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Radiological Survey and/Dose Assessment Report For the Western New York Nuclear'Service Center and Off-Site Areas In Follow Up to Aerial Gamma Radiation Survey
                            '' '. Con~iicted in 2014, Rev. 0 Prepared For New York State Energy      f and Research Development                    .
Authority West Valley Site Management Program 9'o30-B Route 219      I West Valley, NY 14171 Agreement Number 61280
* Prepared By MJW Technical Services Inc.
243 Root Street, Suite 100, Olean, NY 14760 August 22, 2016 243 Root Slreel, Suite 100
                                        . Olean, NY 14760-2436 Voice: (716) 372-5300    fax: (716) 372-5307    Toll Free: (866) 300-3659 mjwts.com
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table of Contents Executive Summary .................................................................................................................................... S.1 Purpose ... : .................................................................................................................................................. S.1 Radiological Survey and Sampling Actions ................................................................................................ S.1 Sample Radiochemical Analysis .....................................................: ........................................................... S.2 Summary of Dose Assessment Results ...................................................................................................... S.2 Conclusion .................................................................................................................................................. S.4 1.0    Introduction ....................................................._. ..............................................................., .......... ~ ..... 1 1.1    Background ........................................................................................................................................ 1 2.0    Project Components and Organization ............................................................................................. 2 2.1    Field Sampling and Dose Assessment Plan ........................................................................................ 2
* 2.2    Quality Assurance Project Plan (QAPP) ............................................................................................. 2 2.3    Project Health and Safety Plan (HASP) .............................................................................................. 2 I
2.4    Participants, Roles, and Responsibilities .................................... :*...................................................... 2 3.0    Summary of 2014 Aerial Survey Results and Areas Selected for Analysis ........................................ 3 3.1    Method to Select Off-Site Survey Areas Based Upon the Results of the Aerial Survey Data and Reduce Uncertainty in the Location and Extent of Contaminated Areas ..................................................... 3 3.1.1  Area 1. ..............................................................................................., .... ;........................................... 6 3.1.2  Area 2.., ........................................ ,..................................................................................., .................. i 3.13. Area 3........................................................................................................,........................................ 8 3.1.4  Area 4 .................................................................................................................................................. 8 3.1.5  Area 5...................................... :......................................................................................................... 10 3*.1.6 WNYNSC Confirmatory .................................................................................................................... 11 4.0    Data Quality Objectives .......................................... :....................................................................... 12 5.0    Field Survey and Sampling Strategy ................................................................................................ 14 5.1    Instrumentation and Equipment Used ............................................................................................ 14 5.2    Overland GPS Walkover Gamma Surveys ........................................................................................ 15 5.3    Direct Radiation Measurements ...................................................................................................... 15 5.4    Sample Collection Activities ............................................................................................................ 15 5.5    Radiochemical Analysis ................................................................................................................... 16 6.0    Dose Assessment Approach ............................................................................................................ 16 6.1    Background Radiation and Radionuclide Determinations .............................................................. 18 6.1.1  WNYNSC Background Determination .............................................................................................. 19 6.1.2  Seneca Nation of Indians (SNI) Background Determination ........................................................... 23
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas
. 7.0    Survey, Sampling and Dose Assessment Results ............................................................................ 27 7.1  Area 1............................................................................................................................................... 27 7.1.1  Description of Area 1 .................. -........................................................................:............................ 27 7.1.2 Survey and Sampling Methodology for Area !.. .............................................................................. 28 7.1.3 Survey and Sampling Results for Area !. .............................................................. ,.......................... 28 7.1.4  Dose Assessment Approach for Area 1 ........................................................................................... 31 7.1.5  Dose Assessment Results for Area 1 .................................................... :.......................................... 32 7.1.6 -Conclusions for Area 1 ...................................................................................................................... 39 7.2    Area 2............................................................................................................................................... 39 7.2.1  Description of Area 2 ............................................................ :......... ~ ................................................ 39 7.2.2 Survey and Sampling Methodology for Area 2 ................................................................................ 39 7.2.3 Survey and Sampling Results for Area 2 ..... :............................................................................;....... 42 7.2.4  Dose Assessment Approach Area L. ........ :~ ....................................................................................... 47 7.2.5  Dose Assessment Results for Area 2 ....................... ,...... :................................................... ,............ 48 7.2.6 Conclusions for Area 2 .................................. :.................................................................................. 55 7.3    Area 3 ............................................................................:.................................. ;............................... 55 7.3.1  Description of Area 3 ......................-................................................................................................. 55 7.3.2 Survey and Sampling. Methodology for Area 3 ......................................................................;......... 55 7.3.3 Survey and Sampling Results for* Area 3 .......................................................................................... 57 7.3.4  Dose Assessment Approach for Area 3 ........................................................................................... 60 7.3.5  Dose Assessment Results for Area 3 ............................................................................................... 62 7.3.6 Conclusions for Area 3 ...................................................................................................................... 6S 7.4    Area 4 ........................................................................... .-................................................................... 68 7.4.1  Description of_Area 4 ...........................................................................-................... .-........... ,....._. ...... 68 7.4.2 Survey and Sampling Methodology for Area 4 ................................................................................ 68 7.4.3 Survey and Sampling Results for Area 4 .......................................................................................... 71 7.4.4  Dose Assessment Approach for Area 4 ................... :....................................................................... 78 7.4.5  Dose Assessment Results for Area 4 Dose ...................................................................................... 78 7.4:6 Conclusions for Area 4 ...................................................... :............................................................. : 80 7.5    Area 5 ..............-.................................................... :............................................................................ 80
. 7.5.1  Description of Area 5 ................................................................................ :...................~ .................. 80 7.5.2 Survey and Sampling Methodology for Area 5 ................................................................................ 80
                                                                              . ii
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 7.5.3 Survey and Sampling Results for Area 5 .......................................................................................... 85 7.5.4 Dose Assessment Approach for Area 5 ............................................................... :........................... 93 7.5.5 Dose Assessment Results for Area 5 ............................................................................................... 93 7.6  Confirmatory Locations Located on the Western NY Nuclear Service Center Property ................. 95 7.6.l Description of Confirmatory Area ...........................................................................:....................... 95 7.6.2 Survey and Sampling Methodology for Confirmatory Area ............................................................ 95 7.6.3 Survey and Sampling Results for Confirmatory Area .... ."................................................................. 96 7.6.4 Estimation of Dose Rates Based Upon 2014 Aerial Survey Results ................................................. 97 7.6.5 Conclusions for Area 5 ................................................. :................................................................... 98 8.0  Final Summary ................................................................................................................................. 98 8.1  Area 1 .............................................................................. , ................................................................ 99 8.2  Area 2 ................................................................................................................................................ 99 8.3  Area 3 ............................................................... ~ ............... \ ............................................................ 100 8.4  Area 4 ............................................................................................................................................. 100 8.5  Area 5 ............................................................................................................................................. 101 8.6  Confirmatory Area ......................................................................................................................... 101 9.0  References .........................................................................................,........................................... 101 iii
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas List of Figures Figure 1    Area 1 Sampling Locations ........................................................................................................ 6 Figure 2. Area 2 Survey and Sampling Locations ...................................................................................... 7 Figure 3. Area 3 Survey and Sampling Locations ...................................................................................... 8 Figure 4. Area 4 Survey and Sampling Locations ................................................................................:..... 9 Figure 5. Area 5 Survey and Sampling Locations .................................................................................... 10 Figure 6. WNYNSC Confirmatory.Sampling Locations ............................................................................ 11 Figure 7. General Locations of Background Areas ................................................................................. 19 Figure 8. Background Area 1 Sample Locations ..................................................................................... 20 Figure 9. Background Area 2 Sample Locations ..................................................................................... 20 Figure 10. WNYNSC Background Area 1 Location on the 2014 Aerial Radiological Survey ..................... 21 Figure 11. WNYNSC Background Area 2 Location on the 2014 Aerial Radiological Survey ..................... 22 Figure 12. SNI Background Locations ....................................................................................................... 24 Figure 13. SN! Background Floodplain Locations on the 2014 Aerial Radiological Survey ...................... 25 Figure 14. SNI Background Non-Floodplain Locations on the 2014 Aerial Radiological Survey .............. 26 Figure 15. Area 1 Locations on the 2014 WNYNSC Aerial Radiological Survey ......................................... 3_3 Figure 16. Sub-Area L12 ........................................................................................................................... 35 Figure 17. Sub-Area L23 ...................................................................................................;................. :..... 36 Figure 18. Sub-Area, 2.2 Survey and Sampling Locations***********************************************************************'* 40 Figure 19. Sub-Area 2.2 Survey and Sampling Locations ................................................ :........................ 41 Figure 20. Sub-Area 2.1 Manual Grid Survey Box .................................................................................... 42 Figure 21. Sub-Area 2.2 Manual Grid Box ................................................... ;............................................ 43 Figure 22. Static 2" x 2" Detector Grid Readings for Sub-Area 2.1 ......................................................_. ... 44 Figure 23. Static 2" x 2" Detector Grid Readings for Sub-Area 2.2 .......................................................... 45 Figure 24. Area 2 Locations on the 2014 WNYNSC Aerial Radiological Survey ........................................ 49 Figure 25. Sub-Area 2.1 and Deer Pasture Area ....................................................................................... 51 Figure 26. Sub-Area 2.2 and Deer Pasture Area ....................................................................................... 52 Figure 27. Sub-Area Sampling Locations .................................................................................................. 56 Figure 28. Sub-Area 3.2 Sampling Locations ............................................................................................ 57 Figure 29. Static 2" x 2" Detector G*rid Readings for Sub-Area 2.2 ..................................................... ." .... 57 Figure 30. Sub-Area 3.2 GPS Survey Results ...............*....... :.................................................................... 58 Figure 31. Area 3 Locations on the 2014 WNYNSC Aerial Radiological Survey ........................................ 62 Figure 32. Sub-Areas 3.1 and 3.2 .............................................................................................................. 64 Figure 33. Sampling Locations in Sub-Areas 4.1, 4.2, and 4.3 .................................................................. 70 Figure 34. Sampling Locations in Sub-Areas 4.4 and 4.5 .......................................................................... 70 Figure 35. Sub-Area 4.1 GPS Walkover Gamma Survey Data ................................................................... 72 Figure 36. Sub-Area 4.2 GPS Walkover Gamma Survey Data ................................................................... 73 Figure 37. Sub-Area 4.3 GPS Walkover Gamma Survey Data ................................................................... 74 Figure 38. Sub-Area 4.4 GPS Walkover Gamma Survey Data ................................................................... 75 Figure 39. Sub-Area 4.5 GPS Walkover Gamma Survey Data ................................................................... 76 .
Figure 40. Area 4 Locations on the 2014 WNYNSC Aerial Radiological Survey ........................................ 78 Figure 41. Sub-Area 5.1 Sampling Locations ............................................................................................ 82 iv
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 42. Sub-Areas 5.2, 5.3 and 5.4 Sampling Locations ....................................................................... 83 Figure 43. Sub-Areas 5.5 and 5.6 Sampling Locations .............................................................................. 84 Figure 44. Sub-Area 5.1 GPS Walkover Survey Data ................................................................................ 86 Figure 45. Sub-Area 5.2 GPS Walkover Gamma Survey Data ................................................................... 87 Figure 46. Sub-Area 5.3 GPS Walkover Gamma Survey Data ................................................................... 88 Figure 47. Sub-Area 5.4 GPS Walkover Gamma Survey Data ................................................................... 89 Figure 48. SubcArea 5.5 GPS Walkover Gamma Survey Data ................................................................... 90 Figure 49. Sub-Area 5.6 Walkover Gamma Survey Dat(! .......................................................................... 91 Figure 50. *Area 5 Locations on the 2014 WNYNSC Aerial Radiological Survey ........................................ 93 Figure 51. WNYNSC Confirmatory Locations on 2014 Aerial Survey ....................................................... 97 v
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas List of Tables Table 1.      Locations Selected for Further Evaluation ................................................................................ 5 Table 2.      DCGLw Peak-of-the-Mean Values, Rev. 2 for 25 mrem/year (pCi/g)l 1 l .................................... 17 Table 3.      WNYNSC Background Area Dose Rates Based Upon 2014 Aerial Survey Data ...................... 22 Table 4.      WNYNSC Background Soil Concentrations ............................................................................. 23 Table 5.      SNI Background Floodplain Area Dose Rates Based Upon 2014 Aerial Survey Data .............. 25 Table 6.      SNI Background Non-Floodplain Area Dose Rates Based Upon 2014 Aerial Survey Data ...... 26 Table 7.    . Area 1 Tissue Equivalent Dose Rate Instrument Gross Readings ........................................... 29 Table 8.      Area 1 Weighted Average Soil Concentrations ....................................................................... 30 Table 9.      Area 1 Cesium-137 Soil Concentrations Comparison ............................................................. 30 Table 10. Area 1 Net Average Soil Concentrations ................................................................................. 31 Table 11. Area 1 Dose Rates Based Upon 2014 Aerial Survey Data ....................................................... 33 Table 12      Area 1 Calculated Doses Based on 2014 WNYNSC Aerial Radiological Survey ....................... 34 Table 13. Sub-Area L12 Current Use Pathway Doses ............................................................................. 35 Table 14. Sub-Area L23 Current Use Pathway Doses ............................................................................. 37 Table 15. Area 1 Comparison to WVDP Phase 1 Decommissioning Plan DCGLw .................................... 37 Table 16. Sub-Area L12 Potential Use Pathway Doses ........................................................................... 38 Table 17. Sub-Area L23 Potential Use Pathway Doses ........................................................................... 38 Table 18. Concentrations in Edible Portions of Fish around Springville Dam ........................................ 38 Table 19. Background Concentrations in Edible Portions of Fish ........................ '. .................................. 39 Table 20. Ingestion dose coefficients (mrem  I µCi) from ICRP 68 ..................................................... :.... 39
*Table 21. Area 2 Tissue Equivalent Dose Rate Instrument Gross Readings ...................... ;........ :........... 45 Table 22      Sub-Area 2.1 Weighted Average Soil Concentrations ............................................................. 46 Table 23. Sub-Area 2.1 Net Average Soil Concentrations ...................................................................... 46 Table 24. Sub-Area 2.2 Weighted Average Soil Concentrations ............................................................. 46 Table 25. Sub-Area 2.2 Net Average Soil Concentrations ..................... ; ................................................ 47 Table 26. Area 2 Dose Rates Based Upon 2014 Aerial Survey Data ....................................................... 49 Table 27. Area 2 Calculated Doses Based on 2014 WNYNSC Aerial Radiological Survey ....................... 49 Table 28. Sub-Area 2.1 Current Use Pathway Doses .............................................. :................................ 50 Table 29. Sub-Area 2.2 Current Use Pathway Doses .............................................................................. 52 Table 30. Area 2 Comparison to WVDP Phase 1 Decommissioning Plan DCGLw .................................... 53 Table 31. Sub-Area 2.2 Potential Use Doses .......................................................................................,... 54 Table 32. Concentrations in Edible Portions* of Fish around Springville Dam ........................................ 54 Table 33. Background Concentrations in Edible Portions of Fish ...... ; .................................................... 54 Table 34. Ingestion dose coefficients (mrem  I µCi) from      ICRP 68 ...................................................... :... 54 Table 35. Sub-Area 3.1 Average Soil Concentrations ................................... :......................................... 59 .
Table 36. Sub-Area 3.1 Net Average Soil Concentrations ...................................................................... 60 Table 37. Sub-Area 3.2 Average Soil Concentrations ............................................................................. 60 Table 38. Sub-Area 3.2 Net Soil Concentrations ..................................................................................... 60 Table 39. Area .3 Dose Rates Based Upon 2014 Aerial Survey Data .................. , .................................... 63 Table 40. Area 3 Calculated Doses Based on 2014 WNYNSC Aerial RadiologiCal Survey ....................... 63 Table 41. Sub-Area 3.1 Pathway Doses ....................................................................*.............................. 65 vi
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 42    Sub-Area 3.2 Pathway Doses ..............................................................................~ ................... 6S Table 43. Area 3 Comparison to WVDP Phase 1 Decommissioning Plan DCGLw .................................... 6S Table 44. Sub-Area 3.1 Potential Use Pathway Doses ............................................................................ 66 Table 4S. Sub-Area 3.2 Potential Use Pathway Doses ............................................................................ 67 Table 46. Concentrations in Edible Portions of Fish around Springville Dam ........................................ 67 Table 47. Background Concentrations in Edible Portions of Fish ........................................................... 67.
Table 48. Ingestion dose coefficients (mrem/µCi) from ICRP 68 ............................................................ 67 Table 49. Area 4 Average Dose Rates ..................................................................................................... 77 Table so. Area 4 Dose Rates Based Upon 2014 Aerial Survey Data ............................................... : ....... 79 Table Sl. Area 4 Calculated Doses Based on 2014 WNYNSC Aerial Radiological Survey ....................... 79 Table S2    Area S Average Dose Rates ........................................................... :......................................... 92 Table S3    Area S Dose Rates Based Upon 2014 Aerial Survey Data ....................................................... 94 Table S4    Area S Calculated Doses Based on 2014 WNYNSC Aerial Radiological Survey ....................... 9S Table SS. WNYNSC On-Center Confirmatory Location Tissue Equivalent Dose Rate Readings ............. 96 Table S6. WNYNSC On-Center Confirmatory Soil Concentrations Including Background ...................... 97 Table S7. Dose Rates Based Upon 2014 Aerial Survey Results ............................................................... 98 Table S8. Area 1 Calculated Annual Dose (mrem/year) ......................................................................... 99 Table S9. Area 2 Calculated Annual Dose (mrem/year) ............................. : ......................................... 100 Table 60. Area 3 Calculated Annual Dose (mrem/year) ....................................................................... 100 Table 61. Area 4 Calculated Annual Dose (mrem/year) ....................................................................... 101 Table 62. Area S Calculated Annual Dose (mrem/year) ....................................................................... 101 vii
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Li~t of Acronyms Aerial Survey  . 2014 Aerial Radiological S1,1rvey (Aerial Survey)
BGA              Background Area cm                Ce.ntimeter CPM              Counts per minute DCF              Dose coefficients factbr DCGL              Derived Concentration Guideline Level DOE              U.S. Department of Energy ELAP              Environmental Laboratory Approval Program EPA              U.S. Environmental Protection Agency
. fl                Fractional Absorption in the Gastrointestinal Tract Rate FS&DP            Field Sampling and Dose Assessment Plan ("Plan")
g                Gram GPS              Global Positioning System HASP              Health and Safety Plan ICRP              International Commission on Radiological Protection kCPM              Thousand counts per minute m                Meter MDL              Minimum Detectable Levels MJWTS            MJW Technical Services* Inc.
mrem              Milli rem Nal              Sodium Iodide NIST              National Institute of Standards and Technology NORM              Naturally Occurring Radioactive Material NRC              Nuclear Regulatory Commission NYSDEC            New York State Department of Environmental Con.servation NYSDOH            New York State Department of Health NYSERDA          New York State Energy Research and Development Authority pCi              Pico Curie PM                Project Manager QAPP              Quality Assurance Project Plan RESRAD*          RESidual RADioactive Material RSL              Remote Sensing Laboratory SNI              Cattaraugus Territory of the Seneca Nation of Indians WNYNSC            Western New York Nuclear Service Center WVDP              West Valley Demonstration Project viii
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Appendices Appendix A- Field Sampling and Dose Assessment Plan, Rev. O and Summary of Field Changes Appendix B - Field Guides Appendix C - Analytical Methodology Appendix D - Land Use Surveys Appendix E - Field Sample Collection and Instrument Check Information Appendix F - Soil Sample Summary Appendix G - Certificates of Analysis Appendix H - Dose Assessment Appendices Appendix I - Summary of Liquid Effluent Discharges NFS Operations and WVDP Activities ix
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Executive Summary Purpose The purpose of the radiological survey and dose assessment project was to determine if areas identified in the 2014 Aerial Radiological Survey (Aerial Survey) of the Western New York Nuclear Service Center (WNYNSC} (Ref. 1} as having elevated levels of radioactivity above background do in fact contain elevated radionuclide concentrations in the soil. If elevated soil concentrations were identified, a dose assessment (based on current and reasonably foreseeable future land use) was conducted to confirm that there were no health and safety concerns for the identified area. Because the areas sampled are off site and the land use*is unrestricted, the dose assessment results were compared to 10 C.F.R. § 20.1402, Radiological Criteria for Unrestricted.Use (Ref. 2).
In addition, the U.S. Nuclear Regulatory Commission (NRC} requested that a comparison of the soil sampling results to the Derived Concentration Guidelines in the WVDP Phase 1 Decommissioning Plan (Ref. 3) be completed as an independent check against a conservative exposure scenario.
The results from this soil sampling and dose assessment project show that radiation exposure to the public for each of the areas evaluated is substantially below the NRC-regulatory unrestricted use requirement of 25 millirem (mrem) per year (in accordance with 10 C.F.R. § 20.1402}. Therefore, no public health and safety concerns were identified through this analysis.
Radiological Survey and Sampling Actions Specific areas were identified in the project Field Sampling and Dose Assessment Plan ("Plan") (Ref. 4, Appendix A) for study based upon the Aerial Survey and other historic knowledge (e.g., Cesium Prong).
The Plan further specified ,the specific survey and sampling parameters for each area including the location and shape of the area, the number of locations within the_ area to be surveyed and sampled, and radiochemical analyses to be performed. Field Guides (Appendix B) provided additional detail and instructions on surveys and sampling.
The number of locations to be surveyed and sampled in each survey area was based upon the size of the area.
* For areas 0- 2,000 m 2 in area, a minimum of four locations were surveyed and sampled.
* For areas 2,001to10,000 m 2 in area, a minimum of 15 locations were surveyed and sampled.
* For areas> than 10,000 m 2 in area, a minimum of 24 locations were surveyed and sampled.
* The following is an overview of radiological survey and sampling actions taken. Additional detail is provided for each area surveyed in Sections 5.1 through 5.6 of this report.
Radiological survey and sampling activities included three components:
* Global Positioning System (GPS) Walkover Gamma Surveys ES-1
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas GPS walkover gamma surveys were conducted over designated survey areas using a Ludlum Model 2241-2 Scaler Rate Meter and a Ludlum Model 44-10 2"x2" Sodium Iodide (Nal) gamma detector, coupled with a GPS unit. Radiation count rates in counts per minute (CPM) were collected as the survey team walked designated grid patterns while the GPS position was simultaneously logged. The purpose of this survey was to determine if any sub-regions within the designated survey area were elevated compared to the rest of that survey area. The results were displayed graphically, and if elevated sub-regions were identified, samples were collected in the elevated sub-regions, along with random samples.
* Collection of Soil Samples Within each survey area, soil samples were collected from the number of locations and at the depth intervals specified in the plan. Specifically, ba~ed on a review of historical information, areas where potential contamination was more likely a result.of airborne deposition, initial surface layer samples were analyzed from the first five cm of soil. Similarly, based on a review of historical information, areas where potential contamination was more likely the result of water deposition, initial samples were analyzed from the first 15 centimeter (cm) of soil.
* Static Direct Radiation Measurements At each location where soil samples were collected, static direct radiation measurements were collected using both a Bicron microRem survey meter, which employs a tissue equivalent gamma detector, and a Ludlum Model 2241-2 Scaler Ratemeter with the Model 44-10 2"x2" Nal gamma detector. Readings were collected at 1 and 100 cr:n above the ground.
Sample Radiochemical Analysis As specified in the Plan, a percentage of the samples collected were submitted for radiochemical analysis. All samples submitted were analyzed by a New York State Department of Health (NYSDOH)
Environmental Laboratory Approval Program (ELAP)-laboratory forgamma spectroscopy (which includes analysis for Cs-137), gross beta, and gross alpha analysis. Some samples were also analyzed for additional isotopic information. Where surface samples statistically exceeded Cs-137 background concentrations plus two standard deviations, the next deeper depth increment samples were analyzed.
All analytical data received Level IV data validation per (Evaluation of Radiochemical Data Usability (es/er/ms-5), 1997 (Ref. 5) and were found to be usable. Additional detail is provided in Sections 6.1 through 6.6 and the Appendices.
Summary of Dose Assessment Results For each area studied, a dose assessment was conducted as specified in the Plan or as subsequently determined to be the appropriate methodology. For Areas 1, 2, and 3, this was based upon property-specific land use, and the size and physical characteristics of the area such as terrain and tree cover. For Areas 4 and 5, which are located on the Cattaraugus Territory ofthe Seneca Nation of Indians (SNI),
culturally specific aspects of land use surveys are still being developed. This report will be revised to ES-2
Radiological Survey and Dose.Assessment Report for the WNYNSC and Off-Site Areas include the modeled dose assessments for Areas 4 and 5 once the culturally specific aspects of the land use surveys are finalized. Additional detail is provided for each area in Sections 5.1 through 5.6 and the Appendices to this report.
The radiation doses were assessed using the following approach:
* Annual radiation doses were estimated based upon the results of the 2014 Aerial Survey. No background level information for the specific areas assessed in this report was provided in the Aerial Survey Report. Therefore, background levels were interpolated from the data.
* Annual radiation doses were estimated based on readings collected using the tissue equivalent dose rate survey.meters.
* Annual radiation doses, for current land use, were estimated by performing RESidual
* RADioactive (RESRAD) OFFSITE 3.1 computer code (Ref. 6) of measured gross alpha, gross beta, and Cesium-137 (Cs-137) soil concentrations in excess of background. The assessment of the gross alpha was based on the most conservative isotopes (Americium-241 [Am-241] or Plutonium-239 [Pu-239]) and the beta was based on Strontium-90 (Sr-90).
: 1. Of the alpha emitters that are of dosimetric concern, Pu-239 and Am-241 were selected as the two alpha-emitting isotopes based on the predominant concentrations of these two radionuclides in the West Valley waste stream (i.e., they were greater than 10,000 times other alpha-emitting radionuclide concentrations for the historical operations). In addition, due to the longer half-lives of these isotopes, Pu-239 and Am-241 would continue to be dosimetrically important in the dose assessments for future land users.
: 2. Of the beta emitters that are of dosimetric concern, Sr-90 was selected as the beta emitting isotope based on the concentrations in the West Valley waste stream, and the fact that Sr-90 is longer-lived than the majority of beta-emitters that would have been generated during historical operations. Sr-90 is a waste product of reprocessing and thus it would likely be a contributor to the beta.dose from the site.
* For purposes of this study, background concentrations were determined from two locations within the WNYNSC and from 10 locations within the SNI, five of which are in the Cattaraugus Creek floodplain and five of which are not in the floodplain.
* These sample results were compared to the Derived Concentration Guideline Level (DCGLw) concentrations established in the Phase 1 Decommissioning Plan for the West Valley Demonstration Project (WVDP). This comparison of the gross alpha and beta was based on the most conservative isotopes (AM-241, Pu-239 and Sr-90, respectively) and accounted for all of the anthropogenic nuclides except Carbon-14 (C-14), lodine-129 (1-129), and Technetium-99 (Tc-99). For these radionuclides, a qualitative analysis was performed. In all cases for these three radionuclides, either the soil concentration was below the detection limit or the soil concentration detected was significantly less than the Phase 1 Decommissioning Plan DCGLw Values. In addition, an analysis of the isotopic data indicates that the radionuclides that account for most of the gross alpha and gross beta soil concentrations are radionuclides that are considered Naturally Occurring Radioactive Material (e.g., natural uranium, natural thorium, and potassium-40. The DCGLs used for this comparison were based on a resident farmer scenario.
* Annual radiation doses for reasonably foreseeable future land use were also estimated using the RESidual RADioactive (RESRAD) 7.0 computer code (Ref. 7) to assess gross alpha, gross beta, and ES-3
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Cs-137 soil concentrations in excess ofbackground. The assessment of the gross alpha was based on the most conservative isotopes between Am-241 and Pu-239 and the beta was based on Sr-90.
* Annual radiation doses from the consumption of fish were also estimated. Calculations were performed using the average concentration of Sr-90 and Cs-137 in the edible portion of fish above background from the 2012 WVDP Annual Site Environmental Report (Ref. 8). Annual exposures were calculated based on ingestion dose' coefficients from the International Commission on Radiological Protection (ICRP) ICRP Publication 68 (Ref. 9).
In two areas located on the SNI (Areas 4 and 5), dose assessments were performed based on aerial survey and direct radiation measurements. Soil sampling actions were performed, however dose assessments based upon soil concentrations will be prepared after more fully characterizing the current and future uses of these areas including culturally specific aspects of the SN l's use of these properties.
Conclusion The assessed doses in Areas 1, 2, and 3, based upon multiple approaches and covering current and reasonably foreseeable future land use scenarios, were determined to be significantly less than the 25 mrem per year requirement identified in 10 C.F.R. § 20.1402, and there are no health and safety concerns identified for these locations.
For Areas 4 and 5, which are located on the SNI, culturally specific aspects of SNI land use are being developed. Therefore, any dose assessment included in this version of the report will be revised once the culturally specific aspects of land use are finalized.
ES-4
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 1.0      Introduction 1.1      Background The New York State Energy Research and Development Authority (NYSERDA) owns the 3,300-acre Western New York Nuclear Service Center (WNYNSC) in the town of Ashford, New York. Since 1982, NYSERDA and the U.S. Oepartment of. Energy (DOE) have been working at the WNYNSC ("Center") to conduct the West Valley De.monstration Project (WVDP), a high-level radioactive waste solidification and cleanup project.
In September 2014, DOE and NYSERDA jointly initiated an aerial radiological survey (Ref. 1) to examine the radiological conditions of the Center and adjacent areas, as well as Cattaraugus Creek from the Center to Lake Erie in Western New York. This Aerial Survey was conducted by the National Nuclear Security Administration's Remote Sensing Laboratory (RSL).
Previous aerial, soil sampling, and radiological survey studies had identified areas of contamination both on the WNYNSC property, and in nearby off-site locations resulting from routine permitted disc~arges and inadvertent releases of radioactivity from the site (1995 Western New York Nuclear Service Center Off-Site Radiation Investigation Summary Report, Dames & Moore) (Ref. 10). Of note was the identification and analysis of areas referred to as the "Cesium Prong." The Cesium Prong comprises an irregularly shaped area on the Center property that extends outward and generally to the northwest, onto off-Center properties. This contamination is believed to be the result of unintentional airborne releases from the Center in 1968. Historic soil sample data from the Cesium Prong is consistent with airborne surface deposition of Cs-137. In addition to the Cesium Prong, the Aerial Survey showed slightly elevated areas of radioactivity in the on-site creeks including Buttermilk Cree.k, and possibly Cattaraugus Creek. A summary of liquid effluent discharges from the WVDP is provided in Appendix I.
Based on the Aerial Survey, five areas outside the Center property were identified for further evaluation based on information provided by RSL that showed that radiation levels at these locations were slightly above the "background" radiation levels seen throughout Western New York1 . Two of these areas were identified during previous aerial surveys, and the three other locations were newly identified during the 2014 Aerial Survey. The identification of the three new areas is likely due to improvements in detection sensitivity and precision, and the survey extending into areas that had not been previously surveyed.
MJW Technical Services Inc. (MJWTS) was retained by NYSERDA to conduct a survey, sampling, and dose assessment study to "ground truth" the 2014 Aerial Survey results, and to confirm that credible potential radiation exposures to members of the public in unrestricted areas do not exceed the applicable NRC limits per 10 C.F.R. § 20.1402. The survey and sampling operations were extensive, and examined areas in proximity to the Center, as well as the areas further to the west, located on the SNI.
Background radiation is caused by naturally occurring radioactive materials like radon and from certain man-made radioactive materials that are found throughout the environment today.
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas The scope of the activities conducted by MJWTS included development and execution of the Plan (Ref.
4), a project Quality Assurance Project Plan (QAPP) (Ref. 11), a project Health and Safety Plan (HASP)
(Ref. 12}, Field Guides (Appendix B); and procedures.
2.0      Project Components and Organization 2.1      Field Sampling and Dose Assessment Plan The Plan describes the purpose and objectives ofthe project; defines the project organization and structure; establishes the approach for field survey, sample collection, analysis, data validation, and defines the requirements and ~pproach to dose assessment. An initial draft of the Plan was shared with the NRC, the Environmental Protection Agency (EPA}, the New York State Department of Environmental Conservation (NYSDEC), NYSDOH, and the SNI. Comments provided by these agencies were used to develop the Plan, which was issued on October 1, 2015. Minor revisions in the sampling areas identified in the Plan were implemented after further discussion between NYSE RDA and RSL when the final version of the 2014 Aerial Survey was issued. The changes are summarized in Appendix A.
2.2      Quality Assurance Project Plan (QAPP)
The QAPP provides the project specific details on how the surveys _and samples were to be collected to ensure representativeness, traceability and reproducibility. The data quality objectives are defined in
* the QAPP, along with information detailing data quality and validation processes. Appendix E, Data Quality Objectives, provides additional detail on field and laboratory data quality indicators.
2.3      Project Health and Safety Plan (HASP)
The HASP provides the project specific details on how the project activities would be conducted in a safe . *
*manner and in compliance with applicable safety requirements.
2.4      Participants, Roles, and Responsibilities The key project staff and their primary roles and responsibilities were:
NYSERDA Project Manager The NYSERDA Project Manager was the primary point of contact and coordination with the MJWTS Project Manager, and ensured that the MJWTS Project Manager was cognizant of relevant information, issues, objectives, requirements, and potential concerns or deficiencies.
Project Manager The Project Manager (PM} was responsible for execution of the survey, sampling, and dose assessment activities and was responsible for the health physics aspects for all field activities. The PM was also responsible for ensuring that work was executed in a ti.mely manner, in accordance with the Plan, and in conformance with all applicable regulatory requirements.
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Project Certified Health Physicist The Project Certified Health Physicist ensured that the collection and analysis of survey data and the derived dose assessments were conducted properly and in accordance with the Plan and appropriate professional and regulatory standards and practices to ensure thatresults are accurate and defensible.
Project. Health Physicist The Project Health Physicist was responsible for the evaluation of survey and laboratory data, and for the performance of the dose assessments.
Project Quality Assurance and Control Manager The Project Quality Assurance and Control Manager was responsible for all aspects of project Quality Assurance and Quality Control including field surveying, sampling activities, and laboratory analysis.
Project. Data Validation Specialist The Project Data Validation Specialist was responsible for Level IV validation of data as required by accepted professional practices and standards in accordance with the QAPP.
Project lnformatfon Technology/Geographic Information System Specialist The Project Information Technology/Geographic Information System Specialist was responsible for oversight of data file storage and the processing of acquired data, in particular, GPS-driven radiation survey data.
3.0      Summary of 2014 Aerial Survey Results and Areas Selected for Analysis The 2014 Aerial Survey was conducted by RSL. It encompassed areas in proximity to the WNYNSC as well as a corridor following Cattaraugus Creek westward to Lake Erie. The detection capabilities of this survey were considerably better than those of previous a.erial surveys due to improved technology. The aerial survey data was spectroscopic in nature, thus allowing RSL to extract information specific to anthropogenic isotopes including Cs-137 and Cobalt-60 (Co-60). Cobalt-60 was not identified outside of the WNYNSC.
3.1      Method to Select Off-Site Survey Areas Based Upon the Results of the Aerial Survey Data and Reduce Uncertainty in the Location and Extent of Contaminated Areas NYSERDA consulted extensively with RSL personnel on the identification of specific areas that warranted follow-up measurements based upon the results of the aerial survey. Based on RSL's expert knowiedge of this particular dataset and their vast experience with aerial survey methods and results of similar surveys, RSL suggested a methodology that they believed was conservative and would capture the pertinent features and support the identification of areas for follow-up measurements. RSL identified four criteria that when considered in combination (i.e., an area must meet all criteria concurrently),
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas resulted in delineation of specific areas that were meaningful to NVSERDA's ground-level measurements of ambient radiation and collection of soil samples. These criteria included:
: 1. Data from the Cs-137 spectral signature are greater than two standard deviations above backgrou.nd. This threshold (30 counts per second) is only slightly above background and is thus coincidental with statistical noise in the dataset. This particular measure on its own could result in false negatives. That is, given the relatively small variance in the extraction algorithm, Cs-137 may be indicated in the spectral data though not strongly within the photopeak.
: 2. Data from the anthropogenic-sources spectral signature are greater than two standard deviations above background. This threshold (1000 counts per second) is only slightly above background and is thus coincidental with statistical noise in the dataset. This particular measure on its own could result in false positives. That is, because the anthropogenic extraction has a relatively large variance, it can produce false positives if used to look for a specific isotope (Cs-137).
: 3. Both Criteria 1 and 2 are met, and they are both met over the same area (co-located), or both met over areas in close proximity to one another. Given that aerial survey methods result in somewhat "coarse" data, it is difficult to define exact spatial "boundaries" of areas meeting thresholds*1 and 2 strictly from the aerial data. As such, consideration is given to areas that are not only co-located (overlapping), but also to those areas located relatively near one another (less than or equal to 300 feet).
: 4. Both criteria 1 and 2 are met, areas are co-located or located in close proximity (criteria 3), and these areas appear clustered or extended in the area. Given that criteria 1 and 2 are very close to background, the first three criteria produce a dataset that still contains statistical noise, identifying very small randomly located spots across the entire aerial survey area. Having examined.the detailed spectral data, RSL was confident these small random areas represent statistical noise. Where these areas appeared clustered and/or extended in area, RSL believed they are more suggestive of areas that may contain slightly elevated levels of radiation. As such, these four criteria, in combination, provide a reasonable delineation of areas that warrant follow-up measurements of ambient radiation at ground level and soil sample collection.
Based on the criteria identified above, five areas were selected for survey, sampling, and dose assessment. These areas were designated Areas 1, 2, 3, 4, and 5 (Figures 1 through 5). Areas 2, 3, 4, and 5 were further broken down into sub-areas. Area 2 had two sub-areas, Area 3 had two sub-areas, Area 4 had five sub-areas, and Area 5 had six sub-areas. In order to reduce uncertainty in the location and aerial extent of the potentially elevated regions, when GPS or manual survey grids were surveyed using the Ludlum 2241-2 survey meter and 2"x2" Nal gamma detector, the boundaries of the survey areas were extended outside of the boundaries identified by the aerial survey data. These meter readings therefore achieved*two things:
: 1. The identification of any comparatively elevated regions within the areas identified by the RSL data.
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas
: 2. The identification of any elevated regions, within the survey area, but outside the areas identified by the RSL data .
For the Area 2, rectangular survey boxes (associated with the 2"x2" meter readings) encompassed an area at least three times the area of the investigation lines derived from the RSL data.
For Areas 3.1, the shape of the 2"x2" survey readings boundaries were based on configuration of the terrain and other physical features surrounding the investigation areas derived from the RSL data .
For Areas 4 and 5, the sub-areas (e.g., 4.1, 4.2 etc.) were identified by constructing polygons that surrounded the clusters of investigation areas (e.g., 4.lA, 4.1 B, etc.) based upon the RSL criteria . These polygons determined the boundaries of the GPS walkover survey traverses .
In addition to these five areas, "Confirmatory" locations were also sampled on the WNYNSC to compare Aerial Survey results to areas known or suspected to contain contamination .
The five survey areas and their current land characteristics (as determined through aerial photos and land use surveys) (Appendix D) and the on-center confirmatory location are summarized in Table 1.
Table 1.          Locations Selected for Further Evaluation Current Land                    GPS Coordinates Area No.            Location Characteristic                  (centroid location)
Residential properties, Cesium Prong 1                                with cleared and tree        42°27' 46.97" N    78°40'13.53"  w (Off-Site) covered areas.
* Near Scoby Hill Dam (new location likely    Varying in terrain and 2        an extension of the    tree cover. These areas      42°28'25 .66" N    78°41'18.84"  w Cesium Prong) (Sub-        are not residential.
Areas 2.1 and 2.2)
Near confluence of Buttermilk and 3        Cattaraugus Creeks    Active agriculture area.      42°28'56.20" N      78°40'42.19"  w (Sub-Areas 3.1 and 3.2)
Wooded area that does Cattaraugus Territory not include residences 4        of the Seneca Nation                                  42°32'23,84" N      79°02'13.07"  w on the floodplain of of Indians Cattaraugus Creek Wooded area near Cattaraugus Territory residential property not 5        of the Seneca Nation                                  42°31'12. 94"N      78°58'25.11"  w on the floodplain of of Indians Cattaraugus Creek WNYNSC WNYNSC                                      On-Center                  N/A                  N/A Confirmatory Page 5of102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Details on these areas and the discrete locations selected for study on, or in proximity to, the WNYNSC are provided in Figures 1 through 6.
3.1.1    Area 1 Area 1 (Cesium Prong, outside the WNYNSC property) includes three specific locations within the Cesium Prong, but outside of the WNYNSC property. Because the Cesium Prong was extensively sampled and analyzed in the 1990s, these samples were collected to compare currently measured concentrations to previously measured concentrations decay corrected to current day. Figure 1 below provides a map of these locations .
Figure 1          Area 1 Sampling Locations 0
1.1 1.2 w
              -----====--------Feet 0    500    , 000          iooo Area 1 Sampling Locations
* 20 t 5 Con11rmatory Soj Sample Locations
                -    2014Areas 1ee      g Cr'lteria !or Fur'lrler EvaluatlQ'I Wesiem New York Nuclear Service Center Page 6of 102
Rad iological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 3.1.2    Area 2 Area 2 consists of two separate sub-areas northwest of Area 1 in a region transected by the Route 219 Expressway in proxim ity to Cattaraugus Creek. Figure 2 provides a map of these locations .
Figure 2.          Area 2 Survey and Sampling Locations The area near the center of the ma p was identified as meeting criteria fo r further evaluation; however, the lan downer decline d pe rmission to survey an d sample.
UB-AREA2.1 Q
SUB-AREA 2.2
    --9'===------Feet 0    250      500              1,000 Area 2 Survey and/or Sampling Locations
      -    2014Areas Meeting Cnteria fOf Further Evaluation survey and Samphng Sub-Areas Page 7of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 3.13. Area 3 Area 3 consists of two separate sub-areas adjacent to the northern section of the WNYNSC on a farm located at the confluence of Buttermilk and Cattaraugus Creeks. Figure 3 provides a map ofthese locations.
Figure 3.          Area 3 Survey and Sampling Locations Cattaraugus Creek SUB-AREA 3.1 Butlerrmlk Creek
      ---======-----*Feet 0      250      500              1.000 Area 3 Survey and/or Sampling Locations
        -    2014 Areas Meebng Cnter a for Furttler Evaluation Westem New York Nuclear Service Center Survey end Sampling Sub-Areas Page 8of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 3.1.4    Area 4 Area 4 consists of five separate Sub-Areas spanning Cattaraugus Creek, located approximately 20 miles to the west of the WNYNSC and on the Seneca Nation of Indians Cattaraugus Territory. Figure 4 below provides a map of these locations .
Figure 4 .        Area 4 Survey and Sampling Locations Area 4 Survey and/or Sampling Locations
      ~ 014    Areas Meeting Criteria for Further Evaluation urvey and Sampling Sub-Areas Page 9of102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 3.1.5    Area 5 Area 5 consists of six separate sub-areas north of Cattaraugus Creek, located approximately 17 miles to the west of the WNYNSC and on the SNI. Figure 5 below provides a map of these locations .
Figure 5.            Area 5 Survey and Sampling Locations 5.6 5.1 5.5
                                                                                  ~. 4 6 .2 5.3
    ----===-------*lfe<<
250    5()0        t .000 Area 5 Proposed Surrvey and/or Sampling locations
              -      2014Areas Meeting Criteria for Further Evaluation survey and sampling Sub-Areas Page 10 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 3.1.6  WNYNSC Confirmatory Four selected locations on the WNYNSC property were identified for survey and sampling. These were considered "Confirmatory" locations to compare Aerial Survey results to areas known or suspected to be contaminated . Figure 6 below provides a map of these locations .
Figure 6.      WNYNSC Confirmatory Sampling Locations Sampling Locations
* Poienb.al Confinna1Dry Sample ocaUQl!s 2014 Areas Meebng Cntena for Funh er Ev uabon Wes1em New York Nuclear Se111ice Center I
0    0.25 05 Page 11of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 4.0    Data Quality Objectives 4.1    This soil sampling and dose assessment study was completed using the Plan (Ref. 4). Within the context of the Environmental Protection Agency' s guidance for identifying data quality objectives (EPA QA/G-4 Guidance for the Data Quality Objectives Process, 2000), (Ref. 13) and (EPA QA R-5 EPA Requirements for Quality Assurance Planning, 2001) (Ref. 14) the rationale for the sampling approach is as follows :
: 1. State the problem - This soil and dose assessment effort was completed as a follow -up activity to the 2014 Aerial Survey of the WNYNSC. Specifically, the 2014 Aerial Survey identified five areas potentially having elevated levels of radioactivity above background . An aerial radiation survey does not, however, provide the data to confirm that all of the areas identified are below public health and safety standards, for example the criteria in 10 CFR 20.1402, Radiological Criteria for Unrestricted Use.
: 2. Identify the goals of the study - The key goal for this activity was to evaluate each of the five areas to determine if these areas do in fact contain elevated rad ionuclide concentrations in the soils, and for those with elevated concentrations, to complete a dose assessment that evaluates the current and reasonably foreseeable future land use scenarios to determine if there are any health and safety issues for the property.
The criteria used to evaluate each area are the NRC Radiological Criteria for Unrestricted Use (10 CFR 20.1402), which establishes the requirements that exposure for the public must be less than 25 mil Ii rem per year for license termination with unrestricted use.
: 3. Identify the inputs to the decision - The input to the decision of whether the decision criteria were met include:
* The dose rate data collected during the 2014 Aerial Survey,
* The field dose rate measurements collected for each area,
* The soil samples collected and analyzed for specific alpha, beta and gamma-emitting radionuclides,
* A comparison to theWVDP Phase 1 Decommissioning Plan Derived Concentration Guidelines
* A dose assessment completed for the current land use, and
* A conservative dose assessment using a reasonably foreseeable future land use scenario.
: 4. Define the boundaries of the study- The study focused on five areas identified through the aerial radiation survey, and land use information .
: 5. Develop the analytic approach - If the soil sampling data for cesium, gross alpha or gross beta are greater than two standard deviations above background, then a dose assessment is conducted .
If the dose assessment information from the various evaluation methods are below 25 mrem/year, then the 10 CFR 20.1402 criteria used for comparison purposes are met.
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas
: 5. Specify performance or acceptance criteria - Acceptance criteria developed for the aerial survey data are discussed in Section 3.1. The acceptance criteria developed for the field and soil sampling data are listed below.
Field Survey and Soil Sampling Data Acceptance Criteria The field survey and soil sampling acceptance criteria identified in the plan include :
a)  Use of certified standards (e.g., National Institute of Standards and Technology) to calibrate and daily evaluate the operabil ity of instrumentation . The acceptance criteria for the instrumentation is specified in the applicable quality assurance documents for the field and laboratory instrumentation .
b)  Quality control standards to ensure that the laboratory instrumentation maintained calibration during the sample analysis period . The frequency and acceptance criteria for the laboratory analyses is specified in the GEL Quality Assurance Plan, Rev. 29 (Ref. 15).
c)  Field and laboratory duplicates were collected and analyzed at a frequency of 20 percent to ensure that the soil sampling and laboratory analys is methodologies w ere cons istent with the quality control parameters defined by the laboratory.
d)  Multiple sample locations and soil depths sent for analysis to ensure that the soil concentration data was representative of the area
: 7. Optimizing the design for obtaining data - In order to optimize the design and obtain survey data that addresses the goal of this effort, sampling was conducted using multiple survey methods and data collection efforts in order to compare the dose values calculated for each area . These multiple survey and data collection efforts included :
a)  Aerial radiation survey data of the entire area identified the five locations where follow-up activities were warranted .
b)  Follow-up gamma walkovers and tissue equivalent surveys were completed for each area to determine if any elevated locations were within an area, and the dose rates at each location .
c)  If any elevated locations were identified they were sampled and the remainder of the random sampling was conducted based on the size of the areas. Soil samples were collected from 0-100 cm, with at least two at-depth samples collected from each area.
d)  All surface soil samples were sent for gross alpha, gross beta and gamma spectroscopy.
e)  Next depth interval soil sample analysis were completed if the initial surface analysis were greater than background mean plus two standard deviations.
f)  Detailed radionuclid e an alysis we re compl et ed fo r a min imum of 20 percent of each area.
g)  Finally, dose assessments were conducted for all areas with dose rate read ings or soil sample results greater than two standard deviations above background . These assessments were compared to the 10 CFR20.1402 dose standard (25 mrem/year).
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 5.0      Field Survey and Sampling Strategy The following is a description of the equipment and general method s used to conduct field survey and sampling operations.
5.1      Instrumentation and Equipment Used Instrumentation and equ ipment used to collect direct radiation level measurements included:
* Bicron " microRem " Survey Meters - These instruments mea sure gamma radiation exposure rates using a tissue equivalent detector. The manufacture r-stated accuracy for the Bicron instruments is 10 percent (for Cs-137) across the operating ranges that were used . The internal scintillation detector is tissue equivalent and provides a flat energy response over a broad gamma energy range .
* Ludlum Model 2241-2 Scaler Ratemeter connected to a Ludlum Model 44-10 2" x2" Nal gamma detector - This instrument can collect count rates in Counts per Minute (CPM) or can .collect scaler (static) counts (the total number of counts in a designated counting time such as one minute) . The 44-10 Nal detector is nominally nine percent efficient for Cs-137, and exhibits a non-linear energy response (the Am-241 response, for example, is typically 30-40 times higher than the response to Cs -137).
* Ludlum Model 2241-2 Scaler Ratemeter connected to a Ludlum Model 44-lO 2" x2" Nal gamma detector coupled to a Trimble GeoXT-GeoExplorer GPS instrument - This system allowed for the simultaneous collection and logging of CPM and GPS location . Under ideal conditions, the GPS unit can achieve sub-meter location precision . The actual precision varied depending on the number of available satellite signals and the slope of the terrain being surveyed.
* Garmin GPSMAP 64s GPS - This GPS was used to determine the sample locations . This instrument can achieve a nominal five -meter precision. The actual precision varied depending on the number of available satellite signals and the slope of the terrain being surveyed .
* National Institute of Standards and Technology (NIST) Traceable Thermometers - These thermometers were used to log temperatures at the beginning of a day's field operations, nominally at lunch time, and again at the conclusion of the day's operations when instrument operability and source checks (see Appendix E) were performed to verify that no substantive changes in instrument response occurred due to temperature changes . Checks were performed using both a NIST traceable Cs-137 source and a thorium check source .
All radiological detection equipment was calibrated within the last 12 months by an MJW Technical Services' NYSDOH-licensed calibration facility (Ref. 16), using NIST traceable Cs-137 calibration sources.
In addition, the field operability checks were performed typically three times per day as described above (see Appendix E).
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 5.2      Overland GPS Walkover Gamma Surveys The first step taken by the survey team was to perform a GPS walkover gamma survey of the designated survey area. The survey team walked grid patterns across the survey area with the detector suspended close to the ground . To the extent practicable, the grid pattern extended slightly beyond the borders of the designated survey area . In some locations this was not possible because of unsafe terrain or obstructions .
After the data was collected , it was downloaded and transferred to a computer. The data consiste.d of the measured CPM and the GPS Coordinates. The data was overlaid onto maps as color-coded dots . The color of the dots corresponded with increments of CPM . For example, the count rate increments could be 0-5000 CPM, 5000-10,000 CPM, 10,000 to 15,000 CPM, etc. The count rate color coding increments were specific to each survey area . This allowed for the most sensitive graphic analysis for each particular area .
Once displayed graphically, the data was evaluated by the PM to determine if any locations in the map showed count rates that were higher than the rest of the map (elevated locations) . If elevated locations were discerned in a survey area, the PM would direct the sampling and survey team to collect at the elevated locations in addition to the random sample locations .
GPS walkover gamma surveys with the Ludlum/GPS units were not conducted in Area 1 or in the Confirmatory locations in the Cesium Prong inside the WNYNSC property boundary since the objective was to measure radiation levels and collect data at specific preselected locations.
5.3      Direct Radiation Measurements After the GPS Survey was completed and all sampling locations were identified, the survey team collected static direct radiation measurements at each sampling location before collecting samples .
Static radiation measurements consisted of:
* Dose rate measurements using the Tissue Equivalent Bicron survey meter at elevations of one cm and 100 cm above the ground .
* Two consecutive one-minute scaler counts using the Ludlum Scaler Ratemeter and 2" x2" Nal gamma detector, at the one and 100 cm elevations. No dose assessment was performed based on these readings.
5.4      Sample Collection Activities After the direct radiation measurements were completed, soil samples were collected in accordance with the Plan and associated Field Guides .
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas For each sampling location, the number of samples to be collected and the increments of depth (e.g., 0-15 cm depth sample or a 15-30 cm depth sample) were predetermined in accordance with the Plan .
Excavation was performed and samples were collected using hand tools in order to carefully sample from the correct depths. Sampling equipment was thoroughly cleaned in between each depth to ensure against cross-contamination of samples . Field (split) duplicates were collected in accordance with the QAPP. Samples were placed in plastic sample bottles and labeled . Sample information was recorded on the sample bottles and on the field Chain-of-Custody Forms for transfer to a secure sample storage area to await shipment to the analytical laboratory. Equipment blanks and a sample of the deionized water used for instrument cleaning were also sent to the laboratory for quality control analysis . Appendix F provides a summary of all soil samples collected, including locations, depths, and type of laboratory analysis.
5.5      Radiochemical Analysis Most of the samples collected from each area were submitted for radiochemical analysis, while others were archived as specified in the Plan . A total of 641 samples were collected in the field, and 532 were submitted for analysis to GEL Laboratories, a NYSDOH -ELAP analytical laboratory.
All samples submitted for analysis were analyzed for gross alpha activity, beta activity, and by gamma spectroscopy. Some samples also underwent additional isotopic analysis. Appendix C provides further detail regarding the analyses including the isotopes, analytical method, and Minimum Detectable Concentrations. As noted above, Quality Control samples, including field duplicates, equipment (rinsate) blanks, and deionized water were also collected and analyzed.
Analytical data was provided by the laboratory with two standard deviation precision . All analytical data underwent Level IV data validation in accordance with the Evaluation of Radiochemical Data Usability
{Ref. 5) and all data were determined to be usable. Appendix G provides the laboratory Certificates of Analysis.
In Areas 1, 2, 3, 4, and 5 the surface samples were all analyzed and the gross alpha, gross beta and Cs-137 concentrations were compared to the background concentrations (refer to Section 6.1 for information related to determination of background) . For each surface sample, the gross alpha, gross beta and Cs-137 concentration was compared to the background screening level (background plus two standard deviations), and if it exceeded the screening level, the next depth sample from that location was submitted for analysis.
6.0    Dose Assessment Approach The strategy and approach to assess potential radiation doses included the following elements :
* Assessment of dose based upon the Aerial Survey data .
* Assessment of dose based on the tissue equivalent dose rate measurements.
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas
* Assessment of dose based on soil concentrations using the RESRAD OFFSITE 3.1 computer code (Ref.
: 6) with input parameters adjusted to meet current land use based on land use survey forms (i.e.,
Recreational Hiker/Hunter, Resident Homemaker, Resident Farmer). Appendix H provides key RESRAD information and data .
* Comparison of the surface soil concentrations to the surface soil decay-corrected DCGLw Peak-of-the-Mean values of the WVDP Phase 1 Decommissioning Plan . The peak-of-the mean values are the most conservative DCGLwvalues provided in the Phase 1 WVDP Decommissioning Plan and are for a resident farmer scenario.
Table 2.          DCGLw Peak-of-the-Mean Values, Rev. 2 for 25 mrem/year (pCi/g)! 1 l Nuclide          Surface Soil Am -241              2.9E+01 C-14              1.6E+01 Cm-243              3.SE+Ol Cm-244              6.SE+Ol Cs-137!2!            1.SE+Ol 1-1 29            3.3E-01 Np-237              2.6E-01 Pu-238              4.0E+Ol Pu -239            2.SE+Ol Pu -240            2.6E+01 Pu-241              1.2E+03 Sr-90!2!            4.lE+OO Tc-99              2.1E+01 U-232              1.SE+OO U-233              8.3E+OO U-234              8.4E+OO U-235              3.SE+OO U-238              9.8E+OO (1)      The DCGLw is the DCGL applicable to the average concentration over the survey unit.
(2)      WVDP Phase 1 DP DCGLs for Sr-90 and Cs-137 are based on an assumption of immediate free release w ith no hold time for decay.
* Assessment of dose based on soil concentrations using the RESRAD 7.0 computer code (Ref. 7, Appendix H) with input parameters adjusted to account for potential future use scenarios .
Appendix H provides key RESRAD information and data .
* Assessment of dose associated with the consumption of fish. Calculations were performed using the average concentration of Sr-90 and Cs -137 in the edible portion of fish above background from the ASER (Ref. 8). Annual exposures were calculated based on ingestion dose coefficients from the ICRP (Ref. 9) .
For the current land use RESRAD calculations using the soil analytical results, Area 1 was assessed using a " Resident Homemaker" scenario, Area 2 was assessed using a " Recreational Hiker" scenario (with hunting), and Area 3 was assessed using a " Resident Farmer'' scenario (for Area 3 livestock grazing and Page 17 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas feed corn crop cultivation was assumed). For Areas 4 and 5, which are located on the Cattaraugus Territory of SNI, culturally specific aspects of land use are being developed . This report will be revised to include the modeled dose assessments for Areas 4 and 5 once the culturally specific aspects of land use are finalized .
For the conservative reasonably foreseeable land use evaluation, all areas were assessed using a*
" Resident Farmer" scenario with livestock and crop cultivation for consumption . The only exception was Area 2.1, where the deeply sloped terrain and extremely small size are not suitable to support a resident farmer land use scenario. As such, the only reasonably fore seeable land use for Area 2.1 was a
" Recreat ional Hiker'' (w ith hu nt ing), which is the same scenario as the current land us e.
Dose Assessments based upon soil concentrations were performed using the conservative assumptions that gross beta activity in excess of background was attributable to Sr-90, and that gross alpha concentrations, in excess of background, was attributable to either Am-241 or Pu -239 (separate calculat ions).
6.1      Background Radiation and Radionuclide Determinations In order to assess potential radiation exposures in excess of background, it was necessary to determine background levels for all locations surveyed . This included background soil concentrations for Cs-137, gross beta, and gross alpha activity. In addition, it was necessary to determine instrument backgrounds for the tissue equivalent survey meters that were used to measure direct exposure rates . Two separate background data sets were developed :
* One set of background measurements was conducted for comparison to dose rates and soil concentrations from Areas 1, 2, and 3, and the Confirmatory locations on the WNYNSC property.
This location is designated as "WNYNSC Background ." The initial intent as specified in the Plan was to use the existing background determinations from a 2014 WVDP Terrestrial Background Study {Ref. 17). However, the DOE Background Study did not include gross alpha or gross beta soil concentrations, so it was necessary to obtain new background data as part of the current study. Ten locations were surveyed and sampled from within the two reference background areas identified in the 2014 DOE Background Study.
* A second background data set obtained for Areas 4 and 5 (SNI Background). Within this data set, two subsets of data were developed : one using data collected from the floodplain of Cattaraugus Creek for application to Area 4, and one using data collected from areas not on the floodplain for application to Area 5.
In order to account for the measurements uncertainty in a calculated average, a weighted mean was used to combine any set of similar data into a single average and its combined uncertainty. A weighted mean is used instead of standard average when the data do not all have the same level of precision.
Therefore, a weighted mean was used to calculate the average external dose rates taken at a given distance and the average soil concentrations for the given depth . The equations to calculate a weighted mean for a given depth and its associated standard deviation (one sigma) are shown below:
Page 18 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas L ~i weighti x concentrationi Weighted mean for a given depth=            --"-=:...---'--'-------
L ~ i weighti
                      .                                      1 weight . = - - - - - - - - - - - - - - - - - - - - - -
1    (standard deviation, 1 sigma, of the concentration) i 1
Stan dar d deviation of the weig hted m ean =
6.1.1    WNYNSC Background Determination Two areas on the WNYNSC property that had previously been established as reference background areas in the 2014 DOE Background Study were sampled and surveyed . For purposes of this study, they are refe rred to as Background Area 1 and Background Area 2. Instrument readings and soil samples were collected from five locations in each of the two areas. Instrument readings were collected in a manner identical to the field readings collected in each survey area (i .e., readings using the tissue equivalent Bicron Instrument and the Ludlum Instrument with 2"x2" Nal detector at elevations of one cm and one meter) . Sample depth increments were 0-15 cm, 15-30 cm , 30-60 m, and 60-100 cm. In each of the two areas a total of 12 samples were collected and analyzed including five samples from 0-15 cm, 5 samples from 15-30 cm, one sample from 30-60 cm, and one sample from 60-100 cm.
Figure 7 shows the location of the two background areas designated Background Area 1 (BGAl) and Background Area 2 (BGAl) .
Figure 7.      General Locations of Background Areas General Location Background An?as 1 and 2
* Legend Sample Location
                                                                                        \    '
                )
I
                                                                                  \
Page 19 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figures 8 and 9 provide closer views of each area including sample location points.
Figure 8.        Background Area 1 Sample Locations Figure 9.        Background Area 2 Sample Locations Page 20 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas WNYNSC Survey Background Readings Figures 10 and 11 below are maps extracted from the Aerial Survey data to which the locations for Background Areas 1 and 2 have been added . The dose rates at an elevation of one meter as derived from the map are presented in Table 3. The Aerial Survey states that the contribution to dose from cosmic rays and airborne radon across the entire map is 4.8 &#xb5; R/hour.
Figure 10.        WNYNSC Background Area 1 location on the 2014 Aerial Radiological Survey Exposure Rate micro R per hour LJ 0-1 0 0-2 CJ 2-3 LJ 3-4 L J 4-5 5-6
  -    S-7
                  -                                  . BGA1 9
  -    7-8      c::i
  -    9-10
  -    10-20 fim 20-100 100-200 200-430 Sampling Location WNYNSC Page 21of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 11.            WNYNSC Background Area 2 Location on the 2014 Aerial Radiological Survey Exposure Rate 3-4 4-5
        ~
  -- 87--98 6-7
                                          . BGA2
    -    9-10
    -    10-20
    -    20-lOO 100-200 200-430
* satnplln9 Location WNYNSC Table 3.              WNYNSC Background Area Dose Rates Based Upon 2014 Aerial Survey Data Dose Rate Range    Average Dose        Cosmic + Radon  Total Dose        Average Location              from Map          Rate                Dose Rate        Rate        Dose Rate
(&#xb5;R/hour)      (&#xb5;R/hour)              (&#xb5;R/hour)      (&#xb5;R/hour)      (&#xb5;R/hour)
Area 1                3-4            3.5                  4.8            8.3 8.3 Area 2                3-4            3.5                  4.8            8.3 WNYNSC Nal Detector Background        Reading~
The background area static readings using the 2" x2" Nal detector were averaged between two counts at each location and ranged from 6146 CPM to 6781 CPM at the 100 cm elevation . The average across all locations was 6333 CPM .
All background area Nal detector data is provided in Appendix H32.
WNYNSC Bicron Instrument Background Calculation The average dose rates measured using the Bicron tissue equivalent survey meters were calculated at one and 100 cm elevations. A "screening" value for comparison to the data from Areas 1, 2 and 3, and Page 22 of 102
Radiological Survey and Dose-Assessment Report for the WNYNSC and Off-Site Areas the Confirmatory locations on the WNYNSC property was calculated based on the average of the readings plus two standard deviations. The results were as follows:
Average Background Bicron Instrument Reading (+/- 1 sigma)
* 3.69 +/- 0.12 &#xb5;rem/hour at the 100 cm elevation Background Bicron Reading Based Screening Level (Average + 2 sigma)
* 3.93 &#xb5;rem/hour at the 100 cm elevation WNYNSC Background Soil Concentrations Table 4 below provides the average WNYNSC background soil concentrations at each depth :
Table 4.            WNYNSC Background Soil Concentrations Depth                  Alpha*                Beta*                  Cesium*
(cm)                  (pCi/g)            (pCi/g)                  (pCi/g) 0-15            l.2E+Ol +/- 5.6E-01    2.3E+Ol +/- 4.9E-01        2.9E-01 +/- l.3E-02 15-30          l.lE+Ol +/- 5.3E-01    2.0E+Ol +/- 4.5E-01        l.lE-01 +/- l.OE-02 30-60            l.4E+Ol +/- l.2E+OO    2.4E+Ol +/- l.OE+OO        O.OE-00 +/- l.7E-02 60-100          l.4E+Ol +/- l.2E+OO    2.8E+Ol +/- l.lE+OO        l.lE-01 +/- l.9E-02
* Uncertainty is reported+/- 1 sigma 6.1.2    Seneca Nation of Indians (SNI) Background Determination Ten background locations on the Cattaraugus Territory of the Seneca Nation of Indians were surveyed and sampled . Five locations were in the floodplain of Cattaraugus Creek (Locations 19, 20, 21, 22, and 24), while the remaining locations (18, 23, 25, 26, and 27) were not in the floodplain . Figure 12 provides
- a map of these locations.
Instrument readings and soil samples were collected from the ten specified locations. Instrument readings were collected in the same manner as performed in all other areas (i.e ., readings using the Bicron tissue equivalent survey meter, and the Ludlum Instrument with 2" x2" Nal detector, at elevations of 1and100 cm). Sample depth increments were 0-15 cm, 15-30 cm, 30-60 cm, and 60-100 cm.
Page 23 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 12.              SNI Background Locations Sampling Locations Seneca Nation of Indians Cattaraugus Territory B-189
                                                                        -      2014Areas Meeting Criteria for Further Evaluation e    Saci<ground Sample Locations Survey an<I Sampling SUD-Areas B-229 B-21e
                          "'* g SUB-AREAS 4.1
* 4.5 1 B-2-le SUB*AREAS 3. 1
* S.3
  --'==---FM*
0 I 2!iO 2SOO    S,to:
SNI Aerial Survey Background Readings Figures 13 and 14 below are maps extracted from the Aerial Survey data to which the Floodplain and Non-Floodplain locations have been added . The dose rates at an elevation of one meter as derived from the map are presented in Tables 5 and 6. The Aerial Survey states that the contribution to dose from cosmic rays and airborne radon across the entire map is 4.8 &#xb5;R/hour.
Page 24 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 13.          SNI Background Floodplain Locations on the 2014 Aerial Radiological Survey Exposure Rate 4-5
        ~
es IB 19
  -- s7--g8
  . . l>-7
                                    . SHIS21 9--10 10-20 20-100 100-200 SN1820.
SNfES24 200-430
* Sample Location Cattaraugus Territay Table 5.            SNI Background Floodplain Area Dose Rates Based Upon 2014 Aerial Survey Data Dose Rate Range    Average Dose        Cosmic + Radon    Total Dose        Average Location            from Map          Rate                Dose Rate          Rate        Dose Rate
(&#xb5;R/hour)        (&#xb5;R/hour)            (&#xb5;R/hour)      (&#xb5;R/hour)      (&#xb5;R/hour)
SNIB 19                  4-5          4.5                  4.8              9.3 SNIB 20                  3-4          3.5                  4.8              8.3 SNIB 21                  4-5          4.5                  4.8              9.3            8.9 SNIB 22                  4-5          4.5                  4.8              9.3 SNIB 24                  3-4          3.5                  4.8              8.3 Page 25 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 14.        SNI Background Non-Floodplain Locations on the 2014 Aerial Radiological Survey a::
l/)
* SNIB 25 3-4
                          ~
4-5            E
(!)
5-6
                          ~
m    s.1            0 ll                                                  . SNIB 26 9
7-8 9-10 c:
                                                                                          . SNIB27
      -    10-20
      -    20-100
      ! m 100-200 200-430                    SNl823 .
Cattaraugus ierritoty Table 6.          SNI Background Non-Floodplain Area Dose Rates Based Upon 2014 Aerial Survey Data Dose Rate Average Dose      Cosmic + Radon                        Average Range from                                          Total Dose Rate Location                            Rate              Dose Rate                        Dose Rate Map                                                (&#xb5;R/hour)
(&#xb5;R/hour)            (&#xb5;R/hour)                        (&#xb5;R/hour)
(&#xb5;R/hour)
SNIB 18                3-4          3.5                  4.8            8.3 SNIB 23                2-3          2.5                  4.8            7.3 SNIB 25*                n/a          n/a                  n/a            n/a            7.8 SNIB 26*                n/a          n/a                  n/a            n/a SNIB 27*                n/a          n/a                  n/a            n/a
* Locations outside of aerial survey.
SNI Nal Detector Background Readings The background readings in the SNI Background floodplain locations at the 100 cm elevation ranged from 6512 CPM to 8864 CPM and averaged 7943 CPM . This background is applicable to the Areas 4.1 through 4.5.
The background readings in the SNI Background non-floodplain locations at the 100 cm elevation ranged from 7022 CPM to 12270 CPM and averaged 8745 CPM . This background is applicable to Areas 5.1 through 5.6.
Page 26 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas SNI Bicron Instrument Background Calculation The average dose rates measured using the tissue equivalent survey meters were calculated at the one and 100 cm elevations . A "screening" value for comparison to the data from Areas 4 and 5 was calculated based on the average of the readings plus two standard deviations . The results were as follows:
SNI Average Background Bicron Instrument Readings Floodplain Locations (+/- 1 sigma):
* 4.96 +/- 0.22 wem/hour at the 100 cm elevation Non-Floodplain Locations(+/- 1 sigma):
* 4.40 +/- 0.21 &#xb5;rem/hour at the 100 cm elevation SNI Background Bicron Reading Based Screening Level (Avg+2 sigma)
Floodplain Locations:
* 5.41 &#xb5;rem/hour at the 100 cm elevation Non-Floodplain Locations:
* 4.81 &#xb5;rem/hour at the 100 cm elevation SNI Background Soil Concentration Calculations Thirty-nine samples from 10 locations we re collected to determ ine background for Areas 4 and 5, which are located on the SNI. Soil concentration calculations will be provided in the revised version of this report.
7.0      Survey, Sampling and Dose Assessment Results 7.1      Area 1 7.1.1    Description of Area 1 Area 1 encompasses an area outside the boundaries of the WNYNSC that has been previously characte rize d as th e " Ces iu m Prong." It largely co nsists of resi dential prope rt ies t o the north and west of the Center boundary (see pg. 6, Figure 1).
Three locations were surveyed and sampled for comparison to data from the Off-Site Investigation Report (Ref. 10). Sample Locations 1.1 and 1.2 are in a residential area and located within 350 feet of each other in a wooded lot behind a residence . Sample Location 1.3 was located on the edge of an open Pa ge 27 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas field along a tree line. This area is not currently being used for farming or industrial purposes but could be used for recreation includ ing hunting.
7.1.2    Survey and Sampling Methodology for Area 1 No GPS survey was performed in Area 1 since the objective was to survey and sample at three predetermined locations in order to compare current soil radioactivity concentrations to those measured in the 1995 investigation .
To allow comparison , the survey and sampling locations were selected to coincide with locations previously sampled . Locations 1.1and1.2 were in proximity to the location identified as " L12" in the 1995 report (note the sample data presented in the 1995 Report were for samples collected in 1994).
Location 1.3 was in proximity to the location identified as " L23" in the 1995 report . Since GPS locations for the L12 and L23 locations are not precisely known (due to technology limitations at the time), the correlation between current and former locations was only approximate .
Direct radiation readings and soil samples were collected in the three locations as described above and in Table 3 of the Plan .
Each location was surveyed and sampled as follows :
* Dose rate readings were collected at one and 100 cm from the ground surface using the tissue equivalent dose rate meter.
* Static 2" x 2" Nal detector readings were collected at one and 100 cm from the ground surface using the Ludlum Model 2241-2 survey meter coupled to a Ludlum Model 44-10 detector. Two, one-minute scaler counts were collected at one and 100 cm elevations .
* A total of nine soil samples were collected at each of the three soil depth intervals; Oto 5 cm, 5-15 cm and 15-30 cm .
7.1.3    Survey and Sampling Results for Area 1 As noted above, no GPS survey was required for Area 1 since the goal was to compare current to past soil concentration data .
Static 2"x2" Nal Detector Gross Readings at the 100 cm Elevation
* The Area 1 static readings using the 2" x2" Nal detector were averaged between two counts at each location and ranged from 7607 CPM to 8361 CPM . The average across all locations was 7876 CPM .
* The applicable background count rate for Area 1 was determined to be 6333 CPM.
A tabulation of the static count rates is provided in Appendix H32 .
                                                                                                            *I Page 28 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Tissue Equivalent Survey Meter Readings Table 7 provides the tissue equivalent dose rate readings (including background) for each sample location .
Table 7.        Area 1 Tissue Equivalent Dose Rate Instrument Gross Readings Dose Rate at 100 cm Sample Location
(&#xb5;rem/hour) 1.1                            4 1.2                            5 1.3                            6 Soil Sample Comparison to Background Six soil samples from the 0-5 and 5-15 cm depths were analyzed by gamma spectroscopy and for gross alpha and gross beta activity. Due to the proximity in geographic location, the soil concentration values for Locations 1.1 and 1.2 were averaged together for data comparison and dose assessment purposes.
The weighted average soil concentrations for gross alpha, gross beta and Cs-137 results associated with the 0-15 cm depth are summarized in Table 8. In this study, the Area 1 samples were collected at depths of 0-5 cm and 5-15 cm, while the background samples were collected at 0-15 cm and 15-30 cm depths.
Therefore, a weighted average for the 0-15 cm Area 1 depth was calculated as follows in order to compare the soil concentration to an equivalent background depth .
The individual soil concentrations including background for Area 1, associated with multiple independent depths were combined into a single average soil concentration over a single depth . The weight given to any single layer was based on the thickness of each individual stratum as compared to the overall thickness of the combined layer. This is shown in the following equations below :
thicknessi weighti =-    - -.- - -
00 L j=l thicknessj co Weighted average over multiple depths=          L i=l weighti x concentrationi Page 29 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 8.            Area 1 Weighted Average Soil Concentrations Depth          Gross Alpha"                Gross Beta*              Cesium-137" Location
{cm)              {pCi/g)                    (pCi/g)                  {pCi/g) l.1/l.2(L12b)            0-15        8.6E+OO +/- 7.9E-01          l.9E+01+/-7.7E-01            l.1E+OO +/- 4.lE-02 l.3(L23c)            0-15        l.OE+Ol +/- l.3E+OO          2.3E+01 +/- l.2E+OO          4.6E-01 +/- 5.6E-02
: a. Uncertainty is reported+/- 1 sigma.
: b. Locations 1.1 and 1.2 were combined and compared to the sample collected at the location associated with the L12 de scribed in the 1995 Report.
C. Location 1.3 was compared to the sample collected at the location associated with the L23 described in the 1995 Report.
The weighted average gross alpha and gross beta concentrations were less than background soil concentrations provided in Section 6.1 and therefore no further analysis was performed related to the gross alpha and gross beta data. The Cs-137 soil concentrations were above the background soil concentrations provided in Section 6.1; therefore, they were compared to the decay corrected 1995 data as described below.
Comparison of Soil Sample Concentrations to Decay Corrected 1995 Report Concentrations The Cs-137 soil concentrations values from the 1995 report, plus 10 percent were adjusted for decay (activity on the date of the sample analysis would be 61.8 percent of the 1994 activity), and compared to the two standard deviation concentration range for the corresponding 2014 samples as shown in Table
: 9. The samples collected in 1994 were collected at a depth of 0-10 cm and therefore, the weighted averages in Table 8 were recalculated (using the same formula as above) for a depth of 0-10 cm in order to make a comparison at equivalent depths (see Table 9) .
Table 9.            Area 1 Cesium-137 Soil Concentrations Comparison 1994 Sample            1994 Sample Result Decay              2015 Sample 1994            2015        Depth Result                Corrected Plus 10%                      Result Location        location        {cm)
(pCi/g)                        {pCi/g)                        {pCi/g)
L12          i.1 I i.2      0-10        l.6E+OO                        l.1E+OO                        l.5E+OO L23            1.3          0-10        3.4E-01                        2.3E-01                        4.4E-01 The current soil concentrations were not less than the decay corrected data plus 10 percent. Some possible factors that could explain this difference include :
* The weighted average calculated from the 2015 samples is assumed to be homogeneous with in each layer sampled . Since this is not true, the weighted average would be biased high . For instance, based on a review of the 1995 WNYNSC Off-Site Radiation Investigation Report, the majority of the activity is primarily in the first one or two cm, then the resultant weighted average decreases to nearly the same concentration as the prior results corrected for decay.
* Since the current sampling locations were only approximate to the former sampling locations, the difference could be the result of variations in the ground deposition patterns .
* Poss ible migration of activity from natural environmental influences such as wind, rain, etc.
Page 30 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Since the current results were not less than the 1994 values plus 10 percent corrected for decay, the current soil concentrations, net of background, were used to perform a dose assessment for Area 1 as described in Section 7.1.4 (see Table 10).
Table 10.          Area 1 Net Average Soil Concentrations Depth            Gross Alpha"                Gross Beta*                Cesium-137" location (cm)                (pCi/g)                      (pCi/g)                    (pCi/g) 1.1/1.2{L12*)            0-100              O.OE+OO                    O.OE+OO                    7.9E -01 1.3(L23b)            0-100              O.OE+OO                    7 .OE-03                    1.7E-01
: a. Locations 1.1and 1.2 were co mb ined an d compared to t he sa mple collected at t he locat ion associated wit h th e L12 described in t he 1995 Rep o rt.
: b. Location 1.3 was compared to th e sample collected at th e locat ion associated with th e L23 described in th e 1995 Report.
The individual sample numbers, depths, concentrations, uncertainties, and minimum detectable levels (MDLs) are provided in Appendix H2.
7.1.4    Dose Assessment Approach for Area 1 The dose assessment approach for Area 1 was to:
* Develop an estimate of annual exposure based upon the 2014 Aerial Survey.
* Develop an estimate of annual exposure based upon the tissue equivalent meter readings .
* Perform an assessment based on the current land use Resident Homemaker scenario to determine the exposure in excess of background using current and appropriate parameters (e.g., hydrology, occupancy and consumption). Parameters were adjusted based on published references for the region or historical site specific data . Calculations were performed using the weighted mean above background for the data analyzed.
Dose assessments associated with soil data were performed using the RESRAD-OFFSITE 3.1 computer code. Hydrology data for the contaminated, unsaturated, and saturated zones were based on Revision 2 of the Phase 1 Decommissioning Plan for the West Valley Demonstration Project. The RESRAD input parameters used that differed from the RESRAD defaults are summarized in Appendix H3 . In cases where area specific scenarios were not consistent with assumptions used in the Decommissioning Plan, modifications are described below and in Appendix H3 . This would include, but are not limited to, exposure pathways, irrigation, consumption, erosion rates, and occupancy times. For parameters where there were no site-specific data or there was no corresponding Decommissioning Plan value, the RESRAD-OFFSITE default parameters were used .
The Area 1 dose assessment was based on a resident homemaker. The resident is assumed to spend eight hou rs sleeping and another eight hours working inside the dwelling. Of the remaining eight hours, 50 percent is assumed to be spent inside the dwelling (bringing total time in the dwelling to 20 hours) and 50 percent is assumed to be spent outside in the elevated area (bringing the total time spent outside the dwelling to four hours) . It is assumed that this resident homemaker also Page 31of102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas hunts deer and consumes the deer meat. No plant, fish, or dairy cattle milk is consumed from this area . The res ident homemaker's dwelling is located on -site and within the area assessed .
In addition, no irrigation was assumed for any part of Area 1. The evapotranspiration coefficient provided in the Decommissioning Plan was recalculated to maintain the same infiltration rate of 0.26 meters per year. The soil erodibility factor, which is used to calculate the erosion rate, was set to the maximum value ofthe default range (0 to 0.5) in the User Manual for RESRAD-OFFSITE 3.1 (Ref. 6) . Th is will allow transport of elevated concentrations from these areas to the surface water and subsequently ingested by the deer, whi ch is then consumed by the resident homemaker.
* The sample results were compared to the DCGLw concentrations established in the Phase 1 Decommissioning Plan for the WVDP . The peak-of-the-mean values are the most conservative DCGLw values provided in the Phase 1 WVDP Decommissioning Plan and are for a resident farmer scenario.
* Perform an assessment based on a conservative potential use scenario of a Resident Farmer' s exposure to determine the exposure in excess of background using current and appropriate parameters (e.g., hydrology, occupancy and consumption) . Parameters were adjusted based on published references for the region or historical site specific data. Calculations were performed using the weighted mean above background for the data analyzed . Dose assessments associated with soil data were performed using the RESRAD 7.0 computer code . RESRAD input parameters were based on Revision 2 of the Phase 1 Decommissioning Plan for the West Valley Demonstration Project Appendix C. The RESRAD input parameters are summarized in Appendix H33.
* Perform an assessment based on consumption of fish caught from the Cattaraugus Creek. Current land use surveys indicate that in Areas 1, 2, and 3, no consumption of fish occurs. Calculations were performed using the average concentration of Sr-90 and Cs-137 in the edible portion of fish above background from the ASER (Ref. 8) . Annual exposures were calculated based on ingestion dose coefficients from the ICRP (Ref. 9) .
7.1.S    Dose Assessment Results for Area        i Dose estimate based upon 2014 WNYNSC Aerial Survey Data Figure 15 below is an aerial radiological survey map extracted from the Aerial Survey data to which the locations for Areas 1.1, 1.2, and 1.3 have been added . The dose rates at an elevation of 100 cm as derived from the map were determined to be 2-3 (&#xb5;R/hour) for Area 1.1 and 3-4 (&#xb5; R/hour) for Areas 1.2 and 1.3 . The Aerial Survey states that the contribution to dose from cosmic rays and airborne radon across the entire map is 4.8 &#xb5;R/hour.
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 15.            Area 1 Locations on t he 2014 W NYNSC Aerial Radi ological Survey Exposure Rate micro R per hour LJ 0-1 c::J 0-2 0      2-3 3-4
* SUB-AREA 1.1 4-5
            ~
* SUB-AREA 1.2 m      s..1 8              "'
    -- 9-10&-9 0
    -      10-20
    -      20-100 100-200 200-430
* sampling LocatlOl\
WNYNSC SUB-AREA 1.3 .
Based on this aerial map and the assumed cosmic and airborne radon contribution, the dose rates were determ ined for Area 1 as shown in Table 11. Consistent w ith the methodologies of the Aerial Survey, a value of 4.8 was added to all readings derived from Figure 15 to account for the contribution to background from cosm ic radiation and airborne radon .
Table 11.            Area 1 Dose Rates Based Upon 2014 Aerial Survey Data Dose Rate Average Dose        Cosmic + Radon    Total Dose Range from Location                                    Rate            Dose Rate          Rate Map
(&#xb5;R/hour)          (&#xb5;R/hour)      (&#xb5;R/hour)
(&#xb5;R/hour)
Sub-Area L12              2-3                2.5                4.8              7.3
{l.1+1.2)                3-4                3.5                4.8              8.3 Sub-Area L23 3-4                3.5                4.8              8.3
{1.3)
The average background dose rate based on the WNYNSC Aerial Survey w as 8.3 ~LR/ho u r at 100 cm above the ground . This was subtracted from the total doses rate in Table 11, and based an average occupancy time of 365 days per year, the calculated doses for Area 1 are provided in Table 12.
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 12            Area 1 Calculated Doses Based on 2014 WNYNSC Aerial Radiological Survey Total          Background          Annual Occupancy Location                  Dose Rate          Dose Rate                    Tim eh
(&#xb5;R/hour)            (&#xb5;R/hour)              (hours/year)
Sub-Area L12                    7.8c                8.3                      8670 Sub-Area L23                    8.3                  8.3                      8670                    0.0
: a. The aerial survey dose rates were recorded in units of Roentgen . The quality factors for photons and electrons are both one; therefore 1 R equals 0.877 rem .
: b. Occupancy hours are divided into 83.3 percent Indoors and 16.7 percent Outdoors; a 0.273 gamma shielding fraction is applied to the time indoors.
: c. Average of Sub-Areas 1.1 and 1.2.
Dose Estimate Based on Tissue Equivalent Survey Meter Readings All three survey locations exhibited dose rates in excess of background at the 100 cm elevation . The average dose rate for Sub ~Area L12 was 4.4 +/- 0.3 &#xb5;rem/hour at 100 cm (+/- 1 sigma) . The average dose rate for Sub-Area L23 was 6 +/- 0.6 &#xb5;rem/hour at 100 cm (+/- 1 sigma). The dose rate net of background in Sub-Area L12 and L23 respectively was 0.7 and 2.3 &#xb5;rem/hour at 100 cm . As a result, the annual estimated dose at these locations based on 8760 hours (the occupancy hours derived from the RESRAD Scenario for Area 1) of which 83 .3 percent of the time is spent indoors (with a 0.273 gamma shielding fraction) and 16. 7% of the time is spent outdoors, is 2.4 mrem and 8.0 mrem per year, respectively.
Current Use RESRAD Dose Assessment Based Upon Soil Concentrations Assuming a Resident Homemaker Scenario Sub-Area L12 Sub-Area L12 was defined as a 69,600-square-meter piece of property (see Figure 16). The deer associated with Sub-Area L12 are assumed to stay within the boundaries of the road . This results in a deer pasture area of about 1,062,100 square meters . In addition, the creek bed to the north of the elevated area is assumed to provide the drinking water resources for the deer. The creek is assumed to be about 50 meters wide and averages about one-meter deep over the course of the year.
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 16.        Sub-Area L12 Soil samples for Sub-Area L12 from Locations 1.1and1.2 were analyzed for the first 15 cm of soil.
Therefore, the assumption was made that the entire first meter of soil was the same average soil concentrations as the first 15 cm.
The exposure to a resident homemaker in Sub-Area L12 that also consumed deer meat is provided in Table 13. The RESRAD input parameters are provided in Appendix H3 .
Table 13.        Sub-Area L12 Current Use Pathway Doses Ground              Inhalation              Meat                Soil          Total (mrem/year)          (mrem/year)        (mrem/year)          (mrem/year)    (mrem/year) 1.02E-OO              6.34E-07              2.94E -03          7.14E-04      1.02E-OO The main source of exposure is direct external from the ground . This accounted for over 99 percent of th e overa ll exposure . The full RESRAD output file is provided in Appendix H8 .
Sub-Area L23 Sub-Area L23 was defined as a 130,760-square-meter piece of property (Figure 17) . The deer associated with Sub-Area L23 are assumed to stay within the boundaries of the creek and the road. This results in a Page 35 of 102
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas deer pasture area of about 1,330,000 square meters. In addition, the pond area to the south of the elevated area is assumed to provide the drinking water resources for the deer. The pond is estimated to be about 18,252 square meters and averages about one-meter deep over the course of the year.
Figure 17.      Sub-Area L23 Soil sample for Sub-Area L23 from Locations 1.3 was analyzed for the first 15 cm of soil. Therefore, the assumption was made that the entire first meter of soil was the same average soil concentrations as the first 15 cm .
The exposure to a resident homemaker in Sub-Area L23 that also consumed deer meat is provided in Table 14. The RESRAD input parameters are provided in Appendix H3 .
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 14.        Sub-Area L23 Current Use Pathway Doses Ground              Inhalation                Meat                Soil            Total (mrem/year)          (mrem/year) .          (mrem/year)          (mrem/year)      (mrem/year) 2.19E-01            3.86E-07              1.34E-03            1.72E-04          2.21E-01 The main source of exposure is direct external from the ground . This accounted for over 99 percent of the overall exposure. The full RESRAD output file is provided in Appendix H9.
Comparison to the WVDP Phase 1 Decommissioning Plan DCGLw Values for Area 1 Table 15 provides a comparison of the Area 1 soil concentrations to the WVDP Phase 1 Decommissioning Plan DCGLw Values .
Table 15.        Area 1 Comparison to WVDP Phase 1 Decommissioning Plan DCGLw Measurement        Nuclide      WVDP DCGL        Net Soil Concentrations (pCi/g)          Comparison Type            Used            (pCi/g)            L12              L23            L12            L23 Alpha          Pu-239          2.SOE+Ol          O.OE+OO          O.OE+OO        Below          Below Beta          Sr-90          4.lOE+OO          O.OE+OO          7.0E-03        Below          Below Cesium          Cs-137          1.SOE+Ol          1.7E+OO          1.7E-01        Below          Below Sum of the Fractions:    Below          Below The assessment of the gross alpha and beta based on the most conservative isotopes (Pu-239 and Sr-90, respectively) will account for all of the anthropogenic nuclides listed in Table 2 except for C-14, 1-129, and Tc-99. For these radionuclides, a qualitative analysis was performed . In all cases for these three radionuclides, either the soil concentration was below the detection limit or the soil concentration detected was significantly less than the Phase 1 Decommissioning Plan DCGLw Values. In addition, an analysis of the isotopic data indicates that the radionuclides that account for most of the gross alpha and beta soil concentrations are radionuclides that are considered NORM (e.g., natural uranium, natural thorium, and potassium-40.
Therefore, the use of the DCGLs based on the WVDP Phase 1 Decommissioning Plan resident farmer
* scenario and gross results assuming the most conservative nuclides result in a highly conservative comparison.
Conservative Potential Use RESRAD Dose Assessment Based Upon Soil Concentrations Assuming a Resident Farmer Scenario Sub-Area L12 Sub-Area L12 was defined as a 69,600-square-meter piece of property (see Figure 16). This assessment is based on a resident farmer scenario. It is assumed that the farmer's dwelling, crop fields, and pasture lands resides in the elevated area . In addition, the crop that is grown is consumed by the farmer. The farmer also maintains and consumes both dairy and meat from the cattle. The annual exposure for Sub-Area L12 is provided in Table 16. The RESRAD input parameters are provided in Appendix H33 .
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 16.          Sub-Area L12 Potential Use Pathway Doses Ground          Inhalation        Plant            Meat            Milk            Soil            Total (mrem/year)      (mrem/year)    (mrem/year)      (mrem/year)      (mrem/year)    (mrem/year)    (mrem/year) l.llE+OO          5.SSE-07        2.08E-01          l.21E-01        2.23E-01      6.SOE-04        l.66E+OO The full RESRAD output file is provided in Appendix H34.
Sub-Area L23 Sub-Area L23 was defined as a 130,760-square-meter piece of property (Figu re 17). This assessment is based on a resident farmer scenario. It is assumed that the farmer' s dwell ing, crop fields, and pasture lands resides in the elevated area. In addition, the crop that is grown is consumed by the farmer. The farmer also maintains and consumes both dairy and meat from the cattle . The annual exposure for Sub-Area L23 is provided in Table 17. The RESRAD input parameters are provided in Appendix H33 .
Table 17.          Sub-Area L23 Potential Use Pathway Doses Ground          Inhalation        Plant            Meat            Milk            Soil            Total (mrem/year)        (mrem/year)    (mrem/year)      (mrem/year)      (mrem/year)    (mrem/year)    (mrem/year) 2.40E -01        3.38E -07      8.60E -02        3.07E-02        5.74E-02      l.56E-04        4.14E-01 The full RESRAD output file is provided in Appendix H35.
Dose Assessment for Consumption of Fish Based Upon 2012 WVDP Annual Site Environmental Report The ASER (Ref. 8) provides rad iological concentrations of strontium and cesium in the edible portion of the fish in Cattaraugus Creek. Biological data from these locations are provided . Hog-nosed Sucker and White Sucker are sampled from above the Springville Dam, and Steelhead Trout are sampled from below the Springville Dam . Brown Trout, White Sucker, Bullhead, and Hog-nosed Sucker were also sampled at a background location . This data is provided in Appendix H41. The average radiological concentrations of strontium and cesium in the edible portion of the fish for the two areas around Springville Dam and the background area are provided in Tables 18 and 19 below.
Table 18.          Concentrations in Edible Portions of Fish around Springville Dam Isotope            Average            1 Sigma                Units Sr-90            1.40E-08          l.16E-09              &#xb5;Ci/g - wet Cs-137            5.46E-08          l.31E-08              &#xb5;Ci/g - wet Page 38 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 19.          Background Concentrations in Edible Portions of Fish Isotope            Average            1 Sigma                Units Sr-90            l.02E-08          l.77E-09              &#xb5;Ci/g - wet Cs-137            4.75E-08          4.00E-08              &#xb5;Ci/g -wet This results in a net above background concentration in the edible portions of the fish of 3.74E-09 &#xb5;Ci Sr-90 per gram offish flesh and 7.08E-09 &#xb5;Ci Cs-137 per gram offish flesh . The ingestion dose coefficients factor (DCF) and the fraction of an ingested element directly absorbed to body fluids (fl) from ICRP 68 are provided in Table 20.
Table 20.          Ingestion dose coefficients (mrem / &#xb5;Ci) from ICRP 68 Isotope              fl*            DCF                    Units Sr-90              0.3        l.04E+02            mrem/&#xb5;Ci Ingestion Sr-90              0.01        l.OOE+Ol            mrem/&#xb5;Ci Ingestion Cs -137              1          4.81E+Ol            mrem/&#xb5;Ci Ingestion
* fl - Fractional absorption in the Gastrointestinal tract rate .
EPA's Exposure Factors Handbook (Ref. 18) indicates that the 95th percentile offish consumption by recreational anglers is about nine kg of fish per year. This results in an annual exposure rate of less than 0.1 mrem per year.
7.1.6    Conclusions for Area 1 Annual doses based on the Aerial Survey, tissue equivalent survey meter readings, and RESRAD analysis ranged from 0.0 to 8.0 mrem per year. Soil concentrations were all below the DCGL values. This demonstrates that Area 1 is well below the NRC regulatory release requirement of less than 25 mrem per year in accordance with 10 C.F .R. &sect; 20.1402.
7.2      Area 2 7.2.1    Description of Area 2 Area 2 consisted of two Sub-Areas (Area 2.1, and Area 2.2) . These areas lie in a region nominally three miles to the northwest of the WVDP that is transected by the Route 219 Expressway. Area 2.1 is to the north and on the west side of the expressway, while Area 2.2 is to the south on the east side of the Expressway (see pg. 7, Figure 2). Area 2.1 and Area 2.2 are both sloped, and tree covered.
7.2.2    Survey and Sampling Methodology for Area 2 GPS Walkover Gamma Surveys of Area 2 Because both areas were steeply sloped, making footing in some places treacherous, coupled with the heavy tree cover interfering with GPS satellite signal reception, it was not possible to utilize the GPS and Page 39 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas automated data logging system . As specified in the Plan, the contingency method of laying out a grid system and collecting data by hand in discrete locations was employed .
The 2" x 2" gamma detector survey grid readings in Area 2.1 were on average lower than the readings in Area 2.2. An evaluation of the readings for each individual sub-area however did not identify zones within either sub-area that were elevated compared to the rest of the readings from that particular sub-area . Consequently, the random sampling locations and survey locations were used. Figures 18 and 19 show the sampling locations in Sub-Areas 2.1 and 2.2, respectively .
The general orientation of the Cesium Prong as it projects outward from the WNYNSC is in a northwest direction on an axis, which roughly transects Area 2.1 and 2.2 on the map. In light of the elevations of the areas and their alignment with the direction of the Cesium Prong, there is supposition that any anthropogenic contamination on these sites could be from an airborne deposition pathway. As a result, the surface samples in Area 2 were collected in a 0-5 cm increment, which is where most contamination was predicted from an air deposition pathway.
Figure 18.      Sub-Area 2.2 Survey and Sampling Locations Page 40 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 19.        Sub-Area 2.2 Survey and Sampling Locations SampJe Locations Sub Are Direct radiation readings and soil samples were collected in four locations in each sub-area as described below.
* Dose rate readings were collected at one and 100 cm from the ground surface using the tissue equivalent dose rate meter.
* Static .2" x 2" Nal detector readings were collected at one and 100 cm from the ground surface using the Ludlum Model 2241-2 survey meter coupled to a Ludlum Model 44-10 detector. Two, one-minute counts were collected at each location at both elevations .
* Soil samples were collected in depth increments of 0-5 cm, 5-15 cm, and 15-100 cm . Four locations were sampled in each of Sub-Areas 2.1 and 2.2. Samples were collected from the first two depths at all locations . Samples were collected from the 15-100 cm depth at all locations in Sub-Area 2.2. Due to the difficult terrain and soil conditions, a 15-100 cm sample was only collected in one location in Sub-Area 2.1.
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 7.2.3  Survey and Sampling Results for Area 2 GPS Survey Results Area 2 Figure 20 shows the location of the manual grid for Area 2.1. The manual survey box for Area 2.1 was roughly 19 meters east to west, and 17 meters north to south (Figure 22).
Figure 20.      Sub-Area 2.1 Manual Grid Survey Box Legend Manual Survey Box Figure 21 shows the location of the manual grid for Area 2.2. The manual survey box for Area 2.2 was approximately 37 meters east to west and 27 meters north to south (Figure 23) .
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 21.      Sub-Area 2.2 Manual Grid Box Static 2"x2" Nal Detector Gross Readings at the 100 cm Elevation
* The Area 2.1 static readings using the 2"x2" Nal detector were averaged between two counts at each location and ranged from 9426 CPM to 10117 CPM . The average across all locations was 9736 CPM .
* The Area 2.2 static readings using the 2"x 2" Nal c;letector were averaged between two counts at each location and ranged from 5690 CPM to 6052 CPM . The average across all locations was 5917 CPM.
* The applicable background count rate for Area 2 was determined to be 6333 CPM .
A tabulation of the static count rates is provided in Appendix H32 .
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 22.      Static 2" x 2" Detector Grid Readings for Sub-Area 2.1 7.9      9.9            9.7 i 10.2 I    9.5            10.2 Area too steep too access    9.6 10.6 11.2    10.7            10.4 Page 44 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 23.      Static 2" x 2" Detector Grid Readings for Sub-Area 2.2 Tissue Equivalent Dose Rate Survey Meter Readings .
Table 21 provides the tissue equivalent dose rate readings (including background) for the Area 2 survey and sample locations :
Table 21.        Area 2 Tissue Equivalent Dose Rate Instrument Gross Readings Sample Location      Dose Rate at 100 cm (&#xb5;rem/hour) 2.1.1                            7 2.1.2                            9 2.1.3                            8 2.1.4                            7 2.2.1                            3 2.2.2                            4 2.2.3                            5 Page 45 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 2.2.4                            4 Soil Sampling Results Area 2 Sub-Area 2.1 Six soil samples were analyzed in Sub-Area 2.1. The weighted average soil concentrations for gross alpha, gross beta, and cesium results associated with each stratum depth sampled are summarized in Table 22.
Table 22            Sub-Area 2.1 Weighted Average Soil Concentrations Depth              Gross Alpha*        Gross Beta*        Cesium-137*
(cm)                (pCi/g)              (pCi/g)            (pCi/g) 0-15          l.OE+Ol +/- 9.4E-01  2.4E+Ol +/- 7.lE -01 . 4 .8E-01 +/- 3.2 E-02
* Uncertainty is reported+/- 1 sigma The gross alpha soil concentration was less than background levels . For gross beta and cesium, the soil concentrations were above background levels. The net soil concentrations were used to assess potential exposure to a recreational hiker. As only the first 15 cm of soil was sampled, the concentration for the first meter of soil was assumed to be represented by this depth interval. The net soil concentrations used in the dose assessm ent are provided in Table 23 .
Table 23.          Sub-Area 2.1 Net Average Soil Concentrations Depth                Gross Alpha        Gross Beta          Cesium-137 (cm)                (pCi/g)              (pCi/g)            (pCi/g) 0-100                0.0E+OO            l.3E+OO            l.9E-01 The individual sample numbers, depths, concentrations, uncertainties, and MDLs are provided in Appendix H2.
Sub-Area 2.2 Nine soil samples were analyzed in Sub-Area 2.2. The weighted average soil concentrations for gross alpha, gross beta, and cesium results associated with each stratum depth analyzed are summarized in Table 24 below.
Table 24.          Sub-Area 2.2 Weighted Average Soil Concentrations Depth              Gross Alpha        Gross Beta          Cesium-137 (cm)                  (pCi/g)            (pCi/g)            (pCi/g) 0-15          9.8E+OO +/- l.2E+OO  l.8E+Ol +/- l.lE-00  7.3E-01+/-4.4E-02 15-100          l.3E+Ol +/- l.OE+OO  l.8E+Ol +/- 6.7E-01  0.0E -00 +/- 2.2E-02
* Uncertainty is reported+/- 1 sigma Pa ge 46 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas The gross alpha and gross beta soil concentrations were less than background levels. For cesium, the soil concentration was above background levels. The net soil concentration was used to assess potential exposure to a recreational hiker. The calculated weighted net average soil concentrations used in the dose assessment are provided in Table 25.
Table 25.          Sub-Area 2.2 Net Average Soil Concentrations Depth          Gross Alpha              Gross Beta        Cesium-137 (cm)              (pCi/g)                  (pCi/g)            (pCi/g) 0-100            O.OE+OO                  O.OE+OO            6.6E-02 The individual sample numbers, depths, concentrations, uncertainties, and MDLs are provided in Appendix H2 .
7 .2.4  Dose Assessment Approach Area 2 The dose assessment approach for Area 2 was to :
* Develop an estimate of annual exposure based on the Aerial Survey data .
* Develop an estimate of annual exposure based upon the tissue equivalent dose rate survey meter readings .
* Perform an assessment based on the current land use Recreational Hiker scenario to determine the exposure in excess of background using current and appropriate parameters (e.g., hydrology, occupancy and consumption) . Parameters were adjusted based on published references for the region or historical site specific data . Calculations were performed using the weighted mean above background for the data analyzed .
Dose assessments associated with soil data were performed using the RESRAD-OFFSITE 3.1 computer code . Hydrology data for the contaminated, unsaturated, and saturated zones were based on Revision 2 of the Phase 1 Decommissioning Plan for the WVDP. The RESRAD input parameters used that differed from the RESRAD defaults are summarized in Appendix H3. In cases where area specific scenarios were not consistent with assumptions used in the Decommissioning Plan, modification are described below and in Appendix H4. This would include, but are not limited to, exposure pathways, irrigation, consumption, erosio*n rates, and occupancy times . For. parameters where there were no site-specific data or there was no corresponding Decommission ing Plan value, the RESRAD-OFFSITE default parameters were used .
The Area 2 dose assessment was based on a recreational hiker that spends 100 hours per year in the elevated area . It is assumed that this recreational hiker also hunts deer and consumes the deer meat. No plant, fish, or dairy cattle milk is consumed from this area. The recreational hiker' s dwelling is located off-site and not within the area assessed .
In addition, no irrigation was assumed for any part of Area 2, as the entire area contains undeveloped land . The evapotranspiration coefficient provided in the Decommissioning Plan was Page 47 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas recalculated to maintain the same infiltration rate of 0.26 meters per year. The soil erodibility factor, which is used to calculate the erosion rate, was set to the maximum value of the default range (Oto 0.5) in the User Manual for (Ref. 6). This will allow transport of contamination from the contamination zone to the surface water and subsequently ingested by the deer which is then consumed by the recreational hiker.
* The sample results were compared to the DCGLw concentrations established in the Phase 1 Decommissioning Plan for the WVDP. The peak-of-the mean values are the most conservative DCGLw values provided in the Phase 1 WVDP Decommissioning Plan and are for a resident farmer scenario.
* Perform an assessment based on a conservative potential land use scenario of a Resident Farmer' s exposure in Area 2.2 to determine the exposure in excess of background using current and appropriate parameters (e.g., hydrology, occupancy and consumption) . As stated earlier, the small size and steep terrain of Area 2.1 preclude current or future use for farming. Parameters were adjusted based on published references for the region or historical site specific data . Calculations were performed using the weighted mean above background for the data analyzed . Dose assessments associated with soil data were performed using the RESRAD 7.0 computer code .
RESRAD input parameters were based on Revision 2 of the Phase 1 Decommissioning Plan for the West Valley Demo*nstration Project Appendix C. The RESRAD input parameters are summarized in Appendix H33 .
* Perform an assessment based on consumption of fish caught from the Cattaraugus Creek. Current land use surveys indicate that in Areas 1, 2, and 3, no consumption offish occurs. Calculations were performed using the average concentration of Sr-90 and Cs-13 7 in the edible portion of fish above background from the 2012 WVDP Annual Site Environmental Report . Annual exposures were calculated based on ingestion dose coefficients from ICRP 68.
7 .2.5    Dose Assessment Results for Area 2 Dose Based Upon 2014 Aerial Survey Data Figure 24 is an aerial radiological survey map extracted from the Aerial Survey data onto which the locations for Area 2 have been placed. Tlie dose rates at an elevation of one meter as derived from the
* map were determined to be 4-5 (&#xb5;R/hour) for Area 2.1 and 4-5 (&#xb5;R/hour) for Area 2.2. The Aerial Survey states that the contribution to dose from cosmic rays and airborne radon across the entire map is 4.8
&#xb5; R/hr.
Based on this aerial map and the assumed cosmic and airborne radon contribution, the dose rates were determined for Area 2 as shown in Table 26. Consistent with the methodologies of the Aerial Survey, a value of 4.8 was added to all readings derived from Figure 24 to account for the contribution to background from cosmic radiation and airborne radon .
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Radiologica l Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 24.          Area 2 Locations on the 2014 WNYNSC Aerial Radiological Survey Exposure Rate micro R per hour
                                                  . SUB-AREA 2.1 4-5 0-6 7
* 7*8 9
    -    9-10
    -    10-20
    -    20-100 100-200                                                                    e suB-AREA 2.2 200-430
* Sampling Location Table 26.            Area 2 Dose Rates Based Upon 2014 Aerial Survey Data Dose Rate Average Dose          Cosmic + Radon Range from                                                          Total Dose Rate Location                                          Rate                Dose Rate Map                                                                (&#xb5;R/hour)
(&#xb5;R/hour)              (&#xb5;R/hour)
(&#xb5;R/hour)
Sub-Area 2.1                    4-5                  4.5                      4.8                    9.3 Sub-Area 2.2                    4-5                  4.5                      4.8                    9.3 The average background dose rate based ori the WNYNSC Aerial Survey was 8.3 &#xb5; R/hour at one meter above the ground . This was subtracted from the total doses rate in Table 26, and based on occupancy time of 100 hours per year, the calculated doses for Area 2 are provided in Table 27.
Table 27.            Area 2 Calculated Doses Based on 2014 WNYNSC Aerial Radiological Survey Annual Total          Background                                          Annual Occupancy Location                Dose Rate              Dose Rate                                      Dose Rate*
Time
(&#xb5;R/hour)              (&#xb5;R/hour)                                      (mrem/year)
(hours/year)
Sub -Area 2.1                    9.3                  8.3                    100                      0.1 Sub-Area 2.2                    9.3                  8.3                    100                      0.1
* The aerial survey dose rates were recorded in units of Roentge n. The quality fact ors for photons and electrons are both on e, th erefore 1 R equa ls 0.877 rem .
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Dose Assessment Based Upon Tissue Equivalent Survey Meter Readings Sub-Area 2.1 Sub-Area 2.1 indicated external dose rates higher than the background screening level calculated in Section 5.1. The average dose rate for Sub-Area 2.1 was 7.59 +/- 0.38 &#xb5;rem/hour at 100 cm(+/- 1 sigma).
The average dose rate minus background for Sub-Area 2.1 was 3.9 &#xb5;rem/hour at 100 cm . Therefore, a recreational hiker that spends 100 hours per year in the elevated area would receive 0.4 mrem per year.
Sub-Area 2.2 Sub-Area 2.2 indicated external dose rates slightly higher than the background screening level calculated in Section 5.1. The average dose rate for Sub -Area 2.2 was 3.74 +/- 0.19 &#xb5;rem/hour at 100 cm(+/- 1 sigma).
The average dose rate minus background was 0.05 &#xb5;rem/hour at 100 cm . Therefore, a recreational hiker that spends 100 hours per year in the elevated area would receive a dose of less than 0.1 mrem per year.
Current Use RESRAD Dose Assessment Based Upon Soil Concentrations Assuming a Recreational Hiker Scenario Sub-Area 2.1 Sub-Area 2.1 is a small 42-square-meter patch of undeveloped land (see red marker in Figure 25) . The deer associated with Sub-Area 2.1 are assumed to stay within the boundaries of the creek and the road .
This results in a deer pasture area (white box in Figure 25 below) of about 55,800 square meters. In addition, the creek bed next to the elevated area is assumed to provide the drinking water resources for the deer. The creek is assumed to be about 50 meters wide and averages about one-meter deep over the course of the year.
The exposure to a recreational hiker in Sub-Area 2.1 that also consumed deer meat is provided in Table
: 28. The RESRAD input parameters are provided in Appendix H4.
Table 28.        Sub-Area 2.1 Current Use Pathway Doses Ground            Inhalation              Meat                  Soil            Total (mrem/year)        (mrem/year)          (mrem/year)        (mrem/year)
                                      ~t--~~~~~~~-t-~~~~~-t--~~~~~~~--i (mrem/year) 4.71E-03            2.17E-07            9.47E-05            1. 73E-06        4.81E -03 The main source of exposure is direct external from the ground . This accounted for over 97 percent of the overall exposure . The full RESRAD output file is provided in Appendix HlO.
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 25.      Sub-Area 2.1 and Deer Pasture Area Sub-Area 2.2 Sub-Area 2.2 is a small 350-square-meter patch of undeveloped land (red marker in Figure 26) located between Cattaraugus Creek, Route 219 Expressway, and Cascade Road . The deer associated with Sub-Area 2.2 are assumed to stay within the boundaries of the creek and the road. This res ults in a deer pasture area of about 76,000 square meters . In addition, the creek bed next to the elevated area is assumed to provide the drinking water resources for the deer. The creek is assumed to be about 50 meters wide, runs the entire 329.4 m length of the elevated area, and averages about one-meter deep over the course of the year.
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas The exposure to a recreational hiker in Sub-Area 2.2 that also consumed deer meat is provided in Table
: 29. The RESRAD input parameters are provided in Appendix H4.
Figure 26.      Sub-Area 2.2 and Deer Pasture Area Table 29.        Sub-Area 2.2 Current Use Pathway Doses Ground            Inhalation          Meat                  Soil            Total (mrem/year)        (mrem/year)      (mrem/year)          (mrem/year)      (mrem/year) 2.16E-03          . 3.SOE-10        l.73E -OS            2.38E-07        2.18E-03 The main source of exposure is direct external from the ground . This accounted for over 99 percent of the overall exposure . The full RESRAD output file is provided in Appendix Hll.
Comparison to the WVDP Phase 1 Decommissioning Plan DCGLw Values for Area 2 Table 30 provides a comparison of the Area 2 soil concentrations to the WVDP Phase 1 Decommissioning Plan DCGLw Values .
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 30.          Area 2 Comparison to WVDP Phase 1 Decommissioning Plan DCGlw Net Soil Concentration Measurement            Nuclide      WVDP DCGL                                            Comparison (pCi/g)
Type              Used            (pCi/g) 2.1            2.2        2.1            2.2 Alpha            Pu-239        2.50E+Ol          O.OE+OO          O.OE+OO    Below          Below Beta              Sr-90        4.lOE+OO          l. 3E+OO        O.OE+OO    Below          Below Cesium            Cs-137        l.50E+Ol          l.9E-01          6.6E -02    Below          Below Sum of the Fractions : Below          Below The assessment of the gross alpha and beta based on the most conservative isotopes (Am-241, Pu-239 and Sr-90, respectively) will account for all of the anthropogenic nuclides listed in Table 2 except C-14, 1-129, and Tc-99. For these radionuclides, a qualitative analysis was performed . In all cases for these three radionuclides, either the soil concentration was below the detection limit or the soil concentration detected was significantly less than the Phase 1 Decommissioning Plan DCGLw Values . In addition, an analysis of the isotopic data indicates that the radionuclides that account for most of the gross alpha and beta soil concentrations are radionuclides that are considered NORM (e.g., natural uranium, natural tho rium, and potassium-40.
Therefore, the use of the DCGLs based on the WVDP Phase 1 Decommissioning Plan resident farmer scenario and gross results assuming the most conservative nuclide results in a highly conservative comparison .
Conservative Potential Use Dose Assessment Based Upon Soil Concentrations Assuming a Resident Farmer Scenario Sub-Area 2.1 Sub-Area 2.1 is a small 42-square-meter patch of undeveloped land (see red marker in Figure 25) . Based on its small size and steep terrain, it was determined that a resident farmer scenario was not a viable scenario for this sub-area. The current use scenario of a recreational hiker that also consumed deer meat is considered to be the bounding scenario for any future use of this parcel of land . Therefore, the future use dose is the same as presented in Table 28.
Sub-Area 2.2 Sub-Area 2.2 is a small 350-square-meter patch of undeveloped land (see red maker in Figure 26) located between Cattaraugus Creek, Route 219 Expressway, and Cascade Road . The future land use scenario is a re sident farmer scenario. It is assumed that the farmer' s dwell ing, crop fields, and pasture land s resi des in t he elevated area . In addition, the crop that is grown is consumed by the farmer. The farmer also maintains and consumes both dairy and meat from the cattle . The annual exposure for Sub-Area 2.2 is provided in Table 31. The RESRAD input parameters are provided in Appendix H33 .
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 31.            Sub-Area 2.2 Potential Use Doses Ground            Inhalation          Plant            Meat            Milk        Soil        Total (mrem/year)        (mrem/year)      (mrem/year)      (mrem/year)      (mrem/year) (mrem/year)  (mrem/year) f--'-~---''-'----''-+--'-~-'--'---'--+--'--
8.17 E-02          2.69E-08        1.74E-02          1.0lE-02        1.87E-02  1.90E-05      1.28E-01 The full RESRAD output file is provided in Appendix H36.
Dose Assessment for Consumption of Fish Based Upon 2012 WVDP Annual Site Environmental Report The ASER (Ref. 8) provides radiological concentrations of strontium and ces ium in the edible portion of the fish in Cattaraugus Creek. Biological data from there locations are provided . Hog-nosed Sucker and White Sucker are sampled from above the Springville Dam and Steelhead Trout are sampled from below the Springville Dam . Brown Trout, White Sucker, Bullhead, and Hog-nosed Sucker were also sampled at a background location . This data is provided in Appendix H41. The average radiological concentrations of strontium and cesium in the edible portion of the fish for the two areas around Springville Dam and the background area are provided in Tables 32 and 33 below.
Table 32.            Concentrations in Edible Portions of Fish around Springville Dam Isotope            Average              1 Sigma                Units Sr-90            1.40E-08              1.16E-09            &#xb5;Ci/g - wet Cs-137            S.46E -08            1.31E-08            &#xb5;Ci/g -wet Table 33.            Background Concentrations in Edible Portions of Fish Isotope            Average              1 Sigma                Units Sr-90            1.02E-08              1.77E-09            &#xb5;Ci/g -wet Cs-137            4.75E-08              4.00E-08            &#xb5;Ci/g - wet This results in a net above background concentration in the edible portions of the fish of 3.74E-09 &#xb5;Ci Sr-90 per gram offish flesh and 7.08E-09 &#xb5;Ci Cs-137 per gram offish flesh . The ingestion dose coefficients factors (DCF) and the fraction of an ingested element directly absorbed to body flu ids (fl) from ICRP 68 are provided in Table 34.
Table 34.            Ingestion dose coeffic ients (mrem    I &#xb5;Ci) from ICRP 68 Isotope              fl
* DCF                  Units Sr-90              0.3            1.04E+02          mrem/&#xb5;Ci Ingestion Sr-90              0.01            1.00E+Ol          mrem/&#xb5;Ci Ingestion Cs-137              1              4.81E+01          mrem/&#xb5;Ci Ingestion
* fl - Fractional absorption in the Gastrointestinal tract rate .
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas The Exposure Factors Handbook (Ref. 18) indicates that the 95th percentile of fish consumption by recreational anglers is about nine kg of fish per year. This results in an annual exposure rate of less.than 0.1 mrem per year.
7 .2.6    Conclusions for Area 2 Annual doses based on the Aerial Survey, tissue equivalent survey meter readings, and RESRAD analysis ranged from 0.0 to 0.4 mrem per year. Soil concentrations were all below the DCGL values. This demonstrates that Area 2 is well below the NRC regulatory release requirement of less than 25 mrem per year in accordance with 10 C.F.R. &sect; 20.1402.
7.3      Area 3 7.3.1    Description of Area 3 Area 3 is located at the confluence of Buttermilk and Cattaraugus Creeks (pg. 8, Figure 3), and also consisted of two sub-areas designated 3.1 and 3.2. Both areas are located on an active farm . Sub-Area 3.1 is a large, slightly sloped area, the majority of wh ich is currently utilized to grow corn for livestock consumption . Sub-Area 3.2 is a smaller area located just n.orth of Thomas Corners Road . This area sloped upward from the roadway towards the farm dwelling, and was transected by a gravel driveway.
7.3.2    Survey and Sampling Methodology for Area 3 GPS Walkover Gamma Surveys of Area 3 GPS walkover gamma surveys were conducted in both sub-areas using a nominal grid spacing of 20 meters or less . Some portions of Sub-Area 3.1 were heavily wooded and overgrown . As a result, it was not possible to completely survey the designated survey box. However, the cultivated areas within the designated survey area and immediately adjacent areas were surveyed. Some sections of Sub-Area 3.2 were obstructed by trees, shrubs, and a debris pile, and therefore the path walked by the survey team cou Id not traverse these obstructed areas.
In Sub-Area 3.1, a pattern of elevated readings was identified by the GPS walkover gamma data {Figure
: 29) immediately to the southwest and down slope of the sub-area. As a result, samples were collected from seven elevated locations, and random locations were used for 17 other locations.
In Sub-Area 3.2, no elevated locations were identified by the GPS walkover gamma data (Figure 30) . As a result, samples were collected from four random locations . One planned sample location was relocated slightly west to avoid an existing driveway on the property.
Direct radiation readings and soil samples were collected in the 24 locations in Sub-Area 3.1 and from fo ur locations in Sub-Area 3.2 as described in Table 4 of the Plan (Ref. 4) .
Each location was surveyed and sampled as follows :
* Dose rate readings were collected at one and 100 cm from the ground surface using the tissue equivalent dose rate meter.
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas
* Static 2" x 2" Nal detector readings were collected at one and 100 cm from the ground surface using the Ludlum Model 2241-2 survey meter coupled to a Ludlum Model 44-10 detector. Two, one-minute counts were collected at each location at both elevations.
* Soil samples were collected in depth increments of 0-15 cm, 15-30 cm, 30-60 cm and 60-100 cm .
* In Area 3.1 a total of 24 locations were sampled, 17 random and seven elevated.
* In Area 3.2 a total of four locations were sampled.
Figures 27 and 28 show the sampling locations of Area 3.1 and 3.2, respect ively.
Figure 27.      Sub-Area Sampling Locations Page 56 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 28.      Sub-Area 3.2 Sampling Locations 7.3.3  Survey and Sampling Results for Area 3 GPS Survey Results Figures 29 and 30 provide the graphical display of the GPS survey data for Sub-Areas 3.1 and 3.2.
Figure 29.      Static 2" x 2" Detector Grid Readings for Sub-Area 2.2 Page 57 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 30.      Sub-Area 3.2 GPS Survey Results
* 9730.9330 0  8331 .8930 0  8931 *9430 0  9431
* 10030 Static 2"x2" Nal Detector Gross Readings at the 100 cm Elevation
* The Area 3.1 static readings us ing the 2" x2" Nal detector were averaged between two counts at each location and ranged from 8360 CPM to 10980 CPM . The average across all locations was 9939 CPM.
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas
* The Area 3.2 static readings using the 2" x2" Na! detector were averaged between two counts at each location and ranged from 7074 CPM to 7760 CPM . The average across all locations was 7760 CPM .
* The applicable background count rate for Area 3 was determined to be 6333 CPM A tabulation of the static count rates is provided in Appendix H32.
Tissue Equivalent Dose Rate Survey Meter Readings Tissue equivalent survey meter readings were collected at 24 locations in Area 3.1 and at 4 locations in Area 3.2.
The average of the readings in Area 3.1 was 7.55 +/- 0.16 &#xb5;rem/hour at 100 cm(+/- 1 sigma) . This reading exceeded the background screening level.
The average of the readings in Area 3.2 was 4.11+/-0.21 &#xb5;rem/hour at 100 cm(+/- 1 sigma) . This reading also exceeded the background screening level.
A tabulation of the individual readings in Area 3 is provided in Appendix Hl.
Soil Sampling Results for Area 3 Sub-Area 3.1 Fifty-three soil samples were analyzed in Sub-Area 3.1. The average soil concentrations for gross alpha, gross beta and cesium results associated with each stratum depth sampled are summarized in Table 35 .
Table 35.          Sub-Area 3.1 Average Soil Concentrations Depth          Gross Alpha            Gross Beta              Cesium-137 (cm)            (pCi/g)                (pCi/g)                  (pCi/g) 0-15      1.3E+Ol +/- 2.9E-01      2.2E+Ol +/- 2.5E-01      1.lE+OO +/- 1.3E-02 15-30    1.4E+Ol +/- 3.5E-01      2.4E+Ol +/- 2.8E-01      1.4E+OO +/- 1.5E-02 30-60      l .6E+Ol +/- 1.lE+OO      2.3E+Ol +/- 7.7E-01      2.2E+OO +/- 8.7E-02 60-100      1.4E+Ol +/- 5.3E-01      2.3E+Ol +/- 4.5E-01      2.5E-01 +/- 2.lE-02
*Uncertainty is reported as+/- 1 sigma .
The gross alpha, gross beta and cesium soil concentrations were above background levels . The net soil concentrations were used to assess potential exposure to a resident farmer. The calculated weighted net average soil concentrations used in the dose assessment are provided in Table 36.
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 36.          Sub-Area 3.1 Net Average Soil Concentrations Depth          Gross Alpha            Gross Beta              Cesium-137
{cm)            (pCi/g)                {pCi/g)                  (pCi/g) 0-100            1.lE+OO                5.6E-01                  1.0E+OO The individual sample numbers, depths, concentrations, uncertainties, and MDLs are provided in Appendix H2.
Sub-Area 3.2 Six soil samples were analyzed in Sub-Area 3.2. The average so il concentrations for gross alpha, gross beta, and cesium results associated with each stratum depth sampled are summarized in Table 37 .
Table 37.          Sub-Area 3.2 Average Soil Concentrations Depth          Gross Alpha            Gross Beta              Cesium-137 (cm)            (pCi/g)                (pCi/g)                  {pCi/g) 0-15      1.3E+Ol +/- 9.9E-01      1.9E+Ol +/- 8.2E-01        5.5E-01 +/- 2.4E-02 15-30 **    1.2E+Ol +/- 1.4E+OO      1.9E+Ol +/- l.2E+OO        3.4E-01 +/- 3.3E-02 30-60      l.2E+Ol +/- l.8E+OO      l.9E+Ol +/- l .6E+OO        l.3E-01+/-4.2E-02 60-100      7.8E+OO +/- 1.6E+OO      2.2E+Ol +/- l.6E+OO        8.lE-02 +/- 2.6E-02
* Uncertainty is reported as+/- 1 sigma .
** No samples were analyzed at th is depth, the average of 0-15 and 30-60 were calculated and used for this depth.
The gross beta soil concentration was less than background levels. The gross alpha and cesium soil concentrations were above background levels. The net soil concentrations were used to assess potential exposure to a resident farmer. The calculated weighted net average soil concentrations used in the dose assessment are provided in Table 38.
Table 38.          Sub-Area 3.2 Net Soil Concentrations Depth          Gross Alpha            Gross Beta              Cesium-137 (cm)            (pCi/g)                (pCi/g)                  (pCi/g) 0-100            1.9E-01                O.OE-00                  l.lE-01 The individual sample numbers, depths, concentrat ions, uncertainties, and MDLs are provided in Appendix H2.
7.3.4    Dose Assessment Approach for Area 3 The dose assessment approach for Area 3 was to :
* Develop an estimate of annual exposure based on the Aerial Survey data .
* Develop an estimate of annual exposure based upon the t issue equivalent dose rate survey meter readings .
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas
* Perform an assessment based on the current land use Resident Farmer scenario to determine the exposure in excess of backgroun.d using current and appropriate parameters (e.g., hydrology, occupancy and consumption). Parameters were adjusted based on published references for the region or historical site specific data . Calculations were performed using the weighted mean above background for the data analyzed.
Dose assessments associated with soil data were performed using the RESRAD-OFFSITE 3.1 computer code. Hydrology data for the contaminated, unsaturated, and saturated zones were based on Revision 2 of the Phase 1 Decommissioning Plan for the WVDP. The RESRAD input parameters used that differed from the RESRAD defaults are summarized in .Appendix H3. In cases where area specific scenarios were not consistent with assumptions used in the Decommissioning Plan, modifications are described below and in Appendix HS . This would include, but are not limited to, exposure pathways, irrigation, consumption, erosion rates, and occupancy times . For parameters where there were no site-specific data or there was no corresponding Decommissioning Plan value, the RESRAD-OFFSITE default parameters were used .
The Area 3 dose assessment was based on a resident farmer that spends 1000 hours per year tending feed crops in Sub-Area 3.1and1000 hours per year tending livestock. It is assumed that this resident farmer consumes the cattle meat. No plant, milk, or fish is consumed from this area . The resident farmer's dwelling is located off-site, but within the general area and therefore is included in this assessment. It is assumed that 100 hours was spent traversing Sub-Area 3.2.
In addition, irrigation was only assumed for crop fields in Area 3. The evapotranspiration coefficient provided in the Decommissioning Plan was recalculated to maintain the same infiltration rate of 0.26 meters per year.
* The sample results were compared to the DCGLw concentrations established in the Phase 1 Decommissioning Plan for the WVDP. The peak-of-the-mean values are the most conservative DCGLw values provided in the Phase 1 WVDP Decommissioning Plan and are for a resident farmer scenario.
* Perform an assessment based on a conservative potential land use scenario of a Resident Farmer's
  . exposure to determine the exposure in excess of background using current and appropriate parameters (e.g., hydrology, occupancy and consumption) . Parameters were adjusted based on published references for the region or historical site specific data. Calculations were performed using the weighted mean above background for the data analyzed . Dose assessments associated with soil data were performed using the RESRAD 7.0 computer code. RESRAD input parameters were based on Revision 2 of the Phase 1 Decommissioning Plan for the West Valley Demonstration Project Appendix C. The RESRAD input parameters are summarized in Appendix H33 .
* Perform an assessment based on consumption offish caught from the Cattaraugus Creek. Current land use surveys indicate that in Areas 1, 2, and 3, no consumption of fish occurs. Calculations were performed using the average concentration of Sr-90 and Cs-137 in the edible portion of fish above background from the 2012 WVDP Annual Site Environmental Report. Annual exposures were calculated based on ingestion dose coefficients from ICRP 68.
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 7 .3.5    Dose Assessment Results for Area 3 Dose Based Upon 2014 Aerial Survey Data Figure 31 is an aerial radiological survey map extracted from the Aerial Survey data onto which the locations for Area 3 have been placed . The dose rates at an elevation of one meter as derived from the map were determined to be 5-6 (&#xb5;R/hour) for Area 3.1 and 5-6 (&#xb5;R/hour) for Areas 3.2. The Aerial Survey states that the contribution to dose from cosmic rays and airborne radon across the entire map is 4.8 &#xb5;R/hour.
Figure 31.            Area 3 Locations on the 2014 WNYNSC Aerial Radiological Survey Exposure Rate micro R per hour
                        -~
4-5 7 5-6 9
7*8 9-10                                                                . SUB-AREA 3.2
    -    10-20 200-430 Sampling Locabon Sampling Area vmYNSC Based on this aerial map and the assumed cosmic and airborne radon contribution, the dose rates were determined for Area 3 as shown in Table 39. Consistent with the methodologies of the Aerial Survey, a value of 4.8 was added to all readings derived from Figure 31 to account for the contribution to background from cosmic radiation and airborne radon .
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 39.          Area 3 Dose Rates Based Upon 2014 Aerial Survey Data Dose Rate Range          Average Dose            Cosmic + Radon Total Dose Rate Location                from Map                  Rate                Dose Rate
(&#xb5;R/hour)
(&#xb5;R/hour)              (&#xb5;R/hour)                (&#xb5;R/hour)
Sub-Area 3.1                  5-6                    5.5                      4.8                    10.3 Sub-Area 3.2                  5-6                    5.5                      4.8                    10.3 The average background dose rate based on the WNYNSC Aerial Survey was 8.3 &#xb5;R/hour at one meter above the ground . This was subtracted from the total doses rate in Table 39, and based on occupancy time of 1000 hours per year in Area 3.1and100 hours per year in Area 3.2, the calculated doses for Area 3 are provided in Table 40.
Table 40.          Area 3 Calculated Doses Based on 2014 WNYNSC Aerial Radiological Survey Annual Total              Background                                          Annual Occupancy location                Dose Rate              Dose Rate                                        Dose Rate*
Time
(&#xb5;R/hour)              (&#xb5;R/hour)                                        (mrem/year)
(hours/year)
Sub-Area 3.1                  10.3                    8.3                      1000                    1.8 Sub-Area 3.2                  10.3                    8.3                      100                    0.2
* The aerial survey dose rates were recorded in units of Ro entgen. Th e quality factors fo r photons and electron s are both one, therefore 1 R equal s 0.877 rem.
Dose Assessment Based Upon Tissue Equivalent Survey Meter Readings Sub-Area 3.1 Dose rate readings in Sub-Area 3.1 demonstrated external dose rates higher than the background screening level. The average dose rate for Sub-Area 3.1 was 7.55 +/- 0.16 &#xb5;rem/hour at 100 cm(+/- 1 sigma) . The dose rate net of background in Sub-Area 3.1was3.86 &#xb5;rem/hour at 100 cm . Based on the annual occupancy derived from the Resident Farmer scenario of.1000 hours per year in Area 3.1, the net dose to the farmer based upon the tissue equivalent survey meter readings is 3.9 mrem per year.
Sub-Area 3.2 Readings in Sub-Area 3.2 demonstrated dose rates lower than the background screening level and therefore the assessed dose for Sub-Area 3.2 based on tissue equivalent tissue equivalent survey meter readings is 0.0 mrem per year.
Current Use RESRAD Dose Assessment Based Upon Soil Concentrations Assuming a Resident Farmer Scenario RESRAD dose assessments were based on a resident farmer that spends 11.42 percent (1000 hours per year) working in the elevated area where feed grain is grown . The resident farmer also spends 11.42 percent (1000 hours per year) maintaining their livestock in a pasture just north of the dwelling. Sixty-six Page 63 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas percent of the year is assumed to be spent inside the dwelling and the remaining time (11.16 percent) outdoors, but not associated with farming or maintaining their livestock. No edible vegetation is grown for human consumption . Cattle are assumed to graze in the pasture and are assumed to consume grain grown in the elevated area. The number of livestock consumed is assumed to be 10. No livestock are directly located within the elevated area . The dwelling is assumed to house four individuals. The consumption of milk or fish is not considered for this area .
Irrigation was only assumed for feed grain crop field . For all other areas, the evapotranspiration coefficient was recalculated to maintain the same infiltration rate in the Decommissioning Plan of 0.26 meters per yea r. All water used is assumed to be pumped from a well. The total well pump rate was calculated 32,100 cubic meters per year based on the water usage for irrigation, livestock, dwelling, and human consumption.
Sub-Area 3.1 Sub-Area 3.1 is a 64,500-square-meter crop field, located about 300 meters west of the dwelling. For purposes of the analysis, the size was increased to include the entire field . Feed gra in is grown as a crop in this field . See Figure 32 below.
Figure 32.          Sub-Areas 3.1 and 3.2 Page 64 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas The exposure to a resident farmer in Sub-Area 3.1 that also consumed cattle meat is provided in Table
: 41. The RESRAD input parameters are provided in Appendix HS.
Table 41.          Sub-Area 3.1 Pathway Doses Ground                  Inhalation                    Meat                      Soil                  Total (mrem/year)              (mrem/year)                (mrem/year)              (mrem/year)            (mrem/year)
                                                                          --!~--'-~--'--'---''------+-----''----~---'--''-------'-~
3.87E-01                  4.23E-OS                  4.31E -01                4.81E-ll                8.18E-01
* The gross alpha was assesse d as Am-241, as th is provi ded th e more conservat ive dose estimate.
The main sources of exposure were direct external from the ground and consumption of cattle meat.
These accounted for over 47 and S2 percent, respectively, of the overall exposure. Th e full RESRAD output files are provided in Appendix H12 and H13 .
Sub-Area 3.2 Sub-Area 3.2 is a 1,000-squ are-meter section of overgrowth (F igure 32 above ) located about lS meters west of the dwelling. No crop or livestoc k are located in th is area .
The exposure to a resident farmer in Sub-Area 3.2 that also consumed cattle meat is provided in Table 42 . The RESRAD input parameters are provided in Appendix HS.
Table 42          Sub-Area 3.2 Pathway Doses Ground                  Inhalation                  Meat                      Soil                    Total (mrem/year)              (mrem/year)                (mrem/year)            (mrem/year)            (mrem/year) 4.08E-03                  2.07E-OS                  9.21E-ll                l.4SE-04                4.2SE -03
* The gross alpha wa s assesse d as Am-241, as th is provi ded the more conservative dose estimate .
The main source of exposure is direct external from the.ground. This accounted for over 96% of the overall exposure. The full RESRAD output files are provided in Appendix H14 and HlS .
Comparison to the WVDP Phase 1 Decommissioning Plan DCGLw Values for Area 3 Table 43 provides a comparison of the Area 3 soil concentrations to the WVDP Phase 1 Decommissioning Plan DCGLw Values .
Table 43.          Area 3 Comparison to WVDP Phase 1 Decommissioning Plan DCGLw WVDP              Net Soil Concentration Measurement          Nuclide                                                                      Comparison DCGL                      (pCi/g)
Type              Used (pCi/g)              3.1                3.2          Sub-Area 3.1        Sub-Area 3.2 Alpha            Pu-239      2.SOE+Ol            l.lE+OO            l.9E-01              Below                Below Beta              Sr-90      4.lOE+OO            S.6E -01          O.OE+OO              Below                Below Cesium            Cs -137      l.SOE+Ol            l.OE+OO            l.lE-01              Below                Below Sum of the Fractions :          Below                Below Page 65 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas The assessment of the gross alpha and beta based on the most conservative isotopes (Pu -239 and Sr-90, respectively) will account for all of the anthropogenic nu elides listed in Table 2 except C-14, 1-129, and Tc-99. For these radionuclides, a qualitative analysis was performed. In all cases for these three radionuclides, either the soil concentration was below the detection lim it or the soil concentration detected was significantly less than the Phase 1 Decommissioning Plan DCGLw Values . In addition, an analysis of the isotopic data indicates that the radionuclides that account for most of the gross alpha and beta soil concentrations are radionuclides that are considered NORM (e.g., natural uranium, natural thorium, and potass fum -40.
These DCGLs are based on a resident farmer scenario used in th e WVDP Phase 1 Decommission ing Plan, which is different than the current land use resident farmer described above. One of the key differences is that RESRAD (onsite) was used to do the calculat ions versus RESRAD -OFFSITE . This resulted in all farming activities to be assumed to occur in the contamination zone. In addition, the resident farmer scenario used in the WVDP Phase 1 Decommissioning Plan assumes the consumption of plant vegetation grown by the farmer. These two items account for most of the difference in the estimated doses.
Therefore, the resident farmer scenario used in the WVDP Phase 1 Decommissioning Plan is a conservative comparison .
Conservative Potential Use Dose Assessment Based Upon Soil Concentrations Assuming a Resident Farmer Scenario Sub-Area 3.1 Sub-Area 3.1 is a 64,500-square-meter crop field, located about 300 meters west of the dwelling. This assessment is based on a resident farmer scenario. It is assumed that the farmer' s dwelling, crop fields, and pasture lands resides in the elevated area . In addition, the crop that is grown is consumed by the farmer. The farmer also maintains and consumes both dairy and meat from the cattle. The annual exposure for Sub-Area 3.1 is provided in Table 44. The RESRA.D input parameters are provided in Appendix H33 .
Table 44.        Sub-Area 3.1 Potential Use Pathway Doses Ground
* Inhalation          Plant            Meat            Milk            Soil            Total (mrem/year)      (mrem/year)      (mrem/year)    (mrem/year) 1--'-~~-'-'-~-'-f--'-~~-'-'-~-'-1--'-~~-'--'-~-'---1--'-~~
(mrem/year)      (mrem/year)      (mrem/year) l.45E+OO          l.07E-02        4.14E+OO        5.42E-01        l.06E+OO        6.83E-02        7.27E+OO The full RESRAD output file is provided in Appendix H37 and H38.
Sub-Area 3.2 Sub-Area 3.2 is a 1,000-square-meter section of overgrowth located about 15 meters west of the dwelling. This assessment is based on a resident farmer scenario. It is assumed that the farmer' s dwelling, crop fields, and pasture lands resides in the elevated area . In addition, the crop that is grown is consumed by the farmer. The farmer also maintains and consumes both dairy and meat from the cattle.
The annual exposure for Sub-Area 3.2 is provided in Table 45. The RESRAD input parameters are provided in Appendix H33 .
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 45.          Sub-Area 3.2 Potential Use Pathway Doses Ground          Inhalation          Plant              Meat            Milk        Soil            Total (mrem/year)        (mrem/year)    (mrem/year)        (mrem/year)      (mrem/year)  (mrem/year)      (mrem/year) l.46E-01          l.21E-03        l.21E-01            l.82E-02        3.16E-02    l.lSE-02          3.29E -01 The full RESRAD output file is provided in Appendi x H39 and H40.
Dose Assessment for Consumption of Fish Based Upon 2012 WVDP Annual Site Environmental Report The ASER (Ref. 8) provides radiological concentrat ions of strontium and cesium in the ed ible portion of the fish in Cattaraugus Creek. Biological data from their locations are provided . Hog-nosed Sucker and White Sucker are sampled from above the Springville Dam and Steelhead Trout are sampled from below the Springville Dam . Brown Trout, White Sucker, Bullhead, and Hog-nosed Sucker were also sampled at a background location . This data is provided in Appendix H41. The average radiological concentrations of strontium and cesium in the edible portion of the fish for the two areas around Springville Dam and the background area are provided in Tables 46 and 47 below.
Table 46.          Concentrations in Edible Portions of Fish around Springville Dam Isotope            Average              1 Sigma                Units Sr-90            l.40E-08            l.16E-09            &#xb5;Ci/g - wet Cs-137            5.46E-08            1.31E-08              &#xb5;Ci/g - wet Table 47.          Background Concentrations in Edible Portions of Fish Isotope            Average              1 Sigma                Units Sr-90            l.02E-08            l.77E-09              &#xb5;Ci/g - wet Cs-137            4.75E-08            4.00E-08              &#xb5;Ci/g - wet This results in a net above background concentration in the edible portions of the fish of 3.74E-09 &#xb5;Ci Sr-90 per gram offish flesh and 7.08E-09 &#xb5;Ci Cs-137 per gram offish flesh . The ingestion dose coefficients factors (DCF) and the. fraction of an ingested element directly absorbed to body fluids (fl) from ICRP 68 are provided in Table 48.
Table 48.          Ingestion dose coefficients (mrem/&#xb5;Ci) from ICRP 68 Isotope              fl*              DCF                    Units Sr-90              0.3          l.04E+02            mrem/&#xb5;Ci Ingestion Sr-90              0.01          l.OOE+Ol            mrem/&#xb5;Ci Ingestion Cs-137                1          4. 81E+Ol            mrem/&#xb5;Ci Ingestion
* fl - Fractional absorption in the Gastrointestinal tract rate .
The Exposure Factors Handbook (Ref. 18) ind icates that the 95th percentile of fi sh consumpt ion by recreational anglers is about nine kg of fish per year. This results in an annual exposure rate of less than 0.1 mrem per year.
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 7 .3.6  Conclusions for Area 3 Annual doses based on the Aerial Survey, tissue equivalent survey meter readings, and RESRAD analysis ranged from 0 to 7.2 mrem per year. Soil concentrations were all below the DCGL values . This demonstrates that Area 3 is well below the NRC regulatory release requirement of less than 25 mrem per year in accordance with 10 C.F.R. &sect; 20.1402.
7.4      Area 4 7.4.1    Description of Area 4 Area 4 lies approximately 20 miles to the west of the WNYNSC on the SNI and spans Cattaraugus Creek (Figure 4) . It includes five sub-areas designated 4.1, 4.2, 4.3, 4.4, and 4.5. As can be seen in Figures 33 and 34, multiple irregularly shaped sub regions, derived from the Aerial Survey, were combined into five sub-areas as follows :
* Sub-Area 4.1-four sub regions designated 4.lA, 4.lB, 4.lC, and 4.lD
* Sub-Area 4.2 - three sub regions designated 4.2A, 4.2B, and 4.2C
* Sub-Area 4.3-two sub region designated 4.3A and 4.3B
* Sub-Area 4.4 - four sub regions designated 4.4A, 4.4B, 4.4C, and 4.4D
* Sub-Area 4.5 - three sub regions designated 4.5A. 4.5B, and 4.5C Area 4 is a wooded area with varying terrain that lies within the historic floodplain . There are no residences located in the Area. For Area 4, which is located on the SNI, culturally specific aspects of land use are being developed. This report will be revised to include the modeled dose assessments for Areas 4 and 5 once the culturally specific aspects of land use are finalized .
7.4.2    Survey and Sampling Methodology for Area 4 GPS Walkover Gamma Surveys of Area 4 GPS walkover gamma surveys were conducted in all sub-areas using a nominal grid spacing of 30 meters (see Figures 35-39) . The areas were generally heavily wooded and GPS precision varied; however, sufficient data was collected and analyzed to determine if any elevated locations would be sampled or if all samples would be from random sampling locations. There were no elevated areas identified.
Static Survey and Sample Collection in Area 4 Direct radiation readings and soil samples were collected in each sub-region as follows :
Sub-Area 4.1
* Sub Region 4.lA - one location
* Sub Region 4.lB - eight locations
* Sub Region 4.lC- nine locations Page 68 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas
* Sub Region 4.10 - six locations Sub-Area 4.2
* Sub Region 4.2A- four locations
* Sub Region 4.2B - eighteen locations
* Sub Region 4.2C - two locations Sub -Area 4.3
* Sub Region 4.3A - four locations
* Sub Region 4.3B - twenty locations Sub-Area 4.4
* Sub Region 4.4A - one location
* Sub Region 4.4B - one location
* Sub Region 4.4C - seven locations
* Sub Region 4.40 - six locations Sub-Area 4.5
* Sub Region 4.SA - seven locations
* Sub Region 4.SB - eight Locations
* Sub Region 4.SC - nine locations Page 69 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 33 shows the sampling locations in Sub-Areas 4.1, 4.2, and 4.3, and Figure 34 shows the sampling locations in Sub-Areas 4.4 and 4.5.
Figure 33.      Sampling Locations in Sub-Areas 4.1, 4.2, and 4.3 Figure 34.      Sampling Locations in Sub-Areas 4.4 and 4.5 Page 70 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Each location was surveyed and sampled as follows :
* Dose rate readings were collected at one and 100 cm from the ground surface using the tissue equivalent dose rate meter.
* Static 2" x 2" Nal detector readings were collected at one and 100 cm from the ground surface using the Ludlum Model 2241-2 survey meter coupled to a Ludlum Model 44-10 detector. Two, one-minute counts were collected at each location at both elevations .
* Soil samples were collected in depth increments of 0-15 cm, 15-30 cm, 30-60 cm, and 60-100 cm .
7.4 .3    Survey and Sampling Results for Area 4 GPS Survey Results Figures 35 through 39 provide the GPS walkover gamma survey results for Area 4 . No pattern of elevated locations was discerned in the GPS maps and therefore only random samples were collected .
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Rad iolog ical Survey and Dose Assessment Report fo r the WNYNSC and Off-Site Areas Figure 35.      Sub-Area 4.1 GPS Walkover Gamma Survey Data Area *4 .1 - Walkover Survey Data
* 3000-8830 0  8831-9730 0  9731
* 10430 0  10431
* 11230
* 11231
* 13330 Page 72 of 102
Rad iological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 36.        Sub-Area 4.2 GPS Walkover Gamma Survey Data Area 4 .2 - Wa'I over Survey Data
* 8730*8330 0  8331-9130 0  9131 9830 0  9831
* 10530 Page 73 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 37.      Sub-Area 4.3 GPS Walkover Gamma Survey Data Area 4.3 - Wal over Survey Data a_ _3_      llkOY CPM
* 6630-8430 0  8431- 9130 0  9131- 9730 0  9731
* 10430
* 10431
* 12230 Page 74 of 102
Radiological Survey and Dose Assessm ent Report for the WNYNSC and Off-Site Areas Figure 38.      Sub-Area 4.4 GPS Walkover Gamma Survey Data Area 4 .4 - Wal over Survey Data CP
* 5630- 7343 0    7344-8330 c    8331 -9030 0    9031-9730
* 0731 -11430 Page 75 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 39.      Sub-Area 4.5 GPS Walkover Gamma Survey Data Area 4.5 - Wa lkover Survey Data c
* 5830-81:53 0  8154*8830 0  8831-9430 0  9431 -10230 Page 76 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Static 2"x2" Nal Detector Gross Readings at the 100 cm Elevation
* The Area 4.1 static readings using the 2" x2" Nal detector were averaged between two counts at each location and ranged from 7871 CPM to 10299 CPM . The average across all locations was 9030 CPM.
* The Area 4.2 static readings using the 2" x2" Nal detector were averaged between two counts at each location and ranged from 7723 CPM to 10383 CPM . The average across all locations wa s 8704 CPiy1 .
* The Area 4. 3 st atic readings using the 2" x2" Nal detector were averaged between two cou nt s at each location and ranged from 7225 CPM to 9804 CPM . The average across all location s was 7966 CPM .
* The Area 4.4 static readings using the 2" x2" Nal detector were ave raged between two counts at each location and ranged from 7130 CPM to 9210 CPM . The average across all locations was 7799 CPM .
* The Area 4.5 static readings using the 2" x2" Nal detector were averaged between two counts at each _location and ranged from 7263 CPM to 9367 CPM . The average across all locations was 8205 CPM.
* The applicable background count rate for Area 4 was determined to be 7943 CPM.
A tabulation of the static count rates is provided in Append ix H32.
Tissue Equivalent Dose Rate Survey Meter Readings The tissue equivalent survey meter readings for Area 4 are provided in Appendix Hl.
The average dose rates for each sub-area are provided below (Table 49) .
Table 49.            Area 4 Average Dose Rates Dose Rate*
Area                        at 100 cm
(&#xb5;rem/hour)
Sub-Area 4.1                      5.6 +/- 0.1 Sub-Area 4.2                      4.9 +/- 0.1 Sub-Area 4.3                      4.4 +/- 0.1 Sub-Area 4.4                      4.5 +/- 0.1 Sub-Area 4.5                      4.5 +/- 0.1
* Uncerta inty is re ported as+/- 1 sigma .
In Sub-Area 4. 1 th e dose rate at th e 100 cm elevat ion exceed ed t he backgrou nd screening level. In all other sub-areas, the dose rate at 100 cm was less than the background screening level.
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Soil Concentration Data For Area 4, which is located on the SNI, culturally specific aspects of land* use surveys are being developed . Soil concentration data calculations will be provided in the revised version of this report .
7 .4.4    Dose Assessment Approach for Area 4 The dose assessment approach for Area 4 will be to :
* Develop an estimate of annual exposure based on the Aerial Survey data .
* Develop an estimate of annual exposure based upon the tissue equivalent dose rate survey meter readings .
* For Area 4, which is located on the SNI, culturally specific aspects of land use are being developed.
This report will be revised to include the modeled dose assessments for Areas 4 and 5 once the culturally specific aspects of land use are finalized .
7 .4.5    Dose Assessment Results for Area 4 Dose Dose Assessment Based on Aerial Survey Data for Area 4 Figure 40 is an aerial radiological survey map extracted from the Aerial Survey data onto which the location of Area 4 has been placed . The dose rates at an elevation of one meter as derived from the map were determined to be 5-6 (&#xb5;R/hour) for Sub-Area 4.1 and 3-4 (&#xb5;R/hour) for all other sub-areas. The Aerial Survey states that the contribution to dose from cosmic rays and airborne radon across the entire map is 4.8 (&#xb5;R/hour) .
Figure 40.            Area 4 Locations on the 2014 WNYNSC Aerial Radiological Survey Exposure Rate micro R per hour SUB-AREA 4.1      SUB-AREA 4.3 4-5
            ~
                        "'"'ci
      - 7.a 6-7 6-9                                                          SUB-AREA 4.4.
      -    9-10 SUB-AREA 4.6*
      -    10-20
      -    20-100 100-200 200430
* Sampl111g Location Page 78 of 102
Radi ological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Based on this aerial map and the assumed cosmic and airborne radon contribution, the dose rates were determined for Area 4 as shown in Table 50. Consistent with the methodologies of the Aerial Survey, a value of 4.8 wa s added to all readings to account for the contribution to background from cosmic radiation and airborne radon .
Table 50.          Area 4 Dose Rates Based Upon 2014 Aerial Survey Data Dose Rate                                  Cosmic+
Average Dose Range from                                Radon Dose      Total Dose Rate Locatio n                                        Rate Map                                      Rate            (&#xb5;R/hour)
(&#xb5;R/hour)
(&#xb5;R/hour)                                (&#xb5;R/hour)
Sub-Area 4.1                  5-6                  5.5                4.8                10.3 Sub-Area 4.2                  3-4                  3.5                4.8                8.3 Sub-Area 4.3                  3-4                  3.5                4.8                8.3 Sub-Area 4.4                  3-4                  3.5                4.8                8.3 Sub-Area 4.5                  3-4                  3.5                4.8                8.3 The average SNI Floodplain background dose rate based on the WNYNSC Aerial Survey was 8.9 &#xb5;R/hour at one meter above the ground . This was subtracted from the total dose rate in Table 50, and the calculated dos es for Area 4 are provided in Table 51. The occupancy time is being updated by culturally specific aspect s of land use . This report will be revised to add the modeled dose assessments for Areas 4 and 5 once the culturally specific aspects of land use are finalized .
Table 51.          Area 4 Calculated Doses Based on 2014 WNYNSC Aerial Radiological Survey Total              Background                Annual Locati on                Dose Rate              Dose Rate              Dose Rate*
(&#xb5;R/hour)              (&#xb5;R/hour)            (mrem/year)
Sub-Area 4 .1                    10.3                    8.9                TBD**
Sub-Area 4.2                      8.3                    8.9                  0.0 Sub-Area 4.3                      8.3                    8.9                  0.0 Sub-Area 4.4                      8.3                    8.9                  0.0 Sub-Area 4.5                      8.3                    8.9                  0.0
* The aerials urvey dose rates were recorded in units of Roentgen . The quality factors for photons and electrons ar e both one, therefore 1 R equals 0.877 rem .
** The report wi ll be revised to include the modeled dose assessm ents for Areas 4 and 5 once the culturally sp ecific aspects of the land use surveys are finalized .
Dose Assessm ent Based Upon Tissue Equivalent Survey Meter Readings for Area 4 For Sub-Area 4 .1, the average dose rate slightly exceeded the background screening level. The occupancy tim e will be based on culturally specific aspects of land use. Therefore, these dose rates included in this version of the report will be revised once the culturally specific land use are final ize d.
For Area 4.2-4.5, the tissue equivalent survey meter readings were all below background dose rates .
Page 79 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 7 .4.6  Conclusions for Area 4 Annual doses based on the Aerial Survey and tissue equivalent survey meter readings for Area 4, which is located on the SNI, will be calculated based on culturally specific aspects of land use surveys. This version of the report will be revised to add the modeled dose assessments for Areas 4 and 5 once the culturally specific aspects of land use surveys are finalized .
7.5      Area 5 7 .5.1  Description of Area 5 Area 5 lies approximately 17 miles to the west of the WNYNSC, and 0.6 miles East of Cattaraugus Creek (pg. 10, Figure 5) . It includes six sub-areas designated 5.1, 5.2, 5.3, 5.4, 5.5, and 5.6. Each sub-area was defined by a polygon as can be seen in Figures 41, 42, and 43 . Also seen in these figures, within each sub-area polygon, one or two irregularly shaped sub-regions were defined as derived from the Aerial Survey as follows :
* Sub-Area 5.1- two sub regions designated 5.lA, and 5.lB.
* Sub-Area 5.2 - two sub regions designated 5.2A, and 5.2B
* Sub-Area 5.3 - one sub region designated 5.3A
* Sub-Area 5.4 - one sub region designated 5.4A
* Sub -Area 5.5 - one sub region designated 5.5A
* Sub-Area 5.6 - one sub region designated 5.6A Area 5 is a relatively undisturbed old growth wooded area with varying terrain that lies outside the floodplain. There are no residences located in Area 5. For Area 5, which is located on the SNI, culturally specific aspects of land use are being developed . This version of the report will be revised to add the modeled dose assessments for Areas 4 and 5 once the culturally specific aspects of land use are finalized.
7.5.2    Survey and Sampling Methodology for Area 5 GPS walkover surveys of Area 5 GPS walkover surveys were conducted in all sub-areas using a nominal grid spacing of 30 meters . The areas were generally heavily wooded and GPS precision varied, however sufficient data was collected and analyzed to determine if any random sampling locations needed to be redirected to elevated areas.
No elevated areas were identified in Area 5.
Static Survey and Sample Collection in Area 5 Direct radiation readings and soil samples were collected in each sub-region as follows :
Page 80 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Sub-Area 5.1
* Sub Region 5.lA - two locations
* Sub Region 5.lB -two locations Sub-Area 5.2
* Sub Region 5.2A - seven locations
* Sub Region 5.2B - eight locations Sub-Area 5.3
* Sub Region 5.3A- four locations Sub-Area 5.4
* Sub Region 5.4A- four locations Sub-Area 5.5
* Sub Region 5.5A - four locations Sub -Area 5.6
* Sub Region 5.6 A - four locations Figures 41to43 show the sampling locations in Area 5.1 Page 81of102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 41.      Sub-Area 5.1 Sampling Locations Page 82 of 102
Radiological Survey and D<:>se Assessment Report for the WNYNSC and Off-Site Areas Figure 42.      Sub-Areas 5.2, 5.3 and 5.4 Sampling Locations Page 83 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 43.      Sub-Areas 5.5 and 5.6 Sampling Locations Page 84 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Each location was surveyed and sampled as follows :
* Dose rate readings were collected at one and 100 cm from the ground surface using the tissue equivalent dose rate meter.
* Static 2" x 2" Nal detector readings were collected at one and 100 cm from the ground surface using the Ludlum Model 2241-2 survey meter coupled to a Ludlum Model 44-10 detector. Two, one-minute counts were collected at each location at both elevations .
* Soil samples were collected in depth increments of 0-15 cm, 15-30 cm, 30-60 cm and 60-100 cm .
7.5.3    Survey and Sampling Results for Area 5 GPS Survey Results Figures 44 to 49 present the graphical results of the GPS walkover surveys conducted in Area 5. No pattern of elevated locations was discerned in the GPS maps and therefore no elevated locations were sampled.
Page 8~ of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 44.      Sub-Area 5.1 GPS Walkover Survey Data Area 5.1 - Walkover Survey Data
* 5323-6583 D    6584-7163 0    7164- 760l 0    7804-8083
* ISOM-9513 Page 86 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 45.      Sub-Area 5.2 GPS Walkover Gamma Survey Data Area 5.2 - Wa1kover Survey Data
* 54t3-ean 0    8974-7493 0    7494-7983 0    7te4-8483
* 8484-10030 Page 87 of 102
I I
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 46.      Sub-Area 5.3 GPS Walkover Gamma Survey Data Area 5.3 - Wa lkover Survey Data
* 4953 71$3 o    11.u-nu 0    774*-82'3
* 82*H
* 8853
* 8854 10230 Page 88 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 47.      Sub-Area 5.4 GPS Walkover Gamma Survey Data Area 5.4 - Wa lkover Survey Data
* 5730 -6830 0    8931 -1"'30 0    1~1-7930
* 79'31 *8430
* 8431 *9830 Pa ge 89 of 102
Radi o logical Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 48.        Sub-Area 5.5 GPS Wa lkove r Gamma Survey Data Area 5.5 -*Walkover Survey Data fP
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 49.      Sub-Area 5.6 Walkover Gamma Survey Data Area 5.6 - Walkover Surv,ey Data D
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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Static 2"x2" Nal Detector Gross Readings at the 100 cm Elevation
* The Area 5.1 static readings using the 2"x2" Nal detector were averaged between two counts at each location and ranged from 6108 CPM to 6464 CPM . The average across all locations was 6295 CPM .
* The Area 5.2 static readings using the 2"x2" Nal detector were averaged between two counts at each location and ranged from 6348 CPM to 8984 CPM . The average across all locations was 7266 CPM .
* The Area 5.3 static readings using the 2" x2" Nal detector were averaged between two counts at each location and ranged from 6839 CPM to 8614 CPM . The average across all locations was 7499 CPM .
* The Area 5.4 static readings using the 2" x2" Nal detector were averaged between two counts at each location and ranged from 5878 CPM to 6126 CPM . The average across all locations was 5992 CPM .
* The Area 5.5 static readings using the 2" x2" Nal detector were averaged between two counts at each location and ranged from 5933 CPM to 7211 CPM . The average across all locations was 6288 CPM.
* The Area 5.6 static readings using the 2"x2" Nal detector were averaged between two counts at each location and ranged from 5724 CPM to 7525 CPM . The average across all locations was 6408 CPM .
* The applicable background count rate for Area 5 was determined to be 8745 CPM .
A tabulation of the static count rates is provided in Appendix H32.
Tissue Equivalent Dose Rate Survey Meter Readings The tissue equivalent survey meter readings for Area 5 are provided in Appendix Hl.
The average dose rates for each sub-area are provided in Table 52 .
Table 52          Area 5 Average Dose Rates Dose Rate*at 100 cm Area
(&#xb5;rem/hour)
Sub-Area 5.1                        6.2 +/- 0.3 Sub-Area 5.2                        4.6 +/- 0.1 Sub-Area 5.3                        4.7 +/- 0.2 Sub-Area 5.4                        5.0 +/- 0.3 Sub-Area5.5                        5.5 +/-0.3 Sub-Area 5.6                        4.5 +/- 0.2
*Uncertainty is reported as+/- 1 sigma .
Page 92 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas In Sub-Areas 5.1- 5.6, the dose rate at the 100 cm elevation exceeded the background screening level.
Soil Concentration Data For Area 5, which is located on the SNI, culturally specific aspects of land use surveys are being developed . This report will be revised to add the modeled dose assessments for Areas 4 and 5 once the culturally specific aspects of land use surveys are finalized .
7.5.4      Dose Assessment Approach for Area 5 The dose assessment approach for Area 5 will be to :
* Develop an estimate of annual exposure based on the Aerial Survey data .
* Develop an estimate of annual exposure based upon the tissue equivalent dose rate survey meter readings .
* For Area 5, which is located on the SNI, culturally specific aspects of land use surveys are being developed . This report will be revised to add the modeled dose assessments for Areas 4 and 5 once the culturally specific aspects of land use surveys are finalized .
7.5.5      Dose Assessment Results for Area 5 Dose Assessment Based on Aerial Survey Data for Area 5 Figure 50 is an aerial radiological survey map extracted from the Aerial Survey onto which the location of Area 5 has been placed. The dose rates at an elevation of one meter as derived from the map were determined to be 3-4 &#xb5;R/hour for all sub-areas . The Aerial Survey states that the contribution to dose from cosmic rays and airborne radon across the entire map is 4.8 &#xb5;R/hour.
Figure 50.                  Area 5 Locations on the 2014 WNYNSC Aerial Radiological Survey Ex posure Rate mtero R per hour (g"j o.1 CJ o.2 CJ 2-3 CJ 34                              SUB-AREA 6.6.
                                                              . SUB-AREA 5.1
          &-6 e.7 SUB-AREA  6.5.
8
  -      8-9
  -      9-10                          SUB-AREA 5.4.
  -      10-20
  -      20-IOO
* sue-AREA s.:z
  -      IOIJ.200
  - 200-430
* S.ntpling LQCl!l>cn SUB-AREA  u*
Page 93 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Based on this aerial map and the assumed cosmic and airborne radon contribution, the dose rates were determined for Area 5 as shown in Table 53 . Consistent with the methodologies of the Aerial Survey, a value of 4.8 was added to all readings to account for the contribution to background from cosmic radiation and airborne radon .
Table 53          Area 5 Dose Rates Bas ed Upon 2014 Aerial Survey Data Dose Rate Range      Average Dose      Cosmic + Radon  Total Dose Location            from Map              Rate            Dose Rate        Rate
(&#xb5;R/hour)          (&#xb5;R/hour)          (&#xb5;R/hour)      (&#xb5;R/hour)
Sub-Area 5.1              3-4                3.5                4.8            8.3 Sub-Area 5.2              3-4                3.5                4.8            8.3 Sub-Area 5.3              3-4                3.5                4.8            8.3 Sub-Area 5.4              3-4                3.5                4.8            8.3 Sub-Area 5.5              3-4                3.5                4.8            8.3 Sub -Area 5.6            3-4                3.5                4.8            8.3 The average SNI Non-Floodplain background dose rate based on the WNYNSC Aerial Survey was 7.8
&#xb5;R/hour at one meter above the ground. This will be used in the calculation of dose rates, once the culturally specific aspects of the land use surveys are finalized .
Page 94 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 54            Area 5 Calculated Doses Based on 2014 WNYNSC Aerial Radiological Survey Total            Background                  Annual location                  Dose Rate            Dose Rate                Dose Rate*
(&#xb5;R/hour)            (&#xb5;R/hour)              (mrem/year)
Sub-Area 5.1                    8.3                  7.8                    TBD**
Sub-Area 5.2                    8.3                  7.8                    TBD **
Sub-Area 5.3                    8.3                  7.8                    TBD **
Sub-Area 5.4                    8.3                  7.8                    TBD **
Sub-Area 5.5                    8.3                  7.8                    TBD **
Sub-Area 5.6                    8.3                  7.8                    TBD **
* The aeria l survey dose rates were recorded in units of Roentgen . The qua lity factors for photons and electrons are both one, therefore 1 R equals 0.877 rem .
  ** The report will be revised to include the modeled dose assessments for Areas 4 and 5 once the culturally specific aspects of the land use surveys are finalized .
Dose Assessment Base Upon Tissue Equivalent Survey Meter Readings for Area 5 For Areas 5.1-5.6 the calculation of dose rates based on the tissue equivalent survey meter readings will be updated once the culturally specific aspects of land use surveys are finalized .
7.6      Confirmatory Locations located on the Western NY Nuclear Service Center Property 7.6.1    Description of Confirmatory Area Selected locations within the property boundary of the WNYNSC were surveyed and sampled . Four sample locations were selected designated Cl, C2, C3, and C4 (pg. 6, Figure 1).
7 .6.2    Survey and Sampling Methodology for Confirmatory Area No GPS survey was performed since the primary objective was to survey and sample predesignated locations.
Direct radiation readings and soil samples were collected in the four locations as described above and in Table 4 of the Plan.
Each location was surveyed and sampled as follows:
* Tissue equivalent dose rate readings were collected at 1 and 100 cm from the ground surface using the Bicron tissue equivalent survey meter.
* Static 2" x 2" Nal detector readings were collected at 1 and 100 cm elevations using the Ludlum Model 2241-2 survey meter coupled to a Ludlum Model 44-10 detector. Two consecutive counts were collected for each reading at each location and averaged .
* Soil samples were collected at depth intervals of 0 to 5, 5-15, 15-30, and 30-100 cm. A total of 13 samples were collected in accordance with Table 4 of the Plan . Samples were collected from the first Page 95 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas three depths at all locations and an additional sample was collected from the 30-100 cm at location C.2.
7.6.3    Survey and Sampling Results for Confirmatory Area As noted above, no GPS survey was required since the objective was to survey and sample at 4 predetermined locations. These areas were selected based on historical process knowledge (e .g.,
Cesium Prong, effluent liquid discharge) along with two locations that may be attributed to direct radiation shine from the WVDP .
Static 2"x2" Nal Detector Gross Readings at the 100 cm Elevation
* The WNYNSC Confirmatory Area static readings using the 2" x2" Nal detector were averaged between two counts at each location and ranged from 7812 CPM to 16586 CPM . The average across all locations was 11405 CPM .
* The applicable background count rate for WNYNSC Confirmatory Area was determined to be 6333 CPM .
These values are likely elevated in part due to the proximity of locations Cl and C2 to the WVDP.
A tabulation of the static count rates is provided in Appendix H32.
Tissue Equivalent Survey Meter Readings Table 55 provides the dose rates based upon the tissue equivalent meter readings including background for each sample location.
Table SS.          WNYNSC On-Center Confirmatory ~ocation Tissue Equivalent Dose Rate Readings Dose Rate at 100 cm Sample Location
(&#xb5;rem/hour)
C.1                                  10 C.2                                  10 C.3                                  6 C.4                                  8 Readings are inclusive of background rad iation Soil Sample Concentrations Four soil samples from the 0-5 cm depth and one sample from the 30-100 cm depth were analyzed by gamma spectroscopy, gross alpha, and gross beta activity. The data is summarized in Table 56.
Page 96 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 56.          WNYNSC On-Center Confirmatory Soil Concentrations Including Background Sample          Depth            Alpha*                      Beta*                        Cesium*
Location          (cm)              (pCi/g)                  (pCi/g)                        (pCi/g)
C.1            0-5        9.4E+OO +/- 3.2E+OO      2.9E+Ol +/- 2.82E+OO            l.2E+OO +/- 1.4E-01 C.2            0-5        8.lE+OO +/- 3.lE+OO      2.0E+Ol +/- 3.40E+OO            8.7E+OO +/- 2.4E-01 C.3            0-5        l.OE+Ol +/- 3.4E+OO      8.7E+OO +/- 2.27E+OO            9.4E-01 +/-2.lE-01 C.4            0-5        2.2E+Ol +/- 5.lE+OO      4.0E+Ol +/- 4.42E+OO            l.4E+OO +/- l.7E-01 C.2          30-100        l.3E+Ol +/- 3.9E+OO      4 .7E+Ol +/- 4 .09E+OO          3 .0E+Ol +/- 5.7E-01
* Uncertainty is reported+/- 1 sigma The individual sample numbers, depths, concentrations, uncertainties, and MDLs are provided in Appendix H2.
7.6.4    Estimation of Dose Rates Based Upon 2014 Aerial Survey Results Figure 51 is an image extracted from Figure 15 of the 2014 Aerial Survey onto which the locations of the Confirmatory locations have been marked .
Figure 51.          WNYNSC Confirmatory Locations on 2014 Aerial Survey Exposure Rate 3-4 4.5 m s..s C2                              7
* 9 7-11
                                                                                  \t-10 10-20
                                                                            -      20-100 C1
                            *                                              -      100-200 llllJl a3G-4:xl WNYlllSC Coolnna<O<y S11111ple Loc4li005 C3 Pa ge 97 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 57 presents the estimated dose rates based on the 2014 Aerial Survey inclusive of background .
Consistent with the methodologies of the Aerial Survey, a value of 4.8 was added to all readings to account for the contribution to background from cosmic radiation and airborne radon .
Table 57.        Dose Rates Based Upon 2014 Aerial Survey Results Dose Rate Range      Average Dose      Cosmic + Radon      Total Dose Location        from Map              Rate            Dose Rate            Rate
(&#xb5;R/hour)          (&#xb5;R/hour)          (&#xb5;R/hour)          (&#xb5;R/hour)
C.1              3-4                3.5                4.8                8.3 C.2              5-6                5.5                4.8              10.3 C.3              5-6                5.5                4.8              10.3 C.4              7-8                7.5                4.8              12.3 Because these confirmatory locations all reside within the NRC-licensed area of the WNYNSC, a dose assessment using current land use and comparison to the NRC regulatory requirement of less than 25 millirem per year per 10 C.F .R. &sect; 20.1402 was not conducted.
7 .6.5  Conclusions for Area 5 Annual doses based on the Aerial Survey and tissue equivalent survey meter readings for Area 5, which is located on the SNI, will be calculated based on culturally specific aspects of land use surveys. This version of the report will be revised to add the modeled dose assessments for Areas 4 and 5 once the culturally specific aspects of land use surveys are finalized .
8.0      Final Summary In summary, with the exception of Sub-Area 3.1, no elevated regions were discerned in the GPS survey data outside of the five areas identified in the 2014 WNYNSC Aerial Survey. For Sub-Area 3.1, an elevated region was identified immediately adjacent to the surveyed area . This area was surveyed, sampled, and included in the dose assessment for Sub-Area 3.1. Areas 1, 2, and 3 were assessed using the methods as described in th is report and all of the results indicate that the radiation exposures to the public are substantially below the NRC regulatory free release requirement of 25 mrem per year in accordance with 10 C.F.R. &sect; 20.1402.
Areas 4 and 5 were surveyed and sampled . Only the Aerial Survey data and tissue equivalent survey meter readings were assessed . Analysis of dose based upon soil concentrations is pending based on the need to further evaluate current and future aspects of culturally specific land uses. This report will be revised to add the modeled dose assessments for Areas 4 and 5 once the culturally specific aspects of land use surveys are finalized .
It should be noted, that for many of the exposure pathways in Areas 1, 2, and 3, the dose was determined to be less than 10 percent of the applicable dose criteria (i.e. less than 2.5 mrem/year). In Page 98 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas accordance with NRC NUREG-1757 (NRC Consolidated Decommissioning Guidance, Section 3.3 of Volume 2) (Ref. 19), the NRC considers these exposure pathways insignificant contributors .
The following is a more detailed summary of the dose assessment for each area. Additional detail is provided for each area in Sections 7.1through7.6, and Appendix Hof this report. As can be seen in the tables below, the doses calculated for Areas 1, 2 and 3 were well below the 25 mrem per yea r limit imposed by 10 C.F .R. &sect; 20.1402.
8.1      Area 1 Area 1 consisted of three discrete locations within a Cesium Prong as it extends outward beyond the boundaries of the WNYNSC (Figure 1). The Cesium Prong is a large area northwest of the WVDP where surface soil became contaminated with Cs-137 when ventilation system filters failed in 1968. Because the Cesium Prong was extensively characterized in the 1990s (Ref. 10), the samples collected in this area were compared to decay-!=orrected results from the earlier investigation . The Plan specified that a dose assessment would be conducted if the comparison of the newly collected data varied by 10 percent.
Two designated locations {1.1 and 1.2) were in close proximity to each other and the data collected was compa red to historic data from Location L12 in the 1995 Off-Site Investigation of the Cesium Prong.
" For Dose assessment purposes, these two locations were averaged and assessed as "L-12 ." The third location designated (Location 1.3) was closer to the WNYNSC boundary, and it was compared to location
" L-23" from the 1995 Report.
Doses were assessed for L12 and L23 using the methodologies described in Section 6. Table 58 below summarizes the assessed doses using the assessment methodologies.
Table 58.          Area 1 Calculated Annual Dose (mrem/year)
Dose Assessment Method              L12          L23              Model Aerial Survey              0.0          0.0      Resident Homemaker Tissue Equivalent Meter            2.4          8.0      Resident Homemaker Current Use RESRAD Calculation          1.0          0.2      Resident Homemaker DCGL Comparison              Below        Below        Resident Farmer Potential Use Calculation          1.7          0.4        Resident Farmer Fish Consumption              <0.1        <0.1                n/a 8.2      Area 2 Area 2 consisted of two sub-areas designated 2.1 and 2.2 (Figure 2) . The two sub-areas are located northwest of the WNYNSC in an area transected by Route 219, and in general proximity to Scoby Dam .
Both areas are small, sloped and heavily wooded . The suspected pathway of contamination for Area 2 is airborne deposition .
Page 99 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Doses were assessed for Sub-Area 2.1 and Sub-Area 2.2 using the methodologies described in Section 6.
Table 59 summarizes the assessed doses using the assessment methodologies.
Table 59.          Area 2 Calculated Annual Dose (mrem/year)
Dose Assessment Method                2.1          2.2                      Model Aerial Survey                0.0          0.0          Recreational Hiker/Hunter Tissue Equivalent Meter              0.4          0.0          Recreational Hiker/Hunter Current Use RESRAD Calculation          0.0          0.0          Recreational Hiker/Hunter DCGL Comparison                Below        Below              Resident Farmer Potential Use Calculation            n/a          0.1              Resident Farmer Fish Consumption                <0.1        <0.1                      n/a 8.3      Area 3 Area 3 is located on a farm at the confluence of Buttermilk and Cattaraugus Creeks (Figure 3) . It consists of two sub-areas designated 3.1 and 3.2. Sub-Area 3.1 is a larger parcel on which corn for livestock feed is grown . Sub-Area 3.2 is a small, sloped parcel that lies between the road and the farmhouse.
Doses were assessed for Sub-Area 3.1 and Sub-Area 3.2 using the methodologies described in Section 6.
Table 60 summarizes the assessed doses using the assessment methodologies .
Table 60.          Area 3 Calculated Annual Dose (mrem/year)
Dose Assessment Method                  3.1          3.2                Model Aerial Survey                1.8          0.2            Resident Farmer Tissue Equivalent Meter              3.9          0.0            Resident Farmer Current Use RESRAD Calculation            0.8          0.0            Resident Farmer DCGL Comparison                Below        Below            Resident Farmer Potential Use Calculation              7.2          0.3            Resident Farmer Fish Consumption                <0.1        <0.1                  n/a 8.4      Area 4 Area 4 lies approximately 20 miles to the west of the WNYNSC in the flood plain of Cattaraugus Creek (Figure 4) . It includes five sub-areas designated 4.1, 4.2, 4.3, 4.4, and 4.5. All of the sub-areas are wooded and no residences are located within the area .
Doses were assessed for each sub-area using the methodologies described in Section 6. Table 61 summarizes the assessed doses using the two assessment methodologies.
Page 100 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 61.            Area 4 Calculated Annual Dose (mrem/year)
Dose Assessment Method              4.1      4.2        4.3        4.4      4.5            Model Aerial Survey              TBD*      0.0        0.0        0.0      0.0            TBD*
Tissue Equivalent Meter            TBD*      0.0        0.0        0.0      0.0            TBD*
*Culturally specific land use needed .
8.5      Area 5 Area 5 lies approximately 17 miles to the west of the WNYNSC on a plateau well above the floodplain of Cattaraugus Creek (Figure 5) . It includes six sub-areas designated 5.1, 5.2, 5.3, 5.4, 5.5, and 5.6. All of the Sub-Areas are wooded and no residences are located within the area .
Doses were assessed for each sub-area using the methodologies described in Section 6. Table 62 summarizes the assessed doses using the two assessment methodologies.
Table 62.            Area 5 Calculated Annual Dose (mrem/year)
Dose Assessment Method              5.1    5.2        5.3      5.4      5.5    5.6            Model Aerial Survey              TBD*  TBD*      TBD*      TBD*    TBD*  TBD*              TBD*
Tissue Equivalent Meter            TBD*  TBD*      TBD*      TBD*    TBD*  TBD*              TBD*
*Culturally specific land use needed.
8.6      Confirmatory Area Four selected locations on the WNYNSC Property were identified for survey and sampling (Figure 6) .
These were considered " Confirmatory" locations to compare Aerial Survey results to areas known or suspected to be contaminated . Because these confirmatory locations all reside within the NRC-Licensed area of the WNYNSC and the subject of a future Decommissioning Plan, a dose assessment was not conducted .
9.0      References 1        An Aerial Radiological Survey of the Western New York Nuclear Service Center (Remote Sensing Laboratory, National Securities Technologies, LLC) October 2015 2        U.S. Nuclear Regulatory Commission, Standards for Protection against Radiation, 10 CFR Part 20.1402, Radiological Criteria for Unrestricted Use 3        Phase 1 Decommissioning Plan for the West Valley Demonstration Project, Rev. 2, December 2009.
4        Project Field Sampling and Dose Assessment Plan 5        Evaluation of Radiochemical Data Usability (DOE, 1997).
Pag e 101 of 102
Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 6  RESRAD-OFFSITE 3.1, July 2013, Argonne National Laboratory and.User Manual for RESRAD-OFFSITE (NUREG/CR-6937) 7  RESRAD 7.0, April 2014, Argonne National Laboratory 8  West Valley Demonstration Project Annual Site Environmental Report for Calendar Year 2012, (ASER), September 2013 .
9  International Commission on Radiological Protection (ICRP) Publication 68, Dose Coefficients for Intakes by Workers, 1994.
10 1995 Western New York Nuclear Service Center Off-Site Radiation Investigation Summary Report (Dames and Moore) 11 Project Quality Assurance Project Plan (QAPP), MJW.
12 Project Health and Safety Plan, MJW.
13 U.S. EPA QA/G-4 Guidance for the Data Quality Objectives Process, 2006.
14 U.S. EPA QA R-5, EPA Requirements for Quality Assurance Project Plans, 2001.
15 GEL Quality Assurance Plan, Rev. 29 (Uncontrolled) 16 MJW Technical Services Radioactive Materials License - C3181.
17 WVDP Terrestrial Background Study, 2014.
18 U.S. Environmental Protection Agency's Exposure Factors Handbook, EPA 1997.
19 NUREG 1757, Volume 2, Rev . 1, Consolidated NMSS Decommissioning Guidance Page 102 of 102}}

Latest revision as of 23:53, 4 February 2020

Radiological Survey and Dose Assessment Report for the Western New York Nuclear Service Center and Off-Site Areas in Follow Up to Aerial Gamma Radiation Survey Conducted in 2014, Rev. 0
ML16293A132
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Site: West Valley Demonstration Project, P00M-032
Issue date: 08/22/2016
From:
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To:
Office of Nuclear Material Safety and Safeguards, State of NY, Energy Research & Development Authority, Office of Nuclear Reactor Regulation
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ML16293A155 List: ... further results
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Download: ML16293A132 (116)
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Radiological Survey and/Dose Assessment Report For the Western New York Nuclear'Service Center and Off-Site Areas In Follow Up to Aerial Gamma Radiation Survey

'. Con~iicted in 2014, Rev. 0 Prepared For New York State Energy f and Research Development .

Authority West Valley Site Management Program 9'o30-B Route 219 I West Valley, NY 14171 Agreement Number 61280

  • Prepared By MJW Technical Services Inc.

243 Root Street, Suite 100, Olean, NY 14760 August 22, 2016 243 Root Slreel, Suite 100

. Olean, NY 14760-2436 Voice: (716) 372-5300 fax: (716) 372-5307 Toll Free: (866) 300-3659 mjwts.com

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table of Contents Executive Summary .................................................................................................................................... S.1 Purpose ... : .................................................................................................................................................. S.1 Radiological Survey and Sampling Actions ................................................................................................ S.1 Sample Radiochemical Analysis .....................................................: ........................................................... S.2 Summary of Dose Assessment Results ...................................................................................................... S.2 Conclusion .................................................................................................................................................. S.4 1.0 Introduction ....................................................._. ..............................................................., .......... ~ ..... 1 1.1 Background ........................................................................................................................................ 1 2.0 Project Components and Organization ............................................................................................. 2 2.1 Field Sampling and Dose Assessment Plan ........................................................................................ 2

  • 2.2 Quality Assurance Project Plan (QAPP) ............................................................................................. 2 2.3 Project Health and Safety Plan (HASP) .............................................................................................. 2 I

2.4 Participants, Roles, and Responsibilities .................................... :*...................................................... 2 3.0 Summary of 2014 Aerial Survey Results and Areas Selected for Analysis ........................................ 3 3.1 Method to Select Off-Site Survey Areas Based Upon the Results of the Aerial Survey Data and Reduce Uncertainty in the Location and Extent of Contaminated Areas ..................................................... 3 3.1.1 Area 1. ..............................................................................................., .... ;........................................... 6 3.1.2 Area 2.., ........................................ ,..................................................................................., .................. i 3.13. Area 3........................................................................................................,........................................ 8 3.1.4 Area 4 .................................................................................................................................................. 8 3.1.5 Area 5...................................... :......................................................................................................... 10 3*.1.6 WNYNSC Confirmatory .................................................................................................................... 11 4.0 Data Quality Objectives .......................................... :....................................................................... 12 5.0 Field Survey and Sampling Strategy ................................................................................................ 14 5.1 Instrumentation and Equipment Used ............................................................................................ 14 5.2 Overland GPS Walkover Gamma Surveys ........................................................................................ 15 5.3 Direct Radiation Measurements ...................................................................................................... 15 5.4 Sample Collection Activities ............................................................................................................ 15 5.5 Radiochemical Analysis ................................................................................................................... 16 6.0 Dose Assessment Approach ............................................................................................................ 16 6.1 Background Radiation and Radionuclide Determinations .............................................................. 18 6.1.1 WNYNSC Background Determination .............................................................................................. 19 6.1.2 Seneca Nation of Indians (SNI) Background Determination ........................................................... 23

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas

. 7.0 Survey, Sampling and Dose Assessment Results ............................................................................ 27 7.1 Area 1............................................................................................................................................... 27 7.1.1 Description of Area 1 .................. -........................................................................:............................ 27 7.1.2 Survey and Sampling Methodology for Area !.. .............................................................................. 28 7.1.3 Survey and Sampling Results for Area !. .............................................................. ,.......................... 28 7.1.4 Dose Assessment Approach for Area 1 ........................................................................................... 31 7.1.5 Dose Assessment Results for Area 1 .................................................... :.......................................... 32 7.1.6 -Conclusions for Area 1 ...................................................................................................................... 39 7.2 Area 2............................................................................................................................................... 39 7.2.1 Description of Area 2 ............................................................ :......... ~ ................................................ 39 7.2.2 Survey and Sampling Methodology for Area 2 ................................................................................ 39 7.2.3 Survey and Sampling Results for Area 2 ..... :............................................................................;....... 42 7.2.4 Dose Assessment Approach Area L. ........ :~ ....................................................................................... 47 7.2.5 Dose Assessment Results for Area 2 ....................... ,...... :................................................... ,............ 48 7.2.6 Conclusions for Area 2 .................................. :.................................................................................. 55 7.3 Area 3 ............................................................................:.................................. ;............................... 55 7.3.1 Description of Area 3 ......................-................................................................................................. 55 7.3.2 Survey and Sampling. Methodology for Area 3 ......................................................................;......... 55 7.3.3 Survey and Sampling Results for* Area 3 .......................................................................................... 57 7.3.4 Dose Assessment Approach for Area 3 ........................................................................................... 60 7.3.5 Dose Assessment Results for Area 3 ............................................................................................... 62 7.3.6 Conclusions for Area 3 ...................................................................................................................... 6S 7.4 Area 4 ........................................................................... .-................................................................... 68 7.4.1 Description of_Area 4 ...........................................................................-................... .-........... ,....._. ...... 68 7.4.2 Survey and Sampling Methodology for Area 4 ................................................................................ 68 7.4.3 Survey and Sampling Results for Area 4 .......................................................................................... 71 7.4.4 Dose Assessment Approach for Area 4 ................... :....................................................................... 78 7.4.5 Dose Assessment Results for Area 4 Dose ...................................................................................... 78 7.4:6 Conclusions for Area 4 ...................................................... :............................................................. : 80 7.5 Area 5 ..............-.................................................... :............................................................................ 80

. 7.5.1 Description of Area 5 ................................................................................ :...................~ .................. 80 7.5.2 Survey and Sampling Methodology for Area 5 ................................................................................ 80

. ii

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 7.5.3 Survey and Sampling Results for Area 5 .......................................................................................... 85 7.5.4 Dose Assessment Approach for Area 5 ............................................................... :........................... 93 7.5.5 Dose Assessment Results for Area 5 ............................................................................................... 93 7.6 Confirmatory Locations Located on the Western NY Nuclear Service Center Property ................. 95 7.6.l Description of Confirmatory Area ...........................................................................:....................... 95 7.6.2 Survey and Sampling Methodology for Confirmatory Area ............................................................ 95 7.6.3 Survey and Sampling Results for Confirmatory Area .... ."................................................................. 96 7.6.4 Estimation of Dose Rates Based Upon 2014 Aerial Survey Results ................................................. 97 7.6.5 Conclusions for Area 5 ................................................. :................................................................... 98 8.0 Final Summary ................................................................................................................................. 98 8.1 Area 1 .............................................................................. , ................................................................ 99 8.2 Area 2 ................................................................................................................................................ 99 8.3 Area 3 ............................................................... ~ ............... \ ............................................................ 100 8.4 Area 4 ............................................................................................................................................. 100 8.5 Area 5 ............................................................................................................................................. 101 8.6 Confirmatory Area ......................................................................................................................... 101 9.0 References .........................................................................................,........................................... 101 iii

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas List of Figures Figure 1 Area 1 Sampling Locations ........................................................................................................ 6 Figure 2. Area 2 Survey and Sampling Locations ...................................................................................... 7 Figure 3. Area 3 Survey and Sampling Locations ...................................................................................... 8 Figure 4. Area 4 Survey and Sampling Locations ................................................................................:..... 9 Figure 5. Area 5 Survey and Sampling Locations .................................................................................... 10 Figure 6. WNYNSC Confirmatory.Sampling Locations ............................................................................ 11 Figure 7. General Locations of Background Areas ................................................................................. 19 Figure 8. Background Area 1 Sample Locations ..................................................................................... 20 Figure 9. Background Area 2 Sample Locations ..................................................................................... 20 Figure 10. WNYNSC Background Area 1 Location on the 2014 Aerial Radiological Survey ..................... 21 Figure 11. WNYNSC Background Area 2 Location on the 2014 Aerial Radiological Survey ..................... 22 Figure 12. SNI Background Locations ....................................................................................................... 24 Figure 13. SN! Background Floodplain Locations on the 2014 Aerial Radiological Survey ...................... 25 Figure 14. SNI Background Non-Floodplain Locations on the 2014 Aerial Radiological Survey .............. 26 Figure 15. Area 1 Locations on the 2014 WNYNSC Aerial Radiological Survey ......................................... 3_3 Figure 16. Sub-Area L12 ........................................................................................................................... 35 Figure 17. Sub-Area L23 ...................................................................................................;................. :..... 36 Figure 18. Sub-Area, 2.2 Survey and Sampling Locations***********************************************************************'* 40 Figure 19. Sub-Area 2.2 Survey and Sampling Locations ................................................ :........................ 41 Figure 20. Sub-Area 2.1 Manual Grid Survey Box .................................................................................... 42 Figure 21. Sub-Area 2.2 Manual Grid Box ................................................... ;............................................ 43 Figure 22. Static 2" x 2" Detector Grid Readings for Sub-Area 2.1 ......................................................_. ... 44 Figure 23. Static 2" x 2" Detector Grid Readings for Sub-Area 2.2 .......................................................... 45 Figure 24. Area 2 Locations on the 2014 WNYNSC Aerial Radiological Survey ........................................ 49 Figure 25. Sub-Area 2.1 and Deer Pasture Area ....................................................................................... 51 Figure 26. Sub-Area 2.2 and Deer Pasture Area ....................................................................................... 52 Figure 27. Sub-Area Sampling Locations .................................................................................................. 56 Figure 28. Sub-Area 3.2 Sampling Locations ............................................................................................ 57 Figure 29. Static 2" x 2" Detector G*rid Readings for Sub-Area 2.2 ..................................................... ." .... 57 Figure 30. Sub-Area 3.2 GPS Survey Results ...............*....... :.................................................................... 58 Figure 31. Area 3 Locations on the 2014 WNYNSC Aerial Radiological Survey ........................................ 62 Figure 32. Sub-Areas 3.1 and 3.2 .............................................................................................................. 64 Figure 33. Sampling Locations in Sub-Areas 4.1, 4.2, and 4.3 .................................................................. 70 Figure 34. Sampling Locations in Sub-Areas 4.4 and 4.5 .......................................................................... 70 Figure 35. Sub-Area 4.1 GPS Walkover Gamma Survey Data ................................................................... 72 Figure 36. Sub-Area 4.2 GPS Walkover Gamma Survey Data ................................................................... 73 Figure 37. Sub-Area 4.3 GPS Walkover Gamma Survey Data ................................................................... 74 Figure 38. Sub-Area 4.4 GPS Walkover Gamma Survey Data ................................................................... 75 Figure 39. Sub-Area 4.5 GPS Walkover Gamma Survey Data ................................................................... 76 .

Figure 40. Area 4 Locations on the 2014 WNYNSC Aerial Radiological Survey ........................................ 78 Figure 41. Sub-Area 5.1 Sampling Locations ............................................................................................ 82 iv

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 42. Sub-Areas 5.2, 5.3 and 5.4 Sampling Locations ....................................................................... 83 Figure 43. Sub-Areas 5.5 and 5.6 Sampling Locations .............................................................................. 84 Figure 44. Sub-Area 5.1 GPS Walkover Survey Data ................................................................................ 86 Figure 45. Sub-Area 5.2 GPS Walkover Gamma Survey Data ................................................................... 87 Figure 46. Sub-Area 5.3 GPS Walkover Gamma Survey Data ................................................................... 88 Figure 47. Sub-Area 5.4 GPS Walkover Gamma Survey Data ................................................................... 89 Figure 48. SubcArea 5.5 GPS Walkover Gamma Survey Data ................................................................... 90 Figure 49. Sub-Area 5.6 Walkover Gamma Survey Dat(! .......................................................................... 91 Figure 50. *Area 5 Locations on the 2014 WNYNSC Aerial Radiological Survey ........................................ 93 Figure 51. WNYNSC Confirmatory Locations on 2014 Aerial Survey ....................................................... 97 v

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas List of Tables Table 1. Locations Selected for Further Evaluation ................................................................................ 5 Table 2. DCGLw Peak-of-the-Mean Values, Rev. 2 for 25 mrem/year (pCi/g)l 1 l .................................... 17 Table 3. WNYNSC Background Area Dose Rates Based Upon 2014 Aerial Survey Data ...................... 22 Table 4. WNYNSC Background Soil Concentrations ............................................................................. 23 Table 5. SNI Background Floodplain Area Dose Rates Based Upon 2014 Aerial Survey Data .............. 25 Table 6. SNI Background Non-Floodplain Area Dose Rates Based Upon 2014 Aerial Survey Data ...... 26 Table 7. . Area 1 Tissue Equivalent Dose Rate Instrument Gross Readings ........................................... 29 Table 8. Area 1 Weighted Average Soil Concentrations ....................................................................... 30 Table 9. Area 1 Cesium-137 Soil Concentrations Comparison ............................................................. 30 Table 10. Area 1 Net Average Soil Concentrations ................................................................................. 31 Table 11. Area 1 Dose Rates Based Upon 2014 Aerial Survey Data ....................................................... 33 Table 12 Area 1 Calculated Doses Based on 2014 WNYNSC Aerial Radiological Survey ....................... 34 Table 13. Sub-Area L12 Current Use Pathway Doses ............................................................................. 35 Table 14. Sub-Area L23 Current Use Pathway Doses ............................................................................. 37 Table 15. Area 1 Comparison to WVDP Phase 1 Decommissioning Plan DCGLw .................................... 37 Table 16. Sub-Area L12 Potential Use Pathway Doses ........................................................................... 38 Table 17. Sub-Area L23 Potential Use Pathway Doses ........................................................................... 38 Table 18. Concentrations in Edible Portions of Fish around Springville Dam ........................................ 38 Table 19. Background Concentrations in Edible Portions of Fish ........................ '. .................................. 39 Table 20. Ingestion dose coefficients (mrem I µCi) from ICRP 68 ..................................................... :.... 39

  • Table 21. Area 2 Tissue Equivalent Dose Rate Instrument Gross Readings ...................... ;........ :........... 45 Table 22 Sub-Area 2.1 Weighted Average Soil Concentrations ............................................................. 46 Table 23. Sub-Area 2.1 Net Average Soil Concentrations ...................................................................... 46 Table 24. Sub-Area 2.2 Weighted Average Soil Concentrations ............................................................. 46 Table 25. Sub-Area 2.2 Net Average Soil Concentrations ..................... ; ................................................ 47 Table 26. Area 2 Dose Rates Based Upon 2014 Aerial Survey Data ....................................................... 49 Table 27. Area 2 Calculated Doses Based on 2014 WNYNSC Aerial Radiological Survey ....................... 49 Table 28. Sub-Area 2.1 Current Use Pathway Doses .............................................. :................................ 50 Table 29. Sub-Area 2.2 Current Use Pathway Doses .............................................................................. 52 Table 30. Area 2 Comparison to WVDP Phase 1 Decommissioning Plan DCGLw .................................... 53 Table 31. Sub-Area 2.2 Potential Use Doses .......................................................................................,... 54 Table 32. Concentrations in Edible Portions* of Fish around Springville Dam ........................................ 54 Table 33. Background Concentrations in Edible Portions of Fish ...... ; .................................................... 54 Table 34. Ingestion dose coefficients (mrem I µCi) from ICRP 68 ...................................................... :... 54 Table 35. Sub-Area 3.1 Average Soil Concentrations ................................... :......................................... 59 .

Table 36. Sub-Area 3.1 Net Average Soil Concentrations ...................................................................... 60 Table 37. Sub-Area 3.2 Average Soil Concentrations ............................................................................. 60 Table 38. Sub-Area 3.2 Net Soil Concentrations ..................................................................................... 60 Table 39. Area .3 Dose Rates Based Upon 2014 Aerial Survey Data .................. , .................................... 63 Table 40. Area 3 Calculated Doses Based on 2014 WNYNSC Aerial RadiologiCal Survey ....................... 63 Table 41. Sub-Area 3.1 Pathway Doses ....................................................................*.............................. 65 vi

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 42 Sub-Area 3.2 Pathway Doses ..............................................................................~ ................... 6S Table 43. Area 3 Comparison to WVDP Phase 1 Decommissioning Plan DCGLw .................................... 6S Table 44. Sub-Area 3.1 Potential Use Pathway Doses ............................................................................ 66 Table 4S. Sub-Area 3.2 Potential Use Pathway Doses ............................................................................ 67 Table 46. Concentrations in Edible Portions of Fish around Springville Dam ........................................ 67 Table 47. Background Concentrations in Edible Portions of Fish ........................................................... 67.

Table 48. Ingestion dose coefficients (mrem/µCi) from ICRP 68 ............................................................ 67 Table 49. Area 4 Average Dose Rates ..................................................................................................... 77 Table so. Area 4 Dose Rates Based Upon 2014 Aerial Survey Data ............................................... : ....... 79 Table Sl. Area 4 Calculated Doses Based on 2014 WNYNSC Aerial Radiological Survey ....................... 79 Table S2 Area S Average Dose Rates ........................................................... :......................................... 92 Table S3 Area S Dose Rates Based Upon 2014 Aerial Survey Data ....................................................... 94 Table S4 Area S Calculated Doses Based on 2014 WNYNSC Aerial Radiological Survey ....................... 9S Table SS. WNYNSC On-Center Confirmatory Location Tissue Equivalent Dose Rate Readings ............. 96 Table S6. WNYNSC On-Center Confirmatory Soil Concentrations Including Background ...................... 97 Table S7. Dose Rates Based Upon 2014 Aerial Survey Results ............................................................... 98 Table S8. Area 1 Calculated Annual Dose (mrem/year) ......................................................................... 99 Table S9. Area 2 Calculated Annual Dose (mrem/year) ............................. : ......................................... 100 Table 60. Area 3 Calculated Annual Dose (mrem/year) ....................................................................... 100 Table 61. Area 4 Calculated Annual Dose (mrem/year) ....................................................................... 101 Table 62. Area S Calculated Annual Dose (mrem/year) ....................................................................... 101 vii

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Li~t of Acronyms Aerial Survey . 2014 Aerial Radiological S1,1rvey (Aerial Survey)

BGA Background Area cm Ce.ntimeter CPM Counts per minute DCF Dose coefficients factbr DCGL Derived Concentration Guideline Level DOE U.S. Department of Energy ELAP Environmental Laboratory Approval Program EPA U.S. Environmental Protection Agency

. fl Fractional Absorption in the Gastrointestinal Tract Rate FS&DP Field Sampling and Dose Assessment Plan ("Plan")

g Gram GPS Global Positioning System HASP Health and Safety Plan ICRP International Commission on Radiological Protection kCPM Thousand counts per minute m Meter MDL Minimum Detectable Levels MJWTS MJW Technical Services* Inc.

mrem Milli rem Nal Sodium Iodide NIST National Institute of Standards and Technology NORM Naturally Occurring Radioactive Material NRC Nuclear Regulatory Commission NYSDEC New York State Department of Environmental Con.servation NYSDOH New York State Department of Health NYSERDA New York State Energy Research and Development Authority pCi Pico Curie PM Project Manager QAPP Quality Assurance Project Plan RESRAD* RESidual RADioactive Material RSL Remote Sensing Laboratory SNI Cattaraugus Territory of the Seneca Nation of Indians WNYNSC Western New York Nuclear Service Center WVDP West Valley Demonstration Project viii

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Appendices Appendix A- Field Sampling and Dose Assessment Plan, Rev. O and Summary of Field Changes Appendix B - Field Guides Appendix C - Analytical Methodology Appendix D - Land Use Surveys Appendix E - Field Sample Collection and Instrument Check Information Appendix F - Soil Sample Summary Appendix G - Certificates of Analysis Appendix H - Dose Assessment Appendices Appendix I - Summary of Liquid Effluent Discharges NFS Operations and WVDP Activities ix

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Executive Summary Purpose The purpose of the radiological survey and dose assessment project was to determine if areas identified in the 2014 Aerial Radiological Survey (Aerial Survey) of the Western New York Nuclear Service Center (WNYNSC} (Ref. 1} as having elevated levels of radioactivity above background do in fact contain elevated radionuclide concentrations in the soil. If elevated soil concentrations were identified, a dose assessment (based on current and reasonably foreseeable future land use) was conducted to confirm that there were no health and safety concerns for the identified area. Because the areas sampled are off site and the land use*is unrestricted, the dose assessment results were compared to 10 C.F.R. § 20.1402, Radiological Criteria for Unrestricted.Use (Ref. 2).

In addition, the U.S. Nuclear Regulatory Commission (NRC} requested that a comparison of the soil sampling results to the Derived Concentration Guidelines in the WVDP Phase 1 Decommissioning Plan (Ref. 3) be completed as an independent check against a conservative exposure scenario.

The results from this soil sampling and dose assessment project show that radiation exposure to the public for each of the areas evaluated is substantially below the NRC-regulatory unrestricted use requirement of 25 millirem (mrem) per year (in accordance with 10 C.F.R. § 20.1402}. Therefore, no public health and safety concerns were identified through this analysis.

Radiological Survey and Sampling Actions Specific areas were identified in the project Field Sampling and Dose Assessment Plan ("Plan") (Ref. 4, Appendix A) for study based upon the Aerial Survey and other historic knowledge (e.g., Cesium Prong).

The Plan further specified ,the specific survey and sampling parameters for each area including the location and shape of the area, the number of locations within the_ area to be surveyed and sampled, and radiochemical analyses to be performed. Field Guides (Appendix B) provided additional detail and instructions on surveys and sampling.

The number of locations to be surveyed and sampled in each survey area was based upon the size of the area.

  • For areas 0- 2,000 m 2 in area, a minimum of four locations were surveyed and sampled.
  • For areas 2,001to10,000 m 2 in area, a minimum of 15 locations were surveyed and sampled.
  • For areas> than 10,000 m 2 in area, a minimum of 24 locations were surveyed and sampled.
  • The following is an overview of radiological survey and sampling actions taken. Additional detail is provided for each area surveyed in Sections 5.1 through 5.6 of this report.

Radiological survey and sampling activities included three components:

  • Global Positioning System (GPS) Walkover Gamma Surveys ES-1

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas GPS walkover gamma surveys were conducted over designated survey areas using a Ludlum Model 2241-2 Scaler Rate Meter and a Ludlum Model 44-10 2"x2" Sodium Iodide (Nal) gamma detector, coupled with a GPS unit. Radiation count rates in counts per minute (CPM) were collected as the survey team walked designated grid patterns while the GPS position was simultaneously logged. The purpose of this survey was to determine if any sub-regions within the designated survey area were elevated compared to the rest of that survey area. The results were displayed graphically, and if elevated sub-regions were identified, samples were collected in the elevated sub-regions, along with random samples.

  • Collection of Soil Samples Within each survey area, soil samples were collected from the number of locations and at the depth intervals specified in the plan. Specifically, ba~ed on a review of historical information, areas where potential contamination was more likely a result.of airborne deposition, initial surface layer samples were analyzed from the first five cm of soil. Similarly, based on a review of historical information, areas where potential contamination was more likely the result of water deposition, initial samples were analyzed from the first 15 centimeter (cm) of soil.
  • Static Direct Radiation Measurements At each location where soil samples were collected, static direct radiation measurements were collected using both a Bicron microRem survey meter, which employs a tissue equivalent gamma detector, and a Ludlum Model 2241-2 Scaler Ratemeter with the Model 44-10 2"x2" Nal gamma detector. Readings were collected at 1 and 100 cr:n above the ground.

Sample Radiochemical Analysis As specified in the Plan, a percentage of the samples collected were submitted for radiochemical analysis. All samples submitted were analyzed by a New York State Department of Health (NYSDOH)

Environmental Laboratory Approval Program (ELAP)-laboratory forgamma spectroscopy (which includes analysis for Cs-137), gross beta, and gross alpha analysis. Some samples were also analyzed for additional isotopic information. Where surface samples statistically exceeded Cs-137 background concentrations plus two standard deviations, the next deeper depth increment samples were analyzed.

All analytical data received Level IV data validation per (Evaluation of Radiochemical Data Usability (es/er/ms-5), 1997 (Ref. 5) and were found to be usable. Additional detail is provided in Sections 6.1 through 6.6 and the Appendices.

Summary of Dose Assessment Results For each area studied, a dose assessment was conducted as specified in the Plan or as subsequently determined to be the appropriate methodology. For Areas 1, 2, and 3, this was based upon property-specific land use, and the size and physical characteristics of the area such as terrain and tree cover. For Areas 4 and 5, which are located on the Cattaraugus Territory ofthe Seneca Nation of Indians (SNI),

culturally specific aspects of land use surveys are still being developed. This report will be revised to ES-2

Radiological Survey and Dose.Assessment Report for the WNYNSC and Off-Site Areas include the modeled dose assessments for Areas 4 and 5 once the culturally specific aspects of the land use surveys are finalized. Additional detail is provided for each area in Sections 5.1 through 5.6 and the Appendices to this report.

The radiation doses were assessed using the following approach:

  • Annual radiation doses were estimated based upon the results of the 2014 Aerial Survey. No background level information for the specific areas assessed in this report was provided in the Aerial Survey Report. Therefore, background levels were interpolated from the data.
  • Annual radiation doses were estimated based on readings collected using the tissue equivalent dose rate survey.meters.
  • Annual radiation doses, for current land use, were estimated by performing RESidual
  • RADioactive (RESRAD) OFFSITE 3.1 computer code (Ref. 6) of measured gross alpha, gross beta, and Cesium-137 (Cs-137) soil concentrations in excess of background. The assessment of the gross alpha was based on the most conservative isotopes (Americium-241 [Am-241] or Plutonium-239 [Pu-239]) and the beta was based on Strontium-90 (Sr-90).
1. Of the alpha emitters that are of dosimetric concern, Pu-239 and Am-241 were selected as the two alpha-emitting isotopes based on the predominant concentrations of these two radionuclides in the West Valley waste stream (i.e., they were greater than 10,000 times other alpha-emitting radionuclide concentrations for the historical operations). In addition, due to the longer half-lives of these isotopes, Pu-239 and Am-241 would continue to be dosimetrically important in the dose assessments for future land users.
2. Of the beta emitters that are of dosimetric concern, Sr-90 was selected as the beta emitting isotope based on the concentrations in the West Valley waste stream, and the fact that Sr-90 is longer-lived than the majority of beta-emitters that would have been generated during historical operations. Sr-90 is a waste product of reprocessing and thus it would likely be a contributor to the beta.dose from the site.
  • For purposes of this study, background concentrations were determined from two locations within the WNYNSC and from 10 locations within the SNI, five of which are in the Cattaraugus Creek floodplain and five of which are not in the floodplain.
  • These sample results were compared to the Derived Concentration Guideline Level (DCGLw) concentrations established in the Phase 1 Decommissioning Plan for the West Valley Demonstration Project (WVDP). This comparison of the gross alpha and beta was based on the most conservative isotopes (AM-241, Pu-239 and Sr-90, respectively) and accounted for all of the anthropogenic nuclides except Carbon-14 (C-14), lodine-129 (1-129), and Technetium-99 (Tc-99). For these radionuclides, a qualitative analysis was performed. In all cases for these three radionuclides, either the soil concentration was below the detection limit or the soil concentration detected was significantly less than the Phase 1 Decommissioning Plan DCGLw Values. In addition, an analysis of the isotopic data indicates that the radionuclides that account for most of the gross alpha and gross beta soil concentrations are radionuclides that are considered Naturally Occurring Radioactive Material (e.g., natural uranium, natural thorium, and potassium-40. The DCGLs used for this comparison were based on a resident farmer scenario.
  • Annual radiation doses for reasonably foreseeable future land use were also estimated using the RESidual RADioactive (RESRAD) 7.0 computer code (Ref. 7) to assess gross alpha, gross beta, and ES-3

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Cs-137 soil concentrations in excess ofbackground. The assessment of the gross alpha was based on the most conservative isotopes between Am-241 and Pu-239 and the beta was based on Sr-90.

  • Annual radiation doses from the consumption of fish were also estimated. Calculations were performed using the average concentration of Sr-90 and Cs-137 in the edible portion of fish above background from the 2012 WVDP Annual Site Environmental Report (Ref. 8). Annual exposures were calculated based on ingestion dose' coefficients from the International Commission on Radiological Protection (ICRP) ICRP Publication 68 (Ref. 9).

In two areas located on the SNI (Areas 4 and 5), dose assessments were performed based on aerial survey and direct radiation measurements. Soil sampling actions were performed, however dose assessments based upon soil concentrations will be prepared after more fully characterizing the current and future uses of these areas including culturally specific aspects of the SN l's use of these properties.

Conclusion The assessed doses in Areas 1, 2, and 3, based upon multiple approaches and covering current and reasonably foreseeable future land use scenarios, were determined to be significantly less than the 25 mrem per year requirement identified in 10 C.F.R. § 20.1402, and there are no health and safety concerns identified for these locations.

For Areas 4 and 5, which are located on the SNI, culturally specific aspects of SNI land use are being developed. Therefore, any dose assessment included in this version of the report will be revised once the culturally specific aspects of land use are finalized.

ES-4

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 1.0 Introduction 1.1 Background The New York State Energy Research and Development Authority (NYSERDA) owns the 3,300-acre Western New York Nuclear Service Center (WNYNSC) in the town of Ashford, New York. Since 1982, NYSERDA and the U.S. Oepartment of. Energy (DOE) have been working at the WNYNSC ("Center") to conduct the West Valley De.monstration Project (WVDP), a high-level radioactive waste solidification and cleanup project.

In September 2014, DOE and NYSERDA jointly initiated an aerial radiological survey (Ref. 1) to examine the radiological conditions of the Center and adjacent areas, as well as Cattaraugus Creek from the Center to Lake Erie in Western New York. This Aerial Survey was conducted by the National Nuclear Security Administration's Remote Sensing Laboratory (RSL).

Previous aerial, soil sampling, and radiological survey studies had identified areas of contamination both on the WNYNSC property, and in nearby off-site locations resulting from routine permitted disc~arges and inadvertent releases of radioactivity from the site (1995 Western New York Nuclear Service Center Off-Site Radiation Investigation Summary Report, Dames & Moore) (Ref. 10). Of note was the identification and analysis of areas referred to as the "Cesium Prong." The Cesium Prong comprises an irregularly shaped area on the Center property that extends outward and generally to the northwest, onto off-Center properties. This contamination is believed to be the result of unintentional airborne releases from the Center in 1968. Historic soil sample data from the Cesium Prong is consistent with airborne surface deposition of Cs-137. In addition to the Cesium Prong, the Aerial Survey showed slightly elevated areas of radioactivity in the on-site creeks including Buttermilk Cree.k, and possibly Cattaraugus Creek. A summary of liquid effluent discharges from the WVDP is provided in Appendix I.

Based on the Aerial Survey, five areas outside the Center property were identified for further evaluation based on information provided by RSL that showed that radiation levels at these locations were slightly above the "background" radiation levels seen throughout Western New York1 . Two of these areas were identified during previous aerial surveys, and the three other locations were newly identified during the 2014 Aerial Survey. The identification of the three new areas is likely due to improvements in detection sensitivity and precision, and the survey extending into areas that had not been previously surveyed.

MJW Technical Services Inc. (MJWTS) was retained by NYSERDA to conduct a survey, sampling, and dose assessment study to "ground truth" the 2014 Aerial Survey results, and to confirm that credible potential radiation exposures to members of the public in unrestricted areas do not exceed the applicable NRC limits per 10 C.F.R. § 20.1402. The survey and sampling operations were extensive, and examined areas in proximity to the Center, as well as the areas further to the west, located on the SNI.

Background radiation is caused by naturally occurring radioactive materials like radon and from certain man-made radioactive materials that are found throughout the environment today.

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas The scope of the activities conducted by MJWTS included development and execution of the Plan (Ref.

4), a project Quality Assurance Project Plan (QAPP) (Ref. 11), a project Health and Safety Plan (HASP)

(Ref. 12}, Field Guides (Appendix B); and procedures.

2.0 Project Components and Organization 2.1 Field Sampling and Dose Assessment Plan The Plan describes the purpose and objectives ofthe project; defines the project organization and structure; establishes the approach for field survey, sample collection, analysis, data validation, and defines the requirements and ~pproach to dose assessment. An initial draft of the Plan was shared with the NRC, the Environmental Protection Agency (EPA}, the New York State Department of Environmental Conservation (NYSDEC), NYSDOH, and the SNI. Comments provided by these agencies were used to develop the Plan, which was issued on October 1, 2015. Minor revisions in the sampling areas identified in the Plan were implemented after further discussion between NYSE RDA and RSL when the final version of the 2014 Aerial Survey was issued. The changes are summarized in Appendix A.

2.2 Quality Assurance Project Plan (QAPP)

The QAPP provides the project specific details on how the surveys _and samples were to be collected to ensure representativeness, traceability and reproducibility. The data quality objectives are defined in

  • the QAPP, along with information detailing data quality and validation processes. Appendix E, Data Quality Objectives, provides additional detail on field and laboratory data quality indicators.

2.3 Project Health and Safety Plan (HASP)

The HASP provides the project specific details on how the project activities would be conducted in a safe . *

  • manner and in compliance with applicable safety requirements.

2.4 Participants, Roles, and Responsibilities The key project staff and their primary roles and responsibilities were:

NYSERDA Project Manager The NYSERDA Project Manager was the primary point of contact and coordination with the MJWTS Project Manager, and ensured that the MJWTS Project Manager was cognizant of relevant information, issues, objectives, requirements, and potential concerns or deficiencies.

Project Manager The Project Manager (PM} was responsible for execution of the survey, sampling, and dose assessment activities and was responsible for the health physics aspects for all field activities. The PM was also responsible for ensuring that work was executed in a ti.mely manner, in accordance with the Plan, and in conformance with all applicable regulatory requirements.

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Project Certified Health Physicist The Project Certified Health Physicist ensured that the collection and analysis of survey data and the derived dose assessments were conducted properly and in accordance with the Plan and appropriate professional and regulatory standards and practices to ensure thatresults are accurate and defensible.

Project. Health Physicist The Project Health Physicist was responsible for the evaluation of survey and laboratory data, and for the performance of the dose assessments.

Project Quality Assurance and Control Manager The Project Quality Assurance and Control Manager was responsible for all aspects of project Quality Assurance and Quality Control including field surveying, sampling activities, and laboratory analysis.

Project. Data Validation Specialist The Project Data Validation Specialist was responsible for Level IV validation of data as required by accepted professional practices and standards in accordance with the QAPP.

Project lnformatfon Technology/Geographic Information System Specialist The Project Information Technology/Geographic Information System Specialist was responsible for oversight of data file storage and the processing of acquired data, in particular, GPS-driven radiation survey data.

3.0 Summary of 2014 Aerial Survey Results and Areas Selected for Analysis The 2014 Aerial Survey was conducted by RSL. It encompassed areas in proximity to the WNYNSC as well as a corridor following Cattaraugus Creek westward to Lake Erie. The detection capabilities of this survey were considerably better than those of previous a.erial surveys due to improved technology. The aerial survey data was spectroscopic in nature, thus allowing RSL to extract information specific to anthropogenic isotopes including Cs-137 and Cobalt-60 (Co-60). Cobalt-60 was not identified outside of the WNYNSC.

3.1 Method to Select Off-Site Survey Areas Based Upon the Results of the Aerial Survey Data and Reduce Uncertainty in the Location and Extent of Contaminated Areas NYSERDA consulted extensively with RSL personnel on the identification of specific areas that warranted follow-up measurements based upon the results of the aerial survey. Based on RSL's expert knowiedge of this particular dataset and their vast experience with aerial survey methods and results of similar surveys, RSL suggested a methodology that they believed was conservative and would capture the pertinent features and support the identification of areas for follow-up measurements. RSL identified four criteria that when considered in combination (i.e., an area must meet all criteria concurrently),

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas resulted in delineation of specific areas that were meaningful to NVSERDA's ground-level measurements of ambient radiation and collection of soil samples. These criteria included:

1. Data from the Cs-137 spectral signature are greater than two standard deviations above backgrou.nd. This threshold (30 counts per second) is only slightly above background and is thus coincidental with statistical noise in the dataset. This particular measure on its own could result in false negatives. That is, given the relatively small variance in the extraction algorithm, Cs-137 may be indicated in the spectral data though not strongly within the photopeak.
2. Data from the anthropogenic-sources spectral signature are greater than two standard deviations above background. This threshold (1000 counts per second) is only slightly above background and is thus coincidental with statistical noise in the dataset. This particular measure on its own could result in false positives. That is, because the anthropogenic extraction has a relatively large variance, it can produce false positives if used to look for a specific isotope (Cs-137).
3. Both Criteria 1 and 2 are met, and they are both met over the same area (co-located), or both met over areas in close proximity to one another. Given that aerial survey methods result in somewhat "coarse" data, it is difficult to define exact spatial "boundaries" of areas meeting thresholds*1 and 2 strictly from the aerial data. As such, consideration is given to areas that are not only co-located (overlapping), but also to those areas located relatively near one another (less than or equal to 300 feet).
4. Both criteria 1 and 2 are met, areas are co-located or located in close proximity (criteria 3), and these areas appear clustered or extended in the area. Given that criteria 1 and 2 are very close to background, the first three criteria produce a dataset that still contains statistical noise, identifying very small randomly located spots across the entire aerial survey area. Having examined.the detailed spectral data, RSL was confident these small random areas represent statistical noise. Where these areas appeared clustered and/or extended in area, RSL believed they are more suggestive of areas that may contain slightly elevated levels of radiation. As such, these four criteria, in combination, provide a reasonable delineation of areas that warrant follow-up measurements of ambient radiation at ground level and soil sample collection.

Based on the criteria identified above, five areas were selected for survey, sampling, and dose assessment. These areas were designated Areas 1, 2, 3, 4, and 5 (Figures 1 through 5). Areas 2, 3, 4, and 5 were further broken down into sub-areas. Area 2 had two sub-areas, Area 3 had two sub-areas, Area 4 had five sub-areas, and Area 5 had six sub-areas. In order to reduce uncertainty in the location and aerial extent of the potentially elevated regions, when GPS or manual survey grids were surveyed using the Ludlum 2241-2 survey meter and 2"x2" Nal gamma detector, the boundaries of the survey areas were extended outside of the boundaries identified by the aerial survey data. These meter readings therefore achieved*two things:

1. The identification of any comparatively elevated regions within the areas identified by the RSL data.

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas

2. The identification of any elevated regions, within the survey area, but outside the areas identified by the RSL data .

For the Area 2, rectangular survey boxes (associated with the 2"x2" meter readings) encompassed an area at least three times the area of the investigation lines derived from the RSL data.

For Areas 3.1, the shape of the 2"x2" survey readings boundaries were based on configuration of the terrain and other physical features surrounding the investigation areas derived from the RSL data .

For Areas 4 and 5, the sub-areas (e.g., 4.1, 4.2 etc.) were identified by constructing polygons that surrounded the clusters of investigation areas (e.g., 4.lA, 4.1 B, etc.) based upon the RSL criteria . These polygons determined the boundaries of the GPS walkover survey traverses .

In addition to these five areas, "Confirmatory" locations were also sampled on the WNYNSC to compare Aerial Survey results to areas known or suspected to contain contamination .

The five survey areas and their current land characteristics (as determined through aerial photos and land use surveys) (Appendix D) and the on-center confirmatory location are summarized in Table 1.

Table 1. Locations Selected for Further Evaluation Current Land GPS Coordinates Area No. Location Characteristic (centroid location)

Residential properties, Cesium Prong 1 with cleared and tree 42°27' 46.97" N 78°40'13.53" w (Off-Site) covered areas.

  • Near Scoby Hill Dam (new location likely Varying in terrain and 2 an extension of the tree cover. These areas 42°28'25 .66" N 78°41'18.84" w Cesium Prong) (Sub- are not residential.

Areas 2.1 and 2.2)

Near confluence of Buttermilk and 3 Cattaraugus Creeks Active agriculture area. 42°28'56.20" N 78°40'42.19" w (Sub-Areas 3.1 and 3.2)

Wooded area that does Cattaraugus Territory not include residences 4 of the Seneca Nation 42°32'23,84" N 79°02'13.07" w on the floodplain of of Indians Cattaraugus Creek Wooded area near Cattaraugus Territory residential property not 5 of the Seneca Nation 42°31'12. 94"N 78°58'25.11" w on the floodplain of of Indians Cattaraugus Creek WNYNSC WNYNSC On-Center N/A N/A Confirmatory Page 5of102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Details on these areas and the discrete locations selected for study on, or in proximity to, the WNYNSC are provided in Figures 1 through 6.

3.1.1 Area 1 Area 1 (Cesium Prong, outside the WNYNSC property) includes three specific locations within the Cesium Prong, but outside of the WNYNSC property. Because the Cesium Prong was extensively sampled and analyzed in the 1990s, these samples were collected to compare currently measured concentrations to previously measured concentrations decay corrected to current day. Figure 1 below provides a map of these locations .

Figure 1 Area 1 Sampling Locations 0

1.1 1.2 w

====--------Feet 0 500 , 000 iooo Area 1 Sampling Locations

  • 20 t 5 Con11rmatory Soj Sample Locations

- 2014Areas 1ee g Cr'lteria !or Fur'lrler EvaluatlQ'I Wesiem New York Nuclear Service Center Page 6of 102

Rad iological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 3.1.2 Area 2 Area 2 consists of two separate sub-areas northwest of Area 1 in a region transected by the Route 219 Expressway in proxim ity to Cattaraugus Creek. Figure 2 provides a map of these locations .

Figure 2. Area 2 Survey and Sampling Locations The area near the center of the ma p was identified as meeting criteria fo r further evaluation; however, the lan downer decline d pe rmission to survey an d sample.

UB-AREA2.1 Q

SUB-AREA 2.2

--9'===------Feet 0 250 500 1,000 Area 2 Survey and/or Sampling Locations

- 2014Areas Meeting Cnteria fOf Further Evaluation survey and Samphng Sub-Areas Page 7of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 3.13. Area 3 Area 3 consists of two separate sub-areas adjacent to the northern section of the WNYNSC on a farm located at the confluence of Buttermilk and Cattaraugus Creeks. Figure 3 provides a map ofthese locations.

Figure 3. Area 3 Survey and Sampling Locations Cattaraugus Creek SUB-AREA 3.1 Butlerrmlk Creek

---======-----*Feet 0 250 500 1.000 Area 3 Survey and/or Sampling Locations

- 2014 Areas Meebng Cnter a for Furttler Evaluation Westem New York Nuclear Service Center Survey end Sampling Sub-Areas Page 8of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 3.1.4 Area 4 Area 4 consists of five separate Sub-Areas spanning Cattaraugus Creek, located approximately 20 miles to the west of the WNYNSC and on the Seneca Nation of Indians Cattaraugus Territory. Figure 4 below provides a map of these locations .

Figure 4 . Area 4 Survey and Sampling Locations Area 4 Survey and/or Sampling Locations

~ 014 Areas Meeting Criteria for Further Evaluation urvey and Sampling Sub-Areas Page 9of102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 3.1.5 Area 5 Area 5 consists of six separate sub-areas north of Cattaraugus Creek, located approximately 17 miles to the west of the WNYNSC and on the SNI. Figure 5 below provides a map of these locations .

Figure 5. Area 5 Survey and Sampling Locations 5.6 5.1 5.5

~. 4 6 .2 5.3

===-------*lfe<<

250 5()0 t .000 Area 5 Proposed Surrvey and/or Sampling locations

- 2014Areas Meeting Criteria for Further Evaluation survey and sampling Sub-Areas Page 10 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 3.1.6 WNYNSC Confirmatory Four selected locations on the WNYNSC property were identified for survey and sampling. These were considered "Confirmatory" locations to compare Aerial Survey results to areas known or suspected to be contaminated . Figure 6 below provides a map of these locations .

Figure 6. WNYNSC Confirmatory Sampling Locations Sampling Locations

  • Poienb.al Confinna1Dry Sample ocaUQl!s 2014 Areas Meebng Cntena for Funh er Ev uabon Wes1em New York Nuclear Se111ice Center I

0 0.25 05 Page 11of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 4.0 Data Quality Objectives 4.1 This soil sampling and dose assessment study was completed using the Plan (Ref. 4). Within the context of the Environmental Protection Agency' s guidance for identifying data quality objectives (EPA QA/G-4 Guidance for the Data Quality Objectives Process, 2000), (Ref. 13) and (EPA QA R-5 EPA Requirements for Quality Assurance Planning, 2001) (Ref. 14) the rationale for the sampling approach is as follows :

1. State the problem - This soil and dose assessment effort was completed as a follow -up activity to the 2014 Aerial Survey of the WNYNSC. Specifically, the 2014 Aerial Survey identified five areas potentially having elevated levels of radioactivity above background . An aerial radiation survey does not, however, provide the data to confirm that all of the areas identified are below public health and safety standards, for example the criteria in 10 CFR 20.1402, Radiological Criteria for Unrestricted Use.
2. Identify the goals of the study - The key goal for this activity was to evaluate each of the five areas to determine if these areas do in fact contain elevated rad ionuclide concentrations in the soils, and for those with elevated concentrations, to complete a dose assessment that evaluates the current and reasonably foreseeable future land use scenarios to determine if there are any health and safety issues for the property.

The criteria used to evaluate each area are the NRC Radiological Criteria for Unrestricted Use (10 CFR 20.1402), which establishes the requirements that exposure for the public must be less than 25 mil Ii rem per year for license termination with unrestricted use.

3. Identify the inputs to the decision - The input to the decision of whether the decision criteria were met include:
  • The dose rate data collected during the 2014 Aerial Survey,
  • The field dose rate measurements collected for each area,
  • The soil samples collected and analyzed for specific alpha, beta and gamma-emitting radionuclides,
  • A comparison to theWVDP Phase 1 Decommissioning Plan Derived Concentration Guidelines
  • A dose assessment completed for the current land use, and
  • A conservative dose assessment using a reasonably foreseeable future land use scenario.
4. Define the boundaries of the study- The study focused on five areas identified through the aerial radiation survey, and land use information .
5. Develop the analytic approach - If the soil sampling data for cesium, gross alpha or gross beta are greater than two standard deviations above background, then a dose assessment is conducted .

If the dose assessment information from the various evaluation methods are below 25 mrem/year, then the 10 CFR 20.1402 criteria used for comparison purposes are met.

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas

5. Specify performance or acceptance criteria - Acceptance criteria developed for the aerial survey data are discussed in Section 3.1. The acceptance criteria developed for the field and soil sampling data are listed below.

Field Survey and Soil Sampling Data Acceptance Criteria The field survey and soil sampling acceptance criteria identified in the plan include :

a) Use of certified standards (e.g., National Institute of Standards and Technology) to calibrate and daily evaluate the operabil ity of instrumentation . The acceptance criteria for the instrumentation is specified in the applicable quality assurance documents for the field and laboratory instrumentation .

b) Quality control standards to ensure that the laboratory instrumentation maintained calibration during the sample analysis period . The frequency and acceptance criteria for the laboratory analyses is specified in the GEL Quality Assurance Plan, Rev. 29 (Ref. 15).

c) Field and laboratory duplicates were collected and analyzed at a frequency of 20 percent to ensure that the soil sampling and laboratory analys is methodologies w ere cons istent with the quality control parameters defined by the laboratory.

d) Multiple sample locations and soil depths sent for analysis to ensure that the soil concentration data was representative of the area

7. Optimizing the design for obtaining data - In order to optimize the design and obtain survey data that addresses the goal of this effort, sampling was conducted using multiple survey methods and data collection efforts in order to compare the dose values calculated for each area . These multiple survey and data collection efforts included :

a) Aerial radiation survey data of the entire area identified the five locations where follow-up activities were warranted .

b) Follow-up gamma walkovers and tissue equivalent surveys were completed for each area to determine if any elevated locations were within an area, and the dose rates at each location .

c) If any elevated locations were identified they were sampled and the remainder of the random sampling was conducted based on the size of the areas. Soil samples were collected from 0-100 cm, with at least two at-depth samples collected from each area.

d) All surface soil samples were sent for gross alpha, gross beta and gamma spectroscopy.

e) Next depth interval soil sample analysis were completed if the initial surface analysis were greater than background mean plus two standard deviations.

f) Detailed radionuclid e an alysis we re compl et ed fo r a min imum of 20 percent of each area.

g) Finally, dose assessments were conducted for all areas with dose rate read ings or soil sample results greater than two standard deviations above background . These assessments were compared to the 10 CFR20.1402 dose standard (25 mrem/year).

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 5.0 Field Survey and Sampling Strategy The following is a description of the equipment and general method s used to conduct field survey and sampling operations.

5.1 Instrumentation and Equipment Used Instrumentation and equ ipment used to collect direct radiation level measurements included:

  • Bicron " microRem " Survey Meters - These instruments mea sure gamma radiation exposure rates using a tissue equivalent detector. The manufacture r-stated accuracy for the Bicron instruments is 10 percent (for Cs-137) across the operating ranges that were used . The internal scintillation detector is tissue equivalent and provides a flat energy response over a broad gamma energy range .
  • Ludlum Model 2241-2 Scaler Ratemeter connected to a Ludlum Model 44-10 2" x2" Nal gamma detector - This instrument can collect count rates in Counts per Minute (CPM) or can .collect scaler (static) counts (the total number of counts in a designated counting time such as one minute) . The 44-10 Nal detector is nominally nine percent efficient for Cs-137, and exhibits a non-linear energy response (the Am-241 response, for example, is typically 30-40 times higher than the response to Cs -137).
  • Ludlum Model 2241-2 Scaler Ratemeter connected to a Ludlum Model 44-lO 2" x2" Nal gamma detector coupled to a Trimble GeoXT-GeoExplorer GPS instrument - This system allowed for the simultaneous collection and logging of CPM and GPS location . Under ideal conditions, the GPS unit can achieve sub-meter location precision . The actual precision varied depending on the number of available satellite signals and the slope of the terrain being surveyed.
  • Garmin GPSMAP 64s GPS - This GPS was used to determine the sample locations . This instrument can achieve a nominal five -meter precision. The actual precision varied depending on the number of available satellite signals and the slope of the terrain being surveyed .
  • National Institute of Standards and Technology (NIST) Traceable Thermometers - These thermometers were used to log temperatures at the beginning of a day's field operations, nominally at lunch time, and again at the conclusion of the day's operations when instrument operability and source checks (see Appendix E) were performed to verify that no substantive changes in instrument response occurred due to temperature changes . Checks were performed using both a NIST traceable Cs-137 source and a thorium check source .

All radiological detection equipment was calibrated within the last 12 months by an MJW Technical Services' NYSDOH-licensed calibration facility (Ref. 16), using NIST traceable Cs-137 calibration sources.

In addition, the field operability checks were performed typically three times per day as described above (see Appendix E).

Page 14 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 5.2 Overland GPS Walkover Gamma Surveys The first step taken by the survey team was to perform a GPS walkover gamma survey of the designated survey area. The survey team walked grid patterns across the survey area with the detector suspended close to the ground . To the extent practicable, the grid pattern extended slightly beyond the borders of the designated survey area . In some locations this was not possible because of unsafe terrain or obstructions .

After the data was collected , it was downloaded and transferred to a computer. The data consiste.d of the measured CPM and the GPS Coordinates. The data was overlaid onto maps as color-coded dots . The color of the dots corresponded with increments of CPM . For example, the count rate increments could be 0-5000 CPM, 5000-10,000 CPM, 10,000 to 15,000 CPM, etc. The count rate color coding increments were specific to each survey area . This allowed for the most sensitive graphic analysis for each particular area .

Once displayed graphically, the data was evaluated by the PM to determine if any locations in the map showed count rates that were higher than the rest of the map (elevated locations) . If elevated locations were discerned in a survey area, the PM would direct the sampling and survey team to collect at the elevated locations in addition to the random sample locations .

GPS walkover gamma surveys with the Ludlum/GPS units were not conducted in Area 1 or in the Confirmatory locations in the Cesium Prong inside the WNYNSC property boundary since the objective was to measure radiation levels and collect data at specific preselected locations.

5.3 Direct Radiation Measurements After the GPS Survey was completed and all sampling locations were identified, the survey team collected static direct radiation measurements at each sampling location before collecting samples .

Static radiation measurements consisted of:

  • Dose rate measurements using the Tissue Equivalent Bicron survey meter at elevations of one cm and 100 cm above the ground .
  • Two consecutive one-minute scaler counts using the Ludlum Scaler Ratemeter and 2" x2" Nal gamma detector, at the one and 100 cm elevations. No dose assessment was performed based on these readings.

5.4 Sample Collection Activities After the direct radiation measurements were completed, soil samples were collected in accordance with the Plan and associated Field Guides .

Page 15 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas For each sampling location, the number of samples to be collected and the increments of depth (e.g., 0-15 cm depth sample or a 15-30 cm depth sample) were predetermined in accordance with the Plan .

Excavation was performed and samples were collected using hand tools in order to carefully sample from the correct depths. Sampling equipment was thoroughly cleaned in between each depth to ensure against cross-contamination of samples . Field (split) duplicates were collected in accordance with the QAPP. Samples were placed in plastic sample bottles and labeled . Sample information was recorded on the sample bottles and on the field Chain-of-Custody Forms for transfer to a secure sample storage area to await shipment to the analytical laboratory. Equipment blanks and a sample of the deionized water used for instrument cleaning were also sent to the laboratory for quality control analysis . Appendix F provides a summary of all soil samples collected, including locations, depths, and type of laboratory analysis.

5.5 Radiochemical Analysis Most of the samples collected from each area were submitted for radiochemical analysis, while others were archived as specified in the Plan . A total of 641 samples were collected in the field, and 532 were submitted for analysis to GEL Laboratories, a NYSDOH -ELAP analytical laboratory.

All samples submitted for analysis were analyzed for gross alpha activity, beta activity, and by gamma spectroscopy. Some samples also underwent additional isotopic analysis. Appendix C provides further detail regarding the analyses including the isotopes, analytical method, and Minimum Detectable Concentrations. As noted above, Quality Control samples, including field duplicates, equipment (rinsate) blanks, and deionized water were also collected and analyzed.

Analytical data was provided by the laboratory with two standard deviation precision . All analytical data underwent Level IV data validation in accordance with the Evaluation of Radiochemical Data Usability

{Ref. 5) and all data were determined to be usable. Appendix G provides the laboratory Certificates of Analysis.

In Areas 1, 2, 3, 4, and 5 the surface samples were all analyzed and the gross alpha, gross beta and Cs-137 concentrations were compared to the background concentrations (refer to Section 6.1 for information related to determination of background) . For each surface sample, the gross alpha, gross beta and Cs-137 concentration was compared to the background screening level (background plus two standard deviations), and if it exceeded the screening level, the next depth sample from that location was submitted for analysis.

6.0 Dose Assessment Approach The strategy and approach to assess potential radiation doses included the following elements :

  • Assessment of dose based upon the Aerial Survey data .
  • Assessment of dose based on the tissue equivalent dose rate measurements.

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas

  • Assessment of dose based on soil concentrations using the RESRAD OFFSITE 3.1 computer code (Ref.
6) with input parameters adjusted to meet current land use based on land use survey forms (i.e.,

Recreational Hiker/Hunter, Resident Homemaker, Resident Farmer). Appendix H provides key RESRAD information and data .

  • Comparison of the surface soil concentrations to the surface soil decay-corrected DCGLw Peak-of-the-Mean values of the WVDP Phase 1 Decommissioning Plan . The peak-of-the mean values are the most conservative DCGLwvalues provided in the Phase 1 WVDP Decommissioning Plan and are for a resident farmer scenario.

Table 2. DCGLw Peak-of-the-Mean Values, Rev. 2 for 25 mrem/year (pCi/g)! 1 l Nuclide Surface Soil Am -241 2.9E+01 C-14 1.6E+01 Cm-243 3.SE+Ol Cm-244 6.SE+Ol Cs-137!2! 1.SE+Ol 1-1 29 3.3E-01 Np-237 2.6E-01 Pu-238 4.0E+Ol Pu -239 2.SE+Ol Pu -240 2.6E+01 Pu-241 1.2E+03 Sr-90!2! 4.lE+OO Tc-99 2.1E+01 U-232 1.SE+OO U-233 8.3E+OO U-234 8.4E+OO U-235 3.SE+OO U-238 9.8E+OO (1) The DCGLw is the DCGL applicable to the average concentration over the survey unit.

(2) WVDP Phase 1 DP DCGLs for Sr-90 and Cs-137 are based on an assumption of immediate free release w ith no hold time for decay.

  • Assessment of dose based on soil concentrations using the RESRAD 7.0 computer code (Ref. 7, Appendix H) with input parameters adjusted to account for potential future use scenarios .

Appendix H provides key RESRAD information and data .

  • Assessment of dose associated with the consumption of fish. Calculations were performed using the average concentration of Sr-90 and Cs -137 in the edible portion of fish above background from the ASER (Ref. 8). Annual exposures were calculated based on ingestion dose coefficients from the ICRP (Ref. 9) .

For the current land use RESRAD calculations using the soil analytical results, Area 1 was assessed using a " Resident Homemaker" scenario, Area 2 was assessed using a " Recreational Hiker" scenario (with hunting), and Area 3 was assessed using a " Resident Farmer scenario (for Area 3 livestock grazing and Page 17 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas feed corn crop cultivation was assumed). For Areas 4 and 5, which are located on the Cattaraugus Territory of SNI, culturally specific aspects of land use are being developed . This report will be revised to include the modeled dose assessments for Areas 4 and 5 once the culturally specific aspects of land use are finalized .

For the conservative reasonably foreseeable land use evaluation, all areas were assessed using a*

" Resident Farmer" scenario with livestock and crop cultivation for consumption . The only exception was Area 2.1, where the deeply sloped terrain and extremely small size are not suitable to support a resident farmer land use scenario. As such, the only reasonably fore seeable land use for Area 2.1 was a

" Recreat ional Hiker (w ith hu nt ing), which is the same scenario as the current land us e.

Dose Assessments based upon soil concentrations were performed using the conservative assumptions that gross beta activity in excess of background was attributable to Sr-90, and that gross alpha concentrations, in excess of background, was attributable to either Am-241 or Pu -239 (separate calculat ions).

6.1 Background Radiation and Radionuclide Determinations In order to assess potential radiation exposures in excess of background, it was necessary to determine background levels for all locations surveyed . This included background soil concentrations for Cs-137, gross beta, and gross alpha activity. In addition, it was necessary to determine instrument backgrounds for the tissue equivalent survey meters that were used to measure direct exposure rates . Two separate background data sets were developed :

  • One set of background measurements was conducted for comparison to dose rates and soil concentrations from Areas 1, 2, and 3, and the Confirmatory locations on the WNYNSC property.

This location is designated as "WNYNSC Background ." The initial intent as specified in the Plan was to use the existing background determinations from a 2014 WVDP Terrestrial Background Study {Ref. 17). However, the DOE Background Study did not include gross alpha or gross beta soil concentrations, so it was necessary to obtain new background data as part of the current study. Ten locations were surveyed and sampled from within the two reference background areas identified in the 2014 DOE Background Study.

  • A second background data set obtained for Areas 4 and 5 (SNI Background). Within this data set, two subsets of data were developed : one using data collected from the floodplain of Cattaraugus Creek for application to Area 4, and one using data collected from areas not on the floodplain for application to Area 5.

In order to account for the measurements uncertainty in a calculated average, a weighted mean was used to combine any set of similar data into a single average and its combined uncertainty. A weighted mean is used instead of standard average when the data do not all have the same level of precision.

Therefore, a weighted mean was used to calculate the average external dose rates taken at a given distance and the average soil concentrations for the given depth . The equations to calculate a weighted mean for a given depth and its associated standard deviation (one sigma) are shown below:

Page 18 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas L ~i weighti x concentrationi Weighted mean for a given depth= --"-=:...---'--'-------

L ~ i weighti

. 1 weight . = - - - - - - - - - - - - - - - - - - - - - -

1 (standard deviation, 1 sigma, of the concentration) i 1

Stan dar d deviation of the weig hted m ean =

6.1.1 WNYNSC Background Determination Two areas on the WNYNSC property that had previously been established as reference background areas in the 2014 DOE Background Study were sampled and surveyed . For purposes of this study, they are refe rred to as Background Area 1 and Background Area 2. Instrument readings and soil samples were collected from five locations in each of the two areas. Instrument readings were collected in a manner identical to the field readings collected in each survey area (i .e., readings using the tissue equivalent Bicron Instrument and the Ludlum Instrument with 2"x2" Nal detector at elevations of one cm and one meter) . Sample depth increments were 0-15 cm, 15-30 cm , 30-60 m, and 60-100 cm. In each of the two areas a total of 12 samples were collected and analyzed including five samples from 0-15 cm, 5 samples from 15-30 cm, one sample from 30-60 cm, and one sample from 60-100 cm.

Figure 7 shows the location of the two background areas designated Background Area 1 (BGAl) and Background Area 2 (BGAl) .

Figure 7. General Locations of Background Areas General Location Background An?as 1 and 2

  • Legend Sample Location

\ '

)

I

\

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figures 8 and 9 provide closer views of each area including sample location points.

Figure 8. Background Area 1 Sample Locations Figure 9. Background Area 2 Sample Locations Page 20 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas WNYNSC Survey Background Readings Figures 10 and 11 below are maps extracted from the Aerial Survey data to which the locations for Background Areas 1 and 2 have been added . The dose rates at an elevation of one meter as derived from the map are presented in Table 3. The Aerial Survey states that the contribution to dose from cosmic rays and airborne radon across the entire map is 4.8 µ R/hour.

Figure 10. WNYNSC Background Area 1 location on the 2014 Aerial Radiological Survey Exposure Rate micro R per hour LJ 0-1 0 0-2 CJ 2-3 LJ 3-4 L J 4-5 5-6

- S-7

- . BGA1 9

- 7-8 c::i

- 9-10

- 10-20 fim 20-100 100-200 200-430 Sampling Location WNYNSC Page 21of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 11. WNYNSC Background Area 2 Location on the 2014 Aerial Radiological Survey Exposure Rate 3-4 4-5

~

-- 87--98 6-7

. BGA2

- 9-10

- 10-20

- 20-lOO 100-200 200-430

  • satnplln9 Location WNYNSC Table 3. WNYNSC Background Area Dose Rates Based Upon 2014 Aerial Survey Data Dose Rate Range Average Dose Cosmic + Radon Total Dose Average Location from Map Rate Dose Rate Rate Dose Rate

(µR/hour) (µR/hour) (µR/hour) (µR/hour) (µR/hour)

Area 1 3-4 3.5 4.8 8.3 8.3 Area 2 3-4 3.5 4.8 8.3 WNYNSC Nal Detector Background Reading~

The background area static readings using the 2" x2" Nal detector were averaged between two counts at each location and ranged from 6146 CPM to 6781 CPM at the 100 cm elevation . The average across all locations was 6333 CPM .

All background area Nal detector data is provided in Appendix H32.

WNYNSC Bicron Instrument Background Calculation The average dose rates measured using the Bicron tissue equivalent survey meters were calculated at one and 100 cm elevations. A "screening" value for comparison to the data from Areas 1, 2 and 3, and Page 22 of 102

Radiological Survey and Dose-Assessment Report for the WNYNSC and Off-Site Areas the Confirmatory locations on the WNYNSC property was calculated based on the average of the readings plus two standard deviations. The results were as follows:

Average Background Bicron Instrument Reading (+/- 1 sigma)

  • 3.69 +/- 0.12 µrem/hour at the 100 cm elevation Background Bicron Reading Based Screening Level (Average + 2 sigma)
  • 3.93 µrem/hour at the 100 cm elevation WNYNSC Background Soil Concentrations Table 4 below provides the average WNYNSC background soil concentrations at each depth :

Table 4. WNYNSC Background Soil Concentrations Depth Alpha* Beta* Cesium*

(cm) (pCi/g) (pCi/g) (pCi/g) 0-15 l.2E+Ol +/- 5.6E-01 2.3E+Ol +/- 4.9E-01 2.9E-01 +/- l.3E-02 15-30 l.lE+Ol +/- 5.3E-01 2.0E+Ol +/- 4.5E-01 l.lE-01 +/- l.OE-02 30-60 l.4E+Ol +/- l.2E+OO 2.4E+Ol +/- l.OE+OO O.OE-00 +/- l.7E-02 60-100 l.4E+Ol +/- l.2E+OO 2.8E+Ol +/- l.lE+OO l.lE-01 +/- l.9E-02

  • Uncertainty is reported+/- 1 sigma 6.1.2 Seneca Nation of Indians (SNI) Background Determination Ten background locations on the Cattaraugus Territory of the Seneca Nation of Indians were surveyed and sampled . Five locations were in the floodplain of Cattaraugus Creek (Locations 19, 20, 21, 22, and 24), while the remaining locations (18, 23, 25, 26, and 27) were not in the floodplain . Figure 12 provides

- a map of these locations.

Instrument readings and soil samples were collected from the ten specified locations. Instrument readings were collected in the same manner as performed in all other areas (i.e ., readings using the Bicron tissue equivalent survey meter, and the Ludlum Instrument with 2" x2" Nal detector, at elevations of 1and100 cm). Sample depth increments were 0-15 cm, 15-30 cm, 30-60 cm, and 60-100 cm.

Page 23 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 12. SNI Background Locations Sampling Locations Seneca Nation of Indians Cattaraugus Territory B-189

- 2014Areas Meeting Criteria for Further Evaluation e Saci<ground Sample Locations Survey an-7

. SHIS21 9--10 10-20 20-100 100-200 SN1820.

SNfES24 200-430

  • Sample Location Cattaraugus Territay Table 5. SNI Background Floodplain Area Dose Rates Based Upon 2014 Aerial Survey Data Dose Rate Range Average Dose Cosmic + Radon Total Dose Average Location from Map Rate Dose Rate Rate Dose Rate

(µR/hour) (µR/hour) (µR/hour) (µR/hour) (µR/hour)

SNIB 19 4-5 4.5 4.8 9.3 SNIB 20 3-4 3.5 4.8 8.3 SNIB 21 4-5 4.5 4.8 9.3 8.9 SNIB 22 4-5 4.5 4.8 9.3 SNIB 24 3-4 3.5 4.8 8.3 Page 25 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 14. SNI Background Non-Floodplain Locations on the 2014 Aerial Radiological Survey a::

l/)

  • SNIB 25 3-4

~

4-5 E

(!)

5-6

~

m s.1 0 ll . SNIB 26 9

7-8 9-10 c:

. SNIB27

- 10-20

- 20-100

! m 100-200 200-430 SNl823 .

Cattaraugus ierritoty Table 6. SNI Background Non-Floodplain Area Dose Rates Based Upon 2014 Aerial Survey Data Dose Rate Average Dose Cosmic + Radon Average Range from Total Dose Rate Location Rate Dose Rate Dose Rate Map (µR/hour)

(µR/hour) (µR/hour) (µR/hour)

(µR/hour)

SNIB 18 3-4 3.5 4.8 8.3 SNIB 23 2-3 2.5 4.8 7.3 SNIB 25* n/a n/a n/a n/a 7.8 SNIB 26* n/a n/a n/a n/a SNIB 27* n/a n/a n/a n/a

  • Locations outside of aerial survey.

SNI Nal Detector Background Readings The background readings in the SNI Background floodplain locations at the 100 cm elevation ranged from 6512 CPM to 8864 CPM and averaged 7943 CPM . This background is applicable to the Areas 4.1 through 4.5.

The background readings in the SNI Background non-floodplain locations at the 100 cm elevation ranged from 7022 CPM to 12270 CPM and averaged 8745 CPM . This background is applicable to Areas 5.1 through 5.6.

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas SNI Bicron Instrument Background Calculation The average dose rates measured using the tissue equivalent survey meters were calculated at the one and 100 cm elevations . A "screening" value for comparison to the data from Areas 4 and 5 was calculated based on the average of the readings plus two standard deviations . The results were as follows:

SNI Average Background Bicron Instrument Readings Floodplain Locations (+/- 1 sigma):

  • 4.96 +/- 0.22 wem/hour at the 100 cm elevation Non-Floodplain Locations(+/- 1 sigma):
  • 4.40 +/- 0.21 µrem/hour at the 100 cm elevation SNI Background Bicron Reading Based Screening Level (Avg+2 sigma)

Floodplain Locations:

  • 5.41 µrem/hour at the 100 cm elevation Non-Floodplain Locations:
  • 4.81 µrem/hour at the 100 cm elevation SNI Background Soil Concentration Calculations Thirty-nine samples from 10 locations we re collected to determ ine background for Areas 4 and 5, which are located on the SNI. Soil concentration calculations will be provided in the revised version of this report.

7.0 Survey, Sampling and Dose Assessment Results 7.1 Area 1 7.1.1 Description of Area 1 Area 1 encompasses an area outside the boundaries of the WNYNSC that has been previously characte rize d as th e " Ces iu m Prong." It largely co nsists of resi dential prope rt ies t o the north and west of the Center boundary (see pg. 6, Figure 1).

Three locations were surveyed and sampled for comparison to data from the Off-Site Investigation Report (Ref. 10). Sample Locations 1.1 and 1.2 are in a residential area and located within 350 feet of each other in a wooded lot behind a residence . Sample Location 1.3 was located on the edge of an open Pa ge 27 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas field along a tree line. This area is not currently being used for farming or industrial purposes but could be used for recreation includ ing hunting.

7.1.2 Survey and Sampling Methodology for Area 1 No GPS survey was performed in Area 1 since the objective was to survey and sample at three predetermined locations in order to compare current soil radioactivity concentrations to those measured in the 1995 investigation .

To allow comparison , the survey and sampling locations were selected to coincide with locations previously sampled . Locations 1.1and1.2 were in proximity to the location identified as " L12" in the 1995 report (note the sample data presented in the 1995 Report were for samples collected in 1994).

Location 1.3 was in proximity to the location identified as " L23" in the 1995 report . Since GPS locations for the L12 and L23 locations are not precisely known (due to technology limitations at the time), the correlation between current and former locations was only approximate .

Direct radiation readings and soil samples were collected in the three locations as described above and in Table 3 of the Plan .

Each location was surveyed and sampled as follows :

  • Dose rate readings were collected at one and 100 cm from the ground surface using the tissue equivalent dose rate meter.
  • Static 2" x 2" Nal detector readings were collected at one and 100 cm from the ground surface using the Ludlum Model 2241-2 survey meter coupled to a Ludlum Model 44-10 detector. Two, one-minute scaler counts were collected at one and 100 cm elevations .
  • A total of nine soil samples were collected at each of the three soil depth intervals; Oto 5 cm, 5-15 cm and 15-30 cm .

7.1.3 Survey and Sampling Results for Area 1 As noted above, no GPS survey was required for Area 1 since the goal was to compare current to past soil concentration data .

Static 2"x2" Nal Detector Gross Readings at the 100 cm Elevation

  • The Area 1 static readings using the 2" x2" Nal detector were averaged between two counts at each location and ranged from 7607 CPM to 8361 CPM . The average across all locations was 7876 CPM .
  • The applicable background count rate for Area 1 was determined to be 6333 CPM.

A tabulation of the static count rates is provided in Appendix H32 .

  • I Page 28 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Tissue Equivalent Survey Meter Readings Table 7 provides the tissue equivalent dose rate readings (including background) for each sample location .

Table 7. Area 1 Tissue Equivalent Dose Rate Instrument Gross Readings Dose Rate at 100 cm Sample Location

(µrem/hour) 1.1 4 1.2 5 1.3 6 Soil Sample Comparison to Background Six soil samples from the 0-5 and 5-15 cm depths were analyzed by gamma spectroscopy and for gross alpha and gross beta activity. Due to the proximity in geographic location, the soil concentration values for Locations 1.1 and 1.2 were averaged together for data comparison and dose assessment purposes.

The weighted average soil concentrations for gross alpha, gross beta and Cs-137 results associated with the 0-15 cm depth are summarized in Table 8. In this study, the Area 1 samples were collected at depths of 0-5 cm and 5-15 cm, while the background samples were collected at 0-15 cm and 15-30 cm depths.

Therefore, a weighted average for the 0-15 cm Area 1 depth was calculated as follows in order to compare the soil concentration to an equivalent background depth .

The individual soil concentrations including background for Area 1, associated with multiple independent depths were combined into a single average soil concentration over a single depth . The weight given to any single layer was based on the thickness of each individual stratum as compared to the overall thickness of the combined layer. This is shown in the following equations below :

thicknessi weighti =- - -.- - -

00 L j=l thicknessj co Weighted average over multiple depths= L i=l weighti x concentrationi Page 29 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 8. Area 1 Weighted Average Soil Concentrations Depth Gross Alpha" Gross Beta* Cesium-137" Location

{cm) {pCi/g) (pCi/g) {pCi/g) l.1/l.2(L12b) 0-15 8.6E+OO +/- 7.9E-01 l.9E+01+/-7.7E-01 l.1E+OO +/- 4.lE-02 l.3(L23c) 0-15 l.OE+Ol +/- l.3E+OO 2.3E+01 +/- l.2E+OO 4.6E-01 +/- 5.6E-02

a. Uncertainty is reported+/- 1 sigma.
b. Locations 1.1 and 1.2 were combined and compared to the sample collected at the location associated with the L12 de scribed in the 1995 Report.

C. Location 1.3 was compared to the sample collected at the location associated with the L23 described in the 1995 Report.

The weighted average gross alpha and gross beta concentrations were less than background soil concentrations provided in Section 6.1 and therefore no further analysis was performed related to the gross alpha and gross beta data. The Cs-137 soil concentrations were above the background soil concentrations provided in Section 6.1; therefore, they were compared to the decay corrected 1995 data as described below.

Comparison of Soil Sample Concentrations to Decay Corrected 1995 Report Concentrations The Cs-137 soil concentrations values from the 1995 report, plus 10 percent were adjusted for decay (activity on the date of the sample analysis would be 61.8 percent of the 1994 activity), and compared to the two standard deviation concentration range for the corresponding 2014 samples as shown in Table

9. The samples collected in 1994 were collected at a depth of 0-10 cm and therefore, the weighted averages in Table 8 were recalculated (using the same formula as above) for a depth of 0-10 cm in order to make a comparison at equivalent depths (see Table 9) .

Table 9. Area 1 Cesium-137 Soil Concentrations Comparison 1994 Sample 1994 Sample Result Decay 2015 Sample 1994 2015 Depth Result Corrected Plus 10% Result Location location {cm)

(pCi/g) {pCi/g) {pCi/g)

L12 i.1 I i.2 0-10 l.6E+OO l.1E+OO l.5E+OO L23 1.3 0-10 3.4E-01 2.3E-01 4.4E-01 The current soil concentrations were not less than the decay corrected data plus 10 percent. Some possible factors that could explain this difference include :

  • The weighted average calculated from the 2015 samples is assumed to be homogeneous with in each layer sampled . Since this is not true, the weighted average would be biased high . For instance, based on a review of the 1995 WNYNSC Off-Site Radiation Investigation Report, the majority of the activity is primarily in the first one or two cm, then the resultant weighted average decreases to nearly the same concentration as the prior results corrected for decay.
  • Since the current sampling locations were only approximate to the former sampling locations, the difference could be the result of variations in the ground deposition patterns .
  • Poss ible migration of activity from natural environmental influences such as wind, rain, etc.

Page 30 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Since the current results were not less than the 1994 values plus 10 percent corrected for decay, the current soil concentrations, net of background, were used to perform a dose assessment for Area 1 as described in Section 7.1.4 (see Table 10).

Table 10. Area 1 Net Average Soil Concentrations Depth Gross Alpha" Gross Beta* Cesium-137" location (cm) (pCi/g) (pCi/g) (pCi/g) 1.1/1.2{L12*) 0-100 O.OE+OO O.OE+OO 7.9E -01 1.3(L23b) 0-100 O.OE+OO 7 .OE-03 1.7E-01

a. Locations 1.1and 1.2 were co mb ined an d compared to t he sa mple collected at t he locat ion associated wit h th e L12 described in t he 1995 Rep o rt.
b. Location 1.3 was compared to th e sample collected at th e locat ion associated with th e L23 described in th e 1995 Report.

The individual sample numbers, depths, concentrations, uncertainties, and minimum detectable levels (MDLs) are provided in Appendix H2.

7.1.4 Dose Assessment Approach for Area 1 The dose assessment approach for Area 1 was to:

  • Develop an estimate of annual exposure based upon the 2014 Aerial Survey.
  • Develop an estimate of annual exposure based upon the tissue equivalent meter readings .
  • Perform an assessment based on the current land use Resident Homemaker scenario to determine the exposure in excess of background using current and appropriate parameters (e.g., hydrology, occupancy and consumption). Parameters were adjusted based on published references for the region or historical site specific data . Calculations were performed using the weighted mean above background for the data analyzed.

Dose assessments associated with soil data were performed using the RESRAD-OFFSITE 3.1 computer code. Hydrology data for the contaminated, unsaturated, and saturated zones were based on Revision 2 of the Phase 1 Decommissioning Plan for the West Valley Demonstration Project. The RESRAD input parameters used that differed from the RESRAD defaults are summarized in Appendix H3 . In cases where area specific scenarios were not consistent with assumptions used in the Decommissioning Plan, modifications are described below and in Appendix H3 . This would include, but are not limited to, exposure pathways, irrigation, consumption, erosion rates, and occupancy times. For parameters where there were no site-specific data or there was no corresponding Decommissioning Plan value, the RESRAD-OFFSITE default parameters were used .

The Area 1 dose assessment was based on a resident homemaker. The resident is assumed to spend eight hou rs sleeping and another eight hours working inside the dwelling. Of the remaining eight hours, 50 percent is assumed to be spent inside the dwelling (bringing total time in the dwelling to 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />) and 50 percent is assumed to be spent outside in the elevated area (bringing the total time spent outside the dwelling to four hours) . It is assumed that this resident homemaker also Page 31of102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas hunts deer and consumes the deer meat. No plant, fish, or dairy cattle milk is consumed from this area . The res ident homemaker's dwelling is located on -site and within the area assessed .

In addition, no irrigation was assumed for any part of Area 1. The evapotranspiration coefficient provided in the Decommissioning Plan was recalculated to maintain the same infiltration rate of 0.26 meters per year. The soil erodibility factor, which is used to calculate the erosion rate, was set to the maximum value ofthe default range (0 to 0.5) in the User Manual for RESRAD-OFFSITE 3.1 (Ref. 6) . Th is will allow transport of elevated concentrations from these areas to the surface water and subsequently ingested by the deer, whi ch is then consumed by the resident homemaker.

  • The sample results were compared to the DCGLw concentrations established in the Phase 1 Decommissioning Plan for the WVDP . The peak-of-the-mean values are the most conservative DCGLw values provided in the Phase 1 WVDP Decommissioning Plan and are for a resident farmer scenario.
  • Perform an assessment based on a conservative potential use scenario of a Resident Farmer' s exposure to determine the exposure in excess of background using current and appropriate parameters (e.g., hydrology, occupancy and consumption) . Parameters were adjusted based on published references for the region or historical site specific data. Calculations were performed using the weighted mean above background for the data analyzed . Dose assessments associated with soil data were performed using the RESRAD 7.0 computer code . RESRAD input parameters were based on Revision 2 of the Phase 1 Decommissioning Plan for the West Valley Demonstration Project Appendix C. The RESRAD input parameters are summarized in Appendix H33.
  • Perform an assessment based on consumption of fish caught from the Cattaraugus Creek. Current land use surveys indicate that in Areas 1, 2, and 3, no consumption of fish occurs. Calculations were performed using the average concentration of Sr-90 and Cs-137 in the edible portion of fish above background from the ASER (Ref. 8) . Annual exposures were calculated based on ingestion dose coefficients from the ICRP (Ref. 9) .

7.1.S Dose Assessment Results for Area i Dose estimate based upon 2014 WNYNSC Aerial Survey Data Figure 15 below is an aerial radiological survey map extracted from the Aerial Survey data to which the locations for Areas 1.1, 1.2, and 1.3 have been added . The dose rates at an elevation of 100 cm as derived from the map were determined to be 2-3 (µR/hour) for Area 1.1 and 3-4 (µ R/hour) for Areas 1.2 and 1.3 . The Aerial Survey states that the contribution to dose from cosmic rays and airborne radon across the entire map is 4.8 µR/hour.

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 15. Area 1 Locations on t he 2014 W NYNSC Aerial Radi ological Survey Exposure Rate micro R per hour LJ 0-1 c::J 0-2 0 2-3 3-4

  • SUB-AREA 1.1 4-5

~

  • SUB-AREA 1.2 m s..1 8 "'

-- 9-10&-9 0

- 10-20

- 20-100 100-200 200-430

  • sampling LocatlOl\

WNYNSC SUB-AREA 1.3 .

Based on this aerial map and the assumed cosmic and airborne radon contribution, the dose rates were determ ined for Area 1 as shown in Table 11. Consistent w ith the methodologies of the Aerial Survey, a value of 4.8 was added to all readings derived from Figure 15 to account for the contribution to background from cosm ic radiation and airborne radon .

Table 11. Area 1 Dose Rates Based Upon 2014 Aerial Survey Data Dose Rate Average Dose Cosmic + Radon Total Dose Range from Location Rate Dose Rate Rate Map

(µR/hour) (µR/hour) (µR/hour)

(µR/hour)

Sub-Area L12 2-3 2.5 4.8 7.3

{l.1+1.2) 3-4 3.5 4.8 8.3 Sub-Area L23 3-4 3.5 4.8 8.3

{1.3)

The average background dose rate based on the WNYNSC Aerial Survey w as 8.3 ~LR/ho u r at 100 cm above the ground . This was subtracted from the total doses rate in Table 11, and based an average occupancy time of 365 days per year, the calculated doses for Area 1 are provided in Table 12.

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 12 Area 1 Calculated Doses Based on 2014 WNYNSC Aerial Radiological Survey Total Background Annual Occupancy Location Dose Rate Dose Rate Tim eh

(µR/hour) (µR/hour) (hours/year)

Sub-Area L12 7.8c 8.3 8670 Sub-Area L23 8.3 8.3 8670 0.0

a. The aerial survey dose rates were recorded in units of Roentgen . The quality factors for photons and electrons are both one; therefore 1 R equals 0.877 rem .
b. Occupancy hours are divided into 83.3 percent Indoors and 16.7 percent Outdoors; a 0.273 gamma shielding fraction is applied to the time indoors.
c. Average of Sub-Areas 1.1 and 1.2.

Dose Estimate Based on Tissue Equivalent Survey Meter Readings All three survey locations exhibited dose rates in excess of background at the 100 cm elevation . The average dose rate for Sub ~Area L12 was 4.4 +/- 0.3 µrem/hour at 100 cm (+/- 1 sigma) . The average dose rate for Sub-Area L23 was 6 +/- 0.6 µrem/hour at 100 cm (+/- 1 sigma). The dose rate net of background in Sub-Area L12 and L23 respectively was 0.7 and 2.3 µrem/hour at 100 cm . As a result, the annual estimated dose at these locations based on 8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br /> (the occupancy hours derived from the RESRAD Scenario for Area 1) of which 83 .3 percent of the time is spent indoors (with a 0.273 gamma shielding fraction) and 16. 7% of the time is spent outdoors, is 2.4 mrem and 8.0 mrem per year, respectively.

Current Use RESRAD Dose Assessment Based Upon Soil Concentrations Assuming a Resident Homemaker Scenario Sub-Area L12 Sub-Area L12 was defined as a 69,600-square-meter piece of property (see Figure 16). The deer associated with Sub-Area L12 are assumed to stay within the boundaries of the road . This results in a deer pasture area of about 1,062,100 square meters . In addition, the creek bed to the north of the elevated area is assumed to provide the drinking water resources for the deer. The creek is assumed to be about 50 meters wide and averages about one-meter deep over the course of the year.

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 16. Sub-Area L12 Soil samples for Sub-Area L12 from Locations 1.1and1.2 were analyzed for the first 15 cm of soil.

Therefore, the assumption was made that the entire first meter of soil was the same average soil concentrations as the first 15 cm.

The exposure to a resident homemaker in Sub-Area L12 that also consumed deer meat is provided in Table 13. The RESRAD input parameters are provided in Appendix H3 .

Table 13. Sub-Area L12 Current Use Pathway Doses Ground Inhalation Meat Soil Total (mrem/year) (mrem/year) (mrem/year) (mrem/year) (mrem/year) 1.02E-OO 6.34E-07 2.94E -03 7.14E-04 1.02E-OO The main source of exposure is direct external from the ground . This accounted for over 99 percent of th e overa ll exposure . The full RESRAD output file is provided in Appendix H8 .

Sub-Area L23 Sub-Area L23 was defined as a 130,760-square-meter piece of property (Figure 17) . The deer associated with Sub-Area L23 are assumed to stay within the boundaries of the creek and the road. This results in a Page 35 of 102

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas deer pasture area of about 1,330,000 square meters. In addition, the pond area to the south of the elevated area is assumed to provide the drinking water resources for the deer. The pond is estimated to be about 18,252 square meters and averages about one-meter deep over the course of the year.

Figure 17. Sub-Area L23 Soil sample for Sub-Area L23 from Locations 1.3 was analyzed for the first 15 cm of soil. Therefore, the assumption was made that the entire first meter of soil was the same average soil concentrations as the first 15 cm .

The exposure to a resident homemaker in Sub-Area L23 that also consumed deer meat is provided in Table 14. The RESRAD input parameters are provided in Appendix H3 .

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 14. Sub-Area L23 Current Use Pathway Doses Ground Inhalation Meat Soil Total (mrem/year) (mrem/year) . (mrem/year) (mrem/year) (mrem/year) 2.19E-01 3.86E-07 1.34E-03 1.72E-04 2.21E-01 The main source of exposure is direct external from the ground . This accounted for over 99 percent of the overall exposure. The full RESRAD output file is provided in Appendix H9.

Comparison to the WVDP Phase 1 Decommissioning Plan DCGLw Values for Area 1 Table 15 provides a comparison of the Area 1 soil concentrations to the WVDP Phase 1 Decommissioning Plan DCGLw Values .

Table 15. Area 1 Comparison to WVDP Phase 1 Decommissioning Plan DCGLw Measurement Nuclide WVDP DCGL Net Soil Concentrations (pCi/g) Comparison Type Used (pCi/g) L12 L23 L12 L23 Alpha Pu-239 2.SOE+Ol O.OE+OO O.OE+OO Below Below Beta Sr-90 4.lOE+OO O.OE+OO 7.0E-03 Below Below Cesium Cs-137 1.SOE+Ol 1.7E+OO 1.7E-01 Below Below Sum of the Fractions: Below Below The assessment of the gross alpha and beta based on the most conservative isotopes (Pu-239 and Sr-90, respectively) will account for all of the anthropogenic nuclides listed in Table 2 except for C-14, 1-129, and Tc-99. For these radionuclides, a qualitative analysis was performed . In all cases for these three radionuclides, either the soil concentration was below the detection limit or the soil concentration detected was significantly less than the Phase 1 Decommissioning Plan DCGLw Values. In addition, an analysis of the isotopic data indicates that the radionuclides that account for most of the gross alpha and beta soil concentrations are radionuclides that are considered NORM (e.g., natural uranium, natural thorium, and potassium-40.

Therefore, the use of the DCGLs based on the WVDP Phase 1 Decommissioning Plan resident farmer

  • scenario and gross results assuming the most conservative nuclides result in a highly conservative comparison.

Conservative Potential Use RESRAD Dose Assessment Based Upon Soil Concentrations Assuming a Resident Farmer Scenario Sub-Area L12 Sub-Area L12 was defined as a 69,600-square-meter piece of property (see Figure 16). This assessment is based on a resident farmer scenario. It is assumed that the farmer's dwelling, crop fields, and pasture lands resides in the elevated area . In addition, the crop that is grown is consumed by the farmer. The farmer also maintains and consumes both dairy and meat from the cattle. The annual exposure for Sub-Area L12 is provided in Table 16. The RESRAD input parameters are provided in Appendix H33 .

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 16. Sub-Area L12 Potential Use Pathway Doses Ground Inhalation Plant Meat Milk Soil Total (mrem/year) (mrem/year) (mrem/year) (mrem/year) (mrem/year) (mrem/year) (mrem/year) l.llE+OO 5.SSE-07 2.08E-01 l.21E-01 2.23E-01 6.SOE-04 l.66E+OO The full RESRAD output file is provided in Appendix H34.

Sub-Area L23 Sub-Area L23 was defined as a 130,760-square-meter piece of property (Figu re 17). This assessment is based on a resident farmer scenario. It is assumed that the farmer' s dwell ing, crop fields, and pasture lands resides in the elevated area. In addition, the crop that is grown is consumed by the farmer. The farmer also maintains and consumes both dairy and meat from the cattle . The annual exposure for Sub-Area L23 is provided in Table 17. The RESRAD input parameters are provided in Appendix H33 .

Table 17. Sub-Area L23 Potential Use Pathway Doses Ground Inhalation Plant Meat Milk Soil Total (mrem/year) (mrem/year) (mrem/year) (mrem/year) (mrem/year) (mrem/year) (mrem/year) 2.40E -01 3.38E -07 8.60E -02 3.07E-02 5.74E-02 l.56E-04 4.14E-01 The full RESRAD output file is provided in Appendix H35.

Dose Assessment for Consumption of Fish Based Upon 2012 WVDP Annual Site Environmental Report The ASER (Ref. 8) provides rad iological concentrations of strontium and cesium in the edible portion of the fish in Cattaraugus Creek. Biological data from these locations are provided . Hog-nosed Sucker and White Sucker are sampled from above the Springville Dam, and Steelhead Trout are sampled from below the Springville Dam . Brown Trout, White Sucker, Bullhead, and Hog-nosed Sucker were also sampled at a background location . This data is provided in Appendix H41. The average radiological concentrations of strontium and cesium in the edible portion of the fish for the two areas around Springville Dam and the background area are provided in Tables 18 and 19 below.

Table 18. Concentrations in Edible Portions of Fish around Springville Dam Isotope Average 1 Sigma Units Sr-90 1.40E-08 l.16E-09 µCi/g - wet Cs-137 5.46E-08 l.31E-08 µCi/g - wet Page 38 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 19. Background Concentrations in Edible Portions of Fish Isotope Average 1 Sigma Units Sr-90 l.02E-08 l.77E-09 µCi/g - wet Cs-137 4.75E-08 4.00E-08 µCi/g -wet This results in a net above background concentration in the edible portions of the fish of 3.74E-09 µCi Sr-90 per gram offish flesh and 7.08E-09 µCi Cs-137 per gram offish flesh . The ingestion dose coefficients factor (DCF) and the fraction of an ingested element directly absorbed to body fluids (fl) from ICRP 68 are provided in Table 20.

Table 20. Ingestion dose coefficients (mrem / µCi) from ICRP 68 Isotope fl* DCF Units Sr-90 0.3 l.04E+02 mrem/µCi Ingestion Sr-90 0.01 l.OOE+Ol mrem/µCi Ingestion Cs -137 1 4.81E+Ol mrem/µCi Ingestion

  • fl - Fractional absorption in the Gastrointestinal tract rate .

EPA's Exposure Factors Handbook (Ref. 18) indicates that the 95th percentile offish consumption by recreational anglers is about nine kg of fish per year. This results in an annual exposure rate of less than 0.1 mrem per year.

7.1.6 Conclusions for Area 1 Annual doses based on the Aerial Survey, tissue equivalent survey meter readings, and RESRAD analysis ranged from 0.0 to 8.0 mrem per year. Soil concentrations were all below the DCGL values. This demonstrates that Area 1 is well below the NRC regulatory release requirement of less than 25 mrem per year in accordance with 10 C.F .R. § 20.1402.

7.2 Area 2 7.2.1 Description of Area 2 Area 2 consisted of two Sub-Areas (Area 2.1, and Area 2.2) . These areas lie in a region nominally three miles to the northwest of the WVDP that is transected by the Route 219 Expressway. Area 2.1 is to the north and on the west side of the expressway, while Area 2.2 is to the south on the east side of the Expressway (see pg. 7, Figure 2). Area 2.1 and Area 2.2 are both sloped, and tree covered.

7.2.2 Survey and Sampling Methodology for Area 2 GPS Walkover Gamma Surveys of Area 2 Because both areas were steeply sloped, making footing in some places treacherous, coupled with the heavy tree cover interfering with GPS satellite signal reception, it was not possible to utilize the GPS and Page 39 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas automated data logging system . As specified in the Plan, the contingency method of laying out a grid system and collecting data by hand in discrete locations was employed .

The 2" x 2" gamma detector survey grid readings in Area 2.1 were on average lower than the readings in Area 2.2. An evaluation of the readings for each individual sub-area however did not identify zones within either sub-area that were elevated compared to the rest of the readings from that particular sub-area . Consequently, the random sampling locations and survey locations were used. Figures 18 and 19 show the sampling locations in Sub-Areas 2.1 and 2.2, respectively .

The general orientation of the Cesium Prong as it projects outward from the WNYNSC is in a northwest direction on an axis, which roughly transects Area 2.1 and 2.2 on the map. In light of the elevations of the areas and their alignment with the direction of the Cesium Prong, there is supposition that any anthropogenic contamination on these sites could be from an airborne deposition pathway. As a result, the surface samples in Area 2 were collected in a 0-5 cm increment, which is where most contamination was predicted from an air deposition pathway.

Figure 18. Sub-Area 2.2 Survey and Sampling Locations Page 40 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 19. Sub-Area 2.2 Survey and Sampling Locations SampJe Locations Sub Are Direct radiation readings and soil samples were collected in four locations in each sub-area as described below.

  • Dose rate readings were collected at one and 100 cm from the ground surface using the tissue equivalent dose rate meter.
  • Static .2" x 2" Nal detector readings were collected at one and 100 cm from the ground surface using the Ludlum Model 2241-2 survey meter coupled to a Ludlum Model 44-10 detector. Two, one-minute counts were collected at each location at both elevations .
  • Soil samples were collected in depth increments of 0-5 cm, 5-15 cm, and 15-100 cm . Four locations were sampled in each of Sub-Areas 2.1 and 2.2. Samples were collected from the first two depths at all locations . Samples were collected from the 15-100 cm depth at all locations in Sub-Area 2.2. Due to the difficult terrain and soil conditions, a 15-100 cm sample was only collected in one location in Sub-Area 2.1.

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 7.2.3 Survey and Sampling Results for Area 2 GPS Survey Results Area 2 Figure 20 shows the location of the manual grid for Area 2.1. The manual survey box for Area 2.1 was roughly 19 meters east to west, and 17 meters north to south (Figure 22).

Figure 20. Sub-Area 2.1 Manual Grid Survey Box Legend Manual Survey Box Figure 21 shows the location of the manual grid for Area 2.2. The manual survey box for Area 2.2 was approximately 37 meters east to west and 27 meters north to south (Figure 23) .

Page 42 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 21. Sub-Area 2.2 Manual Grid Box Static 2"x2" Nal Detector Gross Readings at the 100 cm Elevation

  • The Area 2.1 static readings using the 2"x2" Nal detector were averaged between two counts at each location and ranged from 9426 CPM to 10117 CPM . The average across all locations was 9736 CPM .
  • The Area 2.2 static readings using the 2"x 2" Nal c;letector were averaged between two counts at each location and ranged from 5690 CPM to 6052 CPM . The average across all locations was 5917 CPM.
  • The applicable background count rate for Area 2 was determined to be 6333 CPM .

A tabulation of the static count rates is provided in Appendix H32 .

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 22. Static 2" x 2" Detector Grid Readings for Sub-Area 2.1 7.9 9.9 9.7 i 10.2 I 9.5 10.2 Area too steep too access 9.6 10.6 11.2 10.7 10.4 Page 44 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 23. Static 2" x 2" Detector Grid Readings for Sub-Area 2.2 Tissue Equivalent Dose Rate Survey Meter Readings .

Table 21 provides the tissue equivalent dose rate readings (including background) for the Area 2 survey and sample locations :

Table 21. Area 2 Tissue Equivalent Dose Rate Instrument Gross Readings Sample Location Dose Rate at 100 cm (µrem/hour) 2.1.1 7 2.1.2 9 2.1.3 8 2.1.4 7 2.2.1 3 2.2.2 4 2.2.3 5 Page 45 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 2.2.4 4 Soil Sampling Results Area 2 Sub-Area 2.1 Six soil samples were analyzed in Sub-Area 2.1. The weighted average soil concentrations for gross alpha, gross beta, and cesium results associated with each stratum depth sampled are summarized in Table 22.

Table 22 Sub-Area 2.1 Weighted Average Soil Concentrations Depth Gross Alpha* Gross Beta* Cesium-137*

(cm) (pCi/g) (pCi/g) (pCi/g) 0-15 l.OE+Ol +/- 9.4E-01 2.4E+Ol +/- 7.lE -01 . 4 .8E-01 +/- 3.2 E-02

  • Uncertainty is reported+/- 1 sigma The gross alpha soil concentration was less than background levels . For gross beta and cesium, the soil concentrations were above background levels. The net soil concentrations were used to assess potential exposure to a recreational hiker. As only the first 15 cm of soil was sampled, the concentration for the first meter of soil was assumed to be represented by this depth interval. The net soil concentrations used in the dose assessm ent are provided in Table 23 .

Table 23. Sub-Area 2.1 Net Average Soil Concentrations Depth Gross Alpha Gross Beta Cesium-137 (cm) (pCi/g) (pCi/g) (pCi/g) 0-100 0.0E+OO l.3E+OO l.9E-01 The individual sample numbers, depths, concentrations, uncertainties, and MDLs are provided in Appendix H2.

Sub-Area 2.2 Nine soil samples were analyzed in Sub-Area 2.2. The weighted average soil concentrations for gross alpha, gross beta, and cesium results associated with each stratum depth analyzed are summarized in Table 24 below.

Table 24. Sub-Area 2.2 Weighted Average Soil Concentrations Depth Gross Alpha Gross Beta Cesium-137 (cm) (pCi/g) (pCi/g) (pCi/g) 0-15 9.8E+OO +/- l.2E+OO l.8E+Ol +/- l.lE-00 7.3E-01+/-4.4E-02 15-100 l.3E+Ol +/- l.OE+OO l.8E+Ol +/- 6.7E-01 0.0E -00 +/- 2.2E-02

  • Uncertainty is reported+/- 1 sigma Pa ge 46 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas The gross alpha and gross beta soil concentrations were less than background levels. For cesium, the soil concentration was above background levels. The net soil concentration was used to assess potential exposure to a recreational hiker. The calculated weighted net average soil concentrations used in the dose assessment are provided in Table 25.

Table 25. Sub-Area 2.2 Net Average Soil Concentrations Depth Gross Alpha Gross Beta Cesium-137 (cm) (pCi/g) (pCi/g) (pCi/g) 0-100 O.OE+OO O.OE+OO 6.6E-02 The individual sample numbers, depths, concentrations, uncertainties, and MDLs are provided in Appendix H2 .

7 .2.4 Dose Assessment Approach Area 2 The dose assessment approach for Area 2 was to :

  • Develop an estimate of annual exposure based on the Aerial Survey data .
  • Develop an estimate of annual exposure based upon the tissue equivalent dose rate survey meter readings .
  • Perform an assessment based on the current land use Recreational Hiker scenario to determine the exposure in excess of background using current and appropriate parameters (e.g., hydrology, occupancy and consumption) . Parameters were adjusted based on published references for the region or historical site specific data . Calculations were performed using the weighted mean above background for the data analyzed .

Dose assessments associated with soil data were performed using the RESRAD-OFFSITE 3.1 computer code . Hydrology data for the contaminated, unsaturated, and saturated zones were based on Revision 2 of the Phase 1 Decommissioning Plan for the WVDP. The RESRAD input parameters used that differed from the RESRAD defaults are summarized in Appendix H3. In cases where area specific scenarios were not consistent with assumptions used in the Decommissioning Plan, modification are described below and in Appendix H4. This would include, but are not limited to, exposure pathways, irrigation, consumption, erosio*n rates, and occupancy times . For. parameters where there were no site-specific data or there was no corresponding Decommission ing Plan value, the RESRAD-OFFSITE default parameters were used .

The Area 2 dose assessment was based on a recreational hiker that spends 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> per year in the elevated area . It is assumed that this recreational hiker also hunts deer and consumes the deer meat. No plant, fish, or dairy cattle milk is consumed from this area. The recreational hiker' s dwelling is located off-site and not within the area assessed .

In addition, no irrigation was assumed for any part of Area 2, as the entire area contains undeveloped land . The evapotranspiration coefficient provided in the Decommissioning Plan was Page 47 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas recalculated to maintain the same infiltration rate of 0.26 meters per year. The soil erodibility factor, which is used to calculate the erosion rate, was set to the maximum value of the default range (Oto 0.5) in the User Manual for (Ref. 6). This will allow transport of contamination from the contamination zone to the surface water and subsequently ingested by the deer which is then consumed by the recreational hiker.

  • The sample results were compared to the DCGLw concentrations established in the Phase 1 Decommissioning Plan for the WVDP. The peak-of-the mean values are the most conservative DCGLw values provided in the Phase 1 WVDP Decommissioning Plan and are for a resident farmer scenario.
  • Perform an assessment based on a conservative potential land use scenario of a Resident Farmer' s exposure in Area 2.2 to determine the exposure in excess of background using current and appropriate parameters (e.g., hydrology, occupancy and consumption) . As stated earlier, the small size and steep terrain of Area 2.1 preclude current or future use for farming. Parameters were adjusted based on published references for the region or historical site specific data . Calculations were performed using the weighted mean above background for the data analyzed . Dose assessments associated with soil data were performed using the RESRAD 7.0 computer code .

RESRAD input parameters were based on Revision 2 of the Phase 1 Decommissioning Plan for the West Valley Demo*nstration Project Appendix C. The RESRAD input parameters are summarized in Appendix H33 .

  • Perform an assessment based on consumption of fish caught from the Cattaraugus Creek. Current land use surveys indicate that in Areas 1, 2, and 3, no consumption offish occurs. Calculations were performed using the average concentration of Sr-90 and Cs-13 7 in the edible portion of fish above background from the 2012 WVDP Annual Site Environmental Report . Annual exposures were calculated based on ingestion dose coefficients from ICRP 68.

7 .2.5 Dose Assessment Results for Area 2 Dose Based Upon 2014 Aerial Survey Data Figure 24 is an aerial radiological survey map extracted from the Aerial Survey data onto which the locations for Area 2 have been placed. Tlie dose rates at an elevation of one meter as derived from the

  • map were determined to be 4-5 (µR/hour) for Area 2.1 and 4-5 (µR/hour) for Area 2.2. The Aerial Survey states that the contribution to dose from cosmic rays and airborne radon across the entire map is 4.8

µ R/hr.

Based on this aerial map and the assumed cosmic and airborne radon contribution, the dose rates were determined for Area 2 as shown in Table 26. Consistent with the methodologies of the Aerial Survey, a value of 4.8 was added to all readings derived from Figure 24 to account for the contribution to background from cosmic radiation and airborne radon .

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Radiologica l Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 24. Area 2 Locations on the 2014 WNYNSC Aerial Radiological Survey Exposure Rate micro R per hour

. SUB-AREA 2.1 4-5 0-6 7

  • 7*8 9

- 9-10

- 10-20

- 20-100 100-200 e suB-AREA 2.2 200-430

  • Sampling Location Table 26. Area 2 Dose Rates Based Upon 2014 Aerial Survey Data Dose Rate Average Dose Cosmic + Radon Range from Total Dose Rate Location Rate Dose Rate Map (µR/hour)

(µR/hour) (µR/hour)

(µR/hour)

Sub-Area 2.1 4-5 4.5 4.8 9.3 Sub-Area 2.2 4-5 4.5 4.8 9.3 The average background dose rate based ori the WNYNSC Aerial Survey was 8.3 µ R/hour at one meter above the ground . This was subtracted from the total doses rate in Table 26, and based on occupancy time of 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> per year, the calculated doses for Area 2 are provided in Table 27.

Table 27. Area 2 Calculated Doses Based on 2014 WNYNSC Aerial Radiological Survey Annual Total Background Annual Occupancy Location Dose Rate Dose Rate Dose Rate*

Time

(µR/hour) (µR/hour) (mrem/year)

(hours/year)

Sub -Area 2.1 9.3 8.3 100 0.1 Sub-Area 2.2 9.3 8.3 100 0.1

  • The aerial survey dose rates were recorded in units of Roentge n. The quality fact ors for photons and electrons are both on e, th erefore 1 R equa ls 0.877 rem .

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Dose Assessment Based Upon Tissue Equivalent Survey Meter Readings Sub-Area 2.1 Sub-Area 2.1 indicated external dose rates higher than the background screening level calculated in Section 5.1. The average dose rate for Sub-Area 2.1 was 7.59 +/- 0.38 µrem/hour at 100 cm(+/- 1 sigma).

The average dose rate minus background for Sub-Area 2.1 was 3.9 µrem/hour at 100 cm . Therefore, a recreational hiker that spends 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> per year in the elevated area would receive 0.4 mrem per year.

Sub-Area 2.2 Sub-Area 2.2 indicated external dose rates slightly higher than the background screening level calculated in Section 5.1. The average dose rate for Sub -Area 2.2 was 3.74 +/- 0.19 µrem/hour at 100 cm(+/- 1 sigma).

The average dose rate minus background was 0.05 µrem/hour at 100 cm . Therefore, a recreational hiker that spends 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> per year in the elevated area would receive a dose of less than 0.1 mrem per year.

Current Use RESRAD Dose Assessment Based Upon Soil Concentrations Assuming a Recreational Hiker Scenario Sub-Area 2.1 Sub-Area 2.1 is a small 42-square-meter patch of undeveloped land (see red marker in Figure 25) . The deer associated with Sub-Area 2.1 are assumed to stay within the boundaries of the creek and the road .

This results in a deer pasture area (white box in Figure 25 below) of about 55,800 square meters. In addition, the creek bed next to the elevated area is assumed to provide the drinking water resources for the deer. The creek is assumed to be about 50 meters wide and averages about one-meter deep over the course of the year.

The exposure to a recreational hiker in Sub-Area 2.1 that also consumed deer meat is provided in Table

28. The RESRAD input parameters are provided in Appendix H4.

Table 28. Sub-Area 2.1 Current Use Pathway Doses Ground Inhalation Meat Soil Total (mrem/year) (mrem/year) (mrem/year) (mrem/year)

~t--~~~~~~~-t-~~~~~-t--~~~~~~~--i (mrem/year) 4.71E-03 2.17E-07 9.47E-05 1. 73E-06 4.81E -03 The main source of exposure is direct external from the ground . This accounted for over 97 percent of the overall exposure . The full RESRAD output file is provided in Appendix HlO.

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 25. Sub-Area 2.1 and Deer Pasture Area Sub-Area 2.2 Sub-Area 2.2 is a small 350-square-meter patch of undeveloped land (red marker in Figure 26) located between Cattaraugus Creek, Route 219 Expressway, and Cascade Road . The deer associated with Sub-Area 2.2 are assumed to stay within the boundaries of the creek and the road. This res ults in a deer pasture area of about 76,000 square meters . In addition, the creek bed next to the elevated area is assumed to provide the drinking water resources for the deer. The creek is assumed to be about 50 meters wide, runs the entire 329.4 m length of the elevated area, and averages about one-meter deep over the course of the year.

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas The exposure to a recreational hiker in Sub-Area 2.2 that also consumed deer meat is provided in Table

29. The RESRAD input parameters are provided in Appendix H4.

Figure 26. Sub-Area 2.2 and Deer Pasture Area Table 29. Sub-Area 2.2 Current Use Pathway Doses Ground Inhalation Meat Soil Total (mrem/year) (mrem/year) (mrem/year) (mrem/year) (mrem/year) 2.16E-03 . 3.SOE-10 l.73E -OS 2.38E-07 2.18E-03 The main source of exposure is direct external from the ground . This accounted for over 99 percent of the overall exposure . The full RESRAD output file is provided in Appendix Hll.

Comparison to the WVDP Phase 1 Decommissioning Plan DCGLw Values for Area 2 Table 30 provides a comparison of the Area 2 soil concentrations to the WVDP Phase 1 Decommissioning Plan DCGLw Values .

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 30. Area 2 Comparison to WVDP Phase 1 Decommissioning Plan DCGlw Net Soil Concentration Measurement Nuclide WVDP DCGL Comparison (pCi/g)

Type Used (pCi/g) 2.1 2.2 2.1 2.2 Alpha Pu-239 2.50E+Ol O.OE+OO O.OE+OO Below Below Beta Sr-90 4.lOE+OO l. 3E+OO O.OE+OO Below Below Cesium Cs-137 l.50E+Ol l.9E-01 6.6E -02 Below Below Sum of the Fractions : Below Below The assessment of the gross alpha and beta based on the most conservative isotopes (Am-241, Pu-239 and Sr-90, respectively) will account for all of the anthropogenic nuclides listed in Table 2 except C-14, 1-129, and Tc-99. For these radionuclides, a qualitative analysis was performed . In all cases for these three radionuclides, either the soil concentration was below the detection limit or the soil concentration detected was significantly less than the Phase 1 Decommissioning Plan DCGLw Values . In addition, an analysis of the isotopic data indicates that the radionuclides that account for most of the gross alpha and beta soil concentrations are radionuclides that are considered NORM (e.g., natural uranium, natural tho rium, and potassium-40.

Therefore, the use of the DCGLs based on the WVDP Phase 1 Decommissioning Plan resident farmer scenario and gross results assuming the most conservative nuclide results in a highly conservative comparison .

Conservative Potential Use Dose Assessment Based Upon Soil Concentrations Assuming a Resident Farmer Scenario Sub-Area 2.1 Sub-Area 2.1 is a small 42-square-meter patch of undeveloped land (see red marker in Figure 25) . Based on its small size and steep terrain, it was determined that a resident farmer scenario was not a viable scenario for this sub-area. The current use scenario of a recreational hiker that also consumed deer meat is considered to be the bounding scenario for any future use of this parcel of land . Therefore, the future use dose is the same as presented in Table 28.

Sub-Area 2.2 Sub-Area 2.2 is a small 350-square-meter patch of undeveloped land (see red maker in Figure 26) located between Cattaraugus Creek, Route 219 Expressway, and Cascade Road . The future land use scenario is a re sident farmer scenario. It is assumed that the farmer' s dwell ing, crop fields, and pasture land s resi des in t he elevated area . In addition, the crop that is grown is consumed by the farmer. The farmer also maintains and consumes both dairy and meat from the cattle . The annual exposure for Sub-Area 2.2 is provided in Table 31. The RESRAD input parameters are provided in Appendix H33 .

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 31. Sub-Area 2.2 Potential Use Doses Ground Inhalation Plant Meat Milk Soil Total (mrem/year) (mrem/year) (mrem/year) (mrem/year) (mrem/year) (mrem/year) (mrem/year) f--'-~----'-----+--'-~-'--'---'--+--'--

8.17 E-02 2.69E-08 1.74E-02 1.0lE-02 1.87E-02 1.90E-05 1.28E-01 The full RESRAD output file is provided in Appendix H36.

Dose Assessment for Consumption of Fish Based Upon 2012 WVDP Annual Site Environmental Report The ASER (Ref. 8) provides radiological concentrations of strontium and ces ium in the edible portion of the fish in Cattaraugus Creek. Biological data from there locations are provided . Hog-nosed Sucker and White Sucker are sampled from above the Springville Dam and Steelhead Trout are sampled from below the Springville Dam . Brown Trout, White Sucker, Bullhead, and Hog-nosed Sucker were also sampled at a background location . This data is provided in Appendix H41. The average radiological concentrations of strontium and cesium in the edible portion of the fish for the two areas around Springville Dam and the background area are provided in Tables 32 and 33 below.

Table 32. Concentrations in Edible Portions of Fish around Springville Dam Isotope Average 1 Sigma Units Sr-90 1.40E-08 1.16E-09 µCi/g - wet Cs-137 S.46E -08 1.31E-08 µCi/g -wet Table 33. Background Concentrations in Edible Portions of Fish Isotope Average 1 Sigma Units Sr-90 1.02E-08 1.77E-09 µCi/g -wet Cs-137 4.75E-08 4.00E-08 µCi/g - wet This results in a net above background concentration in the edible portions of the fish of 3.74E-09 µCi Sr-90 per gram offish flesh and 7.08E-09 µCi Cs-137 per gram offish flesh . The ingestion dose coefficients factors (DCF) and the fraction of an ingested element directly absorbed to body flu ids (fl) from ICRP 68 are provided in Table 34.

Table 34. Ingestion dose coeffic ients (mrem I µCi) from ICRP 68 Isotope fl

  • DCF Units Sr-90 0.3 1.04E+02 mrem/µCi Ingestion Sr-90 0.01 1.00E+Ol mrem/µCi Ingestion Cs-137 1 4.81E+01 mrem/µCi Ingestion
  • fl - Fractional absorption in the Gastrointestinal tract rate .

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas The Exposure Factors Handbook (Ref. 18) indicates that the 95th percentile of fish consumption by recreational anglers is about nine kg of fish per year. This results in an annual exposure rate of less.than 0.1 mrem per year.

7 .2.6 Conclusions for Area 2 Annual doses based on the Aerial Survey, tissue equivalent survey meter readings, and RESRAD analysis ranged from 0.0 to 0.4 mrem per year. Soil concentrations were all below the DCGL values. This demonstrates that Area 2 is well below the NRC regulatory release requirement of less than 25 mrem per year in accordance with 10 C.F.R. § 20.1402.

7.3 Area 3 7.3.1 Description of Area 3 Area 3 is located at the confluence of Buttermilk and Cattaraugus Creeks (pg. 8, Figure 3), and also consisted of two sub-areas designated 3.1 and 3.2. Both areas are located on an active farm . Sub-Area 3.1 is a large, slightly sloped area, the majority of wh ich is currently utilized to grow corn for livestock consumption . Sub-Area 3.2 is a smaller area located just n.orth of Thomas Corners Road . This area sloped upward from the roadway towards the farm dwelling, and was transected by a gravel driveway.

7.3.2 Survey and Sampling Methodology for Area 3 GPS Walkover Gamma Surveys of Area 3 GPS walkover gamma surveys were conducted in both sub-areas using a nominal grid spacing of 20 meters or less . Some portions of Sub-Area 3.1 were heavily wooded and overgrown . As a result, it was not possible to completely survey the designated survey box. However, the cultivated areas within the designated survey area and immediately adjacent areas were surveyed. Some sections of Sub-Area 3.2 were obstructed by trees, shrubs, and a debris pile, and therefore the path walked by the survey team cou Id not traverse these obstructed areas.

In Sub-Area 3.1, a pattern of elevated readings was identified by the GPS walkover gamma data {Figure

29) immediately to the southwest and down slope of the sub-area. As a result, samples were collected from seven elevated locations, and random locations were used for 17 other locations.

In Sub-Area 3.2, no elevated locations were identified by the GPS walkover gamma data (Figure 30) . As a result, samples were collected from four random locations . One planned sample location was relocated slightly west to avoid an existing driveway on the property.

Direct radiation readings and soil samples were collected in the 24 locations in Sub-Area 3.1 and from fo ur locations in Sub-Area 3.2 as described in Table 4 of the Plan (Ref. 4) .

Each location was surveyed and sampled as follows :

  • Dose rate readings were collected at one and 100 cm from the ground surface using the tissue equivalent dose rate meter.

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas

  • Static 2" x 2" Nal detector readings were collected at one and 100 cm from the ground surface using the Ludlum Model 2241-2 survey meter coupled to a Ludlum Model 44-10 detector. Two, one-minute counts were collected at each location at both elevations.
  • Soil samples were collected in depth increments of 0-15 cm, 15-30 cm, 30-60 cm and 60-100 cm .
  • In Area 3.1 a total of 24 locations were sampled, 17 random and seven elevated.
  • In Area 3.2 a total of four locations were sampled.

Figures 27 and 28 show the sampling locations of Area 3.1 and 3.2, respect ively.

Figure 27. Sub-Area Sampling Locations Page 56 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 28. Sub-Area 3.2 Sampling Locations 7.3.3 Survey and Sampling Results for Area 3 GPS Survey Results Figures 29 and 30 provide the graphical display of the GPS survey data for Sub-Areas 3.1 and 3.2.

Figure 29. Static 2" x 2" Detector Grid Readings for Sub-Area 2.2 Page 57 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 30. Sub-Area 3.2 GPS Survey Results

  • 9730.9330 0 8331 .8930 0 8931 *9430 0 9431
  • 10030 Static 2"x2" Nal Detector Gross Readings at the 100 cm Elevation
  • The Area 3.1 static readings us ing the 2" x2" Nal detector were averaged between two counts at each location and ranged from 8360 CPM to 10980 CPM . The average across all locations was 9939 CPM.

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas

  • The Area 3.2 static readings using the 2" x2" Na! detector were averaged between two counts at each location and ranged from 7074 CPM to 7760 CPM . The average across all locations was 7760 CPM .
  • The applicable background count rate for Area 3 was determined to be 6333 CPM A tabulation of the static count rates is provided in Appendix H32.

Tissue Equivalent Dose Rate Survey Meter Readings Tissue equivalent survey meter readings were collected at 24 locations in Area 3.1 and at 4 locations in Area 3.2.

The average of the readings in Area 3.1 was 7.55 +/- 0.16 µrem/hour at 100 cm(+/- 1 sigma) . This reading exceeded the background screening level.

The average of the readings in Area 3.2 was 4.11+/-0.21 µrem/hour at 100 cm(+/- 1 sigma) . This reading also exceeded the background screening level.

A tabulation of the individual readings in Area 3 is provided in Appendix Hl.

Soil Sampling Results for Area 3 Sub-Area 3.1 Fifty-three soil samples were analyzed in Sub-Area 3.1. The average soil concentrations for gross alpha, gross beta and cesium results associated with each stratum depth sampled are summarized in Table 35 .

Table 35. Sub-Area 3.1 Average Soil Concentrations Depth Gross Alpha Gross Beta Cesium-137 (cm) (pCi/g) (pCi/g) (pCi/g) 0-15 1.3E+Ol +/- 2.9E-01 2.2E+Ol +/- 2.5E-01 1.lE+OO +/- 1.3E-02 15-30 1.4E+Ol +/- 3.5E-01 2.4E+Ol +/- 2.8E-01 1.4E+OO +/- 1.5E-02 30-60 l .6E+Ol +/- 1.lE+OO 2.3E+Ol +/- 7.7E-01 2.2E+OO +/- 8.7E-02 60-100 1.4E+Ol +/- 5.3E-01 2.3E+Ol +/- 4.5E-01 2.5E-01 +/- 2.lE-02

  • Uncertainty is reported as+/- 1 sigma .

The gross alpha, gross beta and cesium soil concentrations were above background levels . The net soil concentrations were used to assess potential exposure to a resident farmer. The calculated weighted net average soil concentrations used in the dose assessment are provided in Table 36.

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 36. Sub-Area 3.1 Net Average Soil Concentrations Depth Gross Alpha Gross Beta Cesium-137

{cm) (pCi/g) {pCi/g) (pCi/g) 0-100 1.lE+OO 5.6E-01 1.0E+OO The individual sample numbers, depths, concentrations, uncertainties, and MDLs are provided in Appendix H2.

Sub-Area 3.2 Six soil samples were analyzed in Sub-Area 3.2. The average so il concentrations for gross alpha, gross beta, and cesium results associated with each stratum depth sampled are summarized in Table 37 .

Table 37. Sub-Area 3.2 Average Soil Concentrations Depth Gross Alpha Gross Beta Cesium-137 (cm) (pCi/g) (pCi/g) {pCi/g) 0-15 1.3E+Ol +/- 9.9E-01 1.9E+Ol +/- 8.2E-01 5.5E-01 +/- 2.4E-02 15-30 ** 1.2E+Ol +/- 1.4E+OO 1.9E+Ol +/- l.2E+OO 3.4E-01 +/- 3.3E-02 30-60 l.2E+Ol +/- l.8E+OO l.9E+Ol +/- l .6E+OO l.3E-01+/-4.2E-02 60-100 7.8E+OO +/- 1.6E+OO 2.2E+Ol +/- l.6E+OO 8.lE-02 +/- 2.6E-02

  • Uncertainty is reported as+/- 1 sigma .
    • No samples were analyzed at th is depth, the average of 0-15 and 30-60 were calculated and used for this depth.

The gross beta soil concentration was less than background levels. The gross alpha and cesium soil concentrations were above background levels. The net soil concentrations were used to assess potential exposure to a resident farmer. The calculated weighted net average soil concentrations used in the dose assessment are provided in Table 38.

Table 38. Sub-Area 3.2 Net Soil Concentrations Depth Gross Alpha Gross Beta Cesium-137 (cm) (pCi/g) (pCi/g) (pCi/g) 0-100 1.9E-01 O.OE-00 l.lE-01 The individual sample numbers, depths, concentrat ions, uncertainties, and MDLs are provided in Appendix H2.

7.3.4 Dose Assessment Approach for Area 3 The dose assessment approach for Area 3 was to :

  • Develop an estimate of annual exposure based on the Aerial Survey data .
  • Develop an estimate of annual exposure based upon the t issue equivalent dose rate survey meter readings .

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas

  • Perform an assessment based on the current land use Resident Farmer scenario to determine the exposure in excess of backgroun.d using current and appropriate parameters (e.g., hydrology, occupancy and consumption). Parameters were adjusted based on published references for the region or historical site specific data . Calculations were performed using the weighted mean above background for the data analyzed.

Dose assessments associated with soil data were performed using the RESRAD-OFFSITE 3.1 computer code. Hydrology data for the contaminated, unsaturated, and saturated zones were based on Revision 2 of the Phase 1 Decommissioning Plan for the WVDP. The RESRAD input parameters used that differed from the RESRAD defaults are summarized in .Appendix H3. In cases where area specific scenarios were not consistent with assumptions used in the Decommissioning Plan, modifications are described below and in Appendix HS . This would include, but are not limited to, exposure pathways, irrigation, consumption, erosion rates, and occupancy times . For parameters where there were no site-specific data or there was no corresponding Decommissioning Plan value, the RESRAD-OFFSITE default parameters were used .

The Area 3 dose assessment was based on a resident farmer that spends 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> per year tending feed crops in Sub-Area 3.1and1000 hours per year tending livestock. It is assumed that this resident farmer consumes the cattle meat. No plant, milk, or fish is consumed from this area . The resident farmer's dwelling is located off-site, but within the general area and therefore is included in this assessment. It is assumed that 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> was spent traversing Sub-Area 3.2.

In addition, irrigation was only assumed for crop fields in Area 3. The evapotranspiration coefficient provided in the Decommissioning Plan was recalculated to maintain the same infiltration rate of 0.26 meters per year.

  • The sample results were compared to the DCGLw concentrations established in the Phase 1 Decommissioning Plan for the WVDP. The peak-of-the-mean values are the most conservative DCGLw values provided in the Phase 1 WVDP Decommissioning Plan and are for a resident farmer scenario.
  • Perform an assessment based on a conservative potential land use scenario of a Resident Farmer's

. exposure to determine the exposure in excess of background using current and appropriate parameters (e.g., hydrology, occupancy and consumption) . Parameters were adjusted based on published references for the region or historical site specific data. Calculations were performed using the weighted mean above background for the data analyzed . Dose assessments associated with soil data were performed using the RESRAD 7.0 computer code. RESRAD input parameters were based on Revision 2 of the Phase 1 Decommissioning Plan for the West Valley Demonstration Project Appendix C. The RESRAD input parameters are summarized in Appendix H33 .

  • Perform an assessment based on consumption offish caught from the Cattaraugus Creek. Current land use surveys indicate that in Areas 1, 2, and 3, no consumption of fish occurs. Calculations were performed using the average concentration of Sr-90 and Cs-137 in the edible portion of fish above background from the 2012 WVDP Annual Site Environmental Report. Annual exposures were calculated based on ingestion dose coefficients from ICRP 68.

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 7 .3.5 Dose Assessment Results for Area 3 Dose Based Upon 2014 Aerial Survey Data Figure 31 is an aerial radiological survey map extracted from the Aerial Survey data onto which the locations for Area 3 have been placed . The dose rates at an elevation of one meter as derived from the map were determined to be 5-6 (µR/hour) for Area 3.1 and 5-6 (µR/hour) for Areas 3.2. The Aerial Survey states that the contribution to dose from cosmic rays and airborne radon across the entire map is 4.8 µR/hour.

Figure 31. Area 3 Locations on the 2014 WNYNSC Aerial Radiological Survey Exposure Rate micro R per hour

-~

4-5 7 5-6 9

7*8 9-10 . SUB-AREA 3.2

- 10-20 200-430 Sampling Locabon Sampling Area vmYNSC Based on this aerial map and the assumed cosmic and airborne radon contribution, the dose rates were determined for Area 3 as shown in Table 39. Consistent with the methodologies of the Aerial Survey, a value of 4.8 was added to all readings derived from Figure 31 to account for the contribution to background from cosmic radiation and airborne radon .

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 39. Area 3 Dose Rates Based Upon 2014 Aerial Survey Data Dose Rate Range Average Dose Cosmic + Radon Total Dose Rate Location from Map Rate Dose Rate

(µR/hour)

(µR/hour) (µR/hour) (µR/hour)

Sub-Area 3.1 5-6 5.5 4.8 10.3 Sub-Area 3.2 5-6 5.5 4.8 10.3 The average background dose rate based on the WNYNSC Aerial Survey was 8.3 µR/hour at one meter above the ground . This was subtracted from the total doses rate in Table 39, and based on occupancy time of 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> per year in Area 3.1and100 hours per year in Area 3.2, the calculated doses for Area 3 are provided in Table 40.

Table 40. Area 3 Calculated Doses Based on 2014 WNYNSC Aerial Radiological Survey Annual Total Background Annual Occupancy location Dose Rate Dose Rate Dose Rate*

Time

(µR/hour) (µR/hour) (mrem/year)

(hours/year)

Sub-Area 3.1 10.3 8.3 1000 1.8 Sub-Area 3.2 10.3 8.3 100 0.2

  • The aerial survey dose rates were recorded in units of Ro entgen. Th e quality factors fo r photons and electron s are both one, therefore 1 R equal s 0.877 rem.

Dose Assessment Based Upon Tissue Equivalent Survey Meter Readings Sub-Area 3.1 Dose rate readings in Sub-Area 3.1 demonstrated external dose rates higher than the background screening level. The average dose rate for Sub-Area 3.1 was 7.55 +/- 0.16 µrem/hour at 100 cm(+/- 1 sigma) . The dose rate net of background in Sub-Area 3.1was3.86 µrem/hour at 100 cm . Based on the annual occupancy derived from the Resident Farmer scenario of.1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> per year in Area 3.1, the net dose to the farmer based upon the tissue equivalent survey meter readings is 3.9 mrem per year.

Sub-Area 3.2 Readings in Sub-Area 3.2 demonstrated dose rates lower than the background screening level and therefore the assessed dose for Sub-Area 3.2 based on tissue equivalent tissue equivalent survey meter readings is 0.0 mrem per year.

Current Use RESRAD Dose Assessment Based Upon Soil Concentrations Assuming a Resident Farmer Scenario RESRAD dose assessments were based on a resident farmer that spends 11.42 percent (1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> per year) working in the elevated area where feed grain is grown . The resident farmer also spends 11.42 percent (1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> per year) maintaining their livestock in a pasture just north of the dwelling. Sixty-six Page 63 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas percent of the year is assumed to be spent inside the dwelling and the remaining time (11.16 percent) outdoors, but not associated with farming or maintaining their livestock. No edible vegetation is grown for human consumption . Cattle are assumed to graze in the pasture and are assumed to consume grain grown in the elevated area. The number of livestock consumed is assumed to be 10. No livestock are directly located within the elevated area . The dwelling is assumed to house four individuals. The consumption of milk or fish is not considered for this area .

Irrigation was only assumed for feed grain crop field . For all other areas, the evapotranspiration coefficient was recalculated to maintain the same infiltration rate in the Decommissioning Plan of 0.26 meters per yea r. All water used is assumed to be pumped from a well. The total well pump rate was calculated 32,100 cubic meters per year based on the water usage for irrigation, livestock, dwelling, and human consumption.

Sub-Area 3.1 Sub-Area 3.1 is a 64,500-square-meter crop field, located about 300 meters west of the dwelling. For purposes of the analysis, the size was increased to include the entire field . Feed gra in is grown as a crop in this field . See Figure 32 below.

Figure 32. Sub-Areas 3.1 and 3.2 Page 64 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas The exposure to a resident farmer in Sub-Area 3.1 that also consumed cattle meat is provided in Table

41. The RESRAD input parameters are provided in Appendix HS.

Table 41. Sub-Area 3.1 Pathway Doses Ground Inhalation Meat Soil Total (mrem/year) (mrem/year) (mrem/year) (mrem/year) (mrem/year)

--!~--'-~--'--'---------+---------~---'---------'-~

3.87E-01 4.23E-OS 4.31E -01 4.81E-ll 8.18E-01

  • The gross alpha was assesse d as Am-241, as th is provi ded th e more conservat ive dose estimate.

The main sources of exposure were direct external from the ground and consumption of cattle meat.

These accounted for over 47 and S2 percent, respectively, of the overall exposure. Th e full RESRAD output files are provided in Appendix H12 and H13 .

Sub-Area 3.2 Sub-Area 3.2 is a 1,000-squ are-meter section of overgrowth (F igure 32 above ) located about lS meters west of the dwelling. No crop or livestoc k are located in th is area .

The exposure to a resident farmer in Sub-Area 3.2 that also consumed cattle meat is provided in Table 42 . The RESRAD input parameters are provided in Appendix HS.

Table 42 Sub-Area 3.2 Pathway Doses Ground Inhalation Meat Soil Total (mrem/year) (mrem/year) (mrem/year) (mrem/year) (mrem/year) 4.08E-03 2.07E-OS 9.21E-ll l.4SE-04 4.2SE -03

  • The gross alpha wa s assesse d as Am-241, as th is provi ded the more conservative dose estimate .

The main source of exposure is direct external from the.ground. This accounted for over 96% of the overall exposure. The full RESRAD output files are provided in Appendix H14 and HlS .

Comparison to the WVDP Phase 1 Decommissioning Plan DCGLw Values for Area 3 Table 43 provides a comparison of the Area 3 soil concentrations to the WVDP Phase 1 Decommissioning Plan DCGLw Values .

Table 43. Area 3 Comparison to WVDP Phase 1 Decommissioning Plan DCGLw WVDP Net Soil Concentration Measurement Nuclide Comparison DCGL (pCi/g)

Type Used (pCi/g) 3.1 3.2 Sub-Area 3.1 Sub-Area 3.2 Alpha Pu-239 2.SOE+Ol l.lE+OO l.9E-01 Below Below Beta Sr-90 4.lOE+OO S.6E -01 O.OE+OO Below Below Cesium Cs -137 l.SOE+Ol l.OE+OO l.lE-01 Below Below Sum of the Fractions : Below Below Page 65 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas The assessment of the gross alpha and beta based on the most conservative isotopes (Pu -239 and Sr-90, respectively) will account for all of the anthropogenic nu elides listed in Table 2 except C-14, 1-129, and Tc-99. For these radionuclides, a qualitative analysis was performed. In all cases for these three radionuclides, either the soil concentration was below the detection lim it or the soil concentration detected was significantly less than the Phase 1 Decommissioning Plan DCGLw Values . In addition, an analysis of the isotopic data indicates that the radionuclides that account for most of the gross alpha and beta soil concentrations are radionuclides that are considered NORM (e.g., natural uranium, natural thorium, and potass fum -40.

These DCGLs are based on a resident farmer scenario used in th e WVDP Phase 1 Decommission ing Plan, which is different than the current land use resident farmer described above. One of the key differences is that RESRAD (onsite) was used to do the calculat ions versus RESRAD -OFFSITE . This resulted in all farming activities to be assumed to occur in the contamination zone. In addition, the resident farmer scenario used in the WVDP Phase 1 Decommissioning Plan assumes the consumption of plant vegetation grown by the farmer. These two items account for most of the difference in the estimated doses.

Therefore, the resident farmer scenario used in the WVDP Phase 1 Decommissioning Plan is a conservative comparison .

Conservative Potential Use Dose Assessment Based Upon Soil Concentrations Assuming a Resident Farmer Scenario Sub-Area 3.1 Sub-Area 3.1 is a 64,500-square-meter crop field, located about 300 meters west of the dwelling. This assessment is based on a resident farmer scenario. It is assumed that the farmer' s dwelling, crop fields, and pasture lands resides in the elevated area . In addition, the crop that is grown is consumed by the farmer. The farmer also maintains and consumes both dairy and meat from the cattle. The annual exposure for Sub-Area 3.1 is provided in Table 44. The RESRA.D input parameters are provided in Appendix H33 .

Table 44. Sub-Area 3.1 Potential Use Pathway Doses Ground

  • Inhalation Plant Meat Milk Soil Total (mrem/year) (mrem/year) (mrem/year) (mrem/year) 1--'-~~-'-'-~-'-f--'-~~-'-'-~-'-1--'-~~-'--'-~-'---1--'-~~

(mrem/year) (mrem/year) (mrem/year) l.45E+OO l.07E-02 4.14E+OO 5.42E-01 l.06E+OO 6.83E-02 7.27E+OO The full RESRAD output file is provided in Appendix H37 and H38.

Sub-Area 3.2 Sub-Area 3.2 is a 1,000-square-meter section of overgrowth located about 15 meters west of the dwelling. This assessment is based on a resident farmer scenario. It is assumed that the farmer' s dwelling, crop fields, and pasture lands resides in the elevated area . In addition, the crop that is grown is consumed by the farmer. The farmer also maintains and consumes both dairy and meat from the cattle.

The annual exposure for Sub-Area 3.2 is provided in Table 45. The RESRAD input parameters are provided in Appendix H33 .

Page 66 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 45. Sub-Area 3.2 Potential Use Pathway Doses Ground Inhalation Plant Meat Milk Soil Total (mrem/year) (mrem/year) (mrem/year) (mrem/year) (mrem/year) (mrem/year) (mrem/year) l.46E-01 l.21E-03 l.21E-01 l.82E-02 3.16E-02 l.lSE-02 3.29E -01 The full RESRAD output file is provided in Appendi x H39 and H40.

Dose Assessment for Consumption of Fish Based Upon 2012 WVDP Annual Site Environmental Report The ASER (Ref. 8) provides radiological concentrat ions of strontium and cesium in the ed ible portion of the fish in Cattaraugus Creek. Biological data from their locations are provided . Hog-nosed Sucker and White Sucker are sampled from above the Springville Dam and Steelhead Trout are sampled from below the Springville Dam . Brown Trout, White Sucker, Bullhead, and Hog-nosed Sucker were also sampled at a background location . This data is provided in Appendix H41. The average radiological concentrations of strontium and cesium in the edible portion of the fish for the two areas around Springville Dam and the background area are provided in Tables 46 and 47 below.

Table 46. Concentrations in Edible Portions of Fish around Springville Dam Isotope Average 1 Sigma Units Sr-90 l.40E-08 l.16E-09 µCi/g - wet Cs-137 5.46E-08 1.31E-08 µCi/g - wet Table 47. Background Concentrations in Edible Portions of Fish Isotope Average 1 Sigma Units Sr-90 l.02E-08 l.77E-09 µCi/g - wet Cs-137 4.75E-08 4.00E-08 µCi/g - wet This results in a net above background concentration in the edible portions of the fish of 3.74E-09 µCi Sr-90 per gram offish flesh and 7.08E-09 µCi Cs-137 per gram offish flesh . The ingestion dose coefficients factors (DCF) and the. fraction of an ingested element directly absorbed to body fluids (fl) from ICRP 68 are provided in Table 48.

Table 48. Ingestion dose coefficients (mrem/µCi) from ICRP 68 Isotope fl* DCF Units Sr-90 0.3 l.04E+02 mrem/µCi Ingestion Sr-90 0.01 l.OOE+Ol mrem/µCi Ingestion Cs-137 1 4. 81E+Ol mrem/µCi Ingestion

  • fl - Fractional absorption in the Gastrointestinal tract rate .

The Exposure Factors Handbook (Ref. 18) ind icates that the 95th percentile of fi sh consumpt ion by recreational anglers is about nine kg of fish per year. This results in an annual exposure rate of less than 0.1 mrem per year.

Page 67 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 7 .3.6 Conclusions for Area 3 Annual doses based on the Aerial Survey, tissue equivalent survey meter readings, and RESRAD analysis ranged from 0 to 7.2 mrem per year. Soil concentrations were all below the DCGL values . This demonstrates that Area 3 is well below the NRC regulatory release requirement of less than 25 mrem per year in accordance with 10 C.F.R. § 20.1402.

7.4 Area 4 7.4.1 Description of Area 4 Area 4 lies approximately 20 miles to the west of the WNYNSC on the SNI and spans Cattaraugus Creek (Figure 4) . It includes five sub-areas designated 4.1, 4.2, 4.3, 4.4, and 4.5. As can be seen in Figures 33 and 34, multiple irregularly shaped sub regions, derived from the Aerial Survey, were combined into five sub-areas as follows :

  • Sub-Area 4.1-four sub regions designated 4.lA, 4.lB, 4.lC, and 4.lD
  • Sub-Area 4.2 - three sub regions designated 4.2A, 4.2B, and 4.2C
  • Sub-Area 4.3-two sub region designated 4.3A and 4.3B
  • Sub-Area 4.4 - four sub regions designated 4.4A, 4.4B, 4.4C, and 4.4D
  • Sub-Area 4.5 - three sub regions designated 4.5A. 4.5B, and 4.5C Area 4 is a wooded area with varying terrain that lies within the historic floodplain . There are no residences located in the Area. For Area 4, which is located on the SNI, culturally specific aspects of land use are being developed. This report will be revised to include the modeled dose assessments for Areas 4 and 5 once the culturally specific aspects of land use are finalized .

7.4.2 Survey and Sampling Methodology for Area 4 GPS Walkover Gamma Surveys of Area 4 GPS walkover gamma surveys were conducted in all sub-areas using a nominal grid spacing of 30 meters (see Figures 35-39) . The areas were generally heavily wooded and GPS precision varied; however, sufficient data was collected and analyzed to determine if any elevated locations would be sampled or if all samples would be from random sampling locations. There were no elevated areas identified.

Static Survey and Sample Collection in Area 4 Direct radiation readings and soil samples were collected in each sub-region as follows :

Sub-Area 4.1

  • Sub Region 4.lA - one location
  • Sub Region 4.lB - eight locations
  • Sub Region 4.lC- nine locations Page 68 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas

  • Sub Region 4.10 - six locations Sub-Area 4.2
  • Sub Region 4.2A- four locations
  • Sub Region 4.2B - eighteen locations
  • Sub Region 4.2C - two locations Sub -Area 4.3
  • Sub Region 4.3A - four locations
  • Sub Region 4.3B - twenty locations Sub-Area 4.4
  • Sub Region 4.4A - one location
  • Sub Region 4.4B - one location
  • Sub Region 4.4C - seven locations
  • Sub Region 4.40 - six locations Sub-Area 4.5
  • Sub Region 4.SA - seven locations
  • Sub Region 4.SB - eight Locations
  • Sub Region 4.SC - nine locations Page 69 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 33 shows the sampling locations in Sub-Areas 4.1, 4.2, and 4.3, and Figure 34 shows the sampling locations in Sub-Areas 4.4 and 4.5.

Figure 33. Sampling Locations in Sub-Areas 4.1, 4.2, and 4.3 Figure 34. Sampling Locations in Sub-Areas 4.4 and 4.5 Page 70 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Each location was surveyed and sampled as follows :

  • Dose rate readings were collected at one and 100 cm from the ground surface using the tissue equivalent dose rate meter.
  • Static 2" x 2" Nal detector readings were collected at one and 100 cm from the ground surface using the Ludlum Model 2241-2 survey meter coupled to a Ludlum Model 44-10 detector. Two, one-minute counts were collected at each location at both elevations .
  • Soil samples were collected in depth increments of 0-15 cm, 15-30 cm, 30-60 cm, and 60-100 cm .

7.4 .3 Survey and Sampling Results for Area 4 GPS Survey Results Figures 35 through 39 provide the GPS walkover gamma survey results for Area 4 . No pattern of elevated locations was discerned in the GPS maps and therefore only random samples were collected .

Page 71of 102

Rad iolog ical Survey and Dose Assessment Report fo r the WNYNSC and Off-Site Areas Figure 35. Sub-Area 4.1 GPS Walkover Gamma Survey Data Area *4 .1 - Walkover Survey Data

  • 3000-8830 0 8831-9730 0 9731
  • 10430 0 10431
  • 11230
  • 11231
  • 13330 Page 72 of 102

Rad iological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 36. Sub-Area 4.2 GPS Walkover Gamma Survey Data Area 4 .2 - Wa'I over Survey Data

  • 8730*8330 0 8331-9130 0 9131 9830 0 9831
  • 10530 Page 73 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 37. Sub-Area 4.3 GPS Walkover Gamma Survey Data Area 4.3 - Wal over Survey Data a_ _3_ llkOY CPM

  • 6630-8430 0 8431- 9130 0 9131- 9730 0 9731
  • 10430
  • 10431
  • 12230 Page 74 of 102

Radiological Survey and Dose Assessm ent Report for the WNYNSC and Off-Site Areas Figure 38. Sub-Area 4.4 GPS Walkover Gamma Survey Data Area 4 .4 - Wal over Survey Data CP

  • 5630- 7343 0 7344-8330 c 8331 -9030 0 9031-9730
  • 0731 -11430 Page 75 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 39. Sub-Area 4.5 GPS Walkover Gamma Survey Data Area 4.5 - Wa lkover Survey Data c

  • 5830-81:53 0 8154*8830 0 8831-9430 0 9431 -10230 Page 76 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Static 2"x2" Nal Detector Gross Readings at the 100 cm Elevation

  • The Area 4.1 static readings using the 2" x2" Nal detector were averaged between two counts at each location and ranged from 7871 CPM to 10299 CPM . The average across all locations was 9030 CPM.
  • The Area 4.2 static readings using the 2" x2" Nal detector were averaged between two counts at each location and ranged from 7723 CPM to 10383 CPM . The average across all locations wa s 8704 CPiy1 .
  • The Area 4. 3 st atic readings using the 2" x2" Nal detector were averaged between two cou nt s at each location and ranged from 7225 CPM to 9804 CPM . The average across all location s was 7966 CPM .
  • The Area 4.4 static readings using the 2" x2" Nal detector were ave raged between two counts at each location and ranged from 7130 CPM to 9210 CPM . The average across all locations was 7799 CPM .
  • The Area 4.5 static readings using the 2" x2" Nal detector were averaged between two counts at each _location and ranged from 7263 CPM to 9367 CPM . The average across all locations was 8205 CPM.
  • The applicable background count rate for Area 4 was determined to be 7943 CPM.

A tabulation of the static count rates is provided in Append ix H32.

Tissue Equivalent Dose Rate Survey Meter Readings The tissue equivalent survey meter readings for Area 4 are provided in Appendix Hl.

The average dose rates for each sub-area are provided below (Table 49) .

Table 49. Area 4 Average Dose Rates Dose Rate*

Area at 100 cm

(µrem/hour)

Sub-Area 4.1 5.6 +/- 0.1 Sub-Area 4.2 4.9 +/- 0.1 Sub-Area 4.3 4.4 +/- 0.1 Sub-Area 4.4 4.5 +/- 0.1 Sub-Area 4.5 4.5 +/- 0.1

  • Uncerta inty is re ported as+/- 1 sigma .

In Sub-Area 4. 1 th e dose rate at th e 100 cm elevat ion exceed ed t he backgrou nd screening level. In all other sub-areas, the dose rate at 100 cm was less than the background screening level.

Page 77 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Soil Concentration Data For Area 4, which is located on the SNI, culturally specific aspects of land* use surveys are being developed . Soil concentration data calculations will be provided in the revised version of this report .

7 .4.4 Dose Assessment Approach for Area 4 The dose assessment approach for Area 4 will be to :

  • Develop an estimate of annual exposure based on the Aerial Survey data .
  • Develop an estimate of annual exposure based upon the tissue equivalent dose rate survey meter readings .
  • For Area 4, which is located on the SNI, culturally specific aspects of land use are being developed.

This report will be revised to include the modeled dose assessments for Areas 4 and 5 once the culturally specific aspects of land use are finalized .

7 .4.5 Dose Assessment Results for Area 4 Dose Dose Assessment Based on Aerial Survey Data for Area 4 Figure 40 is an aerial radiological survey map extracted from the Aerial Survey data onto which the location of Area 4 has been placed . The dose rates at an elevation of one meter as derived from the map were determined to be 5-6 (µR/hour) for Sub-Area 4.1 and 3-4 (µR/hour) for all other sub-areas. The Aerial Survey states that the contribution to dose from cosmic rays and airborne radon across the entire map is 4.8 (µR/hour) .

Figure 40. Area 4 Locations on the 2014 WNYNSC Aerial Radiological Survey Exposure Rate micro R per hour SUB-AREA 4.1 SUB-AREA 4.3 4-5

~

"'"'ci

- 7.a 6-7 6-9 SUB-AREA 4.4.

- 9-10 SUB-AREA 4.6*

- 10-20

- 20-100 100-200 200430

  • Sampl111g Location Page 78 of 102

Radi ological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Based on this aerial map and the assumed cosmic and airborne radon contribution, the dose rates were determined for Area 4 as shown in Table 50. Consistent with the methodologies of the Aerial Survey, a value of 4.8 wa s added to all readings to account for the contribution to background from cosmic radiation and airborne radon .

Table 50. Area 4 Dose Rates Based Upon 2014 Aerial Survey Data Dose Rate Cosmic+

Average Dose Range from Radon Dose Total Dose Rate Locatio n Rate Map Rate (µR/hour)

(µR/hour)

(µR/hour) (µR/hour)

Sub-Area 4.1 5-6 5.5 4.8 10.3 Sub-Area 4.2 3-4 3.5 4.8 8.3 Sub-Area 4.3 3-4 3.5 4.8 8.3 Sub-Area 4.4 3-4 3.5 4.8 8.3 Sub-Area 4.5 3-4 3.5 4.8 8.3 The average SNI Floodplain background dose rate based on the WNYNSC Aerial Survey was 8.9 µR/hour at one meter above the ground . This was subtracted from the total dose rate in Table 50, and the calculated dos es for Area 4 are provided in Table 51. The occupancy time is being updated by culturally specific aspect s of land use . This report will be revised to add the modeled dose assessments for Areas 4 and 5 once the culturally specific aspects of land use are finalized .

Table 51. Area 4 Calculated Doses Based on 2014 WNYNSC Aerial Radiological Survey Total Background Annual Locati on Dose Rate Dose Rate Dose Rate*

(µR/hour) (µR/hour) (mrem/year)

Sub-Area 4 .1 10.3 8.9 TBD**

Sub-Area 4.2 8.3 8.9 0.0 Sub-Area 4.3 8.3 8.9 0.0 Sub-Area 4.4 8.3 8.9 0.0 Sub-Area 4.5 8.3 8.9 0.0

  • The aerials urvey dose rates were recorded in units of Roentgen . The quality factors for photons and electrons ar e both one, therefore 1 R equals 0.877 rem .
    • The report wi ll be revised to include the modeled dose assessm ents for Areas 4 and 5 once the culturally sp ecific aspects of the land use surveys are finalized .

Dose Assessm ent Based Upon Tissue Equivalent Survey Meter Readings for Area 4 For Sub-Area 4 .1, the average dose rate slightly exceeded the background screening level. The occupancy tim e will be based on culturally specific aspects of land use. Therefore, these dose rates included in this version of the report will be revised once the culturally specific land use are final ize d.

For Area 4.2-4.5, the tissue equivalent survey meter readings were all below background dose rates .

Page 79 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 7 .4.6 Conclusions for Area 4 Annual doses based on the Aerial Survey and tissue equivalent survey meter readings for Area 4, which is located on the SNI, will be calculated based on culturally specific aspects of land use surveys. This version of the report will be revised to add the modeled dose assessments for Areas 4 and 5 once the culturally specific aspects of land use surveys are finalized .

7.5 Area 5 7 .5.1 Description of Area 5 Area 5 lies approximately 17 miles to the west of the WNYNSC, and 0.6 miles East of Cattaraugus Creek (pg. 10, Figure 5) . It includes six sub-areas designated 5.1, 5.2, 5.3, 5.4, 5.5, and 5.6. Each sub-area was defined by a polygon as can be seen in Figures 41, 42, and 43 . Also seen in these figures, within each sub-area polygon, one or two irregularly shaped sub-regions were defined as derived from the Aerial Survey as follows :

  • Sub-Area 5.1- two sub regions designated 5.lA, and 5.lB.
  • Sub-Area 5.2 - two sub regions designated 5.2A, and 5.2B
  • Sub-Area 5.3 - one sub region designated 5.3A
  • Sub-Area 5.4 - one sub region designated 5.4A
  • Sub -Area 5.5 - one sub region designated 5.5A
  • Sub-Area 5.6 - one sub region designated 5.6A Area 5 is a relatively undisturbed old growth wooded area with varying terrain that lies outside the floodplain. There are no residences located in Area 5. For Area 5, which is located on the SNI, culturally specific aspects of land use are being developed . This version of the report will be revised to add the modeled dose assessments for Areas 4 and 5 once the culturally specific aspects of land use are finalized.

7.5.2 Survey and Sampling Methodology for Area 5 GPS walkover surveys of Area 5 GPS walkover surveys were conducted in all sub-areas using a nominal grid spacing of 30 meters . The areas were generally heavily wooded and GPS precision varied, however sufficient data was collected and analyzed to determine if any random sampling locations needed to be redirected to elevated areas.

No elevated areas were identified in Area 5.

Static Survey and Sample Collection in Area 5 Direct radiation readings and soil samples were collected in each sub-region as follows :

Page 80 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Sub-Area 5.1

  • Sub Region 5.lA - two locations
  • Sub Region 5.lB -two locations Sub-Area 5.2
  • Sub Region 5.2A - seven locations
  • Sub Region 5.2B - eight locations Sub-Area 5.3
  • Sub Region 5.3A- four locations Sub-Area 5.4
  • Sub Region 5.4A- four locations Sub-Area 5.5
  • Sub Region 5.5A - four locations Sub -Area 5.6
  • Sub Region 5.6 A - four locations Figures 41to43 show the sampling locations in Area 5.1 Page 81of102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 41. Sub-Area 5.1 Sampling Locations Page 82 of 102

Radiological Survey and D<:>se Assessment Report for the WNYNSC and Off-Site Areas Figure 42. Sub-Areas 5.2, 5.3 and 5.4 Sampling Locations Page 83 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 43. Sub-Areas 5.5 and 5.6 Sampling Locations Page 84 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Each location was surveyed and sampled as follows :

  • Dose rate readings were collected at one and 100 cm from the ground surface using the tissue equivalent dose rate meter.
  • Static 2" x 2" Nal detector readings were collected at one and 100 cm from the ground surface using the Ludlum Model 2241-2 survey meter coupled to a Ludlum Model 44-10 detector. Two, one-minute counts were collected at each location at both elevations .
  • Soil samples were collected in depth increments of 0-15 cm, 15-30 cm, 30-60 cm and 60-100 cm .

7.5.3 Survey and Sampling Results for Area 5 GPS Survey Results Figures 44 to 49 present the graphical results of the GPS walkover surveys conducted in Area 5. No pattern of elevated locations was discerned in the GPS maps and therefore no elevated locations were sampled.

Page 8~ of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 44. Sub-Area 5.1 GPS Walkover Survey Data Area 5.1 - Walkover Survey Data

  • 5323-6583 D 6584-7163 0 7164- 760l 0 7804-8083
  • ISOM-9513 Page 86 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 45. Sub-Area 5.2 GPS Walkover Gamma Survey Data Area 5.2 - Wa1kover Survey Data

  • 8484-10030 Page 87 of 102

I I

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 46. Sub-Area 5.3 GPS Walkover Gamma Survey Data Area 5.3 - Wa lkover Survey Data

  • 4953 71$3 o 11.u-nu 0 774*-82'3
  • 82*H
  • 8853
  • 8854 10230 Page 88 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 47. Sub-Area 5.4 GPS Walkover Gamma Survey Data Area 5.4 - Wa lkover Survey Data

  • 5730 -6830 0 8931 -1"'30 0 1~1-7930
  • 79'31 *8430
  • 8431 *9830 Pa ge 89 of 102

Radi o logical Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 48. Sub-Area 5.5 GPS Wa lkove r Gamma Survey Data Area 5.5 -*Walkover Survey Data fP

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  • 54t3 - 6843 0 8644-1'2n 0 7.2N-7n3
  • 77M - &353
  • 138' . 9513 Page 90 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Figure 49. Sub-Area 5.6 Walkover Gamma Survey Data Area 5.6 - Walkover Surv,ey Data D

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  • a14 .9m Page 91of102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Static 2"x2" Nal Detector Gross Readings at the 100 cm Elevation

  • The Area 5.1 static readings using the 2"x2" Nal detector were averaged between two counts at each location and ranged from 6108 CPM to 6464 CPM . The average across all locations was 6295 CPM .
  • The Area 5.2 static readings using the 2"x2" Nal detector were averaged between two counts at each location and ranged from 6348 CPM to 8984 CPM . The average across all locations was 7266 CPM .
  • The Area 5.3 static readings using the 2" x2" Nal detector were averaged between two counts at each location and ranged from 6839 CPM to 8614 CPM . The average across all locations was 7499 CPM .
  • The Area 5.4 static readings using the 2" x2" Nal detector were averaged between two counts at each location and ranged from 5878 CPM to 6126 CPM . The average across all locations was 5992 CPM .
  • The Area 5.5 static readings using the 2" x2" Nal detector were averaged between two counts at each location and ranged from 5933 CPM to 7211 CPM . The average across all locations was 6288 CPM.
  • The Area 5.6 static readings using the 2"x2" Nal detector were averaged between two counts at each location and ranged from 5724 CPM to 7525 CPM . The average across all locations was 6408 CPM .
  • The applicable background count rate for Area 5 was determined to be 8745 CPM .

A tabulation of the static count rates is provided in Appendix H32.

Tissue Equivalent Dose Rate Survey Meter Readings The tissue equivalent survey meter readings for Area 5 are provided in Appendix Hl.

The average dose rates for each sub-area are provided in Table 52 .

Table 52 Area 5 Average Dose Rates Dose Rate*at 100 cm Area

(µrem/hour)

Sub-Area 5.1 6.2 +/- 0.3 Sub-Area 5.2 4.6 +/- 0.1 Sub-Area 5.3 4.7 +/- 0.2 Sub-Area 5.4 5.0 +/- 0.3 Sub-Area5.5 5.5 +/-0.3 Sub-Area 5.6 4.5 +/- 0.2

  • Uncertainty is reported as+/- 1 sigma .

Page 92 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas In Sub-Areas 5.1- 5.6, the dose rate at the 100 cm elevation exceeded the background screening level.

Soil Concentration Data For Area 5, which is located on the SNI, culturally specific aspects of land use surveys are being developed . This report will be revised to add the modeled dose assessments for Areas 4 and 5 once the culturally specific aspects of land use surveys are finalized .

7.5.4 Dose Assessment Approach for Area 5 The dose assessment approach for Area 5 will be to :

  • Develop an estimate of annual exposure based on the Aerial Survey data .
  • Develop an estimate of annual exposure based upon the tissue equivalent dose rate survey meter readings .
  • For Area 5, which is located on the SNI, culturally specific aspects of land use surveys are being developed . This report will be revised to add the modeled dose assessments for Areas 4 and 5 once the culturally specific aspects of land use surveys are finalized .

7.5.5 Dose Assessment Results for Area 5 Dose Assessment Based on Aerial Survey Data for Area 5 Figure 50 is an aerial radiological survey map extracted from the Aerial Survey onto which the location of Area 5 has been placed. The dose rates at an elevation of one meter as derived from the map were determined to be 3-4 µR/hour for all sub-areas . The Aerial Survey states that the contribution to dose from cosmic rays and airborne radon across the entire map is 4.8 µR/hour.

Figure 50. Area 5 Locations on the 2014 WNYNSC Aerial Radiological Survey Ex posure Rate mtero R per hour (g"j o.1 CJ o.2 CJ 2-3 CJ 34 SUB-AREA 6.6.

. SUB-AREA 5.1

&-6 e.7 SUB-AREA 6.5.

8

- 8-9

- 9-10 SUB-AREA 5.4.

- 10-20

- 20-IOO

  • sue-AREA s.:z

- IOIJ.200

- 200-430

  • S.ntpling LQCl!l>cn SUB-AREA u*

Page 93 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Based on this aerial map and the assumed cosmic and airborne radon contribution, the dose rates were determined for Area 5 as shown in Table 53 . Consistent with the methodologies of the Aerial Survey, a value of 4.8 was added to all readings to account for the contribution to background from cosmic radiation and airborne radon .

Table 53 Area 5 Dose Rates Bas ed Upon 2014 Aerial Survey Data Dose Rate Range Average Dose Cosmic + Radon Total Dose Location from Map Rate Dose Rate Rate

(µR/hour) (µR/hour) (µR/hour) (µR/hour)

Sub-Area 5.1 3-4 3.5 4.8 8.3 Sub-Area 5.2 3-4 3.5 4.8 8.3 Sub-Area 5.3 3-4 3.5 4.8 8.3 Sub-Area 5.4 3-4 3.5 4.8 8.3 Sub-Area 5.5 3-4 3.5 4.8 8.3 Sub -Area 5.6 3-4 3.5 4.8 8.3 The average SNI Non-Floodplain background dose rate based on the WNYNSC Aerial Survey was 7.8

µR/hour at one meter above the ground. This will be used in the calculation of dose rates, once the culturally specific aspects of the land use surveys are finalized .

Page 94 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 54 Area 5 Calculated Doses Based on 2014 WNYNSC Aerial Radiological Survey Total Background Annual location Dose Rate Dose Rate Dose Rate*

(µR/hour) (µR/hour) (mrem/year)

Sub-Area 5.1 8.3 7.8 TBD**

Sub-Area 5.2 8.3 7.8 TBD **

Sub-Area 5.3 8.3 7.8 TBD **

Sub-Area 5.4 8.3 7.8 TBD **

Sub-Area 5.5 8.3 7.8 TBD **

Sub-Area 5.6 8.3 7.8 TBD **

  • The aeria l survey dose rates were recorded in units of Roentgen . The qua lity factors for photons and electrons are both one, therefore 1 R equals 0.877 rem .
    • The report will be revised to include the modeled dose assessments for Areas 4 and 5 once the culturally specific aspects of the land use surveys are finalized .

Dose Assessment Base Upon Tissue Equivalent Survey Meter Readings for Area 5 For Areas 5.1-5.6 the calculation of dose rates based on the tissue equivalent survey meter readings will be updated once the culturally specific aspects of land use surveys are finalized .

7.6 Confirmatory Locations located on the Western NY Nuclear Service Center Property 7.6.1 Description of Confirmatory Area Selected locations within the property boundary of the WNYNSC were surveyed and sampled . Four sample locations were selected designated Cl, C2, C3, and C4 (pg. 6, Figure 1).

7 .6.2 Survey and Sampling Methodology for Confirmatory Area No GPS survey was performed since the primary objective was to survey and sample predesignated locations.

Direct radiation readings and soil samples were collected in the four locations as described above and in Table 4 of the Plan.

Each location was surveyed and sampled as follows:

  • Tissue equivalent dose rate readings were collected at 1 and 100 cm from the ground surface using the Bicron tissue equivalent survey meter.
  • Static 2" x 2" Nal detector readings were collected at 1 and 100 cm elevations using the Ludlum Model 2241-2 survey meter coupled to a Ludlum Model 44-10 detector. Two consecutive counts were collected for each reading at each location and averaged .
  • Soil samples were collected at depth intervals of 0 to 5, 5-15, 15-30, and 30-100 cm. A total of 13 samples were collected in accordance with Table 4 of the Plan . Samples were collected from the first Page 95 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas three depths at all locations and an additional sample was collected from the 30-100 cm at location C.2.

7.6.3 Survey and Sampling Results for Confirmatory Area As noted above, no GPS survey was required since the objective was to survey and sample at 4 predetermined locations. These areas were selected based on historical process knowledge (e .g.,

Cesium Prong, effluent liquid discharge) along with two locations that may be attributed to direct radiation shine from the WVDP .

Static 2"x2" Nal Detector Gross Readings at the 100 cm Elevation

  • The WNYNSC Confirmatory Area static readings using the 2" x2" Nal detector were averaged between two counts at each location and ranged from 7812 CPM to 16586 CPM . The average across all locations was 11405 CPM .
  • The applicable background count rate for WNYNSC Confirmatory Area was determined to be 6333 CPM .

These values are likely elevated in part due to the proximity of locations Cl and C2 to the WVDP.

A tabulation of the static count rates is provided in Appendix H32.

Tissue Equivalent Survey Meter Readings Table 55 provides the dose rates based upon the tissue equivalent meter readings including background for each sample location.

Table SS. WNYNSC On-Center Confirmatory ~ocation Tissue Equivalent Dose Rate Readings Dose Rate at 100 cm Sample Location

(µrem/hour)

C.1 10 C.2 10 C.3 6 C.4 8 Readings are inclusive of background rad iation Soil Sample Concentrations Four soil samples from the 0-5 cm depth and one sample from the 30-100 cm depth were analyzed by gamma spectroscopy, gross alpha, and gross beta activity. The data is summarized in Table 56.

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Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 56. WNYNSC On-Center Confirmatory Soil Concentrations Including Background Sample Depth Alpha* Beta* Cesium*

Location (cm) (pCi/g) (pCi/g) (pCi/g)

C.1 0-5 9.4E+OO +/- 3.2E+OO 2.9E+Ol +/- 2.82E+OO l.2E+OO +/- 1.4E-01 C.2 0-5 8.lE+OO +/- 3.lE+OO 2.0E+Ol +/- 3.40E+OO 8.7E+OO +/- 2.4E-01 C.3 0-5 l.OE+Ol +/- 3.4E+OO 8.7E+OO +/- 2.27E+OO 9.4E-01 +/-2.lE-01 C.4 0-5 2.2E+Ol +/- 5.lE+OO 4.0E+Ol +/- 4.42E+OO l.4E+OO +/- l.7E-01 C.2 30-100 l.3E+Ol +/- 3.9E+OO 4 .7E+Ol +/- 4 .09E+OO 3 .0E+Ol +/- 5.7E-01

  • Uncertainty is reported+/- 1 sigma The individual sample numbers, depths, concentrations, uncertainties, and MDLs are provided in Appendix H2.

7.6.4 Estimation of Dose Rates Based Upon 2014 Aerial Survey Results Figure 51 is an image extracted from Figure 15 of the 2014 Aerial Survey onto which the locations of the Confirmatory locations have been marked .

Figure 51. WNYNSC Confirmatory Locations on 2014 Aerial Survey Exposure Rate 3-4 4.5 m s..s C2 7

  • 9 7-11

\t-10 10-20

- 20-100 C1

  • - 100-200 llllJl a3G-4:xl WNYlllSC Coolnna<O<y S11111ple Loc4li005 C3 Pa ge 97 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 57 presents the estimated dose rates based on the 2014 Aerial Survey inclusive of background .

Consistent with the methodologies of the Aerial Survey, a value of 4.8 was added to all readings to account for the contribution to background from cosmic radiation and airborne radon .

Table 57. Dose Rates Based Upon 2014 Aerial Survey Results Dose Rate Range Average Dose Cosmic + Radon Total Dose Location from Map Rate Dose Rate Rate

(µR/hour) (µR/hour) (µR/hour) (µR/hour)

C.1 3-4 3.5 4.8 8.3 C.2 5-6 5.5 4.8 10.3 C.3 5-6 5.5 4.8 10.3 C.4 7-8 7.5 4.8 12.3 Because these confirmatory locations all reside within the NRC-licensed area of the WNYNSC, a dose assessment using current land use and comparison to the NRC regulatory requirement of less than 25 millirem per year per 10 C.F .R. § 20.1402 was not conducted.

7 .6.5 Conclusions for Area 5 Annual doses based on the Aerial Survey and tissue equivalent survey meter readings for Area 5, which is located on the SNI, will be calculated based on culturally specific aspects of land use surveys. This version of the report will be revised to add the modeled dose assessments for Areas 4 and 5 once the culturally specific aspects of land use surveys are finalized .

8.0 Final Summary In summary, with the exception of Sub-Area 3.1, no elevated regions were discerned in the GPS survey data outside of the five areas identified in the 2014 WNYNSC Aerial Survey. For Sub-Area 3.1, an elevated region was identified immediately adjacent to the surveyed area . This area was surveyed, sampled, and included in the dose assessment for Sub-Area 3.1. Areas 1, 2, and 3 were assessed using the methods as described in th is report and all of the results indicate that the radiation exposures to the public are substantially below the NRC regulatory free release requirement of 25 mrem per year in accordance with 10 C.F.R. § 20.1402.

Areas 4 and 5 were surveyed and sampled . Only the Aerial Survey data and tissue equivalent survey meter readings were assessed . Analysis of dose based upon soil concentrations is pending based on the need to further evaluate current and future aspects of culturally specific land uses. This report will be revised to add the modeled dose assessments for Areas 4 and 5 once the culturally specific aspects of land use surveys are finalized .

It should be noted, that for many of the exposure pathways in Areas 1, 2, and 3, the dose was determined to be less than 10 percent of the applicable dose criteria (i.e. less than 2.5 mrem/year). In Page 98 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas accordance with NRC NUREG-1757 (NRC Consolidated Decommissioning Guidance, Section 3.3 of Volume 2) (Ref. 19), the NRC considers these exposure pathways insignificant contributors .

The following is a more detailed summary of the dose assessment for each area. Additional detail is provided for each area in Sections 7.1through7.6, and Appendix Hof this report. As can be seen in the tables below, the doses calculated for Areas 1, 2 and 3 were well below the 25 mrem per yea r limit imposed by 10 C.F .R. § 20.1402.

8.1 Area 1 Area 1 consisted of three discrete locations within a Cesium Prong as it extends outward beyond the boundaries of the WNYNSC (Figure 1). The Cesium Prong is a large area northwest of the WVDP where surface soil became contaminated with Cs-137 when ventilation system filters failed in 1968. Because the Cesium Prong was extensively characterized in the 1990s (Ref. 10), the samples collected in this area were compared to decay-!=orrected results from the earlier investigation . The Plan specified that a dose assessment would be conducted if the comparison of the newly collected data varied by 10 percent.

Two designated locations {1.1 and 1.2) were in close proximity to each other and the data collected was compa red to historic data from Location L12 in the 1995 Off-Site Investigation of the Cesium Prong.

" For Dose assessment purposes, these two locations were averaged and assessed as "L-12 ." The third location designated (Location 1.3) was closer to the WNYNSC boundary, and it was compared to location

" L-23" from the 1995 Report.

Doses were assessed for L12 and L23 using the methodologies described in Section 6. Table 58 below summarizes the assessed doses using the assessment methodologies.

Table 58. Area 1 Calculated Annual Dose (mrem/year)

Dose Assessment Method L12 L23 Model Aerial Survey 0.0 0.0 Resident Homemaker Tissue Equivalent Meter 2.4 8.0 Resident Homemaker Current Use RESRAD Calculation 1.0 0.2 Resident Homemaker DCGL Comparison Below Below Resident Farmer Potential Use Calculation 1.7 0.4 Resident Farmer Fish Consumption <0.1 <0.1 n/a 8.2 Area 2 Area 2 consisted of two sub-areas designated 2.1 and 2.2 (Figure 2) . The two sub-areas are located northwest of the WNYNSC in an area transected by Route 219, and in general proximity to Scoby Dam .

Both areas are small, sloped and heavily wooded . The suspected pathway of contamination for Area 2 is airborne deposition .

Page 99 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Doses were assessed for Sub-Area 2.1 and Sub-Area 2.2 using the methodologies described in Section 6.

Table 59 summarizes the assessed doses using the assessment methodologies.

Table 59. Area 2 Calculated Annual Dose (mrem/year)

Dose Assessment Method 2.1 2.2 Model Aerial Survey 0.0 0.0 Recreational Hiker/Hunter Tissue Equivalent Meter 0.4 0.0 Recreational Hiker/Hunter Current Use RESRAD Calculation 0.0 0.0 Recreational Hiker/Hunter DCGL Comparison Below Below Resident Farmer Potential Use Calculation n/a 0.1 Resident Farmer Fish Consumption <0.1 <0.1 n/a 8.3 Area 3 Area 3 is located on a farm at the confluence of Buttermilk and Cattaraugus Creeks (Figure 3) . It consists of two sub-areas designated 3.1 and 3.2. Sub-Area 3.1 is a larger parcel on which corn for livestock feed is grown . Sub-Area 3.2 is a small, sloped parcel that lies between the road and the farmhouse.

Doses were assessed for Sub-Area 3.1 and Sub-Area 3.2 using the methodologies described in Section 6.

Table 60 summarizes the assessed doses using the assessment methodologies .

Table 60. Area 3 Calculated Annual Dose (mrem/year)

Dose Assessment Method 3.1 3.2 Model Aerial Survey 1.8 0.2 Resident Farmer Tissue Equivalent Meter 3.9 0.0 Resident Farmer Current Use RESRAD Calculation 0.8 0.0 Resident Farmer DCGL Comparison Below Below Resident Farmer Potential Use Calculation 7.2 0.3 Resident Farmer Fish Consumption <0.1 <0.1 n/a 8.4 Area 4 Area 4 lies approximately 20 miles to the west of the WNYNSC in the flood plain of Cattaraugus Creek (Figure 4) . It includes five sub-areas designated 4.1, 4.2, 4.3, 4.4, and 4.5. All of the sub-areas are wooded and no residences are located within the area .

Doses were assessed for each sub-area using the methodologies described in Section 6. Table 61 summarizes the assessed doses using the two assessment methodologies.

Page 100 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas Table 61. Area 4 Calculated Annual Dose (mrem/year)

Dose Assessment Method 4.1 4.2 4.3 4.4 4.5 Model Aerial Survey TBD* 0.0 0.0 0.0 0.0 TBD*

Tissue Equivalent Meter TBD* 0.0 0.0 0.0 0.0 TBD*

  • Culturally specific land use needed .

8.5 Area 5 Area 5 lies approximately 17 miles to the west of the WNYNSC on a plateau well above the floodplain of Cattaraugus Creek (Figure 5) . It includes six sub-areas designated 5.1, 5.2, 5.3, 5.4, 5.5, and 5.6. All of the Sub-Areas are wooded and no residences are located within the area .

Doses were assessed for each sub-area using the methodologies described in Section 6. Table 62 summarizes the assessed doses using the two assessment methodologies.

Table 62. Area 5 Calculated Annual Dose (mrem/year)

Dose Assessment Method 5.1 5.2 5.3 5.4 5.5 5.6 Model Aerial Survey TBD* TBD* TBD* TBD* TBD* TBD* TBD*

Tissue Equivalent Meter TBD* TBD* TBD* TBD* TBD* TBD* TBD*

  • Culturally specific land use needed.

8.6 Confirmatory Area Four selected locations on the WNYNSC Property were identified for survey and sampling (Figure 6) .

These were considered " Confirmatory" locations to compare Aerial Survey results to areas known or suspected to be contaminated . Because these confirmatory locations all reside within the NRC-Licensed area of the WNYNSC and the subject of a future Decommissioning Plan, a dose assessment was not conducted .

9.0 References 1 An Aerial Radiological Survey of the Western New York Nuclear Service Center (Remote Sensing Laboratory, National Securities Technologies, LLC) October 2015 2 U.S. Nuclear Regulatory Commission, Standards for Protection against Radiation, 10 CFR Part 20.1402, Radiological Criteria for Unrestricted Use 3 Phase 1 Decommissioning Plan for the West Valley Demonstration Project, Rev. 2, December 2009.

4 Project Field Sampling and Dose Assessment Plan 5 Evaluation of Radiochemical Data Usability (DOE, 1997).

Pag e 101 of 102

Radiological Survey and Dose Assessment Report for the WNYNSC and Off-Site Areas 6 RESRAD-OFFSITE 3.1, July 2013, Argonne National Laboratory and.User Manual for RESRAD-OFFSITE (NUREG/CR-6937) 7 RESRAD 7.0, April 2014, Argonne National Laboratory 8 West Valley Demonstration Project Annual Site Environmental Report for Calendar Year 2012, (ASER), September 2013 .

9 International Commission on Radiological Protection (ICRP) Publication 68, Dose Coefficients for Intakes by Workers, 1994.

10 1995 Western New York Nuclear Service Center Off-Site Radiation Investigation Summary Report (Dames and Moore) 11 Project Quality Assurance Project Plan (QAPP), MJW.

12 Project Health and Safety Plan, MJW.

13 U.S. EPA QA/G-4 Guidance for the Data Quality Objectives Process, 2006.

14 U.S. EPA QA R-5, EPA Requirements for Quality Assurance Project Plans, 2001.

15 GEL Quality Assurance Plan, Rev. 29 (Uncontrolled) 16 MJW Technical Services Radioactive Materials License - C3181.

17 WVDP Terrestrial Background Study, 2014.

18 U.S. Environmental Protection Agency's Exposure Factors Handbook, EPA 1997.

19 NUREG 1757, Volume 2, Rev . 1, Consolidated NMSS Decommissioning Guidance Page 102 of 102

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