high quality, personalized analytical services to enable you to meet your analytical needson time every time. We trust that you will find everything in order and to your satisfaction. If you have anyquestions, please do not hesitate to call me at (843) 556-8171, ext. 4453.

Sincerely, PM_SIGN_HERE Edith Kent Project Manager

Purchase Order: 0316-001 Enclosures

Page 1 of 24

Kaitlyn Stone for

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Reviewed by USER_SIGN_HERE

GEL LABORATORIES LLC2040 Savage Road Charleston SC 29407 − (843) 556−8171 − www.gel.com

Certificate of Analysis Report

AMPH002 Ameriphysics, LLC

Client SDG: 398210 GEL Work Order: 398210

Where the analytical method has been performed under NELAP certification, the analysis has met all of therequirements of the NELAC standard unless qualified on the Certificate of Analysis.

The designation ND, if present, appears in the result column when the analyte concentration is not detected abovethe limit as defined in the ’U’ qualifier above.

This data report has been prepared and reviewed in accordance with GEL Laboratories LLCstandard operating procedures. Please direct any questions to your Project Manager, Edith Kent.

The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria** Analyte is a Tracer compound** Analyte is a surrogate compoundU Analyte was analyzed for, but not detected above the MDL, MDA, MDC or LOD.UI Gamma Spectroscopy−−Uncertain identification

for

Page 2 of 24

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Certificate of Analysis

GEL LABORATORIES LLC2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com

Report Date: June 1, 2016

Rad Gamma Spec Analysis

Parameter Result UnitsQualifier Analyst Date Time

15704721126pCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/g

05/31/16MXR1

DF

Mr. Paul JonesContact:

Ameriphysics, LLCCompany :911 Cross Park Dr.

Knoxville, Tennessee 37923

Address :

Ameriphysics, LLCProject:

398210001Misc Solid19-MAY-16 09:0026-MAY-16

1CVF AMPH002Project:AMPH002Client ID:

Client

+/-0.111+/-2.98

+/-0.220+/-1.06

+/-0.135+/-0.218+/-0.203+/-0.395+/-0.884+/-0.452+/-0.311+/-0.274+/-0.236+/-0.127+/-0.241+/-0.083+/-0.202+/-0.159+/-0.432

Sample ID:

Receive Date:

Client Sample ID:

Matrix:Collect Date:

Collector:

Batch

0.1873.69

0.2301.63

0.2310.4390.2210.1170.4680.4150.5660.4710.2090.2250.2430.1420.3060.3140.465

The following Prep Methods were performed:

Dry Soil Prep Dry Soil Prep GL-RAD-A-021 05/26/16 15703781531CXC1

Method Description Analyst Date Time Prep Batch

Method

The following Analytical Methods were performed:

1Method Description

1

DOE HASL 300, 4.5.2.3/Ga-01-RAnalyst Comments

UU

UU

UIU

UU

U

UU

UI

Antimony-124Cadmium-109Cesium-134Chromium-51Cobalt-56Cobalt-57Cobalt-58Cobalt-60Europium-152Europium-154Europium-155Iron-59Manganese-54Niobium-95Scandium-46Silver-108mSilver-110mSodium-22Zinc-65

Gammaspec, Gamma, Solid - Client List "Dry Weight Corrected"

Uncertainty

0.03461.071.94

-0.637-0.0918

0.000.0309

15.943.24.41

0.3080.0514

1.260.0400.792

-0.07430.0465

0.001.03

RLMDC

Notes:Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).

Page 3 of 24

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Certificate of Analysis

GEL LABORATORIES LLC2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com

Report Date: June 1, 2016

Rad Gamma Spec Analysis

Parameter Result UnitsQualifier Analyst Date Time

15704721126pCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/g

05/31/16MXR1

DF

Mr. Paul JonesContact:

Ameriphysics, LLCCompany :911 Cross Park Dr.

Knoxville, Tennessee 37923

Address :

Ameriphysics, LLCProject:

398210002Misc Solid19-MAY-16 09:1026-MAY-16

6CVF AMPH002Project:AMPH002Client ID:

Client

+/-0.062+/-0.895

+/-0.0998+/-0.400

+/-0.0607+/-0.140

+/-0.0543+/-0.152+/-0.385+/-0.207+/-0.131+/-0.111

+/-0.0578+/-0.0521

+/-0.109+/-0.0342+/-0.0841+/-0.0966

+/-0.172

Sample ID:

Receive Date:

Client Sample ID:

Matrix:Collect Date:

Collector:

Batch

0.09911.61

0.09580.7070.0940.186

0.09640.0492

0.2080.3240.2420.186

0.08450.09360.09930.0605

0.1290.0619

0.374

The following Prep Methods were performed:

Dry Soil Prep Dry Soil Prep GL-RAD-A-021 05/26/16 15703781531CXC1

Method Description Analyst Date Time Prep Batch

Method

The following Analytical Methods were performed:

1Method Description

1

DOE HASL 300, 4.5.2.3/Ga-01-RAnalyst Comments

UU

UU

UIU

UUUU

UUU

UI

Antimony-124Cadmium-109Cesium-134Chromium-51Cobalt-56Cobalt-57Cobalt-58Cobalt-60Europium-152Europium-154Europium-155Iron-59Manganese-54Niobium-95Scandium-46Silver-108mSilver-110mSodium-22Zinc-65

Gammaspec, Gamma, Solid - Client List "Dry Weight Corrected"

Uncertainty

0.00250.4340.4150.152

0.01170.00

0.04323.9311.6

0.9590.0976

-0.04060.07490.0488

0.249-0.00902

0.01670.0356

0.00

RLMDC

Notes:Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).

Page 4 of 24

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Certificate of Analysis

GEL LABORATORIES LLC2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com

Report Date: June 1, 2016

Rad Gamma Spec Analysis

Parameter Result UnitsQualifier Analyst Date Time

15704721127pCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/g

05/31/16MXR1

DF

Mr. Paul JonesContact:

Ameriphysics, LLCCompany :911 Cross Park Dr.

Knoxville, Tennessee 37923

Address :

Ameriphysics, LLCProject:

398210003Misc Solid19-MAY-16 09:3026-MAY-16

2CVEW AMPH002Project:AMPH002Client ID:

Client

+/-0.0756+/-2.33

+/-0.190+/-0.781

+/-0.0923+/-0.298+/-0.108+/-0.239+/-0.553+/-0.323+/-0.226+/-0.235+/-0.159

+/-0.0856+/-0.148

+/-0.0568+/-0.151+/-0.176+/-0.326

Sample ID:

Receive Date:

Client Sample ID:

Matrix:Collect Date:

Collector:

Batch

0.1392.55

0.1481.18

0.1580.0935

0.1530.0783

0.3280.5730.4110.3180.1460.1550.168

0.09940.228

0.09240.302

The following Prep Methods were performed:

Dry Soil Prep Dry Soil Prep GL-RAD-A-021 05/26/16 15703781531CXC1

Method Description Analyst Date Time Prep Batch

Method

The following Analytical Methods were performed:

1Method Description

1

DOE HASL 300, 4.5.2.3/Ga-01-RAnalyst Comments

UU

UU

UIU

UU

UI

UU

UI

Antimony-124Cadmium-109Cesium-134Chromium-51Cobalt-56Cobalt-57Cobalt-58Cobalt-60Europium-152Europium-154Europium-155Iron-59Manganese-54Niobium-95Scandium-46Silver-108mSilver-110mSodium-22Zinc-65

Gammaspec, Gamma, Solid - Client List "Dry Weight Corrected"

Uncertainty

0.02420.980

1.600.0317

-0.01690.00

0.03019.9526.43.43

0.104-0.00141

2.440.00

0.6730.0213

0.1990.002.25

RLMDC

Notes:Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).

Page 5 of 24

Page 46: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

Certificate of Analysis

GEL LABORATORIES LLC2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com

Report Date: June 1, 2016

Rad Gamma Spec Analysis

Parameter Result UnitsQualifier Analyst Date Time

15704721138pCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/g

05/31/16MXR1

DF

Mr. Paul JonesContact:

Ameriphysics, LLCCompany :911 Cross Park Dr.

Knoxville, Tennessee 37923

Address :

Ameriphysics, LLCProject:

398210004Misc Solid19-MAY-16 11:3026-MAY-16

3CVWW AMPH002Project:AMPH002Client ID:

Client

+/-0.0829+/-1.33

+/-0.142+/-0.565

+/-0.0854+/-0.182

+/-0.0942+/-0.218+/-0.483+/-0.259+/-0.180+/-0.174

+/-0.0997+/-0.0815

+/-0.135+/-0.0479

+/-0.118+/-0.125+/-0.275

Sample ID:

Receive Date:

Client Sample ID:

Matrix:Collect Date:

Collector:

Batch

0.1682.12

0.1430.9990.1470.2350.143

0.09260.2820.4930.3100.3090.1250.1430.151

0.08880.192

0.09170.321

The following Prep Methods were performed:

Dry Soil Prep Dry Soil Prep GL-RAD-A-021 05/26/16 15703781531CXC1

Method Description Analyst Date Time Prep Batch

Method

The following Analytical Methods were performed:

1Method Description

1

DOE HASL 300, 4.5.2.3/Ga-01-RAnalyst Comments

UU

UU

UIU

UUUU

UUU

Antimony-124Cadmium-109Cesium-134Chromium-51Cobalt-56Cobalt-57Cobalt-58Cobalt-60Europium-152Europium-154Europium-155Iron-59Manganese-54Niobium-95Scandium-46Silver-108mSilver-110mSodium-22Zinc-65

Gammaspec, Gamma, Solid - Client List "Dry Weight Corrected"

Uncertainty

0.0300.6290.5940.119

0.005750.00

0.04634.2611.21.16

-0.09170.168

0.08710.0182

0.2940.02520.09090.0317

1.04

RLMDC

Notes:Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).

Page 6 of 24

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Certificate of Analysis

GEL LABORATORIES LLC2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com

Report Date: June 1, 2016

Rad Gamma Spec Analysis

Parameter Result UnitsQualifier Analyst Date Time

15704721139pCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/g

05/31/16MXR1

DF

Mr. Paul JonesContact:

Ameriphysics, LLCCompany :911 Cross Park Dr.

Knoxville, Tennessee 37923

Address :

Ameriphysics, LLCProject:

398210005Misc Solid19-MAY-16 14:3026-MAY-16

4CVNW AMPH002Project:AMPH002Client ID:

Client

+/-0.0706+/-1.55

+/-0.163+/-0.656+/-0.094+/-0.139+/-0.117+/-0.248+/-0.613+/-0.359+/-0.194+/-0.183+/-0.142+/-0.087+/-0.166

+/-0.0592+/-0.142+/-0.126+/-0.295

Sample ID:

Receive Date:

Client Sample ID:

Matrix:Collect Date:

Collector:

Batch

0.1402.23

0.1651.16

0.1620.2940.152

0.08720.3320.2800.3590.3300.1470.1560.166

0.09960.2120.2180.324

The following Prep Methods were performed:

Dry Soil Prep Dry Soil Prep GL-RAD-A-021 05/26/16 15703781531CXC1

Method Description Analyst Date Time Prep Batch

Method

The following Analytical Methods were performed:

1Method Description

1

DOE HASL 300, 4.5.2.3/Ga-01-RAnalyst Comments

UU

UU

UIU

UU

U

UU

UI

Antimony-124Cadmium-109Cesium-134Chromium-51Cobalt-56Cobalt-57Cobalt-58Cobalt-60Europium-152Europium-154Europium-155Iron-59Manganese-54Niobium-95Scandium-46Silver-108mSilver-110mSodium-22Zinc-65

Gammaspec, Gamma, Solid - Client List "Dry Weight Corrected"

Uncertainty

0.02931.621.36

0.431-0.0091

0.000.0238

7.9424.02.52

0.01260.0618

1.290.1020.564

-0.03780.0111

0.002.19

RLMDC

Notes:Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).

Page 7 of 24

Page 48: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

Certificate of Analysis

GEL LABORATORIES LLC2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com

Report Date: June 1, 2016

Rad Gamma Spec Analysis

Parameter Result UnitsQualifier Analyst Date Time

15704721139pCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/g

05/31/16MXR1

DF

Mr. Paul JonesContact:

Ameriphysics, LLCCompany :911 Cross Park Dr.

Knoxville, Tennessee 37923

Address :

Ameriphysics, LLCProject:

398210006Misc Solid20-MAY-16 08:3026-MAY-16

5CVHW AMPH002Project:AMPH002Client ID:

Client

+/-0.0781+/-1.45

+/-0.167+/-0.564

+/-0.0906+/-0.280+/-0.164+/-0.224+/-0.479+/-0.354+/-0.160+/-0.180+/-0.149

+/-0.0879+/-0.167

+/-0.0548+/-0.145+/-0.125+/-0.290

Sample ID:

Receive Date:

Client Sample ID:

Matrix:Collect Date:

Collector:

Batch

0.1701.56

0.1701.03

0.1630.0722

0.1670.0816

0.3030.2910.2870.3070.1450.1580.173

0.09840.2250.1990.337

The following Prep Methods were performed:

Dry Soil Prep Dry Soil Prep GL-RAD-A-021 05/26/16 15703781531CXC1

Method Description Analyst Date Time Prep Batch

Method

The following Analytical Methods were performed:

1Method Description

1

DOE HASL 300, 4.5.2.3/Ga-01-RAnalyst Comments

UU

UU

UIU

UU

U

UU

UI

Antimony-124Cadmium-109Cesium-134Chromium-51Cobalt-56Cobalt-57Cobalt-58Cobalt-60Europium-152Europium-154Europium-155Iron-59Manganese-54Niobium-95Scandium-46Silver-108mSilver-110mSodium-22Zinc-65

Gammaspec, Gamma, Solid - Client List "Dry Weight Corrected"

Uncertainty

0.04770.5340.6680.044

0.005490.00

0.09233.9313.71.31

-0.105-0.112

0.2940.00833

0.2580.003320.0237

0.000.851

RLMDC

Notes:Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).

Page 8 of 24

Page 49: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

Pages 9 - 14 left out intentionally.

Samples not related to this project.

Page 50: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

QC Summary

GEL LABORATORIES LLC2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com

Rad Gamma Spec1570472Batch

Antimony-124

Cadmium-109

Cesium-134

Chromium-51

Cobalt-56

Cobalt-57

Cobalt-58

Cobalt-60

Europium-152

Europium-154

Europium-155

Iron-59

Manganese-54

Niobium-95

Scandium-46

Silver-108m

Silver-110m

Sodium-22

Zinc-65

Americium-241

Parmname

Mr. Paul JonesContact:

Ameriphysics, LLC911 Cross Park Dr.Knoxville, Tennessee

June 1, 2016Report Date:

Units

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

Anlst Date Time

MXR1 06/01/16 06:51

06/01/16 06:35

QC

0.0424

0.238

1.84

-0.58

-0.0179

0.00

0.0165

15.3

42.0

4.45

0.313

0.194

1.70

0.0863

0.777

0.00738

0.0882

0.00

1.17

550

NOM Sample

0.0346

1.07

1.94

-0.637

-0.0918

0.00

0.0309

15.9

43.2

4.41

0.308

0.0514

1.26

0.040

0.792

-0.0743

0.0465

0.00

1.03

Range

N/A

N/A

(0%-20%)

N/A

N/A

N/A

N/A

(0%-20%)

(0%-20%)

(0%-20%)

N/A

N/A

(0%-20%)

N/A

(0% - 100%)

N/A

N/A

N/A

(0% - 100%)

(75%-125%)

Qual

U

U

U

U

UI

U

U

U

U

U

U

UI

QC1203556803 398210001

QC1203556804

N/A

N/A

4.98

N/A

N/A

N/A

N/A

3.53

2.75

0.994

N/A

N/A

30

N/A

1.81

N/A

N/A

N/A

12.8

REC%

112489

DUP

LCS

398210Workorder:

U

U

U

U

UI

U

U

U

U

U

U

UI

+/-0.111

+/-2.98

+/-0.220

+/-1.06

+/-0.135

+/-0.218

+/-0.203

+/-0.395

+/-0.884

+/-0.452

+/-0.311

+/-0.274

+/-0.236

+/-0.127

+/-0.241

+/-0.083

+/-0.202

+/-0.159

+/-0.432

+/-0.140

+/-3.08

+/-0.345

+/-1.49

+/-0.202

+/-0.304

+/-0.235

+/-0.553

+/-1.37

+/-0.673

+/-0.478

+/-0.428

+/-0.341

+/-0.232

+/-0.324

+/-0.121

+/-0.311

+/-0.237

+/-0.781

*

RPD%

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Page 1 of 4

Page 15 of 24

Page 51: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

QC Summary

GEL LABORATORIES LLC2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com

Rad Gamma Spec1570472Batch

Cesium-137

Antimony-124

Cadmium-109

Cesium-134

Chromium-51

Cobalt-56

Cobalt-57

Cobalt-58

Cobalt-60

Europium-152

Europium-154

Europium-155

Iron-59

Manganese-54

Niobium-95

Scandium-46

Silver-108m

Silver-110m

Sodium-22

Zinc-65

Antimony-124

Parmname Units

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

Anlst Date Time

MXR1 06/01/16 06:35

06/01/16 06:50

QC

177

0.896

455

-0.646

-1.63

1.08

1.89

-0.0386

160

0.769

-0.569

-1.28

1.40

-0.0956

-0.754

-1.05

-0.0446

0.448

-0.186

3.99

-0.0143

NOM Sample Range

(75%-125%)

(75%-125%)

Qual

U

U

U

U

U

U

U

U

U

U

U

U

U

U

U

UQC1203556802

REC%

97.7

94.9

181

168

MB

398210Workorder:

+/-12.4

+/-3.55

+/-0.721

+/-25.6

+/-0.879

+/-5.30

+/-1.12

+/-0.707

+/-0.838

+/-3.88

+/-2.17

+/-1.27

+/-1.50

+/-1.99

+/-0.854

+/-0.745

+/-0.974

+/-0.699

+/-1.29

+/-0.446

+/-2.10

RPD%

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Page 2 of 4

Page 16 of 24

Page 52: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

QC Summary

GEL LABORATORIES LLC2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com

Rad Gamma Spec1570472Batch

Cadmium-109

Cesium-134

Chromium-51

Cobalt-56

Cobalt-57

Cobalt-58

Cobalt-60

Europium-152

Europium-154

Europium-155

Iron-59

Manganese-54

Niobium-95

Scandium-46

Silver-108m

Silver-110m

Sodium-22

Zinc-65

Parmname Units

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

pCi/g

Anlst Date Time

MXR1 06/01/16 06:50

QC

0.0303

0.00601

-0.179

-0.00336

-0.0122

0.0175

-0.01

0.0399

-0.0233

-0.0596

-0.0466

-0.00714

0.00867

-0.00557

0.0506

-0.00265

-0.00731

0.0433

NOM Sample RangeQual

U

U

U

U

U

U

U

U

U

U

U

U

U

U

U

U

U

U

The Qualifiers in this report are defined as follows:

REC%

398210Workorder:

**

<

Analyte is a Tracer compound

Result is less than value reported

+/-0.0672

+/-0.485

+/-0.0226

+/-0.211

+/-0.0244

+/-0.016

+/-0.0345

+/-0.0247

+/-0.0688

+/-0.0834

+/-0.072

+/-0.0526

+/-0.0238

+/-0.0189

+/-0.0269

+/-0.0202

+/-0.0368

+/-0.0295

+/-0.0511

RPD%

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Uncertainty

Notes:

Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).

Page 3 of 4

Page 17 of 24

Page 53: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

QC Summary

GEL LABORATORIES LLC2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com

Parmname

Page 4 of 4

Units Anlst Date TimeQCNOM Sample RangeQual REC%

398210Workorder:

>

BD

FA

H

J

K

L

M

M

N/A

N1

ND

NJ

Q

R

U

UI

UJ

UL

X

Y

^

h

Result is greater than value reported

Results are either below the MDC or tracer recovery is low

Failed analysis.

Analytical holding time was exceeded

Value is estimated

Analyte present. Reported value may be biased high. Actual value is expected to be lower.

Analyte present. Reported value may be biased low. Actual value is expected to be higher.

M if above MDC and less than LLD

REMP Result > MDC/CL and < RDL

RPD or %Recovery limits do not apply.

See case narrative

Analyte concentration is not detected above the detection limit

Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier

One or more quality control criteria have not been met. Refer to the applicable narrative or DER.

Sample results are rejected

Analyte was analyzed for, but not detected above the MDL, MDA, MDC or LOD.

Gamma Spectroscopy--Uncertain identification

Gamma Spectroscopy--Uncertain identification

Not considered detected. The associated number is the reported concentration, which may be inaccurate due to a low bias.

Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier

Other specific qualifiers were required to properly define the results. Consult case narrative.

RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL. Qualifier Not Applicable for Radiochemistry.

Preparation or preservation holding time was exceeded

N/A indicates that spike recovery limits do not apply when sample concentration exceeds spike conc. by a factor of 4 or more or %RPD not applicable.^ The Relative Percent Difference (RPD) obtained from the sample duplicate (DUP) is evaluated against the acceptance criteria when the sample is greater thanfive times (5X) the contract required detection limit (RL). In cases where either the sample or duplicate value is less than 5X the RL, a control limit of +/- theRL is used to evaluate the DUP result.* Indicates that a Quality Control parameter was not within specifications.For PS, PSD, and SDILT results, the values listed are the measured amounts, not final concentrations.

Where the analytical method has been performed under NELAP certification, the analysis has met all of therequirements of the NELAC standard unless qualified on the QC Summary.

RPD%

Page 18 of 24

Page 54: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

Radiochemistry Technical Case Narrative

Ameriphysics, LLC (AMPH) SDG #: 398210

Product: Gammaspec, Gamma, Solid - Client List Analytical Method: DOE HASL 300, 4.5.2.3/Ga-01-R Analytical Procedure: GL-RAD-A-013 REV# 25 Analytical Batch: 1570472 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 20 Preparation Batch: 1570378

The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 398210001 1CVF 398210002 6CVF 398210003 2CVEW 398210004 3CVWW 398210005 4CVNW 398210006 5CVHW 398210007 1CVF 398210008 6CVF 398210009 2CVWW 398210010 3CVNW 398210011 4CVSW 398210012 5CVEW 1203556802 Method Blank (MB) 1203556803 398210001(1CVF) Sample Duplicate (DUP) 1203556804 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on a "dry weight" basis.

Data Summary: All sample data provided in this report met the acceptance criteria specified in the analytical methods andprocedures for initial calibration, continuing calibration, instrument controls and process controls whereapplicable, with the following exceptions. Quality Control (QC) Information QC Information All of the QC samples meet the required acceptance limits with the following exceptions: The sample and theduplicate, 1203556803 (1CVFDUP) and 398210001 (1CVF), did not meet the Mn-54 relative percent differencerequirement (0-20%); however, they do meet the relative error ratio requirement (0-3) with a value of 1.76. Qualifier Information

Page 19 of 24

Page 55: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

Qualifier Reason Analyte Sample Client Sample

UIData rejected due to highcounting uncertainty.

Cesium-134 398210012 5CVEW

UIData rejected due to high peak-width.

Cadmium-109 398210007 1CVF

UIData rejected due to interference.

Cobalt-57 398210003 2CVEW

398210006 5CVHW

398210010 3CVNW

Sodium-22 398210003 2CVEW

398210009 2CVWW

UIData rejected due to low abundance.

Cobalt-57 398210001 1CVF

398210002 6CVF

398210004 3CVWW

398210005 4CVNW

398210007 1CVF

398210008 6CVF

1203556803 1CVF(398210001DUP)

Niobium-95 398210003 2CVEW

Silver-110m 398210008 6CVF

Sodium-22 398210001 1CVF

398210005 4CVNW

398210006 5CVHW

398210007 1CVF

398210012 5CVEW

1203556803 1CVF(398210001DUP)

Zinc-65 398210002 6CVF

398210008 6CVF

Certification Statement Where the analytical method has been performed under NELAP certification, the analysis has met all of therequirements of the NELAC standard unless otherwise noted in the analytical case narrative.

Page 20 of 24

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Page 21 of 24

Page 57: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

Page 22 left out intentionally.

Chain of Custody not related to this project.

Page 58: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

Page 23 of 24

Page 59: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

State CertificationAlaska

ArkansasCLIA

California Colorado

ConnecticutDelaware

DoD ELAP/ ISO17025 A2LAFlorida NELAP

Foreign Soils PermitGeorgia

Georgia SDWAHawaii

Idaho ChemistryIdaho Radiochemistry

Illinois NELAPIndiana

Kansas NELAPKentucky SDWA

Kentucky WastewaterLouisiana NELAPLouisiana SDWA

MarylandMassachusetts

MichiganMississippiNebraskaNevada

New Hampshire NELAPNew Jersey NELAP

New MexicoNew York NELAP

North CarolinaNorth Carolina SDWA

North DakotaOklahoma

Pennsylvania NELAPS.Carolina Radchem

South Carolina ChemistryTennessee

Texas NELAPUtah NELAP

VermontVirginia NELAP

WashingtonWest Virginia

UST−011088−0651

42D09040462940

SC00012PH−0169SC000122567.01E87156

P330−15−00283, P330−15−00253SC00012

967SC00012SC00012SC00012200029

C−SC−01E−10332

9012990129

03046 (AI33904)LA160006

270M−SC012

9976SC00012

NE−OS−26−13SC000122016−1

205415SC002

SC0001211501233

45709R−1589904

68−004851012000210120001TN 02934

T104704235−16−11SC000122016−20

VT87156460202C780

997404

List of current GEL Certifications as of 01 June 2016

Page 24 of 24

Page 60: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

Attachment 2 RESRAD-BUILD DCGLactivation Modeling for Radionuclides of Concern

Page 61: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 62: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 63: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 64: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 65: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 66: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 67: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 68: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 69: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 70: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 71: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 72: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 73: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 74: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 75: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 76: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 77: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 78: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 79: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 80: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 81: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 82: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 83: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 84: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 85: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 86: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 87: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 88: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 89: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 90: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 91: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 92: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 93: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 94: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 95: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 96: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 97: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 98: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 99: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 100: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 101: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 102: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 103: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 104: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 105: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 106: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 107: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 108: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 109: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 110: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 111: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 112: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 113: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 114: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 115: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 116: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 117: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 118: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 119: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 120: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 121: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 122: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 123: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 124: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 125: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 126: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 127: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 128: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 129: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 130: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 131: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 132: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 133: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 134: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 135: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 136: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 137: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 138: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 139: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 140: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 141: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 142: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 143: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 144: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 145: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 146: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 147: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 148: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 149: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 150: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 151: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 152: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 153: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 154: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 155: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 156: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 157: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 158: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 159: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 160: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 161: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 162: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 163: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 164: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 165: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 166: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 167: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 168: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 169: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 170: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 171: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 172: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 173: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 174: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 175: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 176: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 177: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 178: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 179: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 180: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 181: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 182: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 183: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 184: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 185: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 186: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 187: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 188: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 189: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 190: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 191: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 192: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 193: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 194: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 195: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 196: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 197: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 198: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 199: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 200: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 201: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 202: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 203: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 204: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 205: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 206: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 207: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 208: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 209: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 210: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 211: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 212: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 213: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 214: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 215: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
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Page 217: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 1 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld ================================================ ================================================ === === === RESRAD-BUILD Table of Contents === === === ================================================ ================================================

RESRAD-BUILD Input Parameters............ 2 Building Information..................... 3 Source Information....................... 4 For time = 0.00E+00 yr Time Specific Parameters.............. 5 Receptor-Source Dose Summary.......... 6 Dose by Pathway Detail................ 7 Dose by Nuclide Detail................ 8 For time = 1.00E+00 yr Time Specific Parameters.............. 9 Receptor-Source Dose Summary.......... 10 Dose by Pathway Detail................ 11 Dose by Nuclide Detail................ 12 Full Summary............................. 13

Page 218: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 2 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld ================================================ ================================================ === === === RESRAD-BUILD Input Parameters === === === ================================================ ================================================ Number of Sources : 1 Number of Receptors: 1 Total Time : 3.650000E+02 days Fraction Inside : 5.000000E-01 ========== Receptor Information ========== Receptor Room x y z FracTime Inhalation Ingestion(Dust) [m] [m] [m] [m3/day] [m2/hr] 1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04 === Receptor-Source Shielding Relationship === Receptor Source Density Thickness Material [g/cm3] [cm] ——————————————————————————————————————————————— 1 1 2.40E+00 0.00E+00 Concrete

Page 219: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 3 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld ======== Building Information ======== Building Air Exchange Rate: 8.00E-01 1/hr Height[m] Air Exchanges [m3/hr] Area [m2] ******************************* * * * * * <=Q01: 7.20E+01 H1: 2.500 * Room 1 * Q10 : 7.20E+01 * LAMBDA: 8.00E-01 * Area 36.000 * * * * ******************************* Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]

Page 220: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 4 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld ======== Source Information ======== Source: 1 Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m] Geometry:: Type: Volume Area:3.60E+01 [m2] Direction: x Pathway :: Direct Ingestion Rate: 0.000E+00 [gm/hr] Fraction released to air: 1.000E-01

Containment :: Number of Regions: 1 Contaminated Region: 1 Region : 1 Thickness [cm] :1.50E+01 Density [g/cm3] :2.40E+00 Material :Concrete Erosion Rate [cm/day] :2.40E-08

Contamination:: Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity) ——————— ————————————— ——————————————————————————————————— Ingestion Inhalation Submersion [pCi/g] [mrem/pCi] [mrem/pCi] [mrem/yr/ (pCi/m3)] FE-55 1.000E+00 6.070E-07 2.690E-06 0.000E+00

Page 221: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 5 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld Evaluation Time: 0.00000000E+00 years ================================================ ================================================ === Assessment for Time: 1 === === Time =0.00E+00 yr === ================================================ ================================================ ======== Source Information ======== Source: 1 Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m] Geometry:: Type: Volume Area:3.60E+01 [m2] Direction: x Pathway :: Direct Ingestion Rate : 0.000E+00 [gm/hr] Fraction released to air: 1.000E-01

Containment :: Number of Regions: 1 Contaminated Region: 1 Region : 1 Thickness [cm] :1.50E+01 Fraction Contaminated :1.00E+00 Density [g/cm3] :2.40E+00

Contamination:: Nuclide Concentration [pCi/g] FE-55 1.000E+00

Page 222: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 6 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld Evaluation Time: 0.00000000E+00 years ================================================ ================================================ === === === RESRAD-BUILD Dose Tables === === === ================================================ ================================================ Source Contributions to Receptor Doses ====================================== [mrem] Source Total 1 Receptor 1 1.16E-08 1.16E-08 Total 1.16E-08 1.16E-08

Page 223: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 7 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld Evaluation Time: 0.00000000E+00 years Pathway Detail of Doses ======================= [mrem] Source: 1 Receptor External Deposition Immersion Inhalation Radon Ingestion 1 0.00E+00 0.00E+00 0.00E+00 7.26E-09 0.00E+00 4.30E-09 Total 0.00E+00 0.00E+00 0.00E+00 7.26E-09 0.00E+00 4.30E-09

Page 224: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 8 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld Evaluation Time: 0.00000000E+00 years Nuclide Detail of Doses ======================= [mrem] Source: 1 Nuclide Receptor Total 1 FE-55 1.16E-08 1.16E-08

Page 225: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 9 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld Evaluation Time: 1.00000000 years ================================================ ================================================ === Assessment for Time: 2 === === Time =1.00E+00 yr === ================================================ ================================================ ======== Source Information ======== Source: 1 Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m] Geometry:: Type: Volume Area:3.60E+01 [m2] Direction: x Pathway :: Direct Ingestion Rate : 0.000E+00 [gm/hr] Fraction released to air: 1.000E-01

Containment :: Number of Regions: 1 Contaminated Region: 1 Region : 1 Thickness [cm] :1.50E+01 Fraction Contaminated :1.00E+00 Density [g/cm3] :2.40E+00

Contamination:: Nuclide Concentration [pCi/g] FE-55 7.736E-01

Page 226: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 10 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld Evaluation Time: 1.00000000 years ================================================ ================================================ === === === RESRAD-BUILD Dose Tables === === === ================================================ ================================================ Source Contributions to Receptor Doses ====================================== [mrem] Source Total 1 Receptor 1 8.94E-09 8.94E-09 Total 8.94E-09 8.94E-09

Page 227: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 11 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld Evaluation Time: 1.00000000 years Pathway Detail of Doses ======================= [mrem] Source: 1 Receptor External Deposition Immersion Inhalation Radon Ingestion 1 0.00E+00 0.00E+00 0.00E+00 5.62E-09 0.00E+00 3.33E-09 Total 0.00E+00 0.00E+00 0.00E+00 5.62E-09 0.00E+00 3.33E-09

Page 228: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 12 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld Evaluation Time: 1.00000000 years Nuclide Detail of Doses ======================= [mrem] Source: 1 Nuclide Receptor Total 1 FE-55 8.94E-09 8.94E-09

Page 229: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 13 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld Full Summary ================================================ ================================================ === === === RESRAD-BUILD Dose (Time) Tables === === === ================================================ ================================================ Receptor Dose Received for the Exposure Duration ================================================ (mrem) Evaluation Time [yr] 0.00E+00 1.00E+00 ———————— ———————— 1 1.16E-08 8.94E-09 Receptor Dose/Yr Averaged Over Exposure Duration ================================================ (mrem/yr) Evaluation Time [yr] 0.00E+00 1.00E+00 ———————— ———————— 1 1.16E-08 8.95E-09

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** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 1 ** Title : H-3 @ 1 pCi/g Input File : site1.bld ================================================ ================================================ === === === RESRAD-BUILD Table of Contents === === === ================================================ ================================================

RESRAD-BUILD Input Parameters............ 2 Building Information..................... 3 Source Information....................... 4 For time = 0.00E+00 yr Time Specific Parameters.............. 5 Receptor-Source Dose Summary.......... 6 Dose by Pathway Detail................ 7 Dose by Nuclide Detail................ 8 For time = 1.00E+00 yr Time Specific Parameters.............. 9 Receptor-Source Dose Summary.......... 10 Dose by Pathway Detail................ 11 Dose by Nuclide Detail................ 12 Full Summary............................. 13

Page 244: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 2 ** Title : H-3 @ 1 pCi/g Input File : site1.bld ================================================ ================================================ === === === RESRAD-BUILD Input Parameters === === === ================================================ ================================================ Number of Sources : 1 Number of Receptors: 1 Total Time : 3.650000E+02 days Fraction Inside : 5.000000E-01 ========== Receptor Information ========== Receptor Room x y z FracTime Inhalation Ingestion(Dust) [m] [m] [m] [m3/day] [m2/hr] 1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04 === Receptor-Source Shielding Relationship === Receptor Source Density Thickness Material [g/cm3] [cm] ——————————————————————————————————————————————— 1 1 2.40E+00 0.00E+00 Concrete

Page 245: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 3 ** Title : H-3 @ 1 pCi/g Input File : site1.bld ======== Building Information ======== Building Air Exchange Rate: 8.00E-01 1/hr Height[m] Air Exchanges [m3/hr] Area [m2] ******************************* * * * * * <=Q01: 7.20E+01 H1: 2.500 * Room 1 * Q10 : 7.20E+01 * LAMBDA: 8.00E-01 * Area 36.000 * * * * ******************************* Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]

Page 246: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 4 ** Title : H-3 @ 1 pCi/g Input File : site1.bld ======== Source Information ======== Source: 1 Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m] Geometry:: Type: Volume Area:3.60E+01 [m2] Direction: x Tritium Volume Parameters :: Total Thickness: 1.000E+01 [cm] Dry Thickness: 0.000E+00 [cm] Volumetric Water Content: 3.000E-02 Wall Total Porosity: 1.000E-01 Volatization Fraction: 1.000E+00 Wall Density: 2.400E+00 [gm/cm3] Humidity: 8.000E+00 [gm/m3] Erosion rate: 2.400E-08 [cm/d] Direct Ingestion Rate: 0.000E+00 [gm/hr] Fraction released to air: 1.000E-01

Contamination:: Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity) ——————— ————————————— ——————————————————————————————————— Ingestion Inhalation Submersion [pCi/g] [mrem/pCi] [mrem/pCi] [mrem/yr/ (pCi/m3)] H-3 1.000E+00 6.400E-08 6.400E-08 3.866E-08

Page 247: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 5 ** Title : H-3 @ 1 pCi/g Input File : site1.bld Evaluation Time: 0.00000000E+00 years ================================================ ================================================ === Assessment for Time: 1 === === Time =0.00E+00 yr === ================================================ ================================================ ======== Source Information ======== Source: 1 Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m] Geometry:: Type: Volume Area:3.60E+01 [m2] Direction: x Contamination :: Total Thickness: 1.000E+01 [cm] Dry Thickness: 0.000E+00 [cm] Volumetric Water Content: 3.000E-02 Wall Total Porosity: 1.000E-01 Volatization Fraction: 1.000E+00 Wall Density: 2.400E+00 [gm/cm3] Humidity: 8.000E+00 [gm/m3] Erosion Rate: 2.400E-08 [cm/d]

Contamination:: Tritium in Volume Source Initial Volatile Activity [pCi] : 8640000.00 Remaining Volatization Time [yr] : 0.417022973 Unvolatizable activity remaining [pCi]: 0.00000000E+00

Page 248: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 6 ** Title : H-3 @ 1 pCi/g Input File : site1.bld Evaluation Time: 0.00000000E+00 years ================================================ ================================================ === === === RESRAD-BUILD Dose Tables === === === ================================================ ================================================ Source Contributions to Receptor Doses ====================================== [mrem] Source Total 1 Receptor 1 9.67E-03 9.67E-03 Total 9.67E-03 9.67E-03

Page 249: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 7 ** Title : H-3 @ 1 pCi/g Input File : site1.bld Evaluation Time: 0.00000000E+00 years Pathway Detail of Doses ======================= [mrem] Source: 1 Receptor External Deposition Immersion Inhalation Radon Ingestion 1 0.00E+00 0.00E+00 2.14E-07 3.49E-03 0.00E+00 6.18E-03 Total 0.00E+00 0.00E+00 2.14E-07 3.49E-03 0.00E+00 6.18E-03

Page 250: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 8 ** Title : H-3 @ 1 pCi/g Input File : site1.bld Evaluation Time: 0.00000000E+00 years Nuclide Detail of Doses ======================= [mrem] Source: 1 Nuclide Receptor Total 1 H-3 9.67E-03 9.67E-03

Page 251: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 9 ** Title : H-3 @ 1 pCi/g Input File : site1.bld Evaluation Time: 1.00000000 years ================================================ ================================================ === Assessment for Time: 2 === === Time =1.00E+00 yr === ================================================ ================================================ ======== Source Information ======== Source: 1 Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m] Geometry:: Type: Volume Area:3.60E+01 [m2] Direction: x Contamination :: Total Thickness: 1.000E+01 [cm] Dry Thickness: 0.000E+00 [cm] Volumetric Water Content: 3.000E-02 Wall Total Porosity: 1.000E-01 Volatization Fraction: 1.000E+00 Wall Density: 2.400E+00 [gm/cm3] Humidity: 8.000E+00 [gm/m3] Erosion Rate: 2.400E-08 [cm/d]

Contamination:: Tritium in Volume Source Initial Volatile Activity [pCi] : 8640000.00 Remaining Volatization Time [yr] : 0.00000000E+00 Unvolatizable activity remaining [pCi]: 0.00000000E+00

Page 252: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 10 ** Title : H-3 @ 1 pCi/g Input File : site1.bld Evaluation Time: 1.00000000 years ================================================ ================================================ === === === RESRAD-BUILD Dose Tables === === === ================================================ ================================================ Source Contributions to Receptor Doses ====================================== [mrem] Source Total 1 Receptor 1 0.00E+00 0.00E+00 Total 0.00E+00 0.00E+00

Page 253: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 11 ** Title : H-3 @ 1 pCi/g Input File : site1.bld Evaluation Time: 1.00000000 years Pathway Detail of Doses ======================= [mrem] Source: 1 Receptor External Deposition Immersion Inhalation Radon Ingestion 1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 254: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 12 ** Title : H-3 @ 1 pCi/g Input File : site1.bld Evaluation Time: 1.00000000 years Nuclide Detail of Doses ======================= [mrem] Source: 1 Nuclide Receptor Total 1 H-3 0.00E+00 0.00E+00

Page 255: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 13 ** Title : H-3 @ 1 pCi/g Input File : site1.bld Full Summary ================================================ ================================================ === === === RESRAD-BUILD Dose (Time) Tables === === === ================================================ ================================================ Receptor Dose Received for the Exposure Duration ================================================ (mrem) Evaluation Time [yr] 0.00E+00 1.00E+00 ———————— ———————— 1 9.67E-03 0.00E+00 Receptor Dose/Yr Averaged Over Exposure Duration ================================================ (mrem/yr) Evaluation Time [yr] 0.00E+00 1.00E+00 ———————— ———————— 1 9.67E-03 0.00E+00

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Page 270: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 271: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 272: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 273: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
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Page 275: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 276: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 277: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 278: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 279: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 280: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 281: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 282: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 283: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
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Page 285: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
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Page 289: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
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Page 292: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 293: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 294: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 295: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 296: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 297: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
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Page 299: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 300: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 301: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 302: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 303: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 304: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 305: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 306: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 307: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 308: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
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Attachment 3 RESRAD-BUILD DCGLsurface Modeling for Radionuclides of Concern

Page 335: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 1 **

Title : Ag-108m

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Table of Contents ===

=== ===

================================================

================================================

RESRAD-BUILD Input Parameters............ 2

Building Information..................... 3

Source Information....................... 4

For time = 0.00E+00 yr

Time Specific Parameters.............. 5

Receptor-Source Dose Summary.......... 6

Dose by Pathway Detail................ 7

Dose by Nuclide Detail................ 8

For time = 1.00E+00 yr

Time Specific Parameters.............. 9

Receptor-Source Dose Summary.......... 10

Dose by Pathway Detail................ 11

Dose by Nuclide Detail................ 12

Full Summary............................. 13

Page 336: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 2 **

Title : Ag-108m

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Input Parameters ===

=== ===

================================================

================================================

Number of Sources : 1

Number of Receptors: 1

Total Time : 3.650000E+02 days

Fraction Inside : 5.000000E-01

========== Receptor Information ==========

Receptor Room x y z FracTime Inhalation Ingestion(Dust)

[m] [m] [m] [m3/day] [m2/hr]

1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04

=== Receptor-Source Shielding Relationship ===

Receptor Source Density Thickness Material

[g/cm3] [cm]

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

1 1 2.40E+00 0.00E+00 Concrete

Page 337: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 3 **

Title : Ag-108m

Input File : site1.bld

======== Building Information ========

Building Air Exchange Rate: 8.00E-01 1/hr

Height[m] Air Exchanges [m3/hr]

Area [m2]

*******************************

* *

* *

* <=Q01: 7.20E+01

H1: 2.500 * Room 1 * Q10 : 7.20E+01

* LAMBDA: 8.00E-01 *

Area 36.000 * *

* *

*******************************

Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]

Page 338: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 4 **

Title : Ag-108m

Input File : site1.bld

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination::

Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

Ingestion Inhalation Submersion

[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/

(dpm/m3)]

AG-108M 2.800E+06 3.432E-06 1.275E-04 4.108E-03

Page 339: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 5 **

Title : Ag-108m

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== Assessment for Time: 1 ===

=== Time =0.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

AG-108M 2.800E+06

Page 340: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 6 **

Title : Ag-108m

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 2.50E+01 2.50E+01

Total 2.50E+01 2.50E+01

Page 341: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 7 **

Title : Ag-108m

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 1.99E+01 1.57E+00 1.59E-02 3.25E+00 0.00E+00 2.33E-01

Total 1.99E+01 1.57E+00 1.59E-02 3.25E+00 0.00E+00 2.33E-01

Page 342: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 8 **

Title : Ag-108m

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

AG-108M 2.50E+01 2.50E+01

Page 343: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 9 **

Title : Ag-108m

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== Assessment for Time: 2 ===

=== Time =1.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 0.000E+00

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

AG-108M 1.392E+06

Page 344: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 10 **

Title : Ag-108m

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 1.32E+01 1.32E+01

Total 1.32E+01 1.32E+01

Page 345: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 11 **

Title : Ag-108m

Input File : site1.bld

Evaluation Time: 1.00000000 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 1.32E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Total 1.32E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 346: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 12 **

Title : Ag-108m

Input File : site1.bld

Evaluation Time: 1.00000000 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

AG-108M 1.32E+01 1.32E+01

Page 347: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 13 **

Title : Ag-108m

Input File : site1.bld

Full Summary

================================================

================================================

=== ===

=== RESRAD-BUILD Dose (Time) Tables ===

=== ===

================================================

================================================

Receptor Dose Received for the Exposure Duration

================================================

(mrem)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.50E+01 1.32E+01

Receptor Dose/Yr Averaged Over Exposure Duration

================================================

(mrem/yr)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.50E+01 1.32E+01

Page 348: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 1 **

Title : Ag-110m

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Table of Contents ===

=== ===

================================================

================================================

RESRAD-BUILD Input Parameters............ 2

Building Information..................... 3

Source Information....................... 4

For time = 0.00E+00 yr

Time Specific Parameters.............. 5

Receptor-Source Dose Summary.......... 6

Dose by Pathway Detail................ 7

Dose by Nuclide Detail................ 8

For time = 1.00E+00 yr

Time Specific Parameters.............. 9

Receptor-Source Dose Summary.......... 10

Dose by Pathway Detail................ 11

Dose by Nuclide Detail................ 12

Full Summary............................. 13

Page 349: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 2 **

Title : Ag-110m

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Input Parameters ===

=== ===

================================================

================================================

Number of Sources : 1

Number of Receptors: 1

Total Time : 3.650000E+02 days

Fraction Inside : 5.000000E-01

========== Receptor Information ==========

Receptor Room x y z FracTime Inhalation Ingestion(Dust)

[m] [m] [m] [m3/day] [m2/hr]

1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04

=== Receptor-Source Shielding Relationship ===

Receptor Source Density Thickness Material

[g/cm3] [cm]

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

1 1 2.40E+00 0.00E+00 Concrete

Page 350: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 3 **

Title : Ag-110m

Input File : site1.bld

======== Building Information ========

Building Air Exchange Rate: 8.00E-01 1/hr

Height[m] Air Exchanges [m3/hr]

Area [m2]

*******************************

* *

* *

* <=Q01: 7.20E+01

H1: 2.500 * Room 1 * Q10 : 7.20E+01

* LAMBDA: 8.00E-01 *

Area 36.000 * *

* *

*******************************

Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]

Page 351: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 4 **

Title : Ag-110m

Input File : site1.bld

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination::

Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

Ingestion Inhalation Submersion

[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/

(dpm/m3)]

AG-110M 3.000E+06 4.865E-06 3.617E-05 7.157E-03

Page 352: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 5 **

Title : Ag-110m

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== Assessment for Time: 1 ===

=== Time =0.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

AG-110M 3.000E+06

Page 353: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 6 **

Title : Ag-110m

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 2.48E+01 2.48E+01

Total 2.48E+01 2.48E+01

Page 354: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 7 **

Title : Ag-110m

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 2.36E+01 8.04E-01 9.13E-03 3.03E-01 0.00E+00 1.02E-01

Total 2.36E+01 8.04E-01 9.13E-03 3.03E-01 0.00E+00 1.02E-01

Page 355: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 8 **

Title : Ag-110m

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

AG-110M 2.48E+01 2.48E+01

Page 356: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 9 **

Title : Ag-110m

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== Assessment for Time: 2 ===

=== Time =1.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 0.000E+00

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

AG-110M 5.445E+05

Page 357: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 10 **

Title : Ag-110m

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 5.41E+00 5.41E+00

Total 5.41E+00 5.41E+00

Page 358: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 11 **

Title : Ag-110m

Input File : site1.bld

Evaluation Time: 1.00000000 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 5.41E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Total 5.41E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 359: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 12 **

Title : Ag-110m

Input File : site1.bld

Evaluation Time: 1.00000000 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

AG-110M 5.41E+00 5.41E+00

Page 360: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 13 **

Title : Ag-110m

Input File : site1.bld

Full Summary

================================================

================================================

=== ===

=== RESRAD-BUILD Dose (Time) Tables ===

=== ===

================================================

================================================

Receptor Dose Received for the Exposure Duration

================================================

(mrem)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.48E+01 5.41E+00

Receptor Dose/Yr Averaged Over Exposure Duration

================================================

(mrem/yr)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.48E+01 5.41E+00

Page 361: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 1 **

Title : Cd-109

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Table of Contents ===

=== ===

================================================

================================================

RESRAD-BUILD Input Parameters............ 2

Building Information..................... 3

Source Information....................... 4

For time = 0.00E+00 yr

Time Specific Parameters.............. 5

Receptor-Source Dose Summary.......... 6

Dose by Pathway Detail................ 7

Dose by Nuclide Detail................ 8

For time = 1.00E+00 yr

Time Specific Parameters.............. 9

Receptor-Source Dose Summary.......... 10

Dose by Pathway Detail................ 11

Dose by Nuclide Detail................ 12

Full Summary............................. 13

Page 362: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 2 **

Title : Cd-109

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Input Parameters ===

=== ===

================================================

================================================

Number of Sources : 1

Number of Receptors: 1

Total Time : 3.650000E+02 days

Fraction Inside : 5.000000E-01

========== Receptor Information ==========

Receptor Room x y z FracTime Inhalation Ingestion(Dust)

[m] [m] [m] [m3/day] [m2/hr]

1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04

=== Receptor-Source Shielding Relationship ===

Receptor Source Density Thickness Material

[g/cm3] [cm]

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

1 1 2.40E+00 0.00E+00 Concrete

Page 363: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 3 **

Title : Cd-109

Input File : site1.bld

======== Building Information ========

Building Air Exchange Rate: 8.00E-01 1/hr

Height[m] Air Exchanges [m3/hr]

Area [m2]

*******************************

* *

* *

* <=Q01: 7.20E+01

H1: 2.500 * Room 1 * Q10 : 7.20E+01

* LAMBDA: 8.00E-01 *

Area 36.000 * *

* *

*******************************

Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]

Page 364: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 4 **

Title : Cd-109

Input File : site1.bld

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination::

Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

Ingestion Inhalation Submersion

[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/

(dpm/m3)]

CD-109 5.200E+07 5.901E-06 5.135E-05 1.547E-05

Page 365: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 5 **

Title : Cd-109

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== Assessment for Time: 1 ===

=== Time =0.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

CD-109 5.200E+07

Page 366: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 6 **

Title : Cd-109

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 2.46E+01 2.46E+01

Total 2.46E+01 2.46E+01

Page 367: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 7 **

Title : Cd-109

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 8.87E+00 4.14E-01 5.44E-04 1.19E+01 0.00E+00 3.51E+00

Total 8.87E+00 4.14E-01 5.44E-04 1.19E+01 0.00E+00 3.51E+00

Page 368: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 8 **

Title : Cd-109

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

CD-109 2.46E+01 2.46E+01

Page 369: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 9 **

Title : Cd-109

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== Assessment for Time: 2 ===

=== Time =1.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 0.000E+00

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

CD-109 1.506E+07

Page 370: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 10 **

Title : Cd-109

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 3.32E+00 3.32E+00

Total 3.32E+00 3.32E+00

Page 371: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 11 **

Title : Cd-109

Input File : site1.bld

Evaluation Time: 1.00000000 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 3.32E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Total 3.32E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 372: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 12 **

Title : Cd-109

Input File : site1.bld

Evaluation Time: 1.00000000 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

CD-109 3.32E+00 3.32E+00

Page 373: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 13 **

Title : Cd-109

Input File : site1.bld

Full Summary

================================================

================================================

=== ===

=== RESRAD-BUILD Dose (Time) Tables ===

=== ===

================================================

================================================

Receptor Dose Received for the Exposure Duration

================================================

(mrem)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.46E+01 3.32E+00

Receptor Dose/Yr Averaged Over Exposure Duration

================================================

(mrem/yr)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.47E+01 3.33E+00

Page 374: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 1 **

Title : Co-56

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Table of Contents ===

=== ===

================================================

================================================

RESRAD-BUILD Input Parameters............ 2

Building Information..................... 3

Source Information....................... 4

For time = 0.00E+00 yr

Time Specific Parameters.............. 5

Receptor-Source Dose Summary.......... 6

Dose by Pathway Detail................ 7

Dose by Nuclide Detail................ 8

For time = 1.00E+00 yr

Time Specific Parameters.............. 9

Receptor-Source Dose Summary.......... 10

Dose by Pathway Detail................ 11

Dose by Nuclide Detail................ 12

Full Summary............................. 13

Page 375: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 2 **

Title : Co-56

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Input Parameters ===

=== ===

================================================

================================================

Number of Sources : 1

Number of Receptors: 1

Total Time : 3.650000E+02 days

Fraction Inside : 5.000000E-01

========== Receptor Information ==========

Receptor Room x y z FracTime Inhalation Ingestion(Dust)

[m] [m] [m] [m3/day] [m2/hr]

1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04

=== Receptor-Source Shielding Relationship ===

Receptor Source Density Thickness Material

[g/cm3] [cm]

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

1 1 2.40E+00 0.00E+00 Concrete

Page 376: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 3 **

Title : Co-56

Input File : site1.bld

======== Building Information ========

Building Air Exchange Rate: 8.00E-01 1/hr

Height[m] Air Exchanges [m3/hr]

Area [m2]

*******************************

* *

* *

* <=Q01: 7.20E+01

H1: 2.500 * Room 1 * Q10 : 7.20E+01

* LAMBDA: 8.00E-01 *

Area 36.000 * *

* *

*******************************

Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]

Page 377: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 4 **

Title : Co-56

Input File : site1.bld

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination::

Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

Ingestion Inhalation Submersion

[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/

(dpm/m3)]

CO-56 7.400E+06 5.676E-06 1.784E-05 9.628E-03

Page 378: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 5 **

Title : Co-56

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== Assessment for Time: 1 ===

=== Time =0.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

CO-56 7.400E+06

Page 379: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 6 **

Title : Co-56

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 2.48E+01 2.48E+01

Total 2.48E+01 2.48E+01

Page 380: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 7 **

Title : Co-56

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 2.43E+01 3.49E-01 7.51E-03 9.13E-02 0.00E+00 6.44E-02

Total 2.43E+01 3.49E-01 7.51E-03 9.13E-02 0.00E+00 6.44E-02

Page 381: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 8 **

Title : Co-56

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

CO-56 2.48E+01 2.48E+01

Page 382: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 9 **

Title : Co-56

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== Assessment for Time: 2 ===

=== Time =1.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 0.000E+00

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

CO-56 1.495E+05

Page 383: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 10 **

Title : Co-56

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 5.66E-01 5.66E-01

Total 5.66E-01 5.66E-01

Page 384: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 11 **

Title : Co-56

Input File : site1.bld

Evaluation Time: 1.00000000 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 5.66E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Total 5.66E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 385: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 12 **

Title : Co-56

Input File : site1.bld

Evaluation Time: 1.00000000 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

CO-56 5.66E-01 5.66E-01

Page 386: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 13 **

Title : Co-56

Input File : site1.bld

Full Summary

================================================

================================================

=== ===

=== RESRAD-BUILD Dose (Time) Tables ===

=== ===

================================================

================================================

Receptor Dose Received for the Exposure Duration

================================================

(mrem)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.48E+01 5.66E-01

Receptor Dose/Yr Averaged Over Exposure Duration

================================================

(mrem/yr)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.48E+01 5.67E-01

Page 387: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 1 **

Title : Co-57

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Table of Contents ===

=== ===

================================================

================================================

RESRAD-BUILD Input Parameters............ 2

Building Information..................... 3

Source Information....................... 4

For time = 0.00E+00 yr

Time Specific Parameters.............. 5

Receptor-Source Dose Summary.......... 6

Dose by Pathway Detail................ 7

Dose by Nuclide Detail................ 8

For time = 1.00E+00 yr

Time Specific Parameters.............. 9

Receptor-Source Dose Summary.......... 10

Dose by Pathway Detail................ 11

Dose by Nuclide Detail................ 12

Full Summary............................. 13

Page 388: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 2 **

Title : Co-57

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Input Parameters ===

=== ===

================================================

================================================

Number of Sources : 1

Number of Receptors: 1

Total Time : 3.650000E+02 days

Fraction Inside : 5.000000E-01

========== Receptor Information ==========

Receptor Room x y z FracTime Inhalation Ingestion(Dust)

[m] [m] [m] [m3/day] [m2/hr]

1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04

=== Receptor-Source Shielding Relationship ===

Receptor Source Density Thickness Material

[g/cm3] [cm]

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

1 1 2.40E+00 0.00E+00 Concrete

Page 389: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 3 **

Title : Co-57

Input File : site1.bld

======== Building Information ========

Building Air Exchange Rate: 8.00E-01 1/hr

Height[m] Air Exchanges [m3/hr]

Area [m2]

*******************************

* *

* *

* <=Q01: 7.20E+01

H1: 2.500 * Room 1 * Q10 : 7.20E+01

* LAMBDA: 8.00E-01 *

Area 36.000 * *

* *

*******************************

Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]

Page 390: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 4 **

Title : Co-57

Input File : site1.bld

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination::

Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

Ingestion Inhalation Submersion

[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/

(dpm/m3)]

CO-57 6.600E+07 5.315E-07 4.086E-06 2.952E-04

Page 391: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 5 **

Title : Co-57

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== Assessment for Time: 1 ===

=== Time =0.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

CO-57 6.600E+07

Page 392: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 6 **

Title : Co-57

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 2.49E+01 2.49E+01

Total 2.49E+01 2.49E+01

Page 393: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 7 **

Title : Co-57

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 2.30E+01 8.21E-01 8.90E-03 8.09E-01 0.00E+00 2.65E-01

Total 2.30E+01 8.21E-01 8.90E-03 8.09E-01 0.00E+00 2.65E-01

Page 394: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 8 **

Title : Co-57

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

CO-57 2.49E+01 2.49E+01

Page 395: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 9 **

Title : Co-57

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== Assessment for Time: 2 ===

=== Time =1.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 0.000E+00

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

CO-57 1.297E+07

Page 396: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 10 **

Title : Co-57

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 5.73E+00 5.73E+00

Total 5.73E+00 5.73E+00

Page 397: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 11 **

Title : Co-57

Input File : site1.bld

Evaluation Time: 1.00000000 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 5.73E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Total 5.73E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 398: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 12 **

Title : Co-57

Input File : site1.bld

Evaluation Time: 1.00000000 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

CO-57 5.73E+00 5.73E+00

Page 399: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 13 **

Title : Co-57

Input File : site1.bld

Full Summary

================================================

================================================

=== ===

=== RESRAD-BUILD Dose (Time) Tables ===

=== ===

================================================

================================================

Receptor Dose Received for the Exposure Duration

================================================

(mrem)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.49E+01 5.73E+00

Receptor Dose/Yr Averaged Over Exposure Duration

================================================

(mrem/yr)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.49E+01 5.74E+00

Page 400: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 1 **

Title : Co-58

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Table of Contents ===

=== ===

================================================

================================================

RESRAD-BUILD Input Parameters............ 2

Building Information..................... 3

Source Information....................... 4

For time = 0.00E+00 yr

Time Specific Parameters.............. 5

Receptor-Source Dose Summary.......... 6

Dose by Pathway Detail................ 7

Dose by Nuclide Detail................ 8

For time = 1.00E+00 yr

Time Specific Parameters.............. 9

Receptor-Source Dose Summary.......... 10

Dose by Pathway Detail................ 11

Dose by Nuclide Detail................ 12

Full Summary............................. 13

Page 401: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 2 **

Title : Co-58

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Input Parameters ===

=== ===

================================================

================================================

Number of Sources : 1

Number of Receptors: 1

Total Time : 3.650000E+02 days

Fraction Inside : 5.000000E-01

========== Receptor Information ==========

Receptor Room x y z FracTime Inhalation Ingestion(Dust)

[m] [m] [m] [m3/day] [m2/hr]

1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04

=== Receptor-Source Shielding Relationship ===

Receptor Source Density Thickness Material

[g/cm3] [cm]

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

1 1 2.40E+00 0.00E+00 Concrete

Page 402: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 3 **

Title : Co-58

Input File : site1.bld

======== Building Information ========

Building Air Exchange Rate: 8.00E-01 1/hr

Height[m] Air Exchanges [m3/hr]

Area [m2]

*******************************

* *

* *

* <=Q01: 7.20E+01

H1: 2.500 * Room 1 * Q10 : 7.20E+01

* LAMBDA: 8.00E-01 *

Area 36.000 * *

* *

*******************************

Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]

Page 403: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 4 **

Title : Co-58

Input File : site1.bld

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination::

Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

Ingestion Inhalation Submersion

[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/

(dpm/m3)]

CO-58 2.000E+08 1.613E-06 4.910E-06 2.504E-03

Page 404: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 5 **

Title : Co-58

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== Assessment for Time: 1 ===

=== Time =0.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

CO-58 2.000E+08

Page 405: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 6 **

Title : Co-58

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 2.46E+01 2.46E+01

Total 2.46E+01 2.46E+01

Page 406: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 7 **

Title : Co-58

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 2.33E+01 3.04E-01 4.49E-02 5.78E-01 0.00E+00 4.13E-01

Total 2.33E+01 3.04E-01 4.49E-02 5.78E-01 0.00E+00 4.13E-01

Page 407: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 8 **

Title : Co-58

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

CO-58 2.46E+01 2.46E+01

Page 408: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 9 **

Title : Co-58

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== Assessment for Time: 2 ===

=== Time =1.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 0.000E+00

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

CO-58 2.807E+06

Page 409: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 10 **

Title : Co-58

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 3.74E-01 3.74E-01

Total 3.74E-01 3.74E-01

Page 410: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 11 **

Title : Co-58

Input File : site1.bld

Evaluation Time: 1.00000000 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 3.74E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Total 3.74E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 411: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 12 **

Title : Co-58

Input File : site1.bld

Evaluation Time: 1.00000000 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

CO-58 3.74E-01 3.74E-01

Page 412: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 13 **

Title : Co-58

Input File : site1.bld

Full Summary

================================================

================================================

=== ===

=== RESRAD-BUILD Dose (Time) Tables ===

=== ===

================================================

================================================

Receptor Dose Received for the Exposure Duration

================================================

(mrem)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.46E+01 3.74E-01

Receptor Dose/Yr Averaged Over Exposure Duration

================================================

(mrem/yr)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.46E+01 3.74E-01

Page 413: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 1 **

Title : Co-60

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Table of Contents ===

=== ===

================================================

================================================

RESRAD-BUILD Input Parameters............ 2

Building Information..................... 3

Source Information....................... 4

For time = 0.00E+00 yr

Time Specific Parameters.............. 5

Receptor-Source Dose Summary.......... 6

Dose by Pathway Detail................ 7

Dose by Nuclide Detail................ 8

For time = 1.00E+00 yr

Time Specific Parameters.............. 9

Receptor-Source Dose Summary.......... 10

Dose by Pathway Detail................ 11

Dose by Nuclide Detail................ 12

Full Summary............................. 13

Page 414: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 2 **

Title : Co-60

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Input Parameters ===

=== ===

================================================

================================================

Number of Sources : 1

Number of Receptors: 1

Total Time : 3.650000E+02 days

Fraction Inside : 5.000000E-01

========== Receptor Information ==========

Receptor Room x y z FracTime Inhalation Ingestion(Dust)

[m] [m] [m] [m3/day] [m2/hr]

1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04

=== Receptor-Source Shielding Relationship ===

Receptor Source Density Thickness Material

[g/cm3] [cm]

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

1 1 2.40E+00 0.00E+00 Concrete

Page 415: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 3 **

Title : Co-60

Input File : site1.bld

======== Building Information ========

Building Air Exchange Rate: 8.00E-01 1/hr

Height[m] Air Exchanges [m3/hr]

Area [m2]

*******************************

* *

* *

* <=Q01: 7.20E+01

H1: 2.500 * Room 1 * Q10 : 7.20E+01

* LAMBDA: 8.00E-01 *

Area 36.000 * *

* *

*******************************

Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]

Page 416: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 4 **

Title : Co-60

Input File : site1.bld

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination::

Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

Ingestion Inhalation Submersion

[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/

(dpm/m3)]

CO-60 2.100E+06 1.212E-05 9.865E-05 6.629E-03

Page 417: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 5 **

Title : Co-60

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== Assessment for Time: 1 ===

=== Time =0.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

CO-60 2.100E+06

Page 418: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 6 **

Title : Co-60

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 2.40E+01 2.40E+01

Total 2.40E+01 2.40E+01

Page 419: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 7 **

Title : Co-60

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 2.05E+01 1.39E+00 1.59E-02 1.55E+00 0.00E+00 5.05E-01

Total 2.05E+01 1.39E+00 1.59E-02 1.55E+00 0.00E+00 5.05E-01

Page 420: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 8 **

Title : Co-60

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

CO-60 2.40E+01 2.40E+01

Page 421: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 9 **

Title : Co-60

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== Assessment for Time: 2 ===

=== Time =1.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 0.000E+00

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

CO-60 9.206E+05

Page 422: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 10 **

Title : Co-60

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 1.19E+01 1.19E+01

Total 1.19E+01 1.19E+01

Page 423: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 11 **

Title : Co-60

Input File : site1.bld

Evaluation Time: 1.00000000 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 1.19E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Total 1.19E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 424: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 12 **

Title : Co-60

Input File : site1.bld

Evaluation Time: 1.00000000 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

CO-60 1.19E+01 1.19E+01

Page 425: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 13 **

Title : Co-60

Input File : site1.bld

Full Summary

================================================

================================================

=== ===

=== RESRAD-BUILD Dose (Time) Tables ===

=== ===

================================================

================================================

Receptor Dose Received for the Exposure Duration

================================================

(mrem)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.40E+01 1.19E+01

Receptor Dose/Yr Averaged Over Exposure Duration

================================================

(mrem/yr)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.40E+01 1.19E+01

Page 426: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 1 **

Title : Cr-51

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Table of Contents ===

=== ===

================================================

================================================

RESRAD-BUILD Input Parameters............ 2

Building Information..................... 3

Source Information....................... 4

For time = 0.00E+00 yr

Time Specific Parameters.............. 5

Receptor-Source Dose Summary.......... 6

Dose by Pathway Detail................ 7

Dose by Nuclide Detail................ 8

For time = 1.00E+00 yr

Time Specific Parameters.............. 9

Receptor-Source Dose Summary.......... 10

Dose by Pathway Detail................ 11

Dose by Nuclide Detail................ 12

Full Summary............................. 13

Page 427: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 2 **

Title : Cr-51

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Input Parameters ===

=== ===

================================================

================================================

Number of Sources : 1

Number of Receptors: 1

Total Time : 3.650000E+02 days

Fraction Inside : 5.000000E-01

========== Receptor Information ==========

Receptor Room x y z FracTime Inhalation Ingestion(Dust)

[m] [m] [m] [m3/day] [m2/hr]

1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04

=== Receptor-Source Shielding Relationship ===

Receptor Source Density Thickness Material

[g/cm3] [cm]

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

1 1 2.40E+00 0.00E+00 Concrete

Page 428: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 3 **

Title : Cr-51

Input File : site1.bld

======== Building Information ========

Building Air Exchange Rate: 8.00E-01 1/hr

Height[m] Air Exchanges [m3/hr]

Area [m2]

*******************************

* *

* *

* <=Q01: 7.20E+01

H1: 2.500 * Room 1 * Q10 : 7.20E+01

* LAMBDA: 8.00E-01 *

Area 36.000 * *

* *

*******************************

Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]

Page 429: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 4 **

Title : Cr-51

Input File : site1.bld

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination::

Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

Ingestion Inhalation Submersion

[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/

(dpm/m3)]

CR-51 1.300E+09 6.622E-08 1.505E-07 7.945E-05

Page 430: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 5 **

Title : Cr-51

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== Assessment for Time: 1 ===

=== Time =0.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

CR-51 1.300E+09

Page 431: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 6 **

Title : Cr-51

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 2.50E+01 2.50E+01

Total 2.50E+01 2.50E+01

Page 432: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 7 **

Title : Cr-51

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 2.48E+01 1.32E-01 2.13E-03 2.64E-02 0.00E+00 1.96E-02

Total 2.48E+01 1.32E-01 2.13E-03 2.64E-02 0.00E+00 1.96E-02

Page 433: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 8 **

Title : Cr-51

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

CR-51 2.50E+01 2.50E+01

Page 434: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 9 **

Title : Cr-51

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== Assessment for Time: 2 ===

=== Time =1.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 0.000E+00

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

CR-51 6.984E+04

Page 435: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 10 **

Title : Cr-51

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 1.41E-03 1.41E-03

Total 1.41E-03 1.41E-03

Page 436: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 11 **

Title : Cr-51

Input File : site1.bld

Evaluation Time: 1.00000000 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 1.41E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Total 1.41E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 437: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 12 **

Title : Cr-51

Input File : site1.bld

Evaluation Time: 1.00000000 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

CR-51 1.41E-03 1.41E-03

Page 438: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 13 **

Title : Cr-51

Input File : site1.bld

Full Summary

================================================

================================================

=== ===

=== RESRAD-BUILD Dose (Time) Tables ===

=== ===

================================================

================================================

Receptor Dose Received for the Exposure Duration

================================================

(mrem)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.50E+01 1.41E-03

Receptor Dose/Yr Averaged Over Exposure Duration

================================================

(mrem/yr)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.50E+01 1.41E-03

Page 439: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 1 **

Title : Cs-134

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Table of Contents ===

=== ===

================================================

================================================

RESRAD-BUILD Input Parameters............ 2

Building Information..................... 3

Source Information....................... 4

For time = 0.00E+00 yr

Time Specific Parameters.............. 5

Receptor-Source Dose Summary.......... 6

Dose by Pathway Detail................ 7

Dose by Nuclide Detail................ 8

For time = 1.00E+00 yr

Time Specific Parameters.............. 9

Receptor-Source Dose Summary.......... 10

Dose by Pathway Detail................ 11

Dose by Nuclide Detail................ 12

Full Summary............................. 13

Page 440: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 2 **

Title : Cs-134

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Input Parameters ===

=== ===

================================================

================================================

Number of Sources : 1

Number of Receptors: 1

Total Time : 3.650000E+02 days

Fraction Inside : 5.000000E-01

========== Receptor Information ==========

Receptor Room x y z FracTime Inhalation Ingestion(Dust)

[m] [m] [m] [m3/day] [m2/hr]

1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04

=== Receptor-Source Shielding Relationship ===

Receptor Source Density Thickness Material

[g/cm3] [cm]

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

1 1 2.40E+00 0.00E+00 Concrete

Page 441: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 3 **

Title : Cs-134

Input File : site1.bld

======== Building Information ========

Building Air Exchange Rate: 8.00E-01 1/hr

Height[m] Air Exchanges [m3/hr]

Area [m2]

*******************************

* *

* *

* <=Q01: 7.20E+01

H1: 2.500 * Room 1 * Q10 : 7.20E+01

* LAMBDA: 8.00E-01 *

Area 36.000 * *

* *

*******************************

Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]

Page 442: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 4 **

Title : Cs-134

Input File : site1.bld

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination::

Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

Ingestion Inhalation Submersion

[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/

(dpm/m3)]

CS-134 3.600E+06 3.302E-05 2.081E-05 3.983E-03

Page 443: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 5 **

Title : Cs-134

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== Assessment for Time: 1 ===

=== Time =0.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

CS-134 3.600E+06

Page 444: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 6 **

Title : Cs-134

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 2.44E+01 2.44E+01

Total 2.44E+01 2.44E+01

Page 445: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 7 **

Title : Cs-134

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 2.10E+01 1.17E+00 1.24E-02 4.26E-01 0.00E+00 1.76E+00

Total 2.10E+01 1.17E+00 1.24E-02 4.26E-01 0.00E+00 1.76E+00

Page 446: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 8 **

Title : Cs-134

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

CS-134 2.44E+01 2.44E+01

Page 447: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 9 **

Title : Cs-134

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== Assessment for Time: 2 ===

=== Time =1.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 0.000E+00

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

CS-134 1.286E+06

Page 448: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 10 **

Title : Cs-134

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 9.84E+00 9.84E+00

Total 9.84E+00 9.84E+00

Page 449: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 11 **

Title : Cs-134

Input File : site1.bld

Evaluation Time: 1.00000000 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 9.84E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Total 9.84E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 450: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 12 **

Title : Cs-134

Input File : site1.bld

Evaluation Time: 1.00000000 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

CS-134 9.84E+00 9.84E+00

Page 451: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 13 **

Title : Cs-134

Input File : site1.bld

Full Summary

================================================

================================================

=== ===

=== RESRAD-BUILD Dose (Time) Tables ===

=== ===

================================================

================================================

Receptor Dose Received for the Exposure Duration

================================================

(mrem)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.44E+01 9.84E+00

Receptor Dose/Yr Averaged Over Exposure Duration

================================================

(mrem/yr)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.44E+01 9.84E+00

Page 452: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 1 **

Title : Eu-152

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Table of Contents ===

=== ===

================================================

================================================

RESRAD-BUILD Input Parameters............ 2

Building Information..................... 3

Source Information....................... 4

For time = 0.00E+00 yr

Time Specific Parameters.............. 5

Receptor-Source Dose Summary.......... 6

Dose by Pathway Detail................ 7

Dose by Nuclide Detail................ 8

For time = 1.00E+00 yr

Time Specific Parameters.............. 9

Receptor-Source Dose Summary.......... 10

Dose by Pathway Detail................ 11

Dose by Nuclide Detail................ 12

Full Summary............................. 13

Page 453: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 2 **

Title : Eu-152

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Input Parameters ===

=== ===

================================================

================================================

Number of Sources : 1

Number of Receptors: 1

Total Time : 3.650000E+02 days

Fraction Inside : 5.000000E-01

========== Receptor Information ==========

Receptor Room x y z FracTime Inhalation Ingestion(Dust)

[m] [m] [m] [m3/day] [m2/hr]

1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04

=== Receptor-Source Shielding Relationship ===

Receptor Source Density Thickness Material

[g/cm3] [cm]

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

1 1 2.40E+00 0.00E+00 Concrete

Page 454: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 3 **

Title : Eu-152

Input File : site1.bld

======== Building Information ========

Building Air Exchange Rate: 8.00E-01 1/hr

Height[m] Air Exchanges [m3/hr]

Area [m2]

*******************************

* *

* *

* <=Q01: 7.20E+01

H1: 2.500 * Room 1 * Q10 : 7.20E+01

* LAMBDA: 8.00E-01 *

Area 36.000 * *

* *

*******************************

Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]

Page 455: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 4 **

Title : Eu-152

Input File : site1.bld

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination::

Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

Ingestion Inhalation Submersion

[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/

(dpm/m3)]

GD-152 0.000E+00 7.252E-05 1.095E-01 0.000E+00

EU-152 4.000E+06 2.919E-06 9.955E-05 2.973E-03

Page 456: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 5 **

Title : Eu-152

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== Assessment for Time: 1 ===

=== Time =0.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

GD-152 0.000E+00

EU-152 4.000E+06

Page 457: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 6 **

Title : Eu-152

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 2.45E+01 2.45E+01

Total 2.45E+01 2.45E+01

Page 458: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 7 **

Title : Eu-152

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 1.94E+01 1.44E+00 1.53E-02 3.36E+00 0.00E+00 2.62E-01

Total 1.94E+01 1.44E+00 1.53E-02 3.36E+00 0.00E+00 2.62E-01

Page 459: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 8 **

Title : Eu-152

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

GD-152 1.24E-11 1.24E-11

EU-152 2.45E+01 2.45E+01

Page 460: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 9 **

Title : Eu-152

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== Assessment for Time: 2 ===

=== Time =1.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 0.000E+00

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

GD-152 1.251E-08

EU-152 1.898E+06

Page 461: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 10 **

Title : Eu-152

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 1.22E+01 1.22E+01

Total 1.22E+01 1.22E+01

Page 462: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 11 **

Title : Eu-152

Input File : site1.bld

Evaluation Time: 1.00000000 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 1.22E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Total 1.22E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 463: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 12 **

Title : Eu-152

Input File : site1.bld

Evaluation Time: 1.00000000 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

GD-152 0.00E+00 0.00E+00

EU-152 1.22E+01 1.22E+01

Page 464: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 13 **

Title : Eu-152

Input File : site1.bld

Full Summary

================================================

================================================

=== ===

=== RESRAD-BUILD Dose (Time) Tables ===

=== ===

================================================

================================================

Receptor Dose Received for the Exposure Duration

================================================

(mrem)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.45E+01 1.22E+01

Receptor Dose/Yr Averaged Over Exposure Duration

================================================

(mrem/yr)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.45E+01 1.22E+01

Page 465: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 1 **

Title : Eu-154

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Table of Contents ===

=== ===

================================================

================================================

RESRAD-BUILD Input Parameters............ 2

Building Information..................... 3

Source Information....................... 4

For time = 0.00E+00 yr

Time Specific Parameters.............. 5

Receptor-Source Dose Summary.......... 6

Dose by Pathway Detail................ 7

Dose by Nuclide Detail................ 8

For time = 1.00E+00 yr

Time Specific Parameters.............. 9

Receptor-Source Dose Summary.......... 10

Dose by Pathway Detail................ 11

Dose by Nuclide Detail................ 12

Full Summary............................. 13

Page 466: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 2 **

Title : Eu-154

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Input Parameters ===

=== ===

================================================

================================================

Number of Sources : 1

Number of Receptors: 1

Total Time : 3.650000E+02 days

Fraction Inside : 5.000000E-01

========== Receptor Information ==========

Receptor Room x y z FracTime Inhalation Ingestion(Dust)

[m] [m] [m] [m3/day] [m2/hr]

1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04

=== Receptor-Source Shielding Relationship ===

Receptor Source Density Thickness Material

[g/cm3] [cm]

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

1 1 2.40E+00 0.00E+00 Concrete

Page 467: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 3 **

Title : Eu-154

Input File : site1.bld

======== Building Information ========

Building Air Exchange Rate: 8.00E-01 1/hr

Height[m] Air Exchanges [m3/hr]

Area [m2]

*******************************

* *

* *

* <=Q01: 7.20E+01

H1: 2.500 * Room 1 * Q10 : 7.20E+01

* LAMBDA: 8.00E-01 *

Area 36.000 * *

* *

*******************************

Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]

Page 468: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 4 **

Title : Eu-154

Input File : site1.bld

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination::

Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

Ingestion Inhalation Submersion

[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/

(dpm/m3)]

EU-154 3.700E+06 4.302E-06 1.288E-04 3.230E-03

Page 469: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 5 **

Title : Eu-154

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== Assessment for Time: 1 ===

=== Time =0.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

EU-154 3.700E+06

Page 470: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 6 **

Title : Eu-154

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 2.46E+01 2.46E+01

Total 2.46E+01 2.46E+01

Page 471: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 7 **

Title : Eu-154

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 1.90E+01 1.37E+00 1.48E-02 3.87E+00 0.00E+00 3.43E-01

Total 1.90E+01 1.37E+00 1.48E-02 3.87E+00 0.00E+00 3.43E-01

Page 472: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 8 **

Title : Eu-154

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

EU-154 2.46E+01 2.46E+01

Page 473: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 9 **

Title : Eu-154

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== Assessment for Time: 2 ===

=== Time =1.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 0.000E+00

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

EU-154 1.710E+06

Page 474: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 10 **

Title : Eu-154

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 1.17E+01 1.17E+01

Total 1.17E+01 1.17E+01

Page 475: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 11 **

Title : Eu-154

Input File : site1.bld

Evaluation Time: 1.00000000 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 1.17E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Total 1.17E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 476: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 12 **

Title : Eu-154

Input File : site1.bld

Evaluation Time: 1.00000000 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

EU-154 1.17E+01 1.17E+01

Page 477: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 13 **

Title : Eu-154

Input File : site1.bld

Full Summary

================================================

================================================

=== ===

=== RESRAD-BUILD Dose (Time) Tables ===

=== ===

================================================

================================================

Receptor Dose Received for the Exposure Duration

================================================

(mrem)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.46E+01 1.17E+01

Receptor Dose/Yr Averaged Over Exposure Duration

================================================

(mrem/yr)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.46E+01 1.17E+01

Page 478: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 1 **

Title : Eu-155 @ 1 pCi/g

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Table of Contents ===

=== ===

================================================

================================================

RESRAD-BUILD Input Parameters............ 2

Building Information..................... 3

Source Information....................... 4

For time = 0.00E+00 yr

Time Specific Parameters.............. 5

Receptor-Source Dose Summary.......... 6

Dose by Pathway Detail................ 7

Dose by Nuclide Detail................ 8

For time = 1.00E+00 yr

Time Specific Parameters.............. 9

Receptor-Source Dose Summary.......... 10

Dose by Pathway Detail................ 11

Dose by Nuclide Detail................ 12

Full Summary............................. 13

Page 479: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 2 **

Title : Eu-155 @ 1 pCi/g

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Input Parameters ===

=== ===

================================================

================================================

Number of Sources : 1

Number of Receptors: 1

Total Time : 3.650000E+02 days

Fraction Inside : 5.000000E-01

========== Receptor Information ==========

Receptor Room x y z FracTime Inhalation Ingestion(Dust)

[m] [m] [m] [m3/day] [m2/hr]

1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04

=== Receptor-Source Shielding Relationship ===

Receptor Source Density Thickness Material

[g/cm3] [cm]

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

1 1 2.40E+00 0.00E+00 Concrete

Page 480: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 3 **

Title : Eu-155 @ 1 pCi/g

Input File : site1.bld

======== Building Information ========

Building Air Exchange Rate: 8.00E-01 1/hr

Height[m] Air Exchanges [m3/hr]

Area [m2]

*******************************

* *

* *

* <=Q01: 7.20E+01

H1: 2.500 * Room 1 * Q10 : 7.20E+01

* LAMBDA: 8.00E-01 *

Area 36.000 * *

* *

*******************************

Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]

Page 481: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 4 **

Title : Eu-155 @ 1 pCi/g

Input File : site1.bld

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination::

Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

Ingestion Inhalation Submersion

[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/

(dpm/m3)]

EU-155 5.700E+07 6.892E-07 1.865E-05 1.310E-04

Page 482: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 5 **

Title : Eu-155 @ 1 pCi/g

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== Assessment for Time: 1 ===

=== Time =0.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

EU-155 5.700E+07

Page 483: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 6 **

Title : Eu-155 @ 1 pCi/g

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 2.46E+01 2.46E+01

Total 2.46E+01 2.46E+01

Page 484: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 7 **

Title : Eu-155 @ 1 pCi/g

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 1.50E+01 1.01E+00 8.43E-03 7.88E+00 0.00E+00 7.69E-01

Total 1.50E+01 1.01E+00 8.43E-03 7.88E+00 0.00E+00 7.69E-01

Page 485: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 8 **

Title : Eu-155 @ 1 pCi/g

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

EU-155 2.46E+01 2.46E+01

Page 486: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 9 **

Title : Eu-155 @ 1 pCi/g

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== Assessment for Time: 2 ===

=== Time =1.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 0.000E+00

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

EU-155 2.478E+07

Page 487: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 10 **

Title : Eu-155 @ 1 pCi/g

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 8.62E+00 8.62E+00

Total 8.62E+00 8.62E+00

Page 488: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 11 **

Title : Eu-155 @ 1 pCi/g

Input File : site1.bld

Evaluation Time: 1.00000000 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 8.62E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Total 8.62E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 489: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 12 **

Title : Eu-155 @ 1 pCi/g

Input File : site1.bld

Evaluation Time: 1.00000000 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

EU-155 8.62E+00 8.62E+00

Page 490: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 13 **

Title : Eu-155 @ 1 pCi/g

Input File : site1.bld

Full Summary

================================================

================================================

=== ===

=== RESRAD-BUILD Dose (Time) Tables ===

=== ===

================================================

================================================

Receptor Dose Received for the Exposure Duration

================================================

(mrem)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.46E+01 8.62E+00

Receptor Dose/Yr Averaged Over Exposure Duration

================================================

(mrem/yr)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.47E+01 8.62E+00

Page 491: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 492: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 493: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 494: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 495: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 496: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 497: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 498: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 499: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 500: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 501: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 502: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 503: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 504: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 1 **

Title : Fe-59

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Table of Contents ===

=== ===

================================================

================================================

RESRAD-BUILD Input Parameters............ 2

Building Information..................... 3

Source Information....................... 4

For time = 0.00E+00 yr

Time Specific Parameters.............. 5

Receptor-Source Dose Summary.......... 6

Dose by Pathway Detail................ 7

Dose by Nuclide Detail................ 8

For time = 1.00E+00 yr

Time Specific Parameters.............. 9

Receptor-Source Dose Summary.......... 10

Dose by Pathway Detail................ 11

Dose by Nuclide Detail................ 12

Full Summary............................. 13

Page 505: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 2 **

Title : Fe-59

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Input Parameters ===

=== ===

================================================

================================================

Number of Sources : 1

Number of Receptors: 1

Total Time : 3.650000E+02 days

Fraction Inside : 5.000000E-01

========== Receptor Information ==========

Receptor Room x y z FracTime Inhalation Ingestion(Dust)

[m] [m] [m] [m3/day] [m2/hr]

1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04

=== Receptor-Source Shielding Relationship ===

Receptor Source Density Thickness Material

[g/cm3] [cm]

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

1 1 2.40E+00 0.00E+00 Concrete

Page 506: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 3 **

Title : Fe-59

Input File : site1.bld

======== Building Information ========

Building Air Exchange Rate: 8.00E-01 1/hr

Height[m] Air Exchanges [m3/hr]

Area [m2]

*******************************

* *

* *

* <=Q01: 7.20E+01

H1: 2.500 * Room 1 * Q10 : 7.20E+01

* LAMBDA: 8.00E-01 *

Area 36.000 * *

* *

*******************************

Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]

Page 507: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 4 **

Title : Fe-59

Input File : site1.bld

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination::

Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

Ingestion Inhalation Submersion

[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/

(dpm/m3)]

FE-59 3.000E+08 3.018E-06 6.667E-06 3.141E-03

Page 508: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 5 **

Title : Fe-59

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== Assessment for Time: 1 ===

=== Time =0.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

FE-59 3.000E+08

Page 509: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 6 **

Title : Fe-59

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 2.49E+01 2.49E+01

Total 2.49E+01 2.49E+01

Page 510: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 7 **

Title : Fe-59

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 2.36E+01 2.00E-01 4.10E-02 5.71E-01 0.00E+00 5.06E-01

Total 2.36E+01 2.00E-01 4.10E-02 5.71E-01 0.00E+00 5.06E-01

Page 511: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 8 **

Title : Fe-59

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

FE-59 2.49E+01 2.49E+01

Page 512: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 9 **

Title : Fe-59

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== Assessment for Time: 2 ===

=== Time =1.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 0.000E+00

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

FE-59 5.112E+05

Page 513: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 10 **

Title : Fe-59

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 4.40E-02 4.40E-02

Total 4.40E-02 4.40E-02

Page 514: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 11 **

Title : Fe-59

Input File : site1.bld

Evaluation Time: 1.00000000 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 4.40E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Total 4.40E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 515: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 12 **

Title : Fe-59

Input File : site1.bld

Evaluation Time: 1.00000000 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

FE-59 4.40E-02 4.40E-02

Page 516: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 13 **

Title : Fe-59

Input File : site1.bld

Full Summary

================================================

================================================

=== ===

=== RESRAD-BUILD Dose (Time) Tables ===

=== ===

================================================

================================================

Receptor Dose Received for the Exposure Duration

================================================

(mrem)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.49E+01 4.40E-02

Receptor Dose/Yr Averaged Over Exposure Duration

================================================

(mrem/yr)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.49E+01 4.40E-02

Page 517: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 518: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 519: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 520: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 521: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 522: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 523: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 524: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 525: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 526: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 527: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 528: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 529: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”
Page 530: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 1 **

Title : Mn-54

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Table of Contents ===

=== ===

================================================

================================================

RESRAD-BUILD Input Parameters............ 2

Building Information..................... 3

Source Information....................... 4

For time = 0.00E+00 yr

Time Specific Parameters.............. 5

Receptor-Source Dose Summary.......... 6

Dose by Pathway Detail................ 7

Dose by Nuclide Detail................ 8

For time = 1.00E+00 yr

Time Specific Parameters.............. 9

Receptor-Source Dose Summary.......... 10

Dose by Pathway Detail................ 11

Dose by Nuclide Detail................ 12

Full Summary............................. 13

Page 531: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 2 **

Title : Mn-54

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Input Parameters ===

=== ===

================================================

================================================

Number of Sources : 1

Number of Receptors: 1

Total Time : 3.650000E+02 days

Fraction Inside : 5.000000E-01

========== Receptor Information ==========

Receptor Room x y z FracTime Inhalation Ingestion(Dust)

[m] [m] [m] [m3/day] [m2/hr]

1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04

=== Receptor-Source Shielding Relationship ===

Receptor Source Density Thickness Material

[g/cm3] [cm]

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

1 1 2.40E+00 0.00E+00 Concrete

Page 532: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 3 **

Title : Mn-54

Input File : site1.bld

======== Building Information ========

Building Air Exchange Rate: 8.00E-01 1/hr

Height[m] Air Exchanges [m3/hr]

Area [m2]

*******************************

* *

* *

* <=Q01: 7.20E+01

H1: 2.500 * Room 1 * Q10 : 7.20E+01

* LAMBDA: 8.00E-01 *

Area 36.000 * *

* *

*******************************

Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]

Page 533: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 4 **

Title : Mn-54

Input File : site1.bld

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination::

Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

Ingestion Inhalation Submersion

[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/

(dpm/m3)]

MN-54 9.100E+06 1.248E-06 3.018E-06 2.152E-03

Page 534: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 5 **

Title : Mn-54

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== Assessment for Time: 1 ===

=== Time =0.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

MN-54 9.100E+06

Page 535: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 6 **

Title : Mn-54

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 2.48E+01 2.48E+01

Total 2.48E+01 2.48E+01

Page 536: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 7 **

Title : Mn-54

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 2.36E+01 9.14E-01 1.01E-02 9.27E-02 0.00E+00 9.72E-02

Total 2.36E+01 9.14E-01 1.01E-02 9.27E-02 0.00E+00 9.72E-02

Page 537: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 8 **

Title : Mn-54

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

MN-54 2.48E+01 2.48E+01

Page 538: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 9 **

Title : Mn-54

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== Assessment for Time: 2 ===

=== Time =1.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 0.000E+00

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

MN-54 2.025E+06

Page 539: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 10 **

Title : Mn-54

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 6.72E+00 6.72E+00

Total 6.72E+00 6.72E+00

Page 540: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 11 **

Title : Mn-54

Input File : site1.bld

Evaluation Time: 1.00000000 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 6.72E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Total 6.72E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 541: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 12 **

Title : Mn-54

Input File : site1.bld

Evaluation Time: 1.00000000 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

MN-54 6.72E+00 6.72E+00

Page 542: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 13 **

Title : Mn-54

Input File : site1.bld

Full Summary

================================================

================================================

=== ===

=== RESRAD-BUILD Dose (Time) Tables ===

=== ===

================================================

================================================

Receptor Dose Received for the Exposure Duration

================================================

(mrem)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.48E+01 6.72E+00

Receptor Dose/Yr Averaged Over Exposure Duration

================================================

(mrem/yr)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.48E+01 6.72E+00

Page 543: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 1 **

Title : Na-22

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Table of Contents ===

=== ===

================================================

================================================

RESRAD-BUILD Input Parameters............ 2

Building Information..................... 3

Source Information....................... 4

For time = 0.00E+00 yr

Time Specific Parameters.............. 5

Receptor-Source Dose Summary.......... 6

Dose by Pathway Detail................ 7

Dose by Nuclide Detail................ 8

For time = 1.00E+00 yr

Time Specific Parameters.............. 9

Receptor-Source Dose Summary.......... 10

Dose by Pathway Detail................ 11

Dose by Nuclide Detail................ 12

Full Summary............................. 13

Page 544: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 2 **

Title : Na-22

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Input Parameters ===

=== ===

================================================

================================================

Number of Sources : 1

Number of Receptors: 1

Total Time : 3.650000E+02 days

Fraction Inside : 5.000000E-01

========== Receptor Information ==========

Receptor Room x y z FracTime Inhalation Ingestion(Dust)

[m] [m] [m] [m3/day] [m2/hr]

1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04

=== Receptor-Source Shielding Relationship ===

Receptor Source Density Thickness Material

[g/cm3] [cm]

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

1 1 2.40E+00 0.00E+00 Concrete

Page 545: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 3 **

Title : Na-22

Input File : site1.bld

======== Building Information ========

Building Air Exchange Rate: 8.00E-01 1/hr

Height[m] Air Exchanges [m3/hr]

Area [m2]

*******************************

* *

* *

* <=Q01: 7.20E+01

H1: 2.500 * Room 1 * Q10 : 7.20E+01

* LAMBDA: 8.00E-01 *

Area 36.000 * *

* *

*******************************

Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]

Page 546: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 4 **

Title : Na-22

Input File : site1.bld

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination::

Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

Ingestion Inhalation Submersion

[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/

(dpm/m3)]

NA-22 2.700E+06 5.180E-06 3.450E-06 5.682E-03

Page 547: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 5 **

Title : Na-22

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== Assessment for Time: 1 ===

=== Time =0.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

NA-22 2.700E+06

Page 548: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 6 **

Title : Na-22

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 2.42E+01 2.42E+01

Total 2.42E+01 2.42E+01

Page 549: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 7 **

Title : Na-22

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 2.26E+01 1.34E+00 1.45E-02 5.79E-02 0.00E+00 2.28E-01

Total 2.26E+01 1.34E+00 1.45E-02 5.79E-02 0.00E+00 2.28E-01

Page 550: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 8 **

Title : Na-22

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

NA-22 2.42E+01 2.42E+01

Page 551: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 9 **

Title : Na-22

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== Assessment for Time: 2 ===

=== Time =1.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 0.000E+00

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

NA-22 1.034E+06

Page 552: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 10 **

Title : Na-22

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 1.14E+01 1.14E+01

Total 1.14E+01 1.14E+01

Page 553: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 11 **

Title : Na-22

Input File : site1.bld

Evaluation Time: 1.00000000 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 1.14E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Total 1.14E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 554: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 12 **

Title : Na-22

Input File : site1.bld

Evaluation Time: 1.00000000 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

NA-22 1.14E+01 1.14E+01

Page 555: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 13 **

Title : Na-22

Input File : site1.bld

Full Summary

================================================

================================================

=== ===

=== RESRAD-BUILD Dose (Time) Tables ===

=== ===

================================================

================================================

Receptor Dose Received for the Exposure Duration

================================================

(mrem)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.42E+01 1.14E+01

Receptor Dose/Yr Averaged Over Exposure Duration

================================================

(mrem/yr)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.43E+01 1.14E+01

Page 556: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 1 **

Title : Nb-95

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Table of Contents ===

=== ===

================================================

================================================

RESRAD-BUILD Input Parameters............ 2

Building Information..................... 3

Source Information....................... 4

For time = 0.00E+00 yr

Time Specific Parameters.............. 5

Receptor-Source Dose Summary.......... 6

Dose by Pathway Detail................ 7

Dose by Nuclide Detail................ 8

For time = 1.00E+00 yr

Time Specific Parameters.............. 9

Receptor-Source Dose Summary.......... 10

Dose by Pathway Detail................ 11

Dose by Nuclide Detail................ 12

Full Summary............................. 13

Page 557: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 2 **

Title : Nb-95

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Input Parameters ===

=== ===

================================================

================================================

Number of Sources : 1

Number of Receptors: 1

Total Time : 3.650000E+02 days

Fraction Inside : 5.000000E-01

========== Receptor Information ==========

Receptor Room x y z FracTime Inhalation Ingestion(Dust)

[m] [m] [m] [m3/day] [m2/hr]

1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04

=== Receptor-Source Shielding Relationship ===

Receptor Source Density Thickness Material

[g/cm3] [cm]

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

1 1 2.40E+00 0.00E+00 Concrete

Page 558: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 3 **

Title : Nb-95

Input File : site1.bld

======== Building Information ========

Building Air Exchange Rate: 8.00E-01 1/hr

Height[m] Air Exchanges [m3/hr]

Area [m2]

*******************************

* *

* *

* <=Q01: 7.20E+01

H1: 2.500 * Room 1 * Q10 : 7.20E+01

* LAMBDA: 8.00E-01 *

Area 36.000 * *

* *

*******************************

Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]

Page 559: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 4 **

Title : Nb-95

Input File : site1.bld

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination::

Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

Ingestion Inhalation Submersion

[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/

(dpm/m3)]

NB-95 6.800E+07 1.158E-06 2.617E-06 1.968E-03

Page 560: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 5 **

Title : Nb-95

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== Assessment for Time: 1 ===

=== Time =0.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

NB-95 6.800E+07

Page 561: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 6 **

Title : Nb-95

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 2.47E+01 2.47E+01

Total 2.47E+01 2.47E+01

Page 562: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 7 **

Title : Nb-95

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 2.45E+01 1.65E-01 3.99E-03 3.49E-02 0.00E+00 2.82E-02

Total 2.45E+01 1.65E-01 3.99E-03 3.49E-02 0.00E+00 2.82E-02

Page 563: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 8 **

Title : Nb-95

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

NB-95 2.47E+01 2.47E+01

Page 564: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 9 **

Title : Nb-95

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== Assessment for Time: 2 ===

=== Time =1.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 0.000E+00

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

NB-95 2.525E+04

Page 565: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 10 **

Title : Nb-95

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 9.76E-03 9.76E-03

Total 9.76E-03 9.76E-03

Page 566: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 11 **

Title : Nb-95

Input File : site1.bld

Evaluation Time: 1.00000000 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 9.76E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Total 9.76E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 567: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 12 **

Title : Nb-95

Input File : site1.bld

Evaluation Time: 1.00000000 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

NB-95 9.76E-03 9.76E-03

Page 568: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 13 **

Title : Nb-95

Input File : site1.bld

Full Summary

================================================

================================================

=== ===

=== RESRAD-BUILD Dose (Time) Tables ===

=== ===

================================================

================================================

Receptor Dose Received for the Exposure Duration

================================================

(mrem)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.47E+01 9.76E-03

Receptor Dose/Yr Averaged Over Exposure Duration

================================================

(mrem/yr)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.47E+01 9.76E-03

Page 569: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 1 **

Title : Sb-124

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Table of Contents ===

=== ===

================================================

================================================

RESRAD-BUILD Input Parameters............ 2

Building Information..................... 3

Source Information....................... 4

For time = 0.00E+00 yr

Time Specific Parameters.............. 5

Receptor-Source Dose Summary.......... 6

Dose by Pathway Detail................ 7

Dose by Nuclide Detail................ 8

For time = 1.00E+00 yr

Time Specific Parameters.............. 9

Receptor-Source Dose Summary.......... 10

Dose by Pathway Detail................ 11

Dose by Nuclide Detail................ 12

Full Summary............................. 13

Page 570: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 2 **

Title : Sb-124

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Input Parameters ===

=== ===

================================================

================================================

Number of Sources : 1

Number of Receptors: 1

Total Time : 3.650000E+02 days

Fraction Inside : 5.000000E-01

========== Receptor Information ==========

Receptor Room x y z FracTime Inhalation Ingestion(Dust)

[m] [m] [m] [m3/day] [m2/hr]

1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04

=== Receptor-Source Shielding Relationship ===

Receptor Source Density Thickness Material

[g/cm3] [cm]

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

1 1 2.40E+00 0.00E+00 Concrete

Page 571: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 3 **

Title : Sb-124

Input File : site1.bld

======== Building Information ========

Building Air Exchange Rate: 8.00E-01 1/hr

Height[m] Air Exchanges [m3/hr]

Area [m2]

*******************************

* *

* *

* <=Q01: 7.20E+01

H1: 2.500 * Room 1 * Q10 : 7.20E+01

* LAMBDA: 8.00E-01 *

Area 36.000 * *

* *

*******************************

Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]

Page 572: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 4 **

Title : Sb-124

Input File : site1.bld

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination::

Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

Ingestion Inhalation Submersion

[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/

(dpm/m3)]

SB-124 1.700E+08 4.550E-06 1.135E-05 4.814E-03

Page 573: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 5 **

Title : Sb-124

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== Assessment for Time: 1 ===

=== Time =0.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

SB-124 1.700E+08

Page 574: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 6 **

Title : Sb-124

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 2.47E+01 2.47E+01

Total 2.47E+01 2.47E+01

Page 575: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 7 **

Title : Sb-124

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 2.27E+01 2.57E-01 5.72E-02 8.86E-01 0.00E+00 7.48E-01

Total 2.27E+01 2.57E-01 5.72E-02 8.86E-01 0.00E+00 7.48E-01

Page 576: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 8 **

Title : Sb-124

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

SB-124 2.47E+01 2.47E+01

Page 577: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 9 **

Title : Sb-124

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== Assessment for Time: 2 ===

=== Time =1.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 0.000E+00

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

SB-124 1.273E+06

Page 578: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 10 **

Title : Sb-124

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 1.92E-01 1.92E-01

Total 1.92E-01 1.92E-01

Page 579: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 11 **

Title : Sb-124

Input File : site1.bld

Evaluation Time: 1.00000000 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 1.92E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Total 1.92E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 580: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 12 **

Title : Sb-124

Input File : site1.bld

Evaluation Time: 1.00000000 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

SB-124 1.92E-01 1.92E-01

Page 581: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 13 **

Title : Sb-124

Input File : site1.bld

Full Summary

================================================

================================================

=== ===

=== RESRAD-BUILD Dose (Time) Tables ===

=== ===

================================================

================================================

Receptor Dose Received for the Exposure Duration

================================================

(mrem)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.47E+01 1.92E-01

Receptor Dose/Yr Averaged Over Exposure Duration

================================================

(mrem/yr)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.47E+01 1.92E-01

Page 582: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 1 **

Title : Sc-46

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Table of Contents ===

=== ===

================================================

================================================

RESRAD-BUILD Input Parameters............ 2

Building Information..................... 3

Source Information....................... 4

For time = 0.00E+00 yr

Time Specific Parameters.............. 5

Receptor-Source Dose Summary.......... 6

Dose by Pathway Detail................ 7

Dose by Nuclide Detail................ 8

For time = 1.00E+00 yr

Time Specific Parameters.............. 9

Receptor-Source Dose Summary.......... 10

Dose by Pathway Detail................ 11

Dose by Nuclide Detail................ 12

Full Summary............................. 13

Page 583: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 2 **

Title : Sc-46

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Input Parameters ===

=== ===

================================================

================================================

Number of Sources : 1

Number of Receptors: 1

Total Time : 3.650000E+02 days

Fraction Inside : 5.000000E-01

========== Receptor Information ==========

Receptor Room x y z FracTime Inhalation Ingestion(Dust)

[m] [m] [m] [m3/day] [m2/hr]

1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04

=== Receptor-Source Shielding Relationship ===

Receptor Source Density Thickness Material

[g/cm3] [cm]

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

1 1 2.40E+00 0.00E+00 Concrete

Page 584: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 3 **

Title : Sc-46

Input File : site1.bld

======== Building Information ========

Building Air Exchange Rate: 8.00E-01 1/hr

Height[m] Air Exchanges [m3/hr]

Area [m2]

*******************************

* *

* *

* <=Q01: 7.20E+01

H1: 2.500 * Room 1 * Q10 : 7.20E+01

* LAMBDA: 8.00E-01 *

Area 36.000 * *

* *

*******************************

Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]

Page 585: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 4 **

Title : Sc-46

Input File : site1.bld

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination::

Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

Ingestion Inhalation Submersion

[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/

(dpm/m3)]

SC-46 1.600E+09 2.883E-06 1.333E-05 5.251E-03

Page 586: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 5 **

Title : Sc-46

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== Assessment for Time: 1 ===

=== Time =0.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

SC-46 1.600E+09

Page 587: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 6 **

Title : Sc-46

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 2.50E+01 2.50E+01

Total 2.50E+01 2.50E+01

Page 588: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 7 **

Title : Sc-46

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 0.00E+00 0.00E+00 9.72E-01 1.62E+01 0.00E+00 7.84E+00

Total 0.00E+00 0.00E+00 9.72E-01 1.62E+01 0.00E+00 7.84E+00

Page 589: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 8 **

Title : Sc-46

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

SC-46 2.50E+01 2.50E+01

Page 590: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 9 **

Title : Sc-46

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== Assessment for Time: 2 ===

=== Time =1.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 0.000E+00

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

SC-46 3.929E+07

Page 591: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 10 **

Title : Sc-46

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 0.00E+00 0.00E+00

Total 0.00E+00 0.00E+00

Page 592: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 11 **

Title : Sc-46

Input File : site1.bld

Evaluation Time: 1.00000000 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Total 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 593: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 12 **

Title : Sc-46

Input File : site1.bld

Evaluation Time: 1.00000000 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

SC-46 0.00E+00 0.00E+00

Page 594: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 13 **

Title : Sc-46

Input File : site1.bld

Full Summary

================================================

================================================

=== ===

=== RESRAD-BUILD Dose (Time) Tables ===

=== ===

================================================

================================================

Receptor Dose Received for the Exposure Duration

================================================

(mrem)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.50E+01 0.00E+00

Receptor Dose/Yr Averaged Over Exposure Duration

================================================

(mrem/yr)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.50E+01 0.00E+00

Page 595: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 1 **

Title : Zn-65

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Table of Contents ===

=== ===

================================================

================================================

RESRAD-BUILD Input Parameters............ 2

Building Information..................... 3

Source Information....................... 4

For time = 0.00E+00 yr

Time Specific Parameters.............. 5

Receptor-Source Dose Summary.......... 6

Dose by Pathway Detail................ 7

Dose by Nuclide Detail................ 8

For time = 1.00E+00 yr

Time Specific Parameters.............. 9

Receptor-Source Dose Summary.......... 10

Dose by Pathway Detail................ 11

Dose by Nuclide Detail................ 12

Full Summary............................. 13

Page 596: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 2 **

Title : Zn-65

Input File : site1.bld

================================================

================================================

=== ===

=== RESRAD-BUILD Input Parameters ===

=== ===

================================================

================================================

Number of Sources : 1

Number of Receptors: 1

Total Time : 3.650000E+02 days

Fraction Inside : 5.000000E-01

========== Receptor Information ==========

Receptor Room x y z FracTime Inhalation Ingestion(Dust)

[m] [m] [m] [m3/day] [m2/hr]

1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04

=== Receptor-Source Shielding Relationship ===

Receptor Source Density Thickness Material

[g/cm3] [cm]

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

1 1 2.40E+00 0.00E+00 Concrete

Page 597: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 3 **

Title : Zn-65

Input File : site1.bld

======== Building Information ========

Building Air Exchange Rate: 8.00E-01 1/hr

Height[m] Air Exchanges [m3/hr]

Area [m2]

*******************************

* *

* *

* <=Q01: 7.20E+01

H1: 2.500 * Room 1 * Q10 : 7.20E+01

* LAMBDA: 8.00E-01 *

Area 36.000 * *

* *

*******************************

Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]

Page 598: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 4 **

Title : Zn-65

Input File : site1.bld

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination::

Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)

— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —

Ingestion Inhalation Submersion

[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/

(dpm/m3)]

ZN-65 1.400E+07 6.486E-06 9.189E-06 1.526E-03

Page 599: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 5 **

Title : Zn-65

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== Assessment for Time: 1 ===

=== Time =0.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 5.000E-01

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

ZN-65 1.400E+07

Page 600: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 6 **

Title : Zn-65

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 2.44E+01 2.44E+01

Total 2.44E+01 2.44E+01

Page 601: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 7 **

Title : Zn-65

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 2.27E+01 7.61E-01 8.89E-03 3.51E-01 0.00E+00 6.21E-01

Total 2.27E+01 7.61E-01 8.89E-03 3.51E-01 0.00E+00 6.21E-01

Page 602: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 8 **

Title : Zn-65

Input File : site1.bld

Evaluation Time: 0.00000000E+00 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

ZN-65 2.44E+01 2.44E+01

Page 603: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 9 **

Title : Zn-65

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== Assessment for Time: 2 ===

=== Time =1.00E+00 yr ===

================================================

================================================

======== Source Information ========

Source: 1

Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]

Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x

Pathway ::

Direct Ingestion Rate: 0.000E+00 [1/hr]

Fraction released to air: 1.000E-01

Removable fraction: 0.000E+00

Time to Remove: 3.650E+02 [day]

Contamination:: Nuclide Concentration

[dpm/m2]

ZN-65 2.480E+06

Page 604: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 10 **

Title : Zn-65

Input File : site1.bld

Evaluation Time: 1.00000000 years

================================================

================================================

=== ===

=== RESRAD-BUILD Dose Tables ===

=== ===

================================================

================================================

Source Contributions to Receptor Doses

======================================

[mrem]

Source Total

1

Receptor 1 5.06E+00 5.06E+00

Total 5.06E+00 5.06E+00

Page 605: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 11 **

Title : Zn-65

Input File : site1.bld

Evaluation Time: 1.00000000 years

Pathway Detail of Doses

=======================

[mrem]

Source: 1

Receptor External Deposition Immersion Inhalation Radon Ingestion

1 5.06E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Total 5.06E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 606: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 12 **

Title : Zn-65

Input File : site1.bld

Evaluation Time: 1.00000000 years

Nuclide Detail of Doses

=======================

[mrem]

Source: 1

Nuclide Receptor Total

1

ZN-65 5.06E+00 5.06E+00

Page 607: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 13 **

Title : Zn-65

Input File : site1.bld

Full Summary

================================================

================================================

=== ===

=== RESRAD-BUILD Dose (Time) Tables ===

=== ===

================================================

================================================

Receptor Dose Received for the Exposure Duration

================================================

(mrem)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.44E+01 5.06E+00

Receptor Dose/Yr Averaged Over Exposure Duration

================================================

(mrem/yr)

Evaluation Time [yr]

0.00E+00 1.00E+00

— — — — — — — — — — — — — — — —

1 2.44E+01 5.07E+00

Page 608: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

Attachment 4 MicroShield MDC Model

Page 609: Remediation Work Plan - NRC: Home Page · NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “onsolidated NMSS Decommissioning Guidance”

MicroShield 8.03Ameriphysics (8.03-0000)

Date By Checked

Filename Run Date Run Time DurationCase1 August 5, 2016 10:36:09 AM 00:00:00

Project InfoCase Title CH St. Louis

Description Volumetric ActivationGeometry 8 - Cylinder Volume - End Shields

Source DimensionsHeight 15.0 cm (5.9 in)Radius 28.0 cm (11.0 in)

Dose PointsA X Y Z#1 0.0 cm (0 in) 25.0 cm (9.8 in) 0.0 cm (0 in)

ShieldsShield N Dimension Material DensitySource 3.69e+04 cm³ Concrete 2.35Air Gap Air 0.00122

Source Input: Grouping Method - Standard IndicesNumber of Groups: 25

Lower Energy Cutoff: 0.015Photons < 0.015: Included

Library: GroveNuclide Ci Bq µCi/cm³ Bq/cm³Co-60 1.3800e-006 5.1060e+004 3.7353e-005 1.3820e+000Cs-134 1.6800e-007 6.2160e+003 4.5473e-006 1.6825e-001Eu-152 3.7500e-006 1.3875e+005 1.0150e-004 3.7556e+000Eu-154 3.8300e-007 1.4171e+004 1.0367e-005 3.8357e-001Mn-54 1.0900e-007 4.0330e+003 2.9503e-006 1.0916e-001Sc-46 6.8700e-008 2.5419e+003 1.8595e-006 6.8802e-002Zn-65 8.9400e-008 3.3078e+003 2.4198e-006 8.9533e-002

Buildup: The material reference is SourceIntegration Parameters

Radial 20Circumferential 10

Y Direction (axial) 10

Results

Energy (MeV) Activity (Photons/sec)Fluence RateMeV/cm²/secNo Buildup

Fluence RateMeV/cm²/secWith Buildup

Exposure RatemR/hr

No Buildup

Exposure RatemR/hr

With Buildup

Page 1 of 2Case Summary of CH St. Louis

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0.015 2.450e+04 1.612e-04 1.662e-04 1.382e-05 1.426e-050.03 3.791e+01 3.777e-06 4.440e-06 3.744e-08 4.401e-080.04 8.499e+04 2.257e-02 3.131e-02 9.981e-05 1.385e-040.05 2.126e+04 1.090e-02 1.789e-02 2.904e-05 4.765e-050.1 4.518e+04 9.682e-02 2.629e-01 1.481e-04 4.022e-040.2 1.137e+04 6.502e-02 1.804e-01 1.147e-04 3.183e-040.3 3.752e+04 3.695e-01 9.334e-01 7.010e-04 1.771e-030.4 8.820e+03 1.279e-01 2.970e-01 2.492e-04 5.787e-040.5 9.977e+02 1.957e-02 4.246e-02 3.841e-05 8.335e-050.6 1.458e+04 3.663e-01 7.489e-01 7.149e-04 1.462e-030.8 4.266e+04 1.585e+00 2.965e+00 3.015e-03 5.640e-031.0 1.192e+05 6.006e+00 1.053e+01 1.107e-02 1.941e-021.5 8.897e+04 7.777e+00 1.220e+01 1.308e-02 2.053e-022.0 3.050e-04 3.911e-08 5.752e-08 6.049e-11 8.895e-11

Totals 5.001e+05 1.645e+01 2.821e+01 2.928e-02 5.040e-02

Page 2 of 2Case Summary of CH St. Louis

8/5/2016file:///C:/Program%20Files%20(x86)/MicroShield%208/Examples/CaseFiles/HTML/Case1-...


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