U.S. Department of Energy 

West Valley Demonstration Project 

Phase 1 Decommissioning Plan for the 

West Valley Demonstration Project

Revision 1 

March 2009 

Prepared by 

Washington Safety Management Solutions, URS Washington Division 

Science Applications International Corporation 

The proposed decommissioning approach described in this plan is based on the preferred 

alternative in the Revised Draft Environmental Impact Statement for Decommissioning and/or 

Long-Term Stewardship at the West Valley Demonstration Project and Western New York 

Nuclear Service Center, which is referred to as the Decommissioning EIS. If changes to that 

document occur during the course of the National Environmental Policy Act process that affect 

this plan, such as changes to the preferred alternative, or if a different approach is selected in 

the Record of Decision, this plan will be revised as necessary to reflect the changes. 
This page is intentionally blank. 
Record of Revisions 

No. Date Purpose 

0 December 2008 Initial issue for U.S. Nuclear Regulatory Commission review. 

1 March 2009 (1) Corrected some page numbers in the Contents. 

(2) Changed the preliminary, order-of-magnitude dose estimate for 

Waste Management Area 2 on page ES-19 from approximately 

0.1 to approximately 0.05 millirem per year. 

(3) Added report USGS 2007 in the Section 3 reference list. 

(4) Incorporated radiological data on subsurface soil from the 2008 

background and Process Building area north plateau 

groundwater plume investigations into Section 4. 

(5) Replaced Figure 5-3 with a modified figure to more accurately 

show the Lavery till depth where samples were taken. 

(6) Revised Table 5-1 to reflect the 2008 radiological data. 

(7) Corrected values in Table 5-10 and Table 5-11 to be consistent 

with Table C-1. 

(8) Revised Section 5.4.4 to show a maximum of 1.3 millirem per 

year for Waste Management Area 1 and 0.04 mrem per year for 

Waste management Area 2, clarified basis for estimates. 

(9) Corrected French drain location on Figure 7-10. 

(10) Corrected soil data reference on Figure 7-11 and modified the 

figure to more accurately show the Lavery till depth where 

samples were taken. (This figure is the same as Figure 5-3.) 

(11) Added WVNSCO 2004 to Section 7 references. 

(12) Corrected some values in Table 9-1, 9-2, and 9-3. 

(13) Changed cited page numbers on pages A-12 and A-13. 

(14) Incorporated radiological data on subsurface soil from the 2008 

background and Process Building area north plateau 

groundwater plume investigations into Appendix B. 

(15) Revised Table C-4 to add the 2008 data and to clarify the 

content. 

(16) Added Appendix C, Attachment 2 to provide another electronic 

file (Table C-4B Excel spreadsheet for the preliminary, order-ofmagnitude dose estimates). 

(17) Revised Appendix D to describe additional groundwater modeling 

using revised STOMP model. Corrected French drain location on 

Figure D-2. 

Pages affected by Revision 1 are identified in the list of effective pages that follows. The 

changed portions of these pages are marked with vertical lines in the right margins. New and 

revised words appear in blue. 
This page is intentionally blank. 
WVDP PHASE 1 DECOMMISSIONING PLAN

List of Effective Pages 

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WVDP PHASE 1 DECOMMISSIONING PLAN

List of Effective Pages 

Page Rev Page Rev Page Rev Page Rev Page Rev Page Rev Page Rev 

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2-26 0 3-74 0 4-23 1 5-50 0 9-20 0 B-40 1 

2-27 0 3-75 0 4-24 1 5-51 1 9-21 0 B-41 1 

2-28 0 3-76 0 4-25 1 5-52 1 9-22 0 B-42 1 
WVDP PHASE 1 DECOMMISSIONING PLAN

CONTENTS 

Revision 0 i

 NOTATION (Acronyms, Abbreviations, and Units) ..................................................... xxi

 EXECUTIVE SUMMARY ............................................................................................... ES-1

1.0 INTRODUCTION .............................................................................................................. 1-1

1.1 Purpose. ................................................................................................................. 1-1

1.2 Scope ........................................................................................................................ 1-2

1.3 Background .............................................................................................................. 1-4

1.4 Environmental Impact Statements ........................................................................ 1-7

 1.4.1 Waste Management EIS ................................................................................. 1-7

 1.4.2 Decommissioning EIS ....................................................................................... 1-8

1.5 Decommissioning Criteria .................................................................................... 1-8

1.6 Project Management and Organization ............................................................... 1-9

1.7 Health and Safety Program ................................................................................. 1-11

1.8 Environmental Monitoring and Control ............................................................. 1-11

1.9 Radioactive Waste Management ........................................................................ 1-13

1.10 Planned End States Before and After Phase 1 ................................................. 1-14

 1.10.1 The Interim End State ................................................................................... 1-14

 1.10.2 Facilities and Areas Within Phase 1 Scope .................................................. 1-18

1.11 Organizational Responsibilities .......................................................................... 1-22

 1.11.1 DOE .............................................................................................................. 1-23

 1.11.2 NRC .............................................................................................................. 1-23

 1.11.3 NYSERDA .................................................................................................... 1-24

1.12 Organization of This Plan .................................................................................... 1-24

1.13 Control of Changes .............................................................................................. 1-24

1.14 References ............................................................................................................ 1-25

2.0 FACILITY OPERATING HISTORY .................................................................................. 2-1

 2.1 License History ......................................................................................................... 2-2 

 2.1.1 Nuclear Fuel Services Operations From 1966 to 1982 .................................. 2-5

 2.1.2 West Valley Demonstration Project From 1982 to 2008 ............................... 2-15

 2.2 Site Decommissioning Activities (1966 – 2011) .................................................. 2-19
WVDP PHASE 1 DECOMMISSIONING PLAN

CONTENTS 

Revision 0 ii

 2.2.1 NFS Remediation Activities (1966 – 1981) ................................................... 2-20

 2.2.2 WVDP Remediation Activities (1982 – 2011) ................................................ 2-20

 2.2.3 Planned Remediation Prior to Decommissioning .......................................... 2-22

 2.3 Spills and Uncontrolled Release of Radioactivity ............................................... 2-33

 2.3.1 North Plateau Groundwater Plume. .............................................................. 2-33 

 2.3.2 Old Sewage Plant Drainage .......................................................................... 2-36

 2.3.3 The Cesium Prong ........................................................................................ 2-37 

 2.3.4 Summary of Spills During NFS Operations .................................................. 2-37

 2.3.5 WVDP Spills ................................................................................................. 2-41 

 2.4 Prior Onsite Burials ................................................................................................ 2-42

 2.4.1 Lagoon 1 ........................................................................................................ 2-43

 2.4.2 The NRC-Licensed Disposal Area ............................................................... 2-43

 2.4.3 Other Burial Locations .................................................................................. 2-47

2.5 References .............................................................................................................. 2-47

3.0 FACILITY DESCRIPTION ................................................................................................ 3-1

 3.1 Site Location and Description ................................................................................. 3-2 

 3.1.1 Site Location ................................................................................................... 3-2

 3.1.2 Site Description ............................................................................................... 3-2

 3.1.3 Facility Description .......................................................................................... 3-3

 3.1.4 Surrounding Communities, Businesses, and Transportation System ........... 3-25 

 3.2 Population Distribution .......................................................................................... 3-28

 3.2.1 Local Population Data ................................................................................... 3-28

 3.2.2 Population Distribution ................................................................................. 3-30

 3.3 Current and Future Land Use ................................................................................ 3-33

 3.3.1 Current Land Use. ......................................................................................... 3-33 

 3.3.2 Summary of Anticipated Land Uses .............................................................. 3-36 

 3.4 Meteorology and Climatology ............................................................................... 3-38

 3.4.1 The General Climate of Western New York .................................................. 3-38

 3.4.2 Severe Weather Phenomena ........................................................................ 3-39
WVDP PHASE 1 DECOMMISSIONING PLAN

CONTENTS 

Revision 0 iii

 3.4.3 Weather-Related Radionuclide Transmission Factors .................................. 3-40

 3.4.4 Weather-Related Site Deterioration Parameters ........................................... 3-40

 3.4.5 Site Meteorology and Climatology ................................................................. 3-41

 3.5 Geology and Seismology ....................................................................................... 3-45

 3.5.1 Regional Physiography ................................................................................. 3-45

 3.5.2 Site Stratigraphy ............................................................................................ 3-45 

 3.5.3 Site Geomorphology ...................................................................................... 3-49

 3.5.4 Regional Structure and Tectonics ................................................................ 3-52

 3.5.5 Historical Seismicity ...................................................................................... 3-58 

 3.5.6 Evaluation of Seismic Hazard ....................................................................... 3-61

 3.6 Surface Hydrology .................................................................................................. 3-62

 3.6.1 Hydrologic Description .................................................................................. 3-62

 3.6.2 WVDP Effluents ............................................................................................. 3-65

 3.6.3 Influence of Flooding on Site ......................................................................... 3-65

 3.6.4 Water Use ...................................................................................................... 3-65

 3.7 Groundwater Hydrology ........................................................................................ 3-67

 3.7.1 Description of the Saturated Zone ................................................................. 3-67

 3.7.2 Monitoring Wells ............................................................................................ 3-69

 3.7.3 Physical Hydrogeologic Parameters in the Saturated Zone ......................... 3-70

 3.7.4 Unsaturated Zone .......................................................................................... 3-70

 3.7.5 Description of Unsaturated Zone Monitoring Stations................................... 3-72

 3.7.6 Physical Parameters ..................................................................................... 3-72

 3.7.7 Numerical Analysis Techniques .................................................................... 3-72

 3.7.8 Distribution Coefficients ................................................................................. 3-73

 3.7.9 Hydraulic Properties ...................................................................................... 3-78

 3.8 Natural Resources .................................................................................................. 3-79

 3.8.1 Natural Gas and Oil ....................................................................................... 3-79

 3.8.2 Mineral Resources ........................................................................................ 3-80

 3.8.3 Water Resources ........................................................................................... 3-80
WVDP PHASE 1 DECOMMISSIONING PLAN

CONTENTS 

Revision 1 iv

 3.8.4 Timber Resources ......................................................................................... 3-81

 3.8.5 Renewable Energy Resources ...................................................................... 3-82

3.9 References ............................................................................................................. 3-82

4.0 RADIOLOGICAL STATUS OF FACILITY ....................................................................... 4-1

 4.1 Radiological Status of Facilities, Systems, and Equipment ................................ 4-2

 4.1.1 Sources of Available Data .............................................................................. 4-2 

 4.1.2 Impacted Facilities .......................................................................................... 4-5

 4.1.3 Non-Impacted Facilities ............................................................................... 4-12

 4.1.4 Radionuclide Distributions ........................................................................... 4-12

 4.1.5 Radiological Status of Facilities .................................................................... 4-16

 4.2 Radiological Status of Environmental Media ...................................................... 4-23

 4.2.1 Data Sources ................................................................................................ 4-24

 4.2.2 Background Levels ....................................................................................... 4-25

 4.2.3 Radiological Status of Surface Soil and Sediment ....................................... 4-28

 4.2.4 Radiological Status of Subsurface Soil ....................................................... 4-30

 4.2.5 Radiological Concentrations Exceeding Background in Surface Soil, 

Sediment, and Subsurface Soil By WMA ..................................................... 4-35

 4.2.6 Environmental radiation Levels ..................................................................... 4-48

 4.2.7 Radiological Status of Onsite Surface Water ............................................... 4-54

 4.2.8 Radiological Status of Groundwater ............................................................. 4-57

4.3 References ............................................................................................................. 4-67

5.0 DOSE MODELING ........................................................................................................... 5-1 

 5.1 Introduction ............................................................................................................... 5-2 

 5.1.1 Applicable Requirements and Guidance ......................................................... 5-2 

 5.1.2 Context for DCGL Development ..................................................................... 5-2 

 5.1.3 Context for the Integrated Dose Assessment ................................................. 5-9 

 5.1.4 Potential Impact from Long-Term Erosion ................................................... 5-13 

 5.1.5 Potential Changes in Groundwater Flow Fields ........................................... 5-14 

 5.1.6 Seepage of Groundwater ............................................................................. 5-15 
WVDP PHASE 1 DECOMMISSIONING PLAN

CONTENTS 

Revision 1 v

 5.1.7 Potential Impacts on the Kent Recessional Sequence ................................ 5-16 

 5.1.8 General Dose Modeling Process ................................................................. 5-17 

 5.2 DCGL Development ................................................................................................ 5-19 

 5.2.1 Conceptual Models for DCGL Development ................................................. 5-20 

 5.2.2 Mathematic Model ......................................................................................... 5-31 

 5.2.3 Summary of Results ...................................................................................... 5-33 

 5.2.4 Discussion of Sensitivity Analyses and Uncertainty ..................................... 5-35 

 5.3 Limited Site-Wide Dose Assessment ................................................................... 5-43 

 5.3.1 Basis for this Assessment ............................................................................ 5-44 

 5.3.2 Assessment Approach .................................................................................. 5-44 

 5.3.3 Results of the Assessments .......................................................................... 5-45 

 5.4 Cleanup Goals and Additional Analyses ............................................................. 5-46 

 5.4.1 Cleanup Goals .............................................................................................. 5-46 

 5.4.2 Refining DCGLs and Cleanup Goals ............................................................ 5-50 

 5.4.3 Use of a Surrogate Radionuclide DCGL ...................................................... 5-50 

 5.4.4 Preliminary Dose Assessment ...................................................................... 5-50 

 5.4.5 Final Dose Assessment ................................................................................ 5-51 

5.5 References .............................................................................................................. 5-51 

6.0 ALARA ANALYSIS .......................................................................................................... 6-2 

 6.1 Introduction ............................................................................................................... 6-2

 6.1.1 Applicable Requirements and Guidance ......................................................... 6-2

 6.1.2 Remediation Activities of Interest .................................................................... 6-3

 6.1.3 The DCGLs Involved ...................................................................................... 6-3

 6.2 Achieving a Decommissioning Goal Below the Dose Limits ............................... 6-3

 6.2.1 Phase 1 Proposed Decommissioning Strategy Promotes ALARA ................. 6-4

 6.2.2 Conservatism in DCGL Development ............................................................. 6-5

6.3.3 Conservatism from the Decontamination and Final Status Survey 

Processes ........................................................................................................ 6-5

 6.3 DCGL ALARA Analysis ............................................................................................ 6-5

 6.3.1 ALARA Analysis Guidance ............................................................................ 6-5
WVDP PHASE 1 DECOMMISSIONING PLAN

CONTENTS 

Revision 1 vi

 6.3.2 Calculating Benefits and Costs ....................................................................... 6-6

 6.3.3 Surface Soil Preliminary ALARA Analysis ...................................................... 6-8

 6.3.4 Subsurface Soil Preliminary ALARA Analysis ................................................ 6-9

 6.3.5 Streambed Sediment Preliminary ALARA Analysis ........................................ 6-9

 6.4 Additional Analyses ............................................................................................... 6-10

6.5 References .............................................................................................................. 6-10

7.0 PLANNED DECOMMISSIONING ACTIVITIES ............................................................... 7-1 

 7.1 Conditions at the Beginning of the Phase 1 Decommissioning Work .............. 7-2

 7.2 General Approach and General Requirements ................................................... 7-3

 7.2.1 General Approach .......................................................................................... 7-3

 7.2.2 General Requirements ................................................................................... 7-5

 7.3 WMA 1 Proposed Decommissioning Activities ................................................... 7-9

 7.3.1 Characterizing Soil and Streambed Sediment ............................................. 7-10

 7.3.2 Relocating the Vitrified HLW Canisters ........................................................ 7-10

 7.3.3 Removing the Above-Grade Portion of the Process Building ...................... 7-14

 7.3.4 Removing the Above-Grade Portion of the Vitrification Facility .................. 7-16

 7.3.5 Removing the 01-14 Building and the Vitrification Off-Gas Line ................ 7-17

 7.3.6 Removing the Load-In/Load-Out Facility ..................................................... 7-17

 7.3.7 Removing Other WMA 1 Structures ............................................................ 7-18

 7.3.8 Removing the Underground Structures and Equipment and the 

Plume Source Area ...................................................................................... 7-19

 7.3.9 Site Restoration ........................................................................................... 7-26

 7.4 WMA 2 Proposed Decommissioning Activities ................................................. 7-27

 7.4.1 Characterizing Soil and Sediment ................................................................ 7-28

 7.4.2 Removing Structures .................................................................................... 7-28

 7.4.3 Decommissioning the Lagoons .................................................................... 7-29

 7.5 WMA 3 Proposed Decommissioning Activities ................................................. 7-34

 7.5.1 Removing Structures ................................................................................... 7-34

 7.5.2 Removing the Waste Tank Pumps and Pump Support Structures ............. 7-35

 7.5.3 Removing the HLW Transfer Trench Piping and Equipment ...................... 7-35
WVDP PHASE 1 DECOMMISSIONING PLAN

CONTENTS 

Revision 1 vii

 7.5.4 Monitoring and Maintenance ....................................................................... 7-36

 7.6 WMA 5 Proposed Decommissioning Activities ................................................. 7-36

 7.6.1 Removing Lag Storage Addition 4 and the Shipping Depot ........................ 7-36

 7.6.2 Removing the Remote-Handled Waste Facility .......................................... 7-37

 7.6.3 Removing Remaining Floor Slabs and Foundations and Gravel Pads ...... 7-37

 7.7 WMA 6 Proposed Decommissioning Activities ................................................. 7-38

 7.7.1 Removing the Sewage Treatment Plant ...................................................... 7-38

 7.7.2 Removing the Equalization Basin ............................................................... 7-38

 7.7.3 Removing the Equalization Tank ................................................................. 7-38

 7.7.4 Removing the Demineralizer Sludge Ponds ................................................ 7-39

 7.7.5 Removing the South Waste Tank Farm Test Tower .................................... 7-39

 7.7.6 Removing the Remaining Floor Slabs and Foundations ............................. 7-39

 7.8 WMA 7 Proposed Decommissioning Activities ................................................. 7-39

 7.9 WMA 9 Proposed Decommissioning Activities ................................................. 7-39

 7.10 WMA 10 Proposed Decommissioning Activities ............................................... 7-40

 7.11 Remedial Technologies ..................................................................................... 7-40

 7.11.1 Pipe Cutting and Other Metal Cutting ......................................................... 7-41

 7.11.2 Tool Positioning Technologies .................................................................... 7-42

 7.11.3 Concrete Cutting and Demolition ............................................................... 7-43

 7.11.4 Concrete Decontamination ........................................................................ 7-44

 7.11.5 Demolition of Structures ............................................................................. 7-46

 7.11.6 Excavation and Grading ............................................................................. 7-47

7.12 Schedule ............................................................................................................... 7-48

 7.13 References .......................................................................................................... 7-50

8.0 QUALITY ASSURANCE PROGRAM .............................................................................. 8-1

 8.1 Quality Assurance Organization ............................................................................ 8-2 

 8.1.1 Quality Assurance Organization Duties and Responsibilities ....................... 8-3 

 8.1.2 Decommissioning Project Quality Assurance Duties and 

Responsibilities .............................................................................................. 8-4 

 8.2 Assuring Quality in Preliminary Engineering Work ............................................. 8-4 
WVDP PHASE 1 DECOMMISSIONING PLAN

CONTENTS 

Revision 1 viii

 8.2.1 Dose Modeling .............................................................................................. 8-4

 8.2.2 Engineered Barrier Design ............................................................................ 8-5

 8.2.3 Other Engineering Work ................................................................................ 8-6

 8.3 Decommissioning Quality Assurance Program ................................................... 8-6

 8.3.1 General Description of the Program .............................................................. 8-7

 8.3.2 Characterization and Final Status Survey Data .............................................. 8-7

 8.3.3 Engineering Design and Data, Calculations, and Modeling ......................... 8-10

 8.4 Document Control ................................................................................................. 8-11 

 8.5 Control of Measuring and Test Equipment ......................................................... 8-12

 8.6 Control of Purchased Material and Subcontractor Services ............................ 8-12

 8.7 Corrective Action ................................................................................................... 8-12

 8.8 Audits and Surveillances ...................................................................................... 8-13

 8.9 Quality Assurance Records .................................................................................. 8-13

8.10 References ........................................................................................................... 8-14

9.0 FACILITY RADIATION SURVEYS .................................................................................. 9-1

 9.1 Release Criteria ....................................................................................................... 9-2

 9.2 Types of Surveys and Their Purposes .................................................................. 9-5 

 9.2.1 Background Surveys ..................................................................................... 9-5

 9.2.2 Scoping Surveys ............................................................................................ 9-5

 9.2.3 End-of-Task Surveys ..................................................................................... 9-6

 9.2.4 Characterization Surveys ............................................................................... 9-6 

 9.2.5 In-Process Surveys ....................................................................................... 9-6

 9.2.6 Final Status Surveys ..................................................................................... 9-7

 9.2.7 Confirmation Surveys .................................................................................... 9-7

 9.3 Background Surveys ............................................................................................... 9-8

 9.4 Characterization Surveys ....................................................................................... 9-8

 9.4.1 Characterization Sample and Analysis Plan Content .................................... 9-8

 9.4.2 Characterization Data Quality Objectives ................................................... 9-12

 9.4.3 Characterization Quality Requirements ...................................................... 9-13
WVDP PHASE 1 DECOMMISSIONING PLAN

CONTENTS 

Revision 1 ix

 9.5 In-Process Surveys ............................................................................................... 9-15 

 9.6 The Phase 1 Final Status Survey ......................................................................... 9-15

 9.6.1 Phase 1 Final Status Survey Plan Content ................................................. 9-15

 9.6.2 Data Quality Objectives for the Phase 1 Final Status Survey ..................... 9-21 

 9.6.3 Phase 1 Final Status Survey Quality Requirements ................................... 9-22

 9.7 The Survey Process by Waste Management Area ............................................. 9-22

 9.7.1 WMA 1 Process Building and Vitrification Facility Area .............................. 9-22

 9.7.2 WMA 2 Low-Level Waste Treatment Facility Area ...................................... 9-26

 9.7.3 WMA 3 Waste Tank Farm Area .................................................................. 9-29 

 9.7.4 WMA 5 Waste Storage Area ....................................................................... 9-29

 9.7.5 WMA 6 Central Project Premises ................................................................. 9-32

 9.7.6 WMA 7 NDA and Associated Facilities ....................................................... 9-33

 9.7.7 WMA 8, State-Licensed Disposal Area ....................................................... 9-33

 9.7.8 WMA 9, Radwaste Treatment System Drum Cell Area .............................. 9-33

 9.7.9 WMA 10, Support and Services Area .......................................................... 9-34

 9.7.10 WMA 11, Bulk Storage Warehouse and Hydrofracture Test Well Area ..... 9-35

 9.7.11 WMA 12, Balance of the Site ..................................................................... 9-35

 9.7.12 Environmental Media .................................................................................. 9-35

 9.8 Phase 1 Final Status Survey Report Requirements ........................................... 9-37

 9.8.1 Overview of Results .................................................................................... 9-37

 9.8.2 Discussion of Changes ................................................................................ 9-37 

 9.8.3 Description of How Numbers of Samples Were Determined ...................... 9-37 

 9.8.4 Sample Number Determination Values ....................................................... 9-37

 9.8.5 Results for Each Survey Unit ...................................................................... 9-37

 9.8.6 Survey Unit Changes .................................................................................. 9-38

 9.8.7 Actions Taken for Failed Survey Units ........................................................ 9-38

 9.8.8 Impact of Survey Unit Failures .................................................................... 9-38

9.9 References ............................................................................................................. 9-38
WVDP PHASE 1 DECOMMISSIONING PLAN

CONTENTS 

Revision 1 x

APPENDIX 

A Decommissioning Plan Annotated Checklist ........................................................... A-1 

B Environmental Radioactivity Data ............................................................................ B-1 

C Details of DCGL Development and the Integrated Dose Assessment .................... C-1 

D Engineered Barriers and Post-Remediation Activities ............................................. D-1 

FIGURES

ES-1 Location of the Western New York Nuclear Service Center ................................ ES-3 

ES-2 The Former Nuclear Fuel Reprocessing Plant and the WVDP in 2006 .............. ES-4 

ES-3 Waste Management Areas 1-10 ........................................................................... ES-6 

ES-4 The Plant During the Early Years ...................................................................... ES-10 

ES-5 Important Sources of Radioactive Contamination on the Project Premises ...... ES-13 

1-1 The Former Nuclear Fuel Reprocessing Plant and the WVDP in 2006 ................ 1-5 

1-2 The Project Premises Showing WMAs and the Phase 1 Excavations ................. 1-15 

1-3 WMA 1 Area in 2007 ............................................................................................. 1-16 

1-4 WMA 2 in 2007 ..................................................................................................... 1-17 

1-5 Facilities Within the Scope of Phase 1 of the Decommissioning, North Plateau .. 1-20 

1-6 Facilities Within the Scope of Phase 1 of the Decommissioning, South Plateau . 1-21 

1-7 The WVDP in the Interim End State ..................................................................... 1-22 

1-8 The WVDP After Completion of Phase 1 .............................................................. 1-22 

2-1 Spent Fuel Reprocessing Diagram (PUREX Process) ............................................ 2-7 

2-2 Simplified HLW Pretreatment Process Diagram ................................................... 2-16 

2-3 Previous and Current Locations of Radionuclides in North Plateau Facilities 

at the WVDP ......................................................................................................... 2-22 

2-4 Previous and Current Locations of Radionuclides in South Plateau Facilities 

at the WVDP ......................................................................................................... 2-23 

2-5 Location of Process Building Remediation Activities for Site facilities Prior 

to Phase 1 of the Proposed Decommissioning ..................................................... 2-24 

2-6 Sr-90 Groundwater Plume on the North Plateau .................................................. 2-34 

2-7 1984 Aerial Radiation Survey Isopleths of the WVDP and Surrounding Area ...... 2-38 

2-8 NDA Disposal Area Burials ................................................................................... 2-46 
WVDP PHASE 1 DECOMMISSIONING PLAN

CONTENTS 

Revision 1 xi

FIGURES

3-1 Location of the Center in Western New York ........................................................ 3-89 

3-2 The Center, the WVDP, and the Surrounding Area ............................................... 3-90 

3-3 Topography of the Western New York Nuclear Service Center ............................ 3-91 

3-4 Topography of Project Premises, Showing 100-Year Floodplain .......................... 3-92 

3-5 Security Fence Around WVDP Premises Boundary .............................................. 3-93 

3-6 North Plateau Geologic Cross Section ................................................................. 3-94 

3-7 South Plateau Geologic Cross Section ................................................................. 3-94 

3-8 WMAs 1 Through 10 .............................................................................................. 3-95 

3-9 WMAs 11 and 12 ................................................................................................... 3-96 

3-10 WMA 1 ................................................................................................................... 3-97 

3-11 Aerial View of Process Building and Vitrification Facility Area in 2007 ................. 3-98 

3-12 Construction of the Process Building ..................................................................... 3-99 

3-13A Process Building Layout – Below Grade ............................................................. 3-100 

3-13B Process Building Layout at 100-Foot Elevation ................................................... 3-101 

3-13C Process Building Layout at 114.5-Foot Elevation ................................................ 3-102 

3-13D Process Building Layout at 131-Foot Elevation ................................................... 3-103 

3-13E Process Building Layout at 144-Foot Elevation ................................................... 3-104 

3-13F Process Building Layout at 160-Foot Elevation ................................................... 3-105 

3-14 West Side of the Process Building ....................................................................... 3-106 

3-15 Fuel Receiving and Storage Area ........................................................................ 3-106 

3-16 HLW Canisters Stored in the Chemical Process Cell .......................................... 3-107 

3-17 Conditions in the General Purpose Cell in 1999 .................................................. 3-107 

3-18 Process Mechanical Cell During Deactivation ..................................................... 3-108 

3-19 Extraction Cell 3 .................................................................................................. 3-108 

3-20 The Spent Fuel Pool After Deactivation .............................................................. 3-109 

3-21 Equipment Decontamination Room Before Cleanup ........................................... 3-109 

3-22 Vitrification Facility General Arrangement ........................................................... 3-110 

3-23 Vitrification Cell at Time of Startup ...................................................................... 3-110 

3-24 WMA 2 ................................................................................................................. 3-111 
WVDP PHASE 1 DECOMMISSIONING PLAN

CONTENTS 

Revision 1 xii

FIGURES

3-25 The Low-Level Waste Treatment Facility ............................................................ 3-112 

3-26 The LLW2 Building that Replaced the 02 Building ............................................. 3-113 

3-27 The Lagoon 1 Area .............................................................................................. 3-113 

3-28 The New Interceptors ........................................................................................... 3-114 

3-29 WMA 3 ................................................................................................................ 3-115 

3-30 Aerial View of WMA 3 Area ................................................................................ 3-116 

3-31 Cutaway View of 750,000-Gallon HLW Tank ..................................................... 3-116 

3-32 HLW Transfer and Mobilization Pumps .............................................................. 3-117 

3-33 HLW Transfer Trench Under Construction .......................................................... 3-118 

3-34 Typical HLW Pump Pit ......................................................................................... 3-118 

3-35 WMA 5 ................................................................................................................. 3-119 

3-36 The Remote Handled Waste Facility ................................................................... 3-120 

3-37 The Remote Handled Waste Facility First Floor Layout ...................................... 3-120 

3-38 WMA 6 ................................................................................................................. 3-121 

3-39 The Rail Spur ....................................................................................................... 3-122 

3-40 The New Cooling Tower ...................................................................................... 3-122 

3-41 WMA 7 ................................................................................................................. 3-123 

3-42 WMA 9 ................................................................................................................. 3-124 

3-43 WMA 10 ............................................................................................................... 3-125 

3-44 Population Around the WVDP by Compass Vector ............................................. 3-126 

3-45 Land Use in the Vicinity of the Center ................................................................. 3-127 

3-46 Tornado Events in Western New York (1950 – 2002) ........................................ 3-128 

3-47 Thunderstorm Wind Events in Western New York (1950 – 2002) ...................... 3-129 

3-48 Hail Events in Western New York (1950 – 2002) ................................................ 3-130 

3-49 Wind Rose Diagram ............................................................................................ 3-131 

3-50 Cloud Ceiling Information ................................................................................... 3-132 

3-51 Regional Physiographic map .............................................................................. 3-133 

3-52 Bedrock and Glacial Stratigraphy of the WVDP .................................................. 3-134 

3-53 Surface Geology of the Project Premises and the SDA ..................................... 3-135 
WVDP PHASE 1 DECOMMISSIONING PLAN

CONTENTS 

Revision 1 xiii

FIGURES

3-54 Fold and Selected Joint Trends in the Appalachian Plateau of Western 

and Central New York .......................................................................................... 3-136 

3-55 Seismo-Tectonic Map of Western New York Showing Selected 

Regional Geologic Structures ............................................................................. 3-137 

3-56 Major Northwest Trending Lineaments in New York and Pennsylvania ............. 3-138 

3-57 Location of Seismic Lines WVN1 and BER 83-2A ............................................. 3-139 

3-58 Seismic Hazard Curves for Peak Horizontal Acceleration .................................. 3-140 

3-59 Seismic Hazard Curves for 1.0 Second Horizontal Acceleration ....................... 3-141 

3-60 Seismic Source Contributions to Mean Peak Horizontal Acceleration Hazard .. 3-142 

3-61 Buttermilk Creek Drainage Basin ......................................................................... 3-143 

3-62 Groundwater Elevation Contours of the Sand and Gravel Unit, 

First Quarter 2008 ................................................................................................ 3-144 

3-63 Groundwater Elevation Contours of the Weathered Lavery Till, 

First Quarter 2008 ................................................................................................ 3-145 

3-64 Groundwater Elevation Contours of the Lavery Till Sand, 

First Quarter 2008 ................................................................................................ 3-146 

3-65 Groundwater Elevation Contours of the Kent Recessional Sequence, 

First Quarter 2008 ................................................................................................ 3-147 

3-66 Vertical Distribution of Cesium Kd in the Weathered and Unweathered Tills ...... 3-148 

3-67 Vertical Distribution of Iodine Kd in the Weathered and Unweathered Tills ......... 3-148 

3-68 Vertical Distribution of Strontium Kd in the Weathered and Unweathered Tills .. 3-149 

3-69 Locations of Natural Gas and Oil Wells in Western New York ........................... 3-150 

3-70 Locations of Natural Gas and Oil Wells in the Vicinity of the WVDP ................... 3-151 

4-1 Location of Impacted and Non-Impacted Facilities ................................................. 4-7 

4-2 Impacted and Non-Impacted Facilities in WMA 1 .................................................... 4-8 

4-3 Impacted and Non-Impacted Facilities in WMA 2 .................................................... 4-9 

4-4 Impacted Facilities in WMA 3 ................................................................................ 4-10 

4-5 Impacted and Non-Impacted Facilities in WMA 6 .................................................. 4-11 

4-6 Surface Soil and Sediment Locations With Radionuclide Concentrations 

in Excess of Background ....................................................................................... 4-31 

4-7 Subsurface Soil Locations With Radionuclide Concentrations in Excess 

of Background ........................................................................................................ 4-32 
WVDP PHASE 1 DECOMMISSIONING PLAN

CONTENTS 

Revision 1 xiv

FIGURES 

4-8 Cross Section of Sr-90 Concentrations Versus Depth in Subsurface Soil 

in WMA 1 ............................................................................................................... 4-34 

4-9 Onsite Environmental TLD Locations .................................................................... 4-50

4-10 WVDP Radiological Control Areas ........................................................................ 4-53 

4-11 Surface Water Locations With Radionuclide Concentrations in Excess of 

Background ............................................................................................................ 4-55 

4-12 Routine Groundwater Monitoring Locations With Radionuclide 

Concentrations in Excess of Background .............................................................. 4-62 

4-13 Geoprobe® Groundwater Locations with Radionuclide Concentrations 

in Excess of Background ....................................................................................... 4-65 

4-14 North Plateau Groundwater Plume ........................................................................ 4-66 

5-1 Areas of Interest – Surface Soil, Subsurface Soil, and Streambed Sediment 

Within the Project Premises ..................................................................................... 5-3 

5-2 Conceptual Cross Section of WMA 1 Excavation With Representative Data 

on Sr-90 Concentrations .......................................................................................... 5-5 

5-3 Conceptual Cross Section of WMA 2 Excavation With Representative Data 

on Subsurface Soil Contamination .......................................................................... 5-6 

5-4 Sources at the Conclusion of Phase 1 of the Proposed Decommissioning .......... 5-11 

5-5 Locations of Perimeter Seeps on the North Plateau ............................................. 5-15 

5-6 General Dose Modeling Process ........................................................................... 5-18 

5-7 Conceptual Model for Surface Soil DCGL Development ....................................... 5-20 

5-8 Conceptual Model for Subsurface Soil DCGL Development ................................. 5-24 

5-9 Conceptual Model for Stream Sediment DCGL Development .............................. 5-28 

7-1 WMA 1 in 2007 ....................................................................................................... 7-9 

7-2 Conceptual Arrangement for Transferring Vitrified HLW Canisters ...................... 7-12 

7-3 Storage Module Conceptual Design ..................................................................... 7-13 

7-4 Process Building General Arrangement ............................................................... 7-14 

7-5 Layout of Process Building Underground Structures ............................................ 7-20 

7-6 Conceptual Layout of WMA 1 Excavation ............................................................ 7-21 

7-7 Conceptual WMA 1 Excavation Contour, With Selected Subsurface Soil Data ... 7-22 

7-8 Excavation Cross Sections ................................................................................... 7-23 

7-9 WMA 2 in 2007 ..................................................................................................... 7-27 
WVDP PHASE 1 DECOMMISSIONING PLAN

CONTENTS 

Revision 1 xv

FIGURES 

7-10 Conceptual Arrangement of WMA 2 Excavation, Plan View ............................... 7-30 

7-11 Conceptual Arrangement of WMA 2 Excavation, Cross Section ......................... 7-31 

7-12 Typical Demolition Machine ................................................................................. 7-44 

7-13 Moose®

 ................................................................................................................. 7-45 

7-14 Universal Demolition Processor ............................................................................ 7-48 

7-15 Conceptual Schedule of Phase 1 Proposed Decommissioning Activities ........... 7-49 

8-1 Decommissioning Organization Quality Assurance Relationships ........................ 8-2 

B-1 Background Sampling Locations More Than 10 Kilometers From the WVDP ...... B-3 

B-2 Sampling Locations Within 10 Kilometers From the WVDP Used for 

Background Calculations ........................................................................................ B-6 

B-3 Onsite Groundwater and Subsurface Soil Locations Used as Background .......... B-8 

D-1 Plan View of the WMA 1 Excavation ...................................................................... D-4 

D-2 Plan View of the WMA 2 Excavation ...................................................................... D-7 

D-3 North Plateau Groundwater Flow Model Boundary ................................................ D-9 

D-4 Cross Section of North Plateau Near-Field Model – Northwest to Southeast, 

Distance of 0 to 80 Meters .................................................................................... D-10 

D-5 Cross Section of North Plateau Near-Field Model – Northwest to Southeast, 

Distance of 80 to 120 Meters ................................................................................ D-10 

D-6 Cross Section of North Plateau Near-Field Model – Northwest to Southeast, 

Distance of 120 to 250 Meters .............................................................................. D-11 

D-7 Cross Section of North Plateau Near-Field Model – Northwest to Southeast, 

Distance of 250 to 310 Meters .............................................................................. D-11 

D-8 Cross Section of North Plateau Near-Field Model – Northwest to Southeast, 

Distance of 310 to 820 Meters .............................................................................. D-12 

D-9 Groundwater Flow Associated with the WMA 1 and WMA 2 

Engineered Barriers ............................................................................................. D-16 

D-10 Groundwater Monitoring Locations Within the Project Premises During 

the Phase 1 Institutional Control Period ............................................................... D-20

D-11 Surface Water and Sediment Sampling Locations on the Project Premises 

During the Phase 1 Institutional Control Period .................................................... D-25 

D-12 Offsite Surface Water and Sediment Sampling Locations During the 

Phase 1 Institutional Control Period ..................................................................... D-26 
WVDP PHASE 1 DECOMMISSIONING PLAN

CONTENTS 

Revision 1 xvi

FIGURES 

D-13 Storm Water and Sediment Sampling Locations on the Project Premises 

During the Phase 1 Institutional Control Period .................................................... D-28 

D-14 Air Monitoring Locations on the Project Premises During the Phase 1 

Institutional Control Period .................................................................................... D-29 

D-15 Direct Radiation Monitoring Locations on the Project Premises During 

the Phase 1 Institutional Control Period ............................................................... D-30 

D-16 Offsite Direct Radiation Monitoring Locations During the Phase 1 

Institutional Control Period .................................................................................... D-31 

TABLES 

ES-1 DCGLW Values for 25 Millirem per Year (pCi/g) ................................................. ES-17 

ES-2 Cleanup Goals to be Used in Remediation (pCi/g) ............................................ ES-18 

1-1 Facilities and Areas Within Phase 1 Scope .......................................................... 1-19 

2-1 Limits for Nuclear Fuel in Solid Fuel Elements and Solutions ................................ 2-2 

2-2 Limits for Unirradiated Source Material ................................................................... 2-3 

2-3 Limits Used for Standards, Test, Measurements, and Calibrations ........................ 2-3 

2-4 Nuclear Fuel Received and Reprocessed .............................................................. 2-6 

2-5 Estimated Radionuclide Content (in Curies) of Tanks 8D-2 and 8D-4 at the 

Completion of Reprocessing ................................................................................... 2-9 

2-6 Chemical Composition of Tank 8D-2 Supernatant at the Completion of 

Reprocessing ........................................................................................................ 2-11 

2-7 Chemical Composition of Tank 8D-2 Sludge at the Completion of 

Reprocessing .......................................................................................................... 2-8 

2-8 Chemical Composition of Tank 8D-4 Waste at the Completion of 

Reprocessing .......................................................................................................... 2-9 

2-9 Chemical Composition of Glass Waste Form ....................................................... 2-18 

2-10 Typical HLW Canister Radionuclide Content ......................................................... 2-19 

2-11 Activity Removed by NFS for the Period 1972 Through 1977 .............................. 2-20 

2-12 Facilities Shown in Figures 2-3 through 2-6 .......................................................... 2-25 

2-13 Facilities Remediated or to be Remediated by the WVDP 

Before Decommissioning ...................................................................................... 2-26 

2-14 DOE 10 CFR 835 Surface Contamination Guidelines .......................................... 2-31 

2-15 Radiological Areas and Radioactive Material Areas ............................................. 2-32 
WVDP PHASE 1 DECOMMISSIONING PLAN

CONTENTS 

Revision 1 xvii

TABLES 

2-16 Released Radionuclide Activity Estimates for the North Plateau Plume .............. 2-35 

2-17 Principal Radionuclides in Major Spills Occurring During NFS Operations .......... 2-39 

2-18 WVDP Spills Impacting Environmental Media (1982 – 2007) ............................... 2-41 

2-19 Estimated Residual Radioactivity in Lagoon 1 ...................................................... 2-43 

2-20 Summary of Wastes in the NRC-Licensed Disposal Area ..................................... 2-44 

2-21 Estimated Radioactivity in the NDA ...................................................................... 2-45 

3-1 Businesses, Farms, and Community Centers Within a 3.1 Mile Radius of 

the Site ................................................................................................................... 3-26

3-2 2002 Resident Population Estimates by Directional Sector Within a 

3.1 Mile Radius of the Main Plant Stack ................................................................ 3-28

3-3 Nearest Residences by Sector ............................................................................... 3-29

3-4 Number of Residential Wells or Springs Used for Drinking Water By 

Sector Within a 3.1-Mile Radius of the Main Plant Stack ..................................... 3-30

3-5 Locations and Populations of Towns and Villages Partially or Totally 

Within 10 Miles of the Site ..................................................................................... 3-31

3-6 Populations Of Selected Municipalities, Counties, and States Within 50 

Miles of the Site (1960-2000) ................................................................................ 3-32

3-7 Leading Agricultural Products in Cattaraugus County ........................................... 3-34

3-8 2002 Consumable Animal Population Estimates by Sector Within a 3.1-Mile 

Radius of the Main Plant Stack .............................................................................. 3-34

3-9 2002 Crop Estimates in Acres by Sector Within a 3.1-Mile Radius of the 

Main Plant Stack .................................................................................................... 3-35

3-10 Wind Speed and Direction Frequency Distribution at 10 Meters .......................... 3-43

3-11 Wind Speed and Direction Frequency Distribution at 60 Meters .......................... 3-44

3-12 Generalized Paleozoic Stratigraphic Section for Southwestern New York ........... 3-46 

3-13 Summary of Erosion Rates Near the WVDP ........................................................ 3-51 

3-14 Summary of Observed Faults on Seismic Lines WVN-1 and BER83-2A ............. 3-54 

3-15 Historic Seismicity Within 320 Kilometers (200 Miles) of Site ................................ 3-58

3-16 Site-Specific Mean Spectral Accelerations on Hard Rock (g’s) ............................. 3-62 

3-17 Site-Specific Mean Spectral Accelerations on Soil (g’s) for the North Plateau ..... 3-62 

3-18 Site-Specific Mean Spectral Accelerations on Soil (g’s) for the South Plateau .... 3-62 

3-19 WVDP Hydraulic Conductivity (K) Testing Summary Table .................................. 3-70
WVDP PHASE 1 DECOMMISSIONING PLAN

CONTENTS 

Revision 1 xviii

TABLES 

3-20 Distribution Coefficients ......................................................................................... 3-76

3-21 Total Porosity ......................................................................................................... 3-78

3-22 2001 Natural Gas and Oil Production in Ashford, Cattaraugus, and 

Erie Counties, and the State of New York ............................................................. 3-79

4-1 Scaling Factors for Spent Fuel Reprocessed ........................................................ 4-13 

4-2 Batch 10 Sample Data .......................................................................................... 4-14 

4-3 Relative Fractions of Process Building Dominant Radionuclides ......................... 4-15 

4-4 Relative Fractions of Vitrification Facility Dominant Radionuclides ...................... 4-15 

4-5 Estimated Process Building Residual Activity at Start of Decommissioning ........ 4-16 

4-6 Estimated Total Activity in Representative Process Building Areas ..................... 4-16 

4-7 Measured Maximum Gamma Radiation Levels in Process Building Areas .......... 4-17 

4-8 Estimated Total Activity in the Vitrification Facility ................................................ 4-18 

4-9 Estimated Radioactivity in the Underground Waste Tanks ................................... 4-20 

4-10 Estimated Radioactivity in the NDA ...................................................................... 4-22 

4-11 Median and Maximum Background Concentrations for Environmental 

Media at the WVDP ................................................................................................ 4-26 

4-12 Above-Background Concentrations of Radionuclides in Subsurface 

Soil at WMA 1 ........................................................................................................ 4-35 

4-13 Above-Background Concentrations of Radionuclides in Surface Soil From 

WMA 2 ................................................................................................................... 4-36 

4-14 Above-Background Concentrations of Radionuclides in Sediment 

From WMA 2 ......................................................................................................... 4-37 

4-15 Above-Background Concentrations of Radionuclides in Subsurface Soil 

From WMA 2 ......................................................................................................... 4-39 

4-16 Above-Background Concentrations of Radionuclides in Surface Soil 

at WMA 3 ................................................................................................................ 4-40 

4-17 Above-Background Concentrations of Radionuclides in Surface Soil, 

Sediment, and Subsurface Soil From WMA 4 ....................................................... 4-40 

4-18 Above-Background Concentrations of Radionuclides in Surface Soil, 

Sediment, and Subsurface Soil at WMA 5 ............................................................. 4-42 

4-19 Above-Background Concentrations of Radionuclides in Surface Soil, 

Sediment, and Subsurface Soil at WMA 6 ............................................................. 4-43 

4-20 Above-Background Concentrations of Radionuclides in Surface Soil, 

Sediment, and Subsurface Soil at WMA 7 ............................................................. 4-45 
WVDP PHASE 1 DECOMMISSIONING PLAN

CONTENTS 

Revision 1 xix

TABLES 

4-21 Above-Background Concentrations of Radionuclides in Surface Soil and 

Sediment at WMA 10 ............................................................................................. 4-46 

4-22 Above-Background Concentrations of Radionuclides in Surface Soil 

and Sediment at WMA 12 ...................................................................................... 4-47 

4-23 Environmental Radiation Levels on the WVDP Site (1998-2007 Data) ................. 4-51 

4-24 Radionuclide Concentrations (pCi/L) in Excess of Background in 

Surface Water ........................................................................................................ 4-56 

4-25 Routine Groundwater Monitoring Locations With Radionuclide Concentrations 

(pCi/L) in Excess of Background ............................................................................ 4-58 

4-26 Geoprobe® Groundwater Monitoring Points With Radionuclide Concentrations 

(pCi/L) in Excess of Background ............................................................................ 4-63 

5-1 Measured Maximum Lavery Till Radionuclide Concentrations ............................... 5-7 

5-2 Exposure Pathways for Surface Soil DCGL Development .................................... 5-21 

5-3 Key Input Parameters for Surface Soil DCGL Development ................................. 5-22 

5-4 Exposure Pathways for Subsurface Soil DCGL Development .............................. 5-26 

5-5 Key Input Parameters for Subsurface Soil DCGL Development ........................... 5-27 

5-6 Exposure Pathways for Streambed Sediment DCGL Development ..................... 5-29 

5-7 Key Input Parameters for Streambed Sediment DCGL Development ................. 5-31 

5-8 DCGLs For 25 mrem (pCi/g) .................................................................................. 5-33 

5-9 Summary of Parameter Sensitivity Analyses – Surface Soil DCGLs .................... 5-35 

5-10 Summary of Parameter Sensitivity Analyses – Subsurface Soil DCGLs .............. 5-38 

5-11 Summary of Parameter Sensitivity Analyses – Streambed Sediment DCGLs ...... 5-40 

5-12 Limited Site-Wide Dose Assessment 1 Results (DLCG”s in pCi/g) ....................... 5-45 

5-13 Limited Site-Wide Dose Assessment 2 Results (DLCG”s in pCi/g) ....................... 5-46 

5-14 Cleanup Goals to be Used in Remediation in pCi/g .............................................. 5-48 

6-1 Possible Benefits and Costs Related to Decommissioning .................................... 6-6 

7-1 Expected Facility and Area Conditions at the Beginning of Phase 1 ....................... 7-2 

9-1 Surface Soil Cleanup Goal Area Factors ................................................................. 9-3 

9-2 Subsurface Soil Cleanup Goal Area Factors ........................................................... 9-3 

9-3 Streambed Sediment Cleanup Goal Area Factors ................................................... 9-4 

9-4 Radiological Field Instruments ............................................................................... 9-10 
WVDP PHASE 1 DECOMMISSIONING PLAN

CONTENTS 

Revision 1 xx

TABLES 

9-5 Radiological Field Instruments for Phase 1 Final Status Survey ........................... 9-18 

9-6 Scan Surveys for Different Area Classifications .................................................... 9-18 

9-7 Laboratory Methods ............................................................................................... 9-23 

A-1 NUREG-1757 Checklist – Phase 1 Decommissioning Plan Comparison ............... A-2 

B-1 Summary of Comparisons of Radionuclide Data from Test Surface Soil 

Locations vs. SFGRVAL Background ..................................................................... B-4 

B-2 Summary Information for Environmental Medium Background Calculations ......... B-9 

B-3 Surface Soil Background Radionuclide Concentrations for the WVDP ................ B-11 

B-4 Sediment Background Radionuclide Concentrations for the WVDP .................... B-12 

B-5 Subsurface Soil Background Radionuclide Concentrations for the WVDP .......... B-13 

B-6 Surface Water Background Radionuclide Concentrations for the WVDP ............ B-14 

B-7 Groundwater Background Radionuclide Concentrations for the WVDP ............... B-15 

B-8 Background Environmental Radiation Levels the WVDP ..................................... B-16 

B-9 Radionuclides in Surface Soil: Ratios to Cs-137 .................................................. B-22 

B-10 Radionuclides in Sediment: Ratios to Cs-137 ....................................................... B-23 

B-11 Radionuclides in Subsurface Soil: Ratios to Cs-137............................................. B-25 

B-12 Summary of Radionuclide Results from Routine Onsite Sediment 

Monitoring Locations ............................................................................................. B-27

B-13 Summary of Radionuclide Results from Routine Onsite Surface Water 

Monitoring Locations ............................................................................................. B-29 

B-14 Summary of Radionuclide Results from Routine Onsite Groundwater 

Monitoring Locations ............................................................................................. B-33 

B-15 Groundwater Monitoring Locations: Coordinates, Depth, Screened Interval, 

and Geologic Unit .................................................................................................. B-42 

B-16 Location, Elevation, and Depth of Geoprobe® Groundwater Sampling Points ..... B-45 

B-17 Groundwater Points Excluded from the Evaluation .............................................. B-50

C-1 RESRAD Input Parameters ..................................................................................... C-3 

C-2 Soil/Water Distribution Coefficients ....................................................................... C-10 

C-3 Scenario Exposure Pathways for WVDP DCGL Development ............................. C-12 

C-4 Radionuclide Concentrations from Soil Samples Containing Lavery Till 

in the WMA 1 and WMA 2 Excavation Areas ........................................................ C-13 
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CONTENTS 

Revision 1 xxi

TABLES 

C-40 Summary of Surface Soil DCGL Sensitivity Analysis............................................ C-29 

C-66 Summary of Subsurface Soil DCGL Sensitivity Analysis ...................................... C-31 

C-92 Summary of Sediment DCGL Sensitivity Analysis ................................................ C-33 

C-99 Summary of Primary Dose Pathways ................................................................... C-36 

D-1 North Plateau Near-Field Model Calibration for Head .......................................... D-13 

D-2 Summary of Sand and Gravel Unit Flow Balance ................................................. D-14 

D-3 Average Linear Velocity for Flow Path Originating at the Process Building ......... D-14 

D-4 Summary of Sand and Gravel Unit Flow Balance After Phase 1 .......................... D-15 

D-5 Average Linear Velocity for Flow Path Originating at the Process Building 

After Phase 1 ......................................................................................................... D-17 

Note that other tables appear in the Appendix C, Attachment 1 electronic files. 

A single Table (C-4B) is included in the Appendix C, Attachment 2 electronic files. 
This page is intentionally blank.
WVDP PHASE 1 DECOMMISSIONING PLAN

NOTATION 

Revision 1 xxiii

Acronyms and Abbreviations 

AEC U.S. Atomic Energy Commission 

ALARA as low as reasonably achievable 

ASTM American Society for Testing and Materials 

CFR Code of Federal Regulations 

BH bore hole 

CG cleanup goal 

DCGL derived concentration guideline level 

DCGLW derived concentration guideline level, wide 

DCGLEMC derived concentration guideline level, elevated measurement concentration 

DCGLscan derived concentration guideline level, scan 

DOE Department of Energy 

DQO data quality objective 

DSR dose/source ratio 

E east 

EIS environmental impact statement 

EMC elevated measurement concentration 

EPA U.S Environmental Protection Agency 

F Fahrenheit 

FR Federal Register 

HEPA high-efficiency particulate air 

HLW high-level waste 

ICORS Interagency Steering Committee on Radiation Standards 

K hydraulic conductivity 

Kd distribution coefficient 

KRS Kent recessional sequence 

LLW low-level waste 

LTR License Termination Rule 

LTS Lavery till sand 

MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual 

MDC minimum detectable concentration 

MMI Modified Mercalli Intensity 

N north 

ND not detected 
WVDP PHASE 1 DECOMMISSIONING PLAN

NOTATION 

Revision 1 xxiv

NDA NRC-Licensed Disposal Area 

NESHAP National Emissions Standards for Hazardous Air Pollutants 

NPR New Production Reactor 

NRC Nuclear Regulatory Commission 

NFS Nuclear Fuel Services, Inc. 

NYSDEC New York State Department of Environmental Conservation 

NYSERDA New York State Energy Research and Development Authority 

PUREX plutonium uranium refining by extraction 

QA quality assurance 

QC quality control 

qtr quarter 

RCRA Resource Conservation and Recovery Act 

RESRAD Residual radioactivity [computer code] 

RFI RCRA facility investigation 

S&G sand and gravel 

SAIC Science Applications International Corporation 

SB subsurface soil 

SD stream bank sediment 

SDA State-Licensed Disposal Area 

SPDES State Pollutant Discharge Elimination System 

SS surface soil 

THOREX thorium uranium extraction process 

TLD thermoluminescent dosimeter 

ULT unweathered Lavery till 

W west 

WLT weathered Lavery till 

WMA waste management area 

WSMS Washington Safety Management Solutions 

WVDP West Valley Demonstration Project 

WVES West Valley Environmental Services 

WVNSCO West Valley Nuclear Services Company 
WVDP PHASE 1 DECOMMISSIONING PLAN

NOTATION 

Revision 1 xxv

Units 

Ci curie 

cfm cubic feet per minute 

cm centimeter 

cm2

 centimeter squared 

cm3 centimeter cubed 

cpm counts per minute 

dpm disintegrations per minute 

g gram [mass] 

g acceleration due to gravity [in reference to accelerations] 

h hour 

kg kilogram 

km kilometer 

L liter 

m meter 

mCi millicurie 

millirem 0.001 Roentgen equivalent man 

mL milliliter 

mrem millirem 

mR milli Roentgen 

μCi 0.000001 curie 

μR micro Roentgen 

μrem micro rem 

μL 0.000001 liter 

pCi 10-12 curie 

R Roentgen 

rem Roentgen equivalent man 

s second 

y year 
This page is intentionally blank. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 ES-19 

Since these cleanup goals were developed for individual radionuclides of interest, a sum-offractions approach based on radionuclide distributions in different areas would be used to ensure 

that potential doses from the remediated areas would be no more that the dose from one of the 

individual radionuclides at the concentration specified in Table ES-2. 

Although the subsurface soil cleanup goals in Table ES-2 form the criteria for residual 

radioactivity in the two large excavations, remediation plans involve excavation at least one foot 

into the Lavery till and, in Waste Management Area 2, at least one foot below the sediment in the 

bottoms of Lagoons 2 and 3. This approach is expected to produce residual radioactivity levels 

well below the cleanup goals, based on limited existing data on residual radioactive 

contamination in the Lavery till. A preliminary, order-of-magnitude dose analysis using these data 

suggests that potential futures doses from these excavated areas would be approximately one 

millirem per year for Waste Management Area 1 and approximately 0.05 millirem per year for 

Waste Management Area 2. 

After additional characterization data become available early in Phase 1 of the 

decommissioning, the DCGLs and the cleanup goals would be reevaluated using these data and 

refined as appropriate. After the Phase 1 decommissioning activities have been completed, 

another dose analysis using Phase 1 final status survey data would be performed to estimate the 

potential doses from the remediated subsurface areas. 

Summary of ALARA Evaluations 

DOE has performed a preliminary cost-benefit analysis using NRC methodology to determine 

whether removal of soil or sediment with radioactivity concentrations below the DCGLs would be 

consistent with the ALARA principal. These analyses compared the cost of disposal of additional 

soil or sediment with the reduction in radiation exposure associated with removal of additional soil 

or sediment below the DCGLs valued at $2000 per person-rem as set forth in NRC guidance. 

They indicate that removal of soil or sediment with radioactivity concentrations below the DCGLs 

would not be cost-effective. 

DOE would perform another similar analysis when the subsurface soil remediation work is in 

progress (and when surface soil and streambed sediment remediation is in progress, if that work 

is done in Phase 1) to confirm the results of the preliminary ALARA evaluation. This second, 

more-detailed analysis would use updated information and consider other factors such as other 

societal and socioeconomic considerations and costs related to transportation of additional waste.

Initiation and Completion Dates 

Subject to the decision in the Record of Decision for the Decommissioning EIS, expected in 

2009, and upon NRC approval of this plan, DOE would begin Phase 1 of the proposed 

decommissioning in 2011 and it would last until 2018. 

Post-Remediation Activities 

The proposed post remediation activities fall into two categories: (1) a monitoring and 

maintenance program and (2) an institutional control program, both of which focus on the project 

premises.
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 0 ES-20 

The monitoring and maintenance program would continue until Phase 2 of the 

decommissioning starts, when it would be reevaluated. It would include an environmental 

monitoring program tailored to conditions that would exist at the conclusion of the Phase 1 

decommissioning activities. This program would monitor onsite groundwater, storm water, and 

air, along with onsite and offsite surface water, sediment, and radiation. Groundwater monitoring 

would be accomplished using approximately 36 monitoring wells. 

The monitoring and maintenance program would also ensure that important facilities and 

systems serve their intended purposes during the period between the completion of Phase 1 of 

the decommissioning and the start of Phase 2. Facilities and systems within the scope of this 

program include: 

The subsurface hydraulic barrier wall and French drain to be installed during Phase 1 on 

the north and east sides of the excavation for removal of the Waste Management Area 1 

facilities, 

The subsurface hydraulic barrier wall to be installed during Phase 1 on the northwest and 

northeast sides of the excavation for removal of key Waste Management Area 2 facilities, 

The tank and vault drying system for the underground waste tanks that is to be installed 

before Phase 1 of the decommissioning, 

The dewatering well used to minimize in-leakage into the underground waste tank vaults, 

The hydraulic barrier wall and geomembrane cover for the NRC-Licensed Disposal Area, 

and 

The security features and monitoring systems installed for the new Canister Interim 

Storage Facility to be established on the south plateau. 

Performance of the hydraulic barrier walls would be assessed with hydraulic monitoring 

piezometers. 

Insofar as institutional controls are concerned, DOE would continue control of the project 

premises during the Phase 1 decommissioning activities and the period between completion of 

these activities and the start of Phase 2 of the decommissioning. Institutional controls would 

include security fences and signs along the perimeter of the project premises, a full-time security 

force, provisions for controlled access through designated gateways, and appropriate security 

measures for the new Canister Interim Storage Facility on the south plateau, which would be 

established during Phase 1 of the decommissioning. 

 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 0 3-85 

Jacobi and Fountain 1993, “The Southern Extension and Reactivations of the ClarendonLinden Fault System.” Jacobi, R.D., and J. Fountain, Geographie Physique et 

Quaternaire, Vol. 47, No. 3: pp. 285-302, 1993. 

Jacobi, et al. 1996, “Character and Reactivation History of the Clarendon-Linden Fault 

System: Evidence From New York State.” Jacobi, R.D., et al., Geological Society of 

America Abstracts with Programs, Northeastern Section Meeting, Vol. 28, No. 3: 

67, 1996. 

Jacobi and Zhao 1999, “Faults Exposed in Zoar Valley, Western New York, and Their 

Possible Relation to Geophysical Anomalies, Landsat Lineaments and Seismicity.”

Jacobi, R.D., and M. Zhao, Geological Society of America Abstracts with 

Programs, Northeastern Section Meeting, Vol. 31, No. 2: A-25, 1999. 

LaFleur 1979, Glacial Geology and Stratigraphy of Western New York Nuclear Service 

Center and Vicinity, Cattaraugus and Erie Counties,” New York. LaFleur, R.G., 

U.S. Geological Survey Open-File Report 79-989, 1979. 

Matuszek 1980, “Biochemical and Chemical Processes Leading to Radionuclide Transport 

from Low-Level Waste Burial Sites. Matuszek, J.M., Transactions of the American 

Nuclear Society, Vol. 24. pp. 155-156, 1980.

McKinney 1986, Letter Report Review of Erosion Projections, Low-Level Waste Disposal 

Area, Western New York Nuclear Service Center, West Valley, New York.

McKinney, T.F., 1986.

NRC 1982, Atmospheric Dispersion Models for Potential Accident Consequence 

Assessments at Nuclear Power Plants, Regulatory Guide 1.145, Revision 1. U.S. 

Nuclear Regulatory Commission, Washington, D.C., November 1982. 

NRC 2007, Meteorological Programs for Nuclear Power Plants, NUREG 1.23, Revision 1. 

U.S. Nuclear Regulatory Commission, Washington, D.C., March 2007. 

NYASS 2005, Cattaraugus County Farm Statistics. New York Agricultural Statistics 

Service, Albany, New York, 2005. (www.nass.usda.gov/ny/CountyBrochures/Cattaraugus. pdf) 

NYDOT 2003, 2003 Traffic Volume Report. New York State Department of Transportation, 

Albany, New York, 2003. 

NYSDEC 2001, New York State Oil, Gas and Mineral Resources 2001. Annual Report, 

NYSDEC, Albany, New York, 2001. 

NYSDEC 2004, 2003 Annual Report to the Lake Erie Committee and the Great Lakes 

Fishery Commission. New York State Department of Environmental Conservation 

(NYSDEC), Lake Erie Unit, Albany, New York, March 2004. 

NYSDEC 2005, New York State Department of Environmental Conservation online map 

navigator at http://www.dec.state.ny.us/website/imsmaps/minerals/ viewer.htm 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 3-86 

Pietrzak, et al. 1981, “Sorption Measurements Performed under Site-Specific Conditions -- 

Maxey Flats, Kentucky, and West Valley, New York, Disposal Sites.” Pietrzak, R.F., 

K.S. Czyscinski, and A.J. Weiss, Nuclear and Chemical Waste Management, Vol. 

2, pp. 279-285, 1981. 

Prudic 1986, “Groundwater Hydrology and Subsurface Migration of Radionuclides at a 

Commercial Radioactive-Waste Burial Site, West Valley, Cattaraugus County, New 

York.” Prudic, D.E., U.S. Geological Survey Professional Paper 1325, 1986. 

Rickard 1975, Correlation of the Silurian and Devonian Rocks in New York State. Rickard, 

L.V., New York State Museum and Science Service Map and Chart Series, No. 24, 

1975. 

Spector and Grant 2003, Manual for Radiological Assessment of Environmental Releases 

at the WVDP, WVDP-065, Rev. 4. Spector, H. and M. Grant, West Valley Nuclear 

Services Company, West Valley, New York, February 28, 2003. 

STPRDB 2003, 2003 Regional Development Strategy. Southern Tier Planning and 

Regional Development Board, Salamanca, New York, 2003. 

Tober and Jacobi 2000, “Fracture Trends and Spacing in the Appalachian Plateau of 

Western New York: Implications for the Bass Islands Trend and North-Striking 

Lineaments.” Tober, B.K., and R.D. Jacobi, Geological Society of America 

Abstracts with Programs, Northeastern Section Meeting, Vol. 32, No. 1: A-79, 

2000. 

TrueWind 2005, New York State Wind Resource Map, interactive map prepared for the 

New York State Energy and Research Development Authority by TrueWind 

Solutions, LLC. http://.truewind.com. 

URS 2001, Progress Report on Erosion Frame Monitoring at the Western New York 

Nuclear Service Center, West Valley, New York. URS Corporation 2001. 

URS 2002, Land Use Survey in Support of the 2001 National Emissions Standard for 

Hazardous Air Pollutants (NESHAP) and Annual Site Environmental (ASER) 

Reports, TA-2002-3-019. URS Corporation, March 8, 2002. 

USDOT 2003, Record of Decision, U.S. Route 219: Springville to Salamanca, Erie, and 

Cattaraugus Counties, New York, FHWA-NY-EIS-98-02F. U.S. Department of 

Transportation, September 4, 2003. 

USGS 1980, Principles of a Resource/Reserve Classifications for Minerals: A revision of 

the classification system published as U.S. Geological Survey Bulletin 1450-A. U.S. 

Geological Survey Circular 831. U.S. Bureau of Mines and the U.S. Geological 

Survey, 1980. 

USGS 2007, Report to Sandi Doty and Greg Tucker on Buttermilk Creek Watershed, West 

Valley, NY (DOE Waste Disposal Site). Informal memo from USGS Luminescence 

Dating Lab, U.S. Department of Interior, U.S. Geological Survey, Denver Colorado, 

March 15, 2007. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 3-87 

USSCS 1983, Technical Release 20 – Computer Program for Project Formulation 

Hydrology, Version 3.40. Soil Conservation Service, Washington, DC, 1983. 

Wedel 1932, “Geological Structures of the Devonian Strata of South-Central New York.” 

Wedel, A.A., New York State Museum Bulletin, Vol. 294: 74, 1932. 

Wild 2000, Estimated Radionuclide Inventory for the NRC-Licensed Disposal Area at the 

West Valley Demonstration Project. Wild, R.E., URS/Dames and Moore, Orchard 

Park, New York, August 2000. 

Wong, et al. 2004, Seismic Hazard Evaluation for the Western New York Nuclear Service 

Center, New York. Wong, I. et al., URS Corporation, Oakland, California, June 24, 

2004. 

WVES and URS 2008, West Valley Demonstration Project Site Environmental Report, 

Calendar Year 2007. WVNSCO and URS, West Valley, New York, December 2008 

WVNSCO 1975, Subsurface Characterization Report, Low-Level Waste Disposal Area, 

West Valley Demonstration Project, West Valley, New York, WVDP-046. 

WVNSCO, West Valley, New York, October 1985. 

WVNSCO 1992, Environmental Information Document: Volume III: Hydrology, Part 5: 

Unsaturated Zone Hydrology, WVDP-EIS-009, Rev. 0. WVNSCO, West Valley, 

New York, December 1992. 

WVNSCO 1993a, Environmental Information Document Volume I - Geology, Part 4: 

Geochemical Characterization. WVDP-EIS-004. WVNSCO, West Valley, New 

York, January 1993. 

WVNSCO 1993b, Environmental Information Document: Volume VIII: Air Resources, Part 

2: Meteorology, WVDP-EIS-015, Rev. 0. WVNSCO, West Valley, New York, 1993. 

WVNSCO 1993c, Environmental Information Document, Volume III, Hydrology, Part 2: 

Surface Water Hydrology, WVDP-EIS-009, Rev. 0. West Valley Nuclear Services 

Company, West Valley, New York, January 1993.

WVNSCO 1993d, Environmental Information Document, Volume III, Hydrology, Part 3: 

Erosion and Mass Wasting Processes, WVDP-EIS-009, Rev. 0. WVNSCO, West 

Valley, New York, January 1993. 

WVNSCO 1993e, Environmental Information Document, Volume III, Hydrology, Part 4: 

Groundwater Hydrology and Geochemistry, WVDP-EIS-009, Rev. 0. WVNSCO, 

West Valley, New York, February 1993. 

WVNSCO 1993f, Environmental Information Document, Volume III, Hydrology, Part 5: 

Vadose Zone Hydrology, WVDP-EIS-009, Rev. 0. WVNSCO, West Valley, New 

York, February 1993. 

WVNSCO 1995, RCRA Facility Investigation Report, Volume 2, Nuclear Regulatory 

Commission-Licensed Disposal Area, WVDP-RFI-018, Rev. 0. West Valley Nuclear 

Services Company (WVNSCO), West Valley, New York, October 1995. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 3-88 

WVNSCO 1997, RCRA Facility Investigation Report, Volume 4, Low-Level Waste 

Treatment Facility, WVDP-RFI-021, Rev. 0. West Valley Nuclear Services 

Company (WVNSCO), West Valley, New York, January 1997.

WVNSCO 2007, Safety Analysis Report for Waste Processing and Support Activities, 

WVNS-SAR-001, Revision 11. WVNSCO, West Valley, New York, June 28, 2007.

Zhao and Jacobi 1997, “Formation of Regional Cross-Fold Joints in the Northern 

Appalachian Plateau.” Zhao, M. and R.D. Jacobi, Journal of Structural Geology, 

Vol. 19, No. 6: 817-834, 1997. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-23 

4.2 Radiological Status of Environmental Media

Section 4.2 describes the radiological status of surface soil, sediment, subsurface soil, 

surface water, and groundwater within the project premises as compared with background. 

Information in Section 4.2 is organized as follows: 

Section 4.2.1 identifies data sources used for this evaluation. 

Section 4.2.2 summarizes background levels of (1) radionuclide concentrations in 

surface soil, subsurface soil, stream sediment, surface water, and groundwater; 

and (2) environmental radiation. 

Section 4.2.3 summarizes radiological status of surface soil and sediment within 

the project premises. 

Section 4.2.4 provides the same information on subsurface soil. 

Section 4.2.5 summarizes maximum radionuclide concentrations at locations in 

each WMA where background levels were exceeded in soil, sediment, and 

subsurface soil. 

NOTE 

Environmental media have not been fully characterized and, as a result, certain 

information normally included in decommissioning plans is not available. Additional 

characterization is planned in connection with the Phase 1 decommissioning work as 

described in Sections 7 and 9. 

Additional characterization of subsurface soil was performed in 2008. This 

characterization focused on hazardous contaminants and radionuclides in the area of 

the north plateau groundwater plume (Michalczak 2007). DOE plans to provide a copy 

of the summary report of this characterization program to NRC and other involved 

agencies and to revise this plan to incorporate key data from this program. 

The information provided below represents a compilation of environmental radiological 

data collected as part of the routine WVDP Environmental Monitoring and 

Groundwater Monitoring programs. It also includes data from nonroutine investigations 

designed to satisfy regulatory requirements (e.g., RCRA facility investigations) and 

other focused sampling activities. 

Section 2.3 contains information on documented spills of radioactivity that have 

impacted environmental media on the project premises. These spills include the 1968 

airborne radioactivity releases that produced the widespread area of surface 

contamination northeast of the Process Building known as the cesium prong and the 

release of radioactive acid under the southwest corner of the Process Building that 

resulted in the area of subsurface soil and groundwater contamination known today as 

the north plateau groundwater plume. This section focuses on environmental media 

conditions that exist today and duplicates information in Section 2.3 only where 

necessary for clarity. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-24 

Section 4.2.6 provides information on environmental radiation levels on the project 

premises. 

Section 4.2.7 provides information on the radiological status of surface water on 

the project premises. 

Section 4.2.8 addresses the radiological status of groundwater on the project 

premises and, in particular, the north plateau groundwater plume. 

Appendix B, Environmental Radioactivity Data, provides the following information: 

A description of how background radionuclide concentrations and environmental 

radiation levels were estimated; 

Maps showing locations where background data were taken; 

Summary statistics applicable to each medium; 

A description of how data from onsite sampling programs were evaluated to 

determine if radiological concentrations or environmental radiation levels were 

above background; 

Tables summarizing the ratios of above-background concentrations of 

radionuclides with Cs-137 in surface soil, sediment, and subsurface soil; 

Additional summary information about radiological concentrations from routine 

onsite sampling locations; 

Descriptions of both impacted and non-impacted locations; and 

Tables that list the coordinates and descriptions of groundwater sampling locations, 

along with the depths and geologic units at which samples were collected. 

4.2.1 Data Sources 

Radiological data on surface soil, sediment, subsurface soil, surface water, 

groundwater, and environmental radiation levels were taken from the WVDP Laboratory 

Information Management System controlled database, which contains environmental data 

from 1991 through the present. This system is used to manage data from the WVDP 

Environmental Monitoring and Groundwater Monitoring Programs, as well as data from 

special sampling activities (e.g., RCRA facility investigations, north plateau groundwater 

plume investigations). 

If necessary (i.e., if only pre-1991 data were available for an area), data were drawn 

from historical sources or summaries included in reports from previous evaluations. 

Previous Evaluations 

Radiological data from environmental media have been presented in formal reports, for 

example: 

(1) WVDP Annual Site Environmental Reports (years 1982 through 2007 available on 

the Internet at www.wv.doe.gov); 
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Revision 1 4-25 

(2) Groundwater trend analysis reports; 

(3) Reports of RCRA facility investigations of various areas of the WVDP (WVNSCO 

1995, WVNSCO 1996, WVNSCO 1997a, WVNSCO 1997b, WVNSCO and Dames 

& Moore [D&M] 1996a, WVNSCO and D&M 1996b, WVNSCO and D&M 1997a, 

WVNSCO and D&M 1997b, and WVNSCO and D&M 1997c); and 

(4) Results from north plateau groundwater plume investigations (Carpenter and 

Hemann 1995, WVNSCO 1998, URS 2002, and Klenk 2009). The RCRA Facility 

Investigations and the north plateau investigations produced a substantial body of 

soil characterization data, most associated with nonradiological constituents. 

Data Quality 

WVDP environmental samples evaluated in this plan were collected in accordance with 

formal sampling plans. Samples were analyzed by onsite and offsite laboratories in 

accordance with controlled procedures as required by the WVDP quality assurance (QA) 

program. QA requirements applicable to the sampling programs include documented 

training of field personnel; controlled collection procedures; using appropriate containers, 

preservatives, and storage methods to protect samples from contamination and 

degradation; following appropriate field and analytical quality control guidelines; 

maintaining and documenting chain-of-custody; and conducting assessments and audits of 

field and analytical processes to verify compliance. 

Data were validated by a separate data validation group, and validation and approval 

status of sample results were documented in the LIMS. 

4.2.2 Background Levels 

This subsection addresses background radioactivity in environmental media on the 

project premises and provides information on background radiation levels. 

Background Radionuclide Concentrations in Environmental Media 

Radionuclides for which backgrounds were estimated were selected with consideration 

of (1) radionuclides of interest from the Facility Characterization Project, listed in section 

4.1.1, and (2) radionuclides that are routinely monitored in environmental media at the 

WVDP, for which sufficient data were available to develop a reliable estimate of 

background. 

Background radionuclide concentrations were estimated for soil, sediment, subsurface 

soil, surface water, and groundwater for the following radionuclides: 

Sr-90 U-232 U-235/236 Pu-238 Am-241 

Cs-137 U-233/234 U-238 Pu-239/240 

Pu-241, Cm-243, Cm-244, and Np-237, which are radionuclides of interest in the 

Facility Characterization Project, are not routinely measured in environmental media at the 

WVDP so were not included in background estimates. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-26 

In addition, background concentrations were estimated for surface water and 

groundwater for the following nuclides that were not routinely analyzed in soil and 

sediment: 

H-3 C-14 Tc-99 I-129 

Although tritium (H-3) is not identified in Section 4.1.1 as a radionuclide of interest, it is 

commonly found in surface water and groundwater samples at the WVDP and so was 

included in the nuclide listing for environmental media. In addition, gross alpha and gross 

beta measurements are routinely used as screening (i.e., “surrogate” or “indicator”) 

parameters for other nuclides, so background concentrations were estimated for gross 

alpha and gross beta activity. (For instance, gross beta measurements are used as a 

surrogate for Sr-90 measurements in the WVDP Groundwater Monitoring Program.) 

Appendix B provides maps showing locations from which background data were taken 

and a description of how background concentrations were estimated. Appendix B also 

includes a table of summary statistics (e.g., number of samples, percentage of nondetect 

values, average concentrations, medians) for each constituent in each medium.9

 Median 

and maximum background concentrations are summarized in Table 4-11. 

Table 4-11. Median and Maximum(1) Background Concentrations for Environmental 

Media at the WVDP 

Constituent 

Surface soil 

(pCi/g dry) 

Subsurface soil 

(pCi/g dry)(2) 

Sediment

(pCi/g dry) 

Surface water 

(pCi/L) 

Groundwater 

(pCi/L) 

Gross alpha 1.3E+01 

(2.7E+01) 

1.3E+01 

(1.7E+01) 

9.2E+00 

(2.2E+01) 

<9.6E-01 

(5.4E+00) 

<2.6E+00 

(2.2E+01) 

Gross beta 2.0E+01 

(4.0E+01) 

2.9E+01 

(6.1E+01) 

1.6E+01 

(2.7E+01) 

2.3E+00 

(2.0E+01) 

4.6E+00 

(2.8E+01) 

H-3 NA NA NA <8.2E+01 

(6.3E+02) 

<8.6E+01 

(9.4E+02) 

C-14 NA NA NA <1.3E+01 

(4.1E+02) 

<2.7E+01 

(7.4E+00) 

Sr-90 9.5E-02 

(3.1E+00) 

<2.3E-02 

(1.2E-01) 

<3.4E-02 

(1.6E-01) 

9.0E-01 

(1.2E+01) 

2.4E+00 

(7.4E+00) 

Tc-99 NA NA NA <1.8E+00 

(7.3E+00) 

<1.8E+00 

(4.0E+00) 

I-129 NA NA NA <7.9E-01 

(2.0E+00) 

<6.0E-01 

(1.6E+00) 

Cs-137 4.2E-01 

(1.2E+00) 

<2.4E-02 

(1.5E-01) 

3.8E-02 

(7.8E-02) 

<4.2E+00 

(1.0E+01) 

<2.2E+01 

(1.9E+01) 

9

 Note that if a data set is symmetric, the average (i.e., mean) and the median will be the same. However, if 

the distribution is skewed to the right (i.e., contains a large number of low values and a few high values), the 

average will usually be higher than the median. For this reason, the median may be the more reliable 

estimator of central tendency. In this evaluation, both were estimated and are presented in Appendix B. 
WVDP PHASE 1 DECOMMISSIONING PLAN

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Table 4-11. Median and Maximum(1) Background Concentrations for Environmental 

Media at the WVDP 

Constituent 

Surface soil 

(pCi/g dry) 

Subsurface soil 

(pCi/g dry)(2) 

Sediment

(pCi/g dry) 

Surface water 

(pCi/L) 

Groundwater 

(pCi/L) 

U-232 <2.4E-02 

(1.9E-02) 

<2.4E-02 

(<4.2E-02) 

<3.1E-02 

(3.9E-02) 

<4.3E-02 

(2.6E-01) 

<4.9E-02 

(3.8E-01) 

U-233/234 7.9E-01 

(9.4E-01) 

7.9E-01 

(1.1E+00) 

6.6E-01 

(8.6E-01) 

9.9E-02 

(3.0E-01) 

1.6E-01 

(8.2E+00) 

U-235/236 5.2E-02 

(2.2E-01) 

4.2E-02 

(1.2E-01) 

4.6E-02 

(2.8E-01) 

<3.3E-02 

(1.0E-01) 

<5.0E-02 

(1.9E-01) 

U-238 7.9E-01 

(9.3E-01) 

8.6E-01 

(1.1E+00) 

6.5E-01 

(9.0E-01) 

5.7E-02 

(4.0E-01) 

1.2E-01 

(5.3E+00) 

Pu-238 <1.2E-02 

(4.0E-02) 

<1.2E-02 

(<2.4E-02) 

<1.4E-02 

(1.3E-01) 

<3.1E-02 

(1.0E-01) 

<4.6E-02 

(2.2E-01) 

Pu-239/240 1.6E-02 

(2.3E-01) 

<1.0E-02 

(<1.9E-02) 

<1.2E-02 

(6.1E-02) 

<2.7E-02 

(2.0E-01) 

<5.3E-02 

(2.7E-01) 

Am-241 <1.6E-02 

(1.9E-01) 

<1.1E-02 

(<1.3E-02) 

<1.4E-02 

(8.6E-02) 

<3.3E-02 

(2.2E+00) 

<3.8E-02 

(1.8E-01) 

NOTE: (1) Maxima are in parentheses. Maxima were selected from samples in which the radionuclide was 

detected (i.e., a “nondetect” result, indicated by a “<” sign, was used only if no detectable results 

were available). 

(2) This column was added after sufficient background soil samples were collected in 2008 to allow for 

comparison purposes. 

LEGEND: NA = Not analyzed in this medium 

Data on radionuclide concentrations in environmental media on the project premises 

were evaluated to determine the locations where radionuclide concentrations in excess of 

site background levels were found. Methods for evaluating sample data with respect to 

background were dependent on the type of data available for comparison (e.g., a single 

sample result, a data set encompassing several years). Methods for each are described in 

Appendix B. 

Data evaluated in Section 4.2 were taken from samples collected over several years. 

While the majority of data points were from 1991 through the present, the earliest was from 

a sample collected in 1967.10 In Section 4.1, radionuclide activities in facilities on the 

project premises were decay-corrected to the year 2011. However, in Section 4.2 no 

attempt was made to decay-correct results from environmental samples because, unlike 

process cells or tanks, environmental media are not closed, static systems. 

Media such as surface soil, sediment, subsurface soil, surface water, and groundwater 

are all subject to forces (aside from radioactive decay) with the potential to modify their 

10 Note that historical and current data, which were generated over more than 40 years of NFS and WVDP 

operations, may not be directly comparable because different sampling and analytical methodologies have 

been used over the years. Historical and current data were compared with background concentrations using 

different statistical methods, as described in Appendix B. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-28 

radionuclide concentrations. Forces such as weathering, biological activity, atmospheric 

fallout, surface water runoff, wind erosion, and evaporation may act to deposit or remove 

radionuclides from a medium. Also, radionuclides are affected differentially by these 

mechanisms (e.g., Sr-90 is more mobile in water than Cs-137, which is more likely to bind 

to clay particles in soil and sediment). 

Many of the radionuclides considered in this section are long-lived and it is unlikely that 

decay-correction would have affected the determination of whether or not background 

concentrations were exceeded. However, it is possible that estimates of radiological 

concentrations of the shorter-lived radionuclides (i.e., tritium [half-life of 12.3 years], Sr-90 

[half-life of 28.9 years], and Cs-137 [half-life of 30 years]) are conservatively high, that is, 

overestimates. 

Background Environmental Radiation Levels 

Radiation levels have been measured at the WVDP from 1986 through the present with 

a network of environmental thermoluminescent dosimeters (TLDs).11 Average quarterly 

exposure measurements from four background locations over this time period was 19.3 mR 

per quarter (about 8.8E-03 mR/h). The maximum for any single quarter was 35 mR/quarter 

(about 1.6E-02 mR/h). 

Background environmental radiation levels were used to evaluate measurements from 

onsite TLDs near process facilities, waste storage areas, and burial areas. (See Appendix 

B for a map showing the locations of background TLDs. See section 4.2.6 for a discussion 

of onsite exposure measurements.) 

4.2.3 Radiological Status of Surface Soil and Sediment 

Since the facility has operated, numerous soil sampling studies have been conducted 

on site, not as part of a formal site-wide soil program, but rather as area-specific 

investigations in response to specific circumstances or events (WVNSCO 1994). In 1993, a 

site-wide soil sampling program was conducted to obtain additional data to support the EIS 

and RCRA processes. As part of this program, surface soil, sediment, and subsurface soil 

samples were collected. Results were summarized in WVNSCO 1994. 

NUREG-1757 (NRC 2006) defines surface soil as the soil within the top 15 to 30 cm 

(six to 12 inches) of the soil column. That definition has been broadened in this plan to 

include soil within the top 60 cm (0 to two feet) of the soil column. This was done so that 

available data from the top interval (0 to two-foot depth) from onsite soil-borings collected 

as part of the 1993 program could be used to assess the radiological status of surface soil. 

Data from the subsurface portions of the boreholes (i.e., at depths greater than two feet) 

are discussed in section 4.2.5. 

11 While radiation levels were measured at the WVDP prior to 1986, the current methodology has been used 

only since 1986. Therefore, for comparability, only data generated from 1986 through the present were 

used in the background calculation. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-29 

Areas With Radionuclide Concentrations in Excess of Site Background Levels 

Figure 4-6 shows locations at which radiological concentrations exceeding background 

were noted in surface soil and sediment for (1) gross alpha or alpha-emitting radionuclides 

and (2) gross beta or beta-gamma emitting radionuclides.12 

The highest radionuclide concentrations were found in sediment from the lagoons 

in the WMA 2 Low-Level Waste Treatment Facility. See Table 4-14 for a listing of 

maximum radionuclide concentrations above background noted in the lagoon and 

drainage system. The highest radionuclide concentrations were noted in sediment 

from Lagoon 2. (Although higher concentrations are listed for Lagoon 1, the 

Lagoon 1 sediment was transferred to Lagoon 2 when Lagoon 1 was deactivated in 

1984.) 

Cs-137 concentrations in excess of background were found in surface soil samples 

from all waste management areas at which samples had been collected. Although 

no surface soil data were available from WMA 1 (the Process Building and 

Vitrification Facility area), it is suspected that radionuclide concentrations in excess 

of background would be found here based on proximity to the Process Building and 

the elevated concentrations observed in adjoining WMAs. The highest levels noted 

in surface soil from other areas (i.e., 2.8E+02 pCi/g in WMA 2 near the 

Interceptors, 1.6E+02 pCi/g in WMA 6 near the Fuel Receiving and Storage Area 

and 2.3E+01 pCi/g in WMA 3 near the Waste Tank Farm) were all from areas in 

closest proximity to WMA 1. Elevated Cs-137 concentrations are thought to be 

largely attributable to historical releases and continuing low-level airborne releases 

from the main stack of the Process Building. 

Surface soil concentrations of Sr-90 exceeding background were noted in several 

areas, most notably in areas affected by the north plateau groundwater plume, 

such as WMA 2 (the Low-Level Waste Treatment Facility area) and WMA 4 (the 

area of the Construction and Demolition Debris Landfill). 

Radionuclide concentrations exceeding background, primarily from Sr-90 and Cs137, were found in sediment samples from streams and drainage ditches in several 

waste management areas (WMAs 2, 4, 5, 6, 7, 10, and 12). Concentrations of 

alpha-emitting radionuclides (i.e., U-232, Pu-238, Pu-239/240, and/or Am-241) in 

excess of background were also noted in WMAs 2, 4, 5, 7, and 12 downgradient of 

liquid release points or waste burial areas. 

12 WMA 12 is not labeled on the figures in this section because it extends to the boundaries of the Center. 

Areas on the project premises (i.e., within the security fence) that are considered to be part of WMA 12 

include (1) the area between the north and south plateaus, which contains much of the drainage for Erdman 

Brook and Franks Creek, and (2) a small area north of WMA 4. 
WVDP PHASE 1 DECOMMISSIONING PLAN

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High radionuclide concentration levels were also associated with soil and sediment 

from the area of the Old Interceptors, the Solvent Dike, and inactive (filled-in) 

Lagoon 1 in WMA 2. 

South plateau areas with radionuclide concentrations exceeding background in 

surface soil include the two former shallow land burial disposal facilities, the NDA 

(WMA 7) and SDA (WMA 8). Elevated radiological concentrations in the surface 

and near-surface soils in the vicinities of those facilities is expected due to the 

nature of their operations. (As noted previously, WMA 8 is not within plan scope.) 

Levels at which radionuclide concentrations in excess of background were found in 

surface soil and sediment are listed by WMA in the tables in section 4.2.5. As shown in 

Figure 4-6, only one surface soil sampling location (SS-11) had no concentrations 

exceeding background. All sediment sampling locations had at least one constituent 

exceeding background. 

4.2.4 Radiological Status of Subsurface Soil 

Figure 4-7 shows locations at which concentrations of radiological constituents above 

background were noted in subsurface soil for (1) alpha-emitting radionuclides and (2) 

beta-gamma emitting radionuclides. 
WVDP PHASE 1 DECOMMISSIONING PLAN

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Figure 4-6. Surface Soil and Sediment Locations With Radionuclide Concentrations in 

Excess of Background 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-32 

Figure 4-7. Subsurface Soil Locations With Radionuclide Concentrations in Excess of 

Background 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-33 

Most subsurface soil data were taken from the 1993 RCRA Facility Investigation 

sampling program and three Geoprobe®

 sampling efforts (1994, 1998, and 2008) to better 

define the origin and extent of the north plateau groundwater plume. 

 The highest subsurface radiological concentrations on the north plateau were 

observed in WMA 1 (the Process Building and Vitrification Facility area), WMA 2 (the LowLevel Waste Treatment Facility area), and WMA 6 (the Central Project Premises), 

downgradient of the Process Building. On the south plateau, highest concentrations were 

from WMA 7 (the NDA). Subsurface soil concentrations exceeding background were 

primarily associated with the north plateau groundwater plume (see Section 2) or with 

former waste processing or burial activities. Figure 4-8 presents a cross-section of Sr-90 

concentrations in subsurface soil with depth in the north plateau below the Process 

Building. Data from this cross-section were taken from samples collected in 1993, 1994, 

1998, and 2008 from WMAs 1, 2, and 6. The highest concentrations of Sr-90 were 

observed in the sand and gravel unit below the water table. 

In WMA 1, high levels of Sr-90 were measured during the Geoprobe® investigations 

near the Process Building. In WMA 2, the highest levels of both beta-gamma and alphaemitting radionuclides in subsurface soil were observed in sediments from borings taken 

near the Solvent Dike, the interceptors, and the Maintenance Shop leach field. In WMA 6, 

elevated subsurface soil concentrations were noted near the Utility Room and the Fuel 

Receiving and Storage Building. Data from WMA 7 were taken from rolloffs and boxes of 

excavated soil removed from “special holes” during NDA burial activities and from the 

Interceptor Trench, immediately downgradient of the NDA, when it was installed in 1990. 

Although the packaged soil has since been shipped offsite, it is likely that radionuclide 

concentrations in subsurface soil remaining in the NDA would be similar to those from the 

excavated soil. 

Concentrations of radionuclides observed in excess of background levels in subsurface 

soils are summarized in Section 4.2.5. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-34 

Figure 4-8. Cross-section of Sr-90 Concentrations Versus Depth in Subsurface Soil in WMA 1
WVDP PHASE 1 DECOMMISSIONING PLAN

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4.2.5 Radionuclide Concentrations Exceeding Background in Surface Soil, 

Sediment, and Subsurface Soil By WMA 

The following tables summarize locations in each WMA where radionuclide 

concentrations were noted in excess of background. (See Table 4-11 and Appendix B for 

background radionuclide concentrations used to evaluate soil, sediment, and subsurface 

soil.) Data from surface soil, sediment, and subsurface soil are combined into one table for 

each WMA, except for WMA 2, where data are presented in three tables due to the large 

volume of information. 

For each area, the maximum concentration at which the radionuclide was found is 

listed, together with source and location (i.e., reference or specific sample identifier). 

Identifiers from the 1993 RCRA Facility Investigation sampling program are specified as 

boreholes (“BH-“), surface soil (“SS-“) or stream sediment (“ST-“). Subsurface Geoprobe

soil sample locations are designated “GP.” For subsurface soil, the depth at which the 

maximum was noted (if available) is also provided. Gross alpha and gross beta 

measurements are not presented because the measurements represent a mix of 

radionuclides (including those naturally occurring), and because data for specific alphaand beta-emitting radionuclides were available. Ratios of above-background radionuclide 

concentrations to Cs-137 are presented in Appendix B in Tables B-9 (Surface Soil), B-10 

(Sediment), and B-11 (Subsurface Soil). 

WMA 1, Process Building and Vitrification Facility Area 

Limited data are available for WMA 1, none for surface soil or sediment. Most 

subsurface soil data were taken from the Geoprobe Investigations in 1994, 1998, and 

2008 and from three borehole locations from the 1993 RCRA Facility Investigation. 

Additional data were taken from one sample collected in 2004 near a breach in an 

underground wastewater line near the laundry. 

Above-background concentrations in subsurface soil from WMA 1 were noted for Sr-90, 

Cs-137, U-232, U-233/234, U-235/236, U-238, Pu-238, Pu-239/240, and Am-241. 

Maximum radionuclide concentrations are listed in Table 4-12. Except for the Cs-137 and 

Am-241 maxima observed from the sample near the laundry line breach, all maxima were 

from samples taken in 2008 under the Process Building. Maxima from Geoprobe locations 

were found at depths of 14 to 42 feet in the saturated layer of the sand and gravel unit. 

High ratios of Sr-90 to Cs-137 observed in WMA 1 (with a median ratio of about 300 to 1 

and a maximum ratio of over 63,000 to 1 [see Table B-11 in Appendix B]) reflect the 

influence of the north plateau groundwater plume. Maximum ratios of other nuclides to Cs137 in WMA 1 were: U-232 (0.023 to 1), U-233/234 (12 to 1), U-235/236 (1.1 to 1), U-238 

(18 to 1), Pu-238 (0.18 to 1), Pu-239/240 (0.80 to 1) and Am-241 (2.7 to 1). 
WVDP PHASE 1 DECOMMISSIONING PLAN

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Table 4-12. Above-Background Concentrations of Radionuclides in Subsurface Soil 

at WMA 1(1) 

Location

Maximum Concentration (pCi/g dry) 

Cs-137 Sr-90 U-232 U-233/

234

U-235/

236 U-238 Pu-238 Pu-239/240

Am-241 

Note (2) 3.3E+03 9.3E+03 5.0E-02 1.9E+00 2.2E-01 1.7E+00 5.6E-01 3.7E+00 8.7E+01 

NOTES: (1) See Figure 4-2 for a map of facilities in WMA 1. 

 (2) Sampling related to laundry line breach in 2004 (Cs-137, Am-241); Geoprobe sampling 

underneath Process Building in 2008 (GP7608 at 15-17' depth [Sr-90]; GP10408 at 20-22’ depth 

[U-232]; GP7608 at 38-40’ depth [U-233/234]; GP8308 at 40-42’ depth [U-235/236]; GP2908 at 

14-16’ depth [U-238], GP7608 at 19-21’ depth [Pu-238, Pu-239/240].

WMA 2, Low-Level Waste Treatment Facility Area

Extensive data, available both electronically and from historical reports, were available 

for WMA 2. The maximum concentrations observed at each location within WMA 2 are 

listed below. Due to the large volume, data are presented in three tables: Table 4-13 

(surface soil), Table 4-14 (sediment), and Table 4-15 (subsurface soil).

The radionuclides observed above background in surface soil (Table 4-13) were Cs137 and Sr-90. The maximum ratio of Sr-90 to Cs-137 (about 1.4 to 1) was observed in 

surface soil north of Lagoons 4 and 5, which is affected by the north plateau groundwater 

plume. No alpha-emitting radionuclides were observed at concentrations above 

background in surface soil from WMA 2. 

Table 4-13. Above-Background Concentrations of Radionuclides in Surface Soil 

From WMA 2(1) 

Location Maximum Concentration (pCi/g dry) 

Cs-137 Sr-90 

Surface soil near the Old and New 

Interceptors (BH-13) 

2.8E+02 4.1E+00 

Surface soil between the Interceptors and 

inactive Lagoon 1 (WVNSCO 1994 [Table 3-

2] and BH-14) 

1.4E+01 1.4E+00 

Surface soil between inactive Lagoon 1 and 

active Lagoon 2 (BH-08) 

4.8E+00 1.1E+00 

Surface soil from Maintenance Shop Leach 

Field (WVNSCO 1994 [Table 3-2] and BH35) 

2.1E+01 1.3E+00 

Surface soil near the LLW2 Facility (BH-36) Bkg 3.2E-01 

Surface soil near the Vitrification Test 

Facility (BH-37) 

6.6E-01 Bkg 

Surface soil north of Lagoons 4 and 5 (BH04) 8.5E-01 1.2E+00 
WVDP PHASE 1 DECOMMISSIONING PLAN

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Table 4-13. Above-Background Concentrations of Radionuclides in Surface Soil 

From WMA 2(1) 

Location Maximum Concentration (pCi/g dry) 

Cs-137 Sr-90 

Surface soil between the lagoons and WMA 

4 (SS-03, SS-06) 

3.6E+00 3.6E-01 

Surface soil between the road and Lagoon 2 

(BH-33A) 

8.9E-01 Bkg 

 LEGEND: “Bkg” = Background was not exceeded. 

NOTE: (1) See Figure 4-3 for a map of facilities in WMA 2. Facilities not labeled in Fig. 4-3 include the former 

Maintenance Shop (which was located southwest of the LLW2 Facility), and the Vitrification Test 

Facility (located northwest of the LLW2 Facility). See Figure 4-6 for a map with the above sampling 

locations. 

Radionuclides observed above background in sediment (Table 4-14) were Cs-137, Sr90, U-232, U-233/234, U-235/236, U-238, Pu-238, Pu-239/240, and Am-241. Maximum 

ratios to Cs-137 for each were: Sr-90 (144 to 1), U-232 (0.0054 to 1), U-233/234 (0.056 to 

1), U-235/236 (0.011 to 1), U-238 (0.057 to 1), Pu-238 (0.018 to 1), Pu-239/240 (0.019 to 

1), and Am-241 (4.2 to 1). (See Appendix B, Table B-10, for a summary of radionuclide 

ratios in sediment from WMA 2.) 

Maximum ratios to Cs-137 were found in sediment from (or downgradient of) the 

Solvent Dike (Sr-90, U-233/234, U-235/236, Pu-239/240, and Am-241), sediment from 

Lagoon 3 (U-232 and U-238), and sediment from the Lagoon 2 shoreline (Pu-238). The 

highest Am-241 to Cs-137 ratio (4.2 to 1) was from one Solvent Dike sediment sample 

collected in 1986. For comparison, the median Am-241 to Cs-137 ratio in WMA 2 was 

0.0019 to 1. 

Table 4-14. Above-Background Concentrations of Radionuclides in Sediment From WMA 2

Location 

Maximum Concentration (pCi/g dry) 

Cs-137 Sr-90 U-232 U-233/

234

U-235/

236 U-238 Pu-238 Pu-239/240 Am-241

Sediment from drainage 

north of Test and Storage 

Building (ST-34) 

2.0E+00 3.5E-01 NA NA NA NA NA NA NA 

Sediment from Solvent 

Dike (WVNSCO 1994, 

Table 3-12, 1986 samples) 

3.1E+02 1.6E+03 NA NA NA NA NA NA 1.1E+03 

Sediment from drainage 

downgradient of Solvent 

Dike (ST-28) 

1.7E+01 2.9E+00 Bkg 9.5E-01 Bkg Bkg 2.9E-01 3.2E-01 7.1E-01 

Sediment from Lagoon 1 

(Passuite and MonsalveJones 1993, Tables 3-2 

[1982 data] and 3-3 [1984 

data]) 

4.7E+05 1.5E+05 NA NA NA NA 3.9E+04 1.8E+04 1.9E+04 
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Table 4-14. Above-Background Concentrations of Radionuclides in Sediment From WMA 2

Location 

Maximum Concentration (pCi/g dry) 

Cs-137 Sr-90 U-232 U-233/

234

U-235/

236 U-238 Pu-238 Pu-239/240 Am-241

Sediment from Lagoon 

2(1) (WVNSCO 1994, 

Tables 3-5 [1982 data] 

and 3-8 [1990 data])

2.7E+05 3.6E+04 NA NA 6.5E-01 6.2E+00 8.0E+02 6.4E+02 8.3E+02 

Sediment from Lagoon 3 

(WVNSCO 1994, Tables 

3-11 [1990 data], 3-9 

[1967 data]; and 1994 

Lagoon 3 sampling) 

1.1E+04 7.7E+02 7.6E+00 4.5E+00 1.3E+00 8.8E+00 3.1E+00 1.4E+00 5.1E+00 

Sediment from Lagoon 4 

(1994 sampling) 

3.2E+01 7.3E+00 NA NA NA NA NA NA NA 

Sediment from Lagoon 5 

(1994 sampling) 

5.2E+01 4.1E+01 NA NA NA NA NA NA NA 

NOTE: (1) In 1984, an estimated 22,400 cubic feet of sediment were pumped from Lagoon 1 to Lagoon 2 (Passuite and 

Monsalve-Jones 1993) so the 1982 sample results are not necessarily representative of the of the activity in 

Lagoon 2 sediment. 

 (2) See Figure 4-3 for a map of facilities in WMA 2. The Test and Storage Building (which was located near the 

southwestern boundary of WMA 2) is not labeled in Fig. 4-3. See Figure 4-6 for a map with the above 

sampling locations. 

LEGEND: NA = No analysis. “Bkg” = Background was not exceeded. 

Above-background concentrations in subsurface soil from WMA 2 were noted for Sr90, Cs-137, U-232, U-233/234, U-235/236, U-238, Pu-238, Pu-239/240, and Am-241. 

Maximum radionuclide concentrations at various points in WMA 2 are listed in Table 4-15. 

The highest concentrations of all nuclides were found in saturated soil six-to-eight feet 

deep from one location (BH-8) downgradient of Lagoon 1. Other maxima were also found 

in samples taken under the solvent dike and downgradient of the interceptors in saturated 

soil in the sand and gravel unit. 

As noted in the WMA 1 discussion, ratios of Sr-90 to Cs-137 were also elevated in 

WMA 2, downgradient of the source of the north plateau plume. However, ratios were much 

lower than in WMA 1 (i.e., a median ratio of 1.9 to 1 and a maximum of 750 to 1 [as 

compared with the median of about 300 to 1 and the maximum of over 63,000 to 1 in WMA 

1). Maximum ratios of other nuclides to Cs-137 in WMA 2, as summarized in Table B-11, 

were: U-232 (1 to 1), U-233/234 (7 to 1), U-235/236 (1.1 to 1), U-238 (4.4 to 1), Pu-238 

(0.089 to 1), Pu-239/240 (0.11 to 1) and Am-241 (0.23 to 1). 
WVDP PHASE 1 DECOMMISSIONING PLAN

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Table 4-15. Above-Background Concentrations of Radionuclides in Subsurface Soil From 

WMA 2(1) 

Location

Maximum Concentration (pCi/g dry) 

Cs-137 Sr-90 U-232 U-233/

234

U-235/

236 U-238 Pu-238 Pu-239/240 Am-241

Downgradient of 

inactive Lagoon 1 (BH08 at 6-8' depth) 

3.6E+04 1.5E+04 5.8E+02 2.7E+02 4.2E+00 6.8E+01 6.8E+02 1.2E+03 1.7E+03 

Near Solvent Dike (BH11 at 8-10' depth, Cs137 max at 2-4' depth) 1.8E+02 5.6E+01 Bkg 3.6E+00 5.3E-01 2.2E+00 Bkg 7.5E-02 1.1E-01 

Near the Old and New 

Interceptors (BH-13, 8-

10' depth, U-238 max at 

6-8’ depth) 

5.2E+03 1.9E+02 5.1E+01 2.4E+01 2.0E-01 3.7E+00 6.6E+01 5.1E+01 5.3E+01 

Between the 

Interceptors and 

inactive Lagoon 1 (BH14 at 4-6' depth, Pu238 at 14-16' depth) 

6.1E+00 2.8E+01 1.0E-01 Bkg Bkg Bkg 1.7E-01 1.9E-01 2.8E-01 

East of the former TSB

(BH-35, 6-8' depth) 

1.6E+01 3.9E+02 1.3E+00 Bkg Bkg Bkg 4.6E-01 7.4E-02 1.3E+00 

Downgradient of MPPB, 

near the former TSB 

[GP10508, 28-30' 

depth) 

Bkg 7.6E+02 Bkg Bkg Bkg Bkg Bkg Bkg Bkg 

Downgradient of MPPB, 

south of the former 

Maintenance Shop 

(GP10608, at 20-22' 

depth [Sr-90] and at 22-

24' depth [Am-241, U 

isotopes]) 

Bkg 6.6E+01 Bkg 9.0E-01 2.2E-01 Bkg Bkg Bkg 3.4E-02 

Downgradient of MPPB, 

near Vit Test Facility 

(GP10708, at 30-32' 

depth [Sr-90] and at 12-

14' depth [U-235/236]) 

Bkg 3.8E+02 Bkg Bkg 1.9E-01 Bkg Bkg Bkg Bkg 

Downgradient of MPPB, 

near area of the leach 

field for the former 

Maintenance Shop 

(GP10908, at 34-36' 

depth [Sr-90], and at 

36-38' depth [U-232, U238]) 

Bkg 2.3E+02 1.3E-01 Bkg Bkg 1.0E+00 Bkg Bkg Bkg 

NOTE: (1) See Figure 4-3 for a map of facilities in WMA 2. Facilities not labeled in Figure 4-3 include the former 

Maintenance Shop (which was located southwest of the LLW2 Facility), and the Vitrification Test Facility (located 

northwest of the LLW2 Facility). See Figure 4-7 for a map with the above sampling locations. 

LEGEND: “Bkg” = Background was not exceeded. MPPB = Main Plant Process Building. TSB = Test and Storage Building.
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 0 4-40 

WMA 3. High-level Waste Tank Farm 

Minimal data were available for the Waste Tank Farm. Table 4-16 lists maximum 

concentrations of radionuclides found in surface soil at levels above background. Data 

were from a 1990 sampling, as summarized in Table 3-2 of WVNSCO 1994. 

Concentrations in excess of background levels were noted for Cs-137, U-238, and Am-241. 

The ratios of U-238 and Am-241 to Cs-137 in surface soil from the Waste Tank Farm were 

0.047, and 0.011, respectively. No sediment or subsurface soil data were available, 

although subsurface soil concentrations exceeding background are expected because of 

leaks or breaches in transfer lines (see Section 2) and because of elevated radionuclide 

concentrations found in groundwater as discussed below. 

Table 4-16. Above-Background Concentrations of Radionuclides in Surface Soil at 

WMA 3(1) 

Location Maximum Concentration (pCi/g dry) 

Cs-137 U-238 Am-241 

Surface soil at the Waste Tank Farm 

(WVNSCO 1994, Table 3-2 [1990 data]) 

2.3E+01 1.1E+00 2.5E-01 

NOTE: (1) See Figure 4-4 for a map of facilities in WMA 3 and Figure 4-6 for a map showing areas with abovebackground levels of radionuclides in surface soil.

WMA 4, Construction and Demolition Debris Landfill Area 

Concentrations of radiological constituents measured at levels in excess of background 

in surface soil, sediment, and subsurface soil from WMA 4 are listed in Table 4-17. Surface 

soil from WMA 4, a portion of which includes the landfill, was found to contain 

concentrations of Cs-137 and Sr-90 in excess of background. The maximum ratio of Sr-90 

to Cs-137 in surface soil was about 9.5 to 1. 

Table 4-17. Above-Background Concentrations of Radionuclides in Surface Soil, 

Sediment, and Subsurface Soil From WMA 4(1) 

Location

Maximum Concentration (pCi/g dry) 

Cs-137 Sr-90 U-233/

234 U-238 Pu-238 Pu-239/240 Am-241

Surface soil along drainage though 

CDDL (SS-02 and WVNSCO 1994, 

Table 3-2 [1990 data]) 

9.1E+00 1.2E+01 NA NA NA NA NA 

Sediment from drainage through 

CDDL (ST-31, ST-38) 

7.0E+00 8.4E+01 NA NA 7.3E-02 7.4E-02 1.3E-01 

Sediment from Northeast Swamp 

drainage (SNSWAMP) 

3.1E+01 3.0E+01 1.1E+00 1.1E+00 4.3E-01 6.4E-01 1.3E+00 

Subsurface soil in CDDL (BH-27 [Cs137 max at 2-4’], BH-25 [Sr-90 max 

at 12-14’]) 

7.3E-01 4.1E+00 NA NA NA NA NA 

LEGEND: CDDL = Construction and Demolition Debris Landfill; NA = No analysis. 

NOTE: (1) See Figures 4-6 and 4-7 for maps showing locations with radionuclide concentrations in excess of background. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-43 

The highest radionuclide concentrations in surface soil and sediment were from the 

northern portion of WMA 6, closest to the Process Building. However, elevated 

concentrations were also found along the rail spur south of the Sewage Treatment Plant. 

These elevated concentrations may be attributable to events in the 1960s and 1970s (e.g., 

increased radioactivity in treated effluents or possible line leaks [see further detail in 

Section 2.3.2]). 

Subsurface soil samples – one from near the Utility Room and one from near the Fuel 

Receiving and Storage Building – contained Cs-137, Sr-90, Pu-238, Pu-239/240, and Am241 concentrations exceeding background. The highest concentrations were found near 

the Fuel Receiving and Storage Building at a depth of 22 to 24 feet in the sand and gravel 

unit below the water table. (See Figure 4-8.) The maximum concentrations near the Utility 

Room were from 16 to 18 feet below the surface. 

Ratios to Cs-137 for Pu-238, Pu-239/240, and Am-241 were similar for subsurface soil 

samples taken near the Utility Room and the Fuel Receiving and Storage Building (about 

0.03 to 1, 0.04 to 1, and 0.2 to 1, respectively). However, the Sr-90 to Cs-137 ratios for 

each were strikingly different. Near the Utility Room, the ratio was about 1 to 1, but near the 

Fuel Receiving and Storage Building the ratio was 133 to 1, suggesting that the Fuel 

Receiving and Storage Building subsurface location was more central to the north plateau 

groundwater plume. 

Sampling of subsurface soil by Geoprobe in 2008 south of the Fuel Receiving and 

Storage Area, close to 1993 sampling locations BH-17 and BH-19A, continued to show 

above-background concentrations of most nuclides. See Figure 4-7. As with WMA 1 and 

WMA 2, elevated ratios of Sr-90 to Cs-137 in the “tongue” of WMA 6 lying between WMAs 

1 and 2 (with a median of 174 to 1 and a maximum of 1115 to 1) reflected the influence of 

the north plateau groundwater plume. However, maximum concentrations of Cs-137 and 

Sr-90 in the subsurface saturated layer were lower than those observed in BH-17 and BH19A in 1993. 

Table 4-19. Above-Background Concentrations of Radionuclides in Surface Soil, 

Sediment, and Subsurface Soil From WMA 6(1) 

Location

Maximum Concentration (pCi/g dry) 

Cs-137 Sr-90 U-232 U-233/

234

U-235/

236 U-238 Pu-238 Pu-239/240 Am-241

Surface soil along 

rail spur south of 

STP (BH-23, SS-13) 

1.8E+00 3.2E-01 NA NA NA NA NA NA NA 

Sediment along 

drainage by rail spur 

south of STP (ST25) 

2.1E+00 1.3E-01 NA NA NA NA NA NA NA 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-44 

Table 4-19. Above-Background Concentrations of Radionuclides in Surface Soil, 

Sediment, and Subsurface Soil From WMA 6(1) 

Location

Maximum Concentration (pCi/g dry) 

Cs-137 Sr-90 U-232 U-233/

234

U-235/

236 U-238 Pu-238 Pu-239/240 Am-241

Surface soil by FRS 

(1994 sampling 

near rail spur) 

1.6E+02 1.2E+01 NA NA NA NA NA NA NA 

Surface soil by 

Cooling Tower (SS10) 

1.3E+01 1.4E+00 NA NA NA NA NA NA NA 

Surface soil by Old 

Incinerator 

(WVNSCO 1994, 

Table 3-2 [1990 

data]) 

1.9E+01 2.3E+00 NA NA NA NA NA NA NA 

Surface soil by Old 

Warehouse (SS-09) 

1.3E+01 9.3E-01 NA NA NA NA NA NA NA 

Sediment from 

North Demineralizer 

Sludge Pond 

(WVNSCO 1994 

Table 3-18 [1988 

data], ST-35) 

1.3E+01 7.7E-01 NA NA NA NA NA NA NA 

Sediment from 

South Demineralizer 

Sludge Pond 

(WVNSCO 1994 

Table 3-19 [1988 

data], ST-36) 

3.8E+01 3.5E-01 NA NA NA NA NA NA NA 

Subsurface soil 

near the Utility 

Room (BH-17, 14-

16' depth) 

2.4E+00 2.7E+00 Bkg Bkg Bkg Bkg 6.1E-02 9.7E-02 4.9E-01 

Subsurface soil 

near the FRS (BH19A, 22-24' depth) 

4.3E+00 5.7E+02 Bkg Bkg Bkg Bkg 1.5E-01 2.0E-01 8.0E-01 

Subsurface soil 

near rail spur south 

of the FRS 

(GP10208, 14-16’ 

depth) 

1.1E+00 2.2E+02 9.1E-02 1.3E+00 3.5E-01 1.4E+00 Bkg 4.9E-02 1.4E-01 

NOTE: (1) See Figure 4-5 for a map showing facilities in the northern portion of WMA 6. See Figures 4-6 and 4-7 for 

maps showing locations with radionuclide concentrations in excess of background. 

LEGEND: NA = Not analyzed. “Bkg” = Background was not exceeded. FRS = Fuel Receiving and Storage Building, 

STP = Sewage Treatment Plant 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-45 

WMA 7, NDA and Associated Facilities 

Concentrations of radiological constituents measured at levels in excess of background 

in surface soil and sediment from WMA 7 are listed in Table 4-20. Cs-137, Sr-90, and Am241 were found in concentrations exceeding background in surface soil. Sediment samples 

collected near the Interceptor Trench contained concentrations of Cs-137, Sr-90, Pu-238, 

and Am-241 in excess of background. Ratios of Sr-90 to Cs-137 in surface soil ranged from 

0.11 to 1 to 8.2 to 1. The Sr-90 to Cs-137 ratio for sediment was about 3.7 to 1. Maximum 

ratios to Cs-137 for Pu-238, Pu-239/240, and Am-241 in surface soil and sediment were, 

respectively: 0.096 (sediment), 0.022 (surface soil), and 0.046 (sediment). All were found 

near the Interceptor Trench. 

No concentrations above background were found in boreholes of subsurface soil taken 

in 1993 at WMA 7. (Note that the two subsurface soil borings done at this location in 1993 

were taken from the edges of the burial area, one upgradient of the buried waste and the 

other on the opposite side of the Interceptor Trench downgradient of the area.) However, 

analytical results from boxes and rolloffs filled with subsurface soil excavated from “special 

holes” during burial activities on the NDA or during construction of the Interceptor Trench 

contained Am-241 concentrations well in excess of background. Ratios of Am-241 to Cs137 ranged from 0.024 to 0.077 to 1. The excavated soil has been shipped offsite, however, 

results suggest that subsurface soil remaining in the NDA contains radionuclide 

concentrations exceeding background. 

Table 4-20. Above-Background Concentrations of Radionuclides in Surface Soil, 

Sediment, and Subsurface Soil at WMA 7(1) 

Location

Maximum Concentration (pCi/g dry) 

Cs-137 Sr-90 Pu-238 Pu-239/ 

240 Am-241 

Surface soil by the NDA 

Interceptor Trench (SS-15, BH42) 

4.7E+00 3.3E+00 8.5E-02 9.2E-02 1.5E-01 

Surface soil by the NDA 

Hardstand (SS-20) 

6.8E+01 7.7E+00 NA NA NA 

Surface soil at remainder of NDA 

(1994 data from special 

sampling) 

3.2E+00 2.1E+01 NA NA NA 

Sediment from drainage near 

Interceptor Trench (ST-23) 

9.0E-01 3.3E+00 8.6E-02 Bkg 4.1E-02 

Subsurface soil excavated from 

“special holes” or Interceptor 

Trench (1997 sampling of 

excavated soil in boxes and 

rolloffs) 

3.5E+01 NA NA NA 1.8E+00

NOTE: (1) See Figures 4-6 and 4-7 for maps showing locations with radionuclide concentrations in excess of 

background. Not shown on the map, the Interceptor Trench borders the northeast and northwest 

boundaries of the NDA. The Trench was installed in 1990 to intercept and collect leaching from the 

NDA. The NDA Hardstand (not shown on the map) was located at the easternmost point of WMA 7. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-46 

WMA 9, Radwaste Treatment Drum Cell Area 

Data from only two surface soil samples were available for WMA 9. Although gross 

beta concentrations exceeded background for both, data for specific beta-emitting 

radionuclides did not. (See Figure 4-6.) No subsurface soil or sediment data were available 

for WMA 9. 

WMA 10, Support and Services Area 

Concentrations of radiological constituents measured at levels in excess of background 

in surface soil and sediment from WMA 10, the Support and Services Area, are listed in 

Table 4-21. This area includes support facilities (e.g., administrative buildings, offices, 

parking lots, the Environmental Laboratory) that are not known to be radiologically 

contaminated. Note that only one surface soil sample shown on Figure 4-6 did not have 

concentrations exceeding background: SS-11 on the north plateau, located on the western 

side of the project premises in WMA 10. 

Low-level concentrations of Cs-137 exceeding background were found in surface soil 

near support trailers close to the Process Building and in sediment from a drainage ditch 

south of the Environmental Laboratory. Elevated Cs-137 in surface soil is thought to be 

attributable to airborne releases. Elevated Cs-137 in the drainage ditch could be 

attributable to runoff from WMA 6 (i.e., possibly related to historical releases or leaks from 

the old Sewage Treatment Plant that released radionuclides to drainage by the railroad 

bed, as discussed in Section 2). Although gross alpha and gross beta concentrations 

slightly above background were noted for certain surface soil samples from WMA 10 (as 

shown on Figure 4-6), no other concentrations of specific radionuclides above background 

have been reported. 

Table 4-21. Above-Background Concentrations of Radionuclides in Surface Soil and 

Sediment at WMA 10(1) 

Location Maximum Concentration (pCi/g dry) 

Cs-137 

Surface soil by former Trailer City (1998 

special soil sampling) 1.0E+00 

Sediment samples by drainage south of 

Environmental Laboratory (ST-26) 1.7E-01 

NOTE: (1) See Figure 4-6 for a map showing locations with radionuclide concentrations in excess of background. 

Not shown on maps, the former Trailer City was located directly opposite the western entrance to the 

Process Building. The Environmental Laboratory (shown, but not labeled, on Figure 4-6) is located 

immediately north of sampling point ST-26. 

WMA 12, Remainder of the Site 

Concentrations of radiological constituents measured at levels in excess of background 

in surface soil and sediment from WMA 12 are listed in Table 4-22. Only the portion of 

WMA 12 within the project premises, which includes the onsite segments of Franks Creek 

and Erdman Brook, is addressed in this evaluation. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-47 

Surface soil concentrations of both Cs-137 and Sr-90 were noted in excess of 

background in WMA 12 (see Figure 4-6). Cs-137 and Sr-90 exceeding background 

concentrations were also found in sediment samples from both Franks Creek and Erdman 

Brook, as well as in drainage downgradient of the demineralizer sludge ponds. Sediment 

samples collected along the lengths of both Franks Creek and Erdman Brook also 

contained alpha-emitting radionuclides at concentrations in excess of background, although 

the radionuclides varied in relationship to the stream segment. 

In Erdman Brook downstream of drainage from the NDA (locations ST-22 and ST-21), 

Am-241 and Pu-238 were observed in concentrations greater than background. Further 

downstream, at point ST-20, after the stream receives inflow from via a drainage from 

WMA 2, Am-241, Pu-238, and Pu-239/240 concentrations were all above background. At 

point ST-19, located downstream where the stream receives effluent from Lagoon 3, U-232 

(in addition to the other nuclides) was also found above background. 

Similarly, sediment at the southernmost segments of Franks Creek (points ST-13, ST12, and ST-11) contained gross alpha concentrations in excess of background. However, 

at point ST-10, located downstream of its junction with Erdman Brook, concentrations of 

Am-241, Pu-238, and Pu-239/240 were found in its sediment in excess of background. 

NOTES: (1) See Figure 4-6 for a map showing locations with radionuclide concentrations in excess of 

background. The location of the Demineralizer Sludge Ponds is shown in Figure 4-5. 

LEGEND: NA = No analysis. “Bkg” = Concentrations did not exceed background. 

Table 4-22. Above-Background Concentrations of Radionuclides in Surface Soil and 

Sediment at WMA 12(1)

Location

Maximum Concentration (pCi/g) 

Cs-137 Sr-90 U-232 Pu-238 Pu-239/ 

240 Am-241

Surface soil near borders 

with WMA 2 and WMA 6 

(SS-08 [Cs-137], BH-16 [Sr90]) 

8.1E+00 1.3E+00 NA NA NA NA 

Surface soil near eastern 

fence line (SS-07) 

1.6E+00 4.4E+00 Bkg Bkg Bkg Bkg 

Sediment from drainage 

downgradient of 

Demineralizer Sludge 

Ponds (ST-27) 

6.0E+00 8.5E-01 Bkg Bkg 7.3E-02 1.4E-01

Sediment from Erdman 

Brook (ST-19 [Cs-137, Sr90, U-232], ST-20 [Pu-238, 

Pu-239/240], ST-22 [Am241]) 

3.5E+01 1.6E+00 1.1E-01 2.5E-01 7.3E-02 1.4E-01

Sediment from Franks 

Creek (ST-10 [Cs-137 only], 

SNSP006) 

1.0E+02 1.0E+01 1.4E-01 1.4E-01 1.1E-01 2.4E-01
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-48 

The highest concentrations of all radionuclides (except Pu-238, for which the maximum 

was found at point ST-20 on Erdman Brook) were observed in sediment from Franks Creek 

at location SNSP006, where it flows off site at the security fence.13 As was found with 

sediment from Erdman Brook, sediment from Franks Creek collected downgradient of the 

controlled effluent water release point WNSP001 contained U-232 at concentrations 

exceeding background. (Effluent water discharged from lagoon 3 through WNSP001 often 

contains measureable quantities of U-232.) Summary statistics for radionuclide 

concentrations at SNSP006 are presented in Appendix B. 

The highest ratio of Sr-90 to Cs-137 (about 3 to 1) in surface soil from WMA 12 was 

noted for one sample collected near the eastern edge of the fenced area. In sediment, the 

maximum ratios to Cs-137 for Sr-90 (0.1 to 1), Pu-239/240 (0.012 to 1), and Am-241 (0.023 

to 1) were all found downgradient of the Demineralizer Sludge Ponds. The highest ratios to 

Cs-137 of U-232 (0.003 to 1) and U-238 (0.007 to 1) were found in sediment from Erdman 

Brook, immediately after the point where it receives Lagoon 3 effluent. 

4.2.6 Environmental Radiation Levels 

As part of the WVDP Environmental Monitoring Program, since 1986 thermoluminescent dosimeters (TLDs) have been placed in the field to measure levels of integrated 

gamma radiation exposure. TLDs are placed: 

(1) At background locations far from the Center, 

(2) At communities near the Center, 

(3) At a ring of perimeter locations around the Center, and 

(4) At onsite locations near process areas, waste storage areas, and waste burial 

locations. 

Figure 4-9 shows the locations of onsite TLDs. 

Note that not all areas on the project premises have environmental TLD monitoring 

locations, therefore, data are not available for these areas. Average results over the last ten 

years, in mR/quarter and in mR/h, are summarized in Table 4-23. Onsite results are presented 

by waste management area. For comparison, measurements from background are included. 

Exposure measurements from the ring of TLDs around the perimeter of the Center and 

at the community locations are evaluated each year as part of preparing the Annual Site 

Environmental Report. Values from offsite TLDs have consistently been indistinguishable 

from background. 

13 In 1990, a sample from a hot spot in Erdman Brook that measured 3000 μR/h during the ground-level 

survey showed 0.01 μCi/g (10,000 pCi/g) Cs-137. (This was a screening analysis that may have been 

performed on a wet sample; it was not validated.) This area of localized contamination was described as 

about six inches by six inches located one meter from the edge of the water. Limited investigation indicated 

that the contamination extended more than seven inches below the streambed surface. (Passuite and 

Monsalve-Jones 1993, Appendix C) 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-49 

Results from all onsite TLDs, with the single exception of DNTLD27 located on the 

eastern border of the security-fenced area, were in excess of background levels. Note that 

exposure levels in the above table may not be indicative of radionuclides in soil, but of 

radiation from the wastes being processed and/or stored nearby. 

The on-site monitoring point with the highest dose readings was location DNTLD24 on 

the north plateau (Figure 4-9). Sealed containers of radioactive components and debris 

from the plant decontamination work are stored nearby in the Chemical Process Cell Waste 

Storage Area. Exposure rates at this location have been generally decreasing over time 

because the radioactivity in the materials stored nearby is decaying. This storage area is 

well within the Center boundary, just inside the WVDP fenced area, and is not accessible 

by the public. 

The maximum quarterly exposure level (1298 mR/qtr [0.59 mR/hr]) was noted at 

DNTLD35, near the rail spur by the Drum Cell in the second quarter of 2007. This high 

reading was associated with waste storage and with staging and shipping drums of 

cement-stabilized waste from the Drum Cell. All remaining drums were shipped from the 

Drum Cell in 2007, and in the fourth quarter of 2007 the exposure level at DNTLD35 had 

dropped to 23 mR/qtr (0.011 mR/hr). 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-50 

Figure 4-9. Onsite Environmental TLD Locations
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-51 

Table 4-23. Environmental Radiation Levels on the WVDP Site (1998-2007 data) 

TLD (s) Location Average

mR/qtr 

Average

mR/h 

Maximum 

mR/qtr 

Maximum 

mR/h 

(1)Exceeds

Background?

DNTLD40 Waste Tank Farm (WMA 3) 119 0.054 268 0.122 Yes 

DNTLD26 Construction and Demolition 

Debris Landfill fence line (WMA 

4) 

23 0.011 30 0.014 Yes 

DNTLD24 Chemical Process Cell Waste 

Storage Area fence line (WMA 

5) 

523 0.239 717 0.327 Yes 

DNTLD25 Quarry Creek, between 

security fence and public road 

(WMA 5) 

23 0.011 31 0.014 Yes 

DNTLD30 Northwest parking lot, near 

public road (WMA 10) 

23 0.010 32 0.015 Yes 

DNTLD39 On fence between parking lot 

and Process Building (WMA 

10) 

49 0.022 70 0.032 Yes 

DNTLD38 Nurse's office across Process 

Building (WMA 10) 

34 0.015 55 0.025 Yes 

DNTLD29 On fence near Environmental 

Laboratory (WMA 10) 

22 0.010 29 0.013 Yes 

DNTLD28 Southwestern corner of Project 

Premises (WMA 10) 

22 0.010 38 0.018 Yes 

DNTLD35 (2)Near rail spur by Drum Cell 

(WMA 9) 

109 0.050 1298 0.592 Yes 

DNTLD36 (2)Drum Cell north fence (WMA 

9)

61 0.028 458 0.209 Yes 

DNTLD43 Drum Cell northeastern fence 

(WMA 9) 

31 0.014 69 0.031 Yes 

DNTLD33 Drum Cell southeastern corner 

(WMA 9) 

32 0.014 54 0.025 Yes 

DNTLD19 Western fence line near waste 

burial areas (WMA 12) 

22 0.010 39 0.018 Yes 

DNTLD27 Eastern fence line farthest from 

process and waste storage 

areas (WMA 12) 

20 0.009 27 0.012 No 

Background Four background locations 

(map in Appendix B) 

19 0.009 35 0.016 NA 

NOTE: (1) Data sets from each location were compared with background data sets using one-way analysis of variance 

(see Appendix B). 

 (2) Exposure measurements near the Drum Cell have been elevated in the last several years because the area 

is being used as a storage area for vessels removed from the Process Building and for staging waste for 

shipping. Waste drums formerly stored in the Drum Cell itself were removed in 2007. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-52 

 As summarized in WVNSCO 1994, two aerial radiation surveys of the WNYNSC in 

1969 and 1979 identified above-background gamma radiation extending from the 

reprocessing plant in a northwest direction along Buttermilk Creek (1969) and in a prong 

extending westward offsite across Rock Springs Road (1979). Cs-137 was determined to 

be the source of the gamma activity. (See Section 2.) 

Soil sampling by NYSDEC in 1971 and by WVNSCO in 1982 determined that Cs-137 

activity was greater in soil northwest of the plant and that activity was greatest at the soil 

surface and decreased with depth (WVNSCO 1994). Activity in the cesium prong is 

attributed to airborne releases from a filter blow-out in 1968, as indicated in Section 2. 

Elevated radionuclide concentrations in the Buttermilk Creek drainage are attributed to 

routine radioactive liquid releases. 

Posted Radiation Areas

At the WVDP Site, radiation areas are posted if exposure can exceed 5 mrem/hr at 30 

centimeters (WVNSCO 2006). Posted radiological control areas on the project premises 

are shown in Figure 4-10. Posted radiation levels are generally indicative of surface and/or 

near surface contamination, storage of radioactive waste, and proximity to radiological 

process areas. Posted areas are delineated in accordance with 10 CFR 835, Occupational 

Radiation Protection. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-53 

Figure 4-10. WVDP Radiological Control Areas. (Facilities with radiological controlled 

areas are outlined in black. Radiological Control Areas are current as of June 2008. )
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-54 

4.2.7 Radiological Status of Onsite Surface Water 

The WVDP Environmental Monitoring Program routinely collects surface water samples 

from the following locations on the project premises: 

(1) Two controlled effluent discharges (releases from lagoon 3 through the weir at 

point WNSP001 and from the Sanitary Waste Treatment Facility at point 

WNSP007); 

(2) Two drainages where water from the North Swamp and the Northeast Swamp 

leave the site (points WNSW74A and WNSWAMP, respectively); 

(3) Facility cooling water from the Cooling Tower (WNCOOLW); 

(4) Two drainage ditches (facility drainage [point WNSP005] and NDA surface 

drainage [point WNNDADR]); and 

(5) Three locations on two streams (point WNERB53 on Erdman Brook, point 

WNFRC67 on Franks Creek, and point WNSP006 where Franks Creek leaves the 

project premises at the security fence). 

Figure 4-11 shows the location of these routine surface water monitoring locations and 

indicates those with gross alpha (or alpha-emitting radionuclide) concentrations and gross 

beta (or beta/gamma-emitting radionuclide) concentrations in excess of background. All 

surface water locations had at least one constituent exceeding background (i.e., no nonimpacted locations were noted). 

Table 4-24 summarizes median, average, and maximum concentrations of those 

radionuclides observed to exceed background in surface water over the ten-year period 

1998-2007. (For a complete summary of radionuclide concentrations in surface water, 

including those not detected above background, see Table B-13 of Appendix B.) Note that 

concentrations of the beta-emitting radionuclide Sr-90 exceeding background were 

observed in surface water throughout the project premises. (See Appendix B for 

comparable summary statistics for each radionuclide in surface water from background 

locations.) The highest Sr-90 concentrations were observed at location WNSWAMP, which 

is downstream of the point where the leading edge of the north plateau groundwater plume 

surfaces. 

The full suite of radionuclides monitored in surface water was detected at abovebackground concentrations at the Lagoon 3 discharge point WNSP001. Tritium was 

detected downstream of the Low-Level Waste Treatment Facility (points WNSP001 and 

WNSP006), at the Northeast Swamp Discharge Point (WNSWAMP), at a point immediately 

downstream of the NDA on the south plateau (WNNDADR), and in Erdman Brook and 

Franks Creek on the south plateau (locations WNERB53 and WNFRC67, respectively). 

Alpha-emitting radionuclides at concentrations exceeding background were noted only 

in surface water from the north plateau, primarily at locations downstream of the Low-Level 

Waste Treatment Facility discharge, but also at the North (WNSW74A) and Northeast 

Swamp (WNSWAMP) discharge points. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-55 

Figure 4-11. Surface Water Locations with Radionuclide Concentrations in Excess of 

Background 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-56 

Table 4-24. Radionuclide Concentrations (pCi/L)(1) in Excess of Background in Surface 

Water(2) 

Location Median Average Maximum 

Result ± Uncertainty 

Lagoon 3 discharge weir (WNSP001), WMA 2 

H-3 2.5E+03 2.8E+03 ± 1.4E+02 7.2E+03 

C-14 < 2.8E+01 1.4E+01 ± 2.2E+01 4.8E+01 

Sr-90 9.9E+01 1.2E+02 ± 7.4E+00 3.2E+02 

Tc-99 6.5E+01 7.9E+01 ± 4.8E+01 3.4E+03 

I-129 2.1E+00 2.4E+00 ± 1.5E+00 1.0E+01 

Cs-137 6.1E+01 7.6E+01 ± 1.9E+01 3.3E+02 

U-232 8.0E+00 9.0E+00 ± 9.9E-01 2.1E+01 

U-233/234 5.0E+00 5.5E+00 ± 6.2E-01 1.4E+01 

U-235/236 2.6E-01 2.8E-01 ± 1.2E-01 5.8E-01 

U-238 3.8E+00 3.8E+00 ± 4.9E-01 7.6E+00 

Pu-238 6.5E-02 1.5E-01 ± 6.8E-02 1.6E+00 

Pu-239/240 5.2E-02 1.3E-01 ± 6.2E-02 1.4E+00 

Am-241 6.8E-02 1.2E-01 ± 6.0E-02 9.7E-01 

Northeast swamp drainage (WNSWAMP), WMA 4 

H-3 1.1E+02 1.1E+02 ± 8.2E+01 5.2E+02 

Sr-90 1.5E+03 1.7E+03 ± 3.1E+01 5.2E+03 

U-233/234 1.7E-01 2.0E-01 ± 1.4E-01 9.3E-01 

U-238 1.0E-01 1.2E-01 ± 1.1E-01 7.2E-01 

North swamp drainage (WNSW74A), WMA 5 

Sr-90 5.5E+00 5.5E+00 ± 1.8E+00 1.2E+01 

U-233/234 1.5E-01 1.6E-01 ± 8.4E-02 3.5E-01 

U-238 1.0E-01 1.0E-01 ± 6.6E-02 2.0E-01 

Sanitary waste discharge (WNSP007), WMA 6 

Sr-90 3.1E+00 3.4E+00 ± 1.9E+00 1.2E+01 

Franks Creek at security fence (WNSP006), WMA 12 

H-3 < 8.5E+01 1.4E+02 ± 8.3E+01 2.2E+03 

Sr-90 1.9E+01 2.0E+01 ± 3.0E+00 5.0E+01 

Tc-99 < 2.1E+00 3.3E+00 ± 2.1E+00 5.2E+01 

Cs-137 < 8.0E+00 6.3E+00 ± 9.5E+00 7.3E+01 

U-232 3.2E-01 3.2E-01 ± 1.3E-01 7.5E-01 

U-233/234 3.7E-01 3.7E-01 ± 1.3E-01 6.9E-01 

U-238 2.5E-01 2.8E-01 ± 1.1E-01 7.4E-01 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-57 

Table 4-24. Radionuclide Concentrations (pCi/L)(1) in Excess of Background in Surface 

Water(2) 

Location Median Average Maximum 

Result ± Uncertainty 

Pu-238 < 3.4E-02 2.1E-02 ± 3.4E-02 1.4E-01 

Facility yard drainage (WNSP005), WMA 12 

H-3 < 8.3E+01 3.8E+01 ± 8.2E+01 1.2E+03 

Sr-90 9.6E+01 1.0E+02 ± 6.5E+00 2.0E+02 

Drainage between NDA and SDA (WNNDADR), WMA 12 

H-3 1.0E+03 1.1E+03 ± 1.0E+02 4.0E+03 

Sr-90 8.5E+01 8.4E+01 ± 5.4E+00 1.2E+02 

Erdman Brook north of disposal areas (WNERB53), WMA 12 

H-3 < 8.3E+01 3.9E+01 ± 8.0E+01 4.9E+02 

Sr-90 8.2E+00 8.0E+00 ± 2.0E+00 9.9E+00 

Franks Creek East of SDA (WNFRC67), WMA 12 

H-3 < 8.3E+01 3.1E+01 ± 8.1E+01 3.5E+02 

NOTES: (1) 1 pCi/L = 3.7E-02 Bq/L 

 (2) Refer to Table 4-11 for median and maximum background values and to Appendix B for summary statistics 

of background radionuclide concentrations in surface water. 

4.2.8 Radiological Status of Groundwater 

Groundwater at the WVDP is routinely monitored in accordance with the WVDP 

Groundwater Monitoring Program. Although the primary focus of the program is on 

nonradiological constituents, all wells are monitored for radiological indicator parameters 

(gross alpha, gross beta, and H-3). Several wells, especially those impacted by the north 

plateau groundwater plume, are sampled for Sr-90. Select wells are monitored for a full 

suite of radionuclides. Table 4-25 lists routine groundwater monitoring locations at which 

radiological concentrations were found at levels exceeding background. Medians, 

averages, and maximum concentrations (in pCi/L) are presented for each. 

For groundwater (unlike the other environmental media discussed in this section), 

gross alpha and gross beta concentrations exceeding background are presented. This is 

because limited radionuclide data are available for routinely monitored groundwater 

locations, and gross alpha and gross beta measurements, taken at all wells, may indicate 

the presence of other alpha- or beta-emitting radionuclides. For instance, gross beta 

measurements are used as a surrogate measurement for Sr-90 at monitoring points where 

the Sr-90-to-gross beta ratio has been determined to be approximately 0.5 to 1. 

Locations at which gross alpha (or alpha-emitting radionuclide) concentrations and/or 

gross beta (or beta-emitting radionuclide, including H-3) concentrations exceeded 

background are shown on Figure 4-12. Locations at which no radiological constituents 

were found to exceed background are also shown. For a complete summary of 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-58 

radionuclide data from both impacted and non-impacted routine groundwater monitoring 

locations, see Appendix B, Table B-14. A listing of supplementary information for each 

point (e.g., geographical coordinates, well construction, screened interval, geologic unit) is 

provided in Appendix B, Table B-15. 

Table 4-25. Routine Groundwater Monitoring Locations With Radionuclide Concentrations 

(pCi/L)(1) in Excess of Background(2) 

WMA Monitoring 

Point Constituent Median 

Average 

Maximum

Result ± Uncertainty 

WMA 1 WP-A Gross beta 2.4E+01 3.1E+01 ± 4.6E+00 5.4E+01 

 H-3 1.2E+04 1.1E+04 ± 6.2E+02 1.3E+04 

WMA 2 WP-C Gross beta 2.4E+01 4.2E+01 ± 5.5E+00 1.2E+02 

 H-3 4.9E+04 4.7E+04 ± 1.6E+03 6.6E+04 

 WP-H Gross alpha 6.1E+00 7.9E+01 ± 2.3E+01 7.4E+02 

 Gross beta 7.0E+03 7.2E+03 ± 1.9E+02 1.2E+04 

 H-3 3.0E+03 3.4E+03 ± 5.0E+02 7.4E+03 

 WNW0103 Gross beta 1.4E+02 1.8E+02 ± 1.9E+01 5.5E+02 

 WNW0104 Gross beta 5.9E+04 5.6E+04 ± 1.6E+03 1.0E+05 

 H-3 3.7E+02 3.9E+02 ± 8.6E+01 7.5E+02 

 WNW0105 Gross beta 3.9E+04 3.3E+04 ± 1.5E+03 1.0E+05 

 H-3 3.6E+02 3.7E+02 ± 9.1E+01 7.1E+02 

 WNW0106 Gross beta 1.6E+01 8.2E+01 ± 8.0E+00 5.8E+02 

 H-3 9.6E+02 1.0E+03 ± 1.0E+02 1.8E+03 

 WNW0107 Gross beta 7.0E+00 8.2E+00 ± 2.6E+00 2.2E+01 

 H-3 3.7E+02 4.8E+02 ± 9.0E+01 9.9E+02 

 WNW0108 Gross alpha 1.6E+00 1.5E+00 ± 1.5E+00 4.3E+00 

 H-3 1.2E+02 1.1E+02 ± 8.4E+01 2.5E+02 

 WNW0110 H-3 1.3E+03 1.3E+03 ± 1.1E+02 1.7E+03 

 WNW0111 Gross alpha <4.4E+00 3.2E+00 ± 5.1E+00 1.0E+01 

 Gross beta 5.6E+03 5.9E+03 ± 1.4E+02 1.2E+04 

 H-3 2.0E+02 2.3E+02 ± 8.4E+01 8.0E+02 

 WNW0116 Gross beta 8.7E+02 2.0E+03 ± 1.6E+02 9.5E+03 

 H-3 1.7E+02 1.9E+02 ± 8.2E+01 4.7E+02 

 WNW0205 Gross beta 1.6E+01 1.7E+01 ± 8.4E+00 4.1E+01 

 WNW0408 Gross beta 4.0E+05 4.0E+05 ± 3.0E+03 6.3E+05 

 H-3 1.5E+02 1.9E+02 ± 1.1E+02 2.2E+03 

 Sr-90 1.5E+05 1.5E+05 ± 1.7E+02 2.5E+05 

 Tc-99 1.6E+01 1.7E+01 ± 3.3E+00 2.5E+01 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-59 

Table 4-25. Routine Groundwater Monitoring Locations With Radionuclide Concentrations 

(pCi/L)(1) in Excess of Background(2) 

WMA Monitoring 

Point Constituent Median 

Average 

Maximum

Result ± Uncertainty 

 WMA 2 U-233/234 4.5E-01 5.3E-01 ± 2.2E-01 1.3E+00 

 U-238 2.9E-01 3.1E-01 ± 1.6E-01 4.8E-01 

 WNW0501 Gross beta 1.9E+05 1.9E+05 ± 2.6E+03 3.2E+05 

 H-3 1.4E+02 1.2E+02 ± 8.4E+01 3.2E+02 

 Sr-90 9.2E+04 9.3E+04 ± 2.4E+02 1.5E+05 

 WNW0502 Gross beta 1.7E+05 1.6E+05 ± 2.8E+03 2.3E+05 

 H-3 1.3E+02 1.4E+02 ± 8.4E+01 5.0E+02 

 Sr-90 8.4E+04 8.3E+04 ± 2.1E+02 1.2E+05 

 WNW8603 Gross beta 5.7E+04 4.8E+04 ± 1.2E+03 9.0E+04 

 H-3 3.4E+02 3.4E+02 ± 8.8E+01 5.8E+02 

 WNW8604 Gross beta 4.1E+04 4.6E+04 ± 1.1E+03 1.0E+05 

 H-3 3.5E+02 3.8E+02 ± 8.4E+01 6.4E+02 

 WNW8605 Gross alpha 9.1E+00 8.5E+00 ± 7.7E+00 2.1E+01 

 Gross beta 1.1E+04 1.1E+04 ± 1.7E+02 1.6E+04 

 H-3 3.7E+02 4.2E+02 ± 8.7E+01 1.3E+03 

 WMA 3 WNW8609 Gross beta 1.5E+03 1.4E+03 ± 4.2E+01 2.3E+03 

 H-3 4.5E+02 4.7E+02 ± 9.1E+01 7.9E+02 

 Sr-90 8.0E+02 7.2E+02 ± 2.1E+01 1.1E+03 

WMA 4 WNW0801 Gross beta 8.0E+03 8.6E+03 ± 2.7E+02 1.5E+04 

 H-3 1.5E+02 1.6E+02 ± 8.2E+01 3.8E+02 

 Sr-90 4.1E+03 4.3E+03 ± 4.7E+01 8.0E+03 

 WNW0802 Gross beta 9.9E+00 3.5E+01 ± 5.1E+00 2.8E+02 

 H-3 <1.1E+02 9.0E+01 ± 8.0E+01 4.2E+02 

 WNW0803 Gross beta 1.5E+01 1.5E+01 ± 4.7E+00 2.5E+01 

 H-3 1.8E+02 1.6E+02 ± 8.5E+01 3.4E+02 

 WNW0804 Gross beta 2.6E+02 2.9E+02 ± 1.1E+01 6.9E+02 

 H-3 1.2E+02 1.1E+02 ± 8.0E+01 3.6E+02 

 WNW8612 H-3 4.2E+02 4.3E+02 ± 8.9E+01 8.5E+02 

WMA 5 WNW0406 Gross beta 7.4E+00 8.1E+00 ± 3.5E+00 1.7E+01 

 H-3 1.2E+02 1.1E+02 ± 8.4E+01 4.4E+02 

 Tc-99 2.2E+00 2.5E+00 ± 1.9E+00 8.5E+00 

 WNW0409 Gross alpha <1.0E+00 9.4E-01 ± 9.9E-01 2.3E+00 

 WNW0602A Gross beta 1.2E+01 1.3E+01 ± 2.9E+00 3.5E+01 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-60 

Table 4-25. Routine Groundwater Monitoring Locations With Radionuclide Concentrations 

(pCi/L)(1) in Excess of Background(2) 

WMA Monitoring 

Point Constituent Median 

Average 

Maximum

Result ± Uncertainty 

 WMA 5 H-3 2.2E+02 2.2E+02 ± 8.9E+01 4.9E+02 

 WNW0604 Gross beta 6.1E+00 6.3E+00 ± 3.0E+00 1.3E+01 

 WNW0605 Gross beta 4.8E+01 5.1E+01 ± 4.0E+00 8.8E+01 

 WNW0704 Gross beta 8.0E+00 8.2E+00 ± 3.0E+00 1.3E+01 

 WNW8607 Gross beta 2.6E+01 2.7E+01 ± 5.3E+00 7.6E+01 

 WNW1304 U-233/234 2.7E-01 2.9E-01 ± 1.3E-01 5.6E-01 

 U-238 1.9E-01 2.2E-01 ± 1.0E-01 5.8E-01 

WMA 7 WNW0902 Gross alpha 1.5E+00 1.3E+00 ± 1.3E+00 5.4E+00 

 WNW0909 Gross beta 3.7E+02 3.7E+02 ± 1.4E+01 6.4E+02 

 H-3 8.2E+02 1.5E+03 ± 1.2E+02 3.9E+03 

 Sr-90 1.9E+02 1.8E+02 ± 8.3E+00 2.2E+02 

 Tc-99 <1.9E+00 1.3E+00 ± 1.8E+00 5.0E+00 

 I-129 6.2E+00 6.3E+00 ± 1.9E+00 9.7E+00 

 U-233/234 6.0E-01 7.4E-01 ± 2.4E-01 1.3E+00 

 U-238 4.7E-01 5.4E-01 ± 2.0E-01 1.0E+00 

 WNW0910 Gross alpha <2.5E+00 1.9E+00 ± 2.3E+00 3.4E+00 

 Gross beta 3.8E+01 1.5E+02 ± 8.5E+01 1.5E+03 

 WNNDATR Gross alpha 2.2E+00 2.1E+00 ± 2.1E+00 1.1E+01 

 Gross beta 1.5E+02 1.8E+02 ± 8.4E+00 5.5E+02 

 H-3 3.6E+03 5.0E+03 ± 2.3E+02 2.0E+04 

 Sr-90 5.8E+01 7.8E+01 ± 5.5E+00 2.8E+02 

 I-129 <9.1E-01 8.4E-01 ± 9.4E-01 7.0E+00 

 U-233/234 1.7E+00 1.5E+00 ± 2.8E-01 2.1E+00 

 U-235/236 1.1E-01 1.4E-01 ± 9.5E-02 3.0E-01 

 U-238 1.3E+00 1.2E+00 ± 2.5E-01 1.7E+00 

WMA 9 WNW1006 Gross alpha <5.1E+00 4.2E+00 ± 5.5E+00 1.0E+01 

NOTES: (1) 1 pCi/L = 3.7E-02 Bq/L 

(2) Refer to Table 4-11 for median and maximum background values and to Appendix B for summary statistics 

of background radionuclide concentrations in groundwater (Table B-7) and at non-impacted groundwater 

monitoring locations (Table B-14). Data sets from each location were compared with background data 

sets using the nonparametric Mann-Whitney “U” test, as described in Appendix B, section 4.3.

As shown in Figure 4-12, elevated gross beta concentrations are evident in 

groundwater northeast of the Process Building (WVNSCO and URS 2005). The beta 

activity is primarily found in the surficial sand and gravel unit, and the general direction of 

flow in this unit is to the northeast. Elevated gross beta concentrations are largely 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-61 

attributed to Sr-90 in the north plateau plume. While concentrations of gross alpha or alphaemitting radionuclides exceeding background were found at only a few locations, the 

locations were associated with (or downgradient of) historical waste processing or waste 

burial activities (i.e., WMAs 1, 2, and 7). 

In December 1993, elevated gross beta concentrations were detected in surface water 

at a former sampling location near the edge of the north plateau. This discovery initiated a 

subsurface groundwater and soil Geoprobe®

 investigation in 1994 (Carpenter and Hemann 

1995). Two additional Geoprobe®

 investigations were conducted in 1997 (Hemann and 

Fallon 1998) and 1998 (Hemann and Steiner 1999). 

Groundwater was collected in 2008 in accordance with a sampling and analysis plan 

(Michalczak 2007) for a Geoprobe characterization of the north plateau. Data from this 

sampling program have been included in the tables and figures for this section. 

A listing of the Geoprobe®

 locations, sample depths, and geologic units from which the 

groundwater was sampled is provided in Appendix B, Table B-16. (NOTE: For 

completeness, Appendix B, Table B-17, provides a listing of groundwater points — in 

addition to the routine groundwater monitoring and Geoprobe®

 locations included in this 

evaluation — that have been sampled over the years. Table B-17 presents information on 

the locations and depths of these points, and summarizes the reasons that the points were 

not included in the current evaluation [dry wells, wells dropped from program, unvalidated 

data, located in areas outside the scope of the Phase 1 DP, etc.].) 

The principal source of the north plateau groundwater plume is believed to be a release 

of radioactively contaminated acid from the NFS acid recovery system in the 1960s when 

NFS was reprocessing fuel, during 10 CFR Part 50 licensed activities. A detailed 

description of the release is provided in Section 2, subsection 2.3.1. See also Table 2-15 

for an estimate of radionuclide activity from this release expected to remain in the plume in 

2011. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-62 

Figure 4-12. Routine Groundwater Monitoring Locations with Radionuclide 

Concentrations in Excess of Background 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-63 

The Geoprobe®

 investigation results were used to estimate the extent of the north 

plateau groundwater plume beneath and downgradient of the Process Building. As part of 

the Geoprobe®

 investigations, a more extensive suite of radionuclides was analyzed in 

groundwater than was done for routine monitoring. Because the Geoprobe®

 groundwater 

samples differed from those taken from routine monitoring locations in that Geoprobe® 

samples may have been taken from several depths (and even from different geologic units) 

at a single location, the sample results were not directly comparable and have not been 

presented in the same table. However, results from the Geoprobe®

 investigations provide 

supplemental information about the presence of radionuclides in groundwater on the north 

plateau. 

Geoprobe®

 locations at which concentrations of alpha-emitting radionuclides or 

beta/gamma-emitting radionuclides, including H-3, exceeded background are shown on 

Figure 4-13. The maximum measured radionuclide concentrations are summarized by 

WMA in Table 4-26. (Since radionuclide data were available for these sampling locations, 

gross alpha and gross beta data, which could be affected by naturally occurring 

radionuclides, were not included in Table 4-26 or Figure 4-13). 

As can be seen in Figure 4-13, concentrations of beta/gamma-emitting radionuclides 

exceeding background are evident at most locations downgradient of the Process Building. 

Most non-impacted points were noted in WMA 5 northwest of the north plateau 

groundwater plume. Alpha-emitting radionuclide concentrations exceeding background 

were found immediately downgradient of the Process Building and downgradient of the 

Interceptors. 

Table 4-26. Maximum Above-Background Radionuclide Concentrations (pCi/L) at 

Groundwater Geoprobe®

 Points by WMA, Location, and Depth(1)

WMA Point Constituent Maximum Point Constituent Maximum

WMA 1 GP8098 (22-24’) H-3 6.4E+04 GP2908 (17-19’) U-232 1.0E+00 

 GP29 (27-29’) C-14 2.3E+03 GP2908 (17-19’) U-233/234 1.1E+01 

 GP30 (18-20’) Sr-90 1.2E+06 GP2908 (17-19’) U-235/236 4.6E-01 

 GP72 (30-32’) Tc-99 1.2E+04 GP2908 (17-19’) U-238 1.2E+01 

 GP29 (21-23’) I-129 3.0E+01 GP7608 (20-22’) Pu-239/240 4.5E-01 

 GP7608 (20-22’) Cs-137 1.2E+02 GP76 (27-29’) Am-241 4.7E-01 

WMA 2 GP47 (11-13’) H-3 3.4E+04 GP44 (14-16’) U-233/234 3.7E+01 

 GP66 (30-32’) C-14 4.0E+02 GP44 (14-16’) U-235/236 6.2E-01 

 GP8298 (20-24’) Sr-90 2.8E+05 GP60 (12-14’) U-238 1.5E+01 

 GP68 (25-27’) Tc-99 5.8E+01 GP59 (17-19’) Pu-238 4.5E+00 

 GP47 (11-13’) I-129 8.2E+01 GP59 (17-19’) Pu-239/240 7.9E+00 

 GP46 (12-14’) Cs-137 1.5E+02 GP59 (17-19’) Am-241 5.9E+00 

 GP44 (14-16’) U-232 7.8E+01 - - - 

 WMA 3 GP20 (15-17’) H-3 1.5E+03 GP20 (15-17’) I-129 2.5E+00 

 GP20 (15-17’) Sr-90 5.2E+01 - - - 

WMA 4 GP32A (5-7’) H-3 1.3E+03 GP8998 (16-18’) Sr-90 6.5E+03 

WMA 5 GP43 (12-14’) H-3 2.0E+04 GP53 (14-16’) Tc-99 8.0E+01 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-64 

Table 4-26. Maximum Above-Background Radionuclide Concentrations (pCi/L) at 

Groundwater Geoprobe®

 Points by WMA, Location, and Depth(1)

WMA Point Constituent Maximum Point Constituent Maximum

 GP40 (13-15’) Sr-90 3.8E+03 GP43 (12-14’) I-129 4.6E+00 

WMA 6 GP70 (26-28’) H-3 6.8E+03 GP70 (21-23’) Tc-99 3.1E+01 

 GP70 (16-18’) C-14 1.4E+02 GP70 (21-28’) I-129 1.1E+01 

 GP70 (16-18’) Sr-90 2.8E+04 - - - 

WMA 12 GP48 (7-9’) H-3 1.5E+03 GP50 (8-10’) U-238 7.2E-01 

 GP50 (8-10’) Sr-90 1.3E+01 - - - 

. NOTE: (1) Points ending with “97,” “98,” or “08” were collected in 1997, 1998, or 2008, respectively. The remaining 

points were collected in 1994. Sample results were compared with average background values as described 

in Appendix B, section 4.2.

The north plateau plume, as delineated by the 1,000 pCi/L isopleth, was approximately 

300 feet wide and 800 feet long in 1994. By 2004, the plume area had expanded to 

approximately 350 feet by 1050 feet, and by 2007 to about 540 feet (at its widest point near 

the leading edge) by 1300 feet (WVES and URS 2008). (See Figure 4-14.) 

The highest gross beta concentrations in groundwater and soil were found near the 

southeast corner of the Process Building. In the 1994 study, the maximum concentration in 

groundwater was 3.6E+06 pCi/L, and the maximum concentration in subsurface soil was 

2.4E+04 pCi/g. Sr-90 and its progeny, Y-90, were determined to be the isotopes 

responsible for most of the elevated gross beta activity (WVNSCO and URS 2007). 

As a result of recommendations from a 1997 external review of WVDP response 

actions on the north plateau, more attention was given in 1998 to the core area of the 

plume, determined to be beneath and immediately downgradient of the Process Building. 

Results from the 1998 investigation were presented in a summary report (Hemann and 

Steiner 1999) that compared groundwater and soil sampling data with the 1994 data. 

Concentrations detected in 1998 samples were generally lower than those in the 1994 

samples due to radioactive decay and continuing migration and dispersion of the plume. 

The study also concluded that Lagoon 1 was a possible contributor of gross beta activity to 

groundwater downgradient of the Lagoon. 

Figure 4-14 shows the 1E+03 pCi/L gross beta contour lines defining the extent of the 

plume in 1994, 2001, and 2007. (This figure, which duplicates Figure 2-6 in Section 2, is 

provided here for the sake of completeness.) Figure 4-14 also shows gross beta 

concentrations at the 12 routine groundwater monitoring locations that define the plume as 

of the fourth quarter of 2007. Contour lines show a gradual lengthening and expansion of 

the plume toward the northeast, with the highest concentration (i.e., well 408 at 3.9E+05 

pCi/L) near the Process Building and lower concentrations near the leading edge. Further 

downgradient, the plume appears to be diverging – one prong moving to the north toward 

the surface drainage north of the CDDL and the other toward the east. Figure 4-14 also 

shows 1E+03 pCi/L contour lines of gross beta activity in groundwater over time near 

inactive Lagoon 1. This smaller area of elevated activity, likely associated with 

contamination remaining in Lagoon 1 sediment and backfill, appears to be migrating slightly 

eastward over time. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-65 

Figure 4-13. Geoprobe® Groundwater Locations with Radionuclide Concentrations in 

Excess of Background
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-66 

Figure 4-14. North Plateau Groundwater Plume 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-67 

4.3 References

Code of Federal Regulations 

10 CFR 50, Domestic Licensing of Production and Utilization Facilities. 

10 CFR 835, Occupational Radiation Protection. 

Other References 

Carpenter and Hemann 1995, Subsurface Probing Investigation on the North Plateau at the 

West Valley Demonstration Project, WVDP-220, Rev. 0. Carpenter, B. and M. 

Hemann, West Valley Nuclear Services Company, West Valley, New York, April 

26, 1995. 

Chorosor 2003, Product Purification Cell (PPC) Radioisotope Inventory Report, RIR-403-

022, Revision 0. Chorosor, J., West Valley Nuclear Services Company, West 

Valley, New York, November 24, 2003. 

Choroser 2004, Liquid Waste Cell Radioisotope Inventory Report, RIR-403-023, Revision 

0. Choroser, J., West Valley Nuclear Services Company, West Valley, New York, 

July 21, 2004. 

Choroser, 2005a, General Purpose Cell (GPC) Radioisotope Inventory Report, RIR-403-

036, Revision 1. Choroser, J., West Valley Nuclear Services Company, West 

Valley, New York, January 25, 2005. 

Choroser, 2005b, Process Mechanical Cell (PMC) Radioisotope Inventory Report, RIR403-037, Revision 1. Choroser, J., West Valley Nuclear Services Company, West 

Valley, New York, January 25, 2005. 

Drobot 2003, Sample Storage Cell (SSC), Radioisotope Inventory Report, RIR-403-014, 

Revision 0. Drobot, A., West Valley Nuclear Services Company, West Valley, New 

York, April 30, 2003. 

EG&G/EM 1984, An Aerial Radiological Survey of the WEST VALLEY DEMONSTRATION 

PROJECT and Surrounding Area, EG&G/EM Survey Report, EGG-10617-1080. 

EG&G/EM, Las Vegas, Nevada, 1984. 

Fazio 2001, Data Collection and Analysis Plan (DAP) for Tanks 8D-1 and 8D-2 As Part of 

the Waste Tank Farm (WTF) Project, WVDP-364, Revision 3. Fazio, J.M., West 

Valley Nuclear Services Company, West Valley, New York, November 14, 2001. 

Fazio 2002a, Waste Storage Tank 8D-3 Radioisotope Inventory Report, WVDP-364-003, 

Revision 0. Fazio, J.M., West Valley Nuclear Services Company, West Valley, New 

York, September 24, 2002. 

Fazio 2002b, High-Level Waste Tank 8D-1 and 8D-2 Radionuclide Inventory Report as of 

September 1, 2002, WVDP-364-001, Revision 0. Fazio, J.M., West Valley Nuclear 

Services Company, West Valley, New York, September 30, 2002. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-68 

Fazio 2002c, Supernatant Treatment System (STS) Valve Aisle Radionuclide Inventory 

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WVDP PHASE 1 DECOMMISSIONING PLAN

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Company, West Valley, New York, January 16, 2004. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-70 

Michalczak 2004b, Low Ranking Areas of the Process Building Radioisotope Inventory 

Report, RIR-403-033, Revision 0. Michalczak, L., West Valley Nuclear Services 

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New York, August 2000. 
WVDP PHASE 1 DECOMMISSIONING PLAN

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WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-72 

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New York, September 15, 1994. 

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1995. 

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Valley Nuclear Services Company, WVDP-RFI-023, December 1996. 

WVNSCO 1997a, Resource Conservation and Recovery Act Facility Investigation Report, 

Volume 4, Low-level Waste Treatment Facility, WVDP-RFI-021. West Valley 

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WVNSCO 1997b, Resource Conservation and Recovery Act Facility Investigation Report, 

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1, 1998. 

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2001. 

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WVNSCO 2004c. EM-11. Documentation and Reporting of Environmental Data. Rev. 8. 

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2004. 

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WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 4-73 

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December 1996. 

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Group, Inc., West Valley, New York, August 2007. 
 

This page is intentionally blank. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Rev 0 5-5

Figure 5-2. Conceptual Cross Section View of WMA 1 Excavation With Representative Data on Sr-90 Conce

(See Section 4.2 for more data and 7 for the excavation details.)

The subsurface soil cleanup goals would apply

to the bottom of the excavation and to the sides 

more than three feet below the surface

Typical depth of water table 

GP-23, GP-30, GP-72, and GP-75 indicate locations of subsurface samples collected with a GeoprobeTM. Data shown are from the ________investigation 

GP-23, GP-30, GP-72, and GP-75 indicate locations of subsurface samples collected with a Geoprobe . 

Data shown are from the 1998 Geoprobe investigation (Hemann and Steiner 1999). 

302
WVDP PHASE 1 DECOMMISSIONING PLAN

Rev 1 5-6Figure 5-3. Conceptual Cross Section View of WMA 2 Excavation With Representative Data on Subsurface Soil Co(See Section 4.2 for more data and 7 for excavation details. 

See Table 2-18 for estimated residual radioactivity in Lagoon 1. 

The subsurface soil cleanup goals would apto the bottom of the excavation and to the smore than three feet below the surface. 

See Table 4-14 for maximum radioactivity concentrations in Lagoon 2 and Lagoon 3 s
WVDP PHASE 1 DECOMMISSIONING PLAN

Rev 1 5-7 

 Available data on radioactive contamination in subsurface soil in WMA 1 described in 

Section 4.2 show Sr-90 to be the dominant radionuclide at depth. Figure 4-8 shows key 

data, which include three samples from several feet into the unweathered Lavery till that 

show Sr-90 concentrations of 13 pCi/g, 5.6 pCi/g, and 2.2 pCi/g at depths in the 35 to 40 

feet range. 

Other radionuclides with measured above-background concentrations in subsurface 

soil in WMA 1, with their maximum concentrations and the associated sample depth, 

include: Tc-99 (19 pCi/g at 19-23 feet), Cs-137 (31 pCi/g, at 27 to 29 feet), Pu-241 (15 

pCi/g at 21 to 23 feet), and Am-241 (0.1 pCi/g, 19 to 23 feet). Table 5-1 shows the 

maximum measured radionuclide concentrations in the Lavery till in the areas of the large 

excavations in WMA 1 and WMA 2. Data in the Lavery till in these areas are limited – the 

complete set of data is provided in Table C-4 of Appendix C. 

Table 5-1. Measured Maximum Lavery Till Radionuclide Concentrations(1) 

Nuclide 

WMA 1 Excavation Area WMA 2 Excavation Area 

Result (pCi/g) Depth (ft) Result (pCi/g)(3) Depth (ft) 

C-14 <3.6E-01(2) 24-26 none none 

Sr-90 5.9E+01(4) 38.5-39 8.5E-01 12-14 

Tc-99 <5.5E-01(2) 37-39 none none 

I-129 <2.3E-01(2) 38-40 none none 

Cs-137 7.9E+00(2) 38-40 4.5E-01 12-14 

U-232 4.1E-02(2) 24-26 1.2E-02 12-14 

U-233/234 1.9E+00(2) 38-40 1.8E-01 12-14 

U-235 1.4E-01(2)(5) 24-26 <5.9E-03 12-14 

Np-237 <3.6E-01(2) 38-40 none none 

U-238 1.4E+00(2) 41-43 1.1E-01 12-14 

Pu-238 <3.4E-01(2) 38-40 1.0E-02 12-14 

Pu-239/240 <3.1E-01(2) 38-40 <5.9E-03 12-14 

Pu-241 <3.4E+01(2) 38-40 <1.3E+00 12-14 

Am-241 <2.0E-01(2) 38-40 3.0E-02 12-14 

Cm-243/244 <2.2E-01(2) 38-40 none none 

NOTES: (1) See Table C-4 for the complete data set, which includes samples at nine locations entirely within the 

unweathered Lavery till within the WMA 1 excavation area. Based on boring log data, only one 

sample (BH-05) taken within the WMA 2 excavation area contained only unweathered Lavery till 

soil; the others contained some soil from the sand and gravel layer. 

 (2) Data are from the 2008 north plateau groundwater plume Geoprobe® investigation described in 

Section 4, with the highest non-detection values recorded (non-detection values, i.e., minimum 

detectable concentrations, varied widely among different samples). 

 (3) Data are from sample BH-05 collected during the 1993 RCRA facility investigation described in 

Section 4. 

(4) Data are from point GP3098 from the 1998 north plateau Geoprobe® sampling described in Section 

4. 

(5) U-235/U-236 result. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Rev 0 5-8 

The actual depth of the WMA 1 excavation would be based on removal of soil 

exceeding the subsurface soil cleanup goals, as explained in Section 7. The excavation 

would extend at least one foot into the Lavery till, as noted previously, and this is the point 

where the cleanup goals would apply. The configuration of the residual source would 

therefore be similar to the bottom of the excavation shown in the representative cross 

section in Figure 5-2. 

Figure 5-1 also shows the approximate location of the major excavation in WMA 2. As 

explained in Section 1 and detailed in Section 7, a single excavation would be made to 

remove Lagoons, 1, 2, and 3, the interceptors, the Neutralization Pit, and the Solvent Dike. 

The area of this excavation would be approximately 4.2 acres and its depth would vary 

from approximately 12 feet on the southwest end to approximately 26 feet on the northeast 

end.2

Figure 5-3 shows a conceptual cross section of the WMA 2 excavation. This figure also 

shows representative data on subsurface radioactivity. As indicated on the figure, Table 2-

18 provides an estimate of residual radioactivity in Lagoon 1 and Table 4-14 shows 

maximum radionuclide concentrations measured in sediment in Lagoon 2 and Lagoon 3. 

As indicated in order-of-magnitude estimates in Table 2-18, Cs-137 (at 510 curies) is 

expected to dominate the radioactivity in Lagoon 1. Other radionuclides expected to be 

present include Pu-241 (134 curies), Sr-90 (17 curies), and Pu-238 (6.4 curies). Table 4-14 

shows significant concentrations of Sr-90, Cs-137, Pu-238, Pu-239/240, and Am-241 in 

Lagoon 2 sediment and lower concentrations of these radionuclides in Lagoon 3 sediment. 

The actual depth of the WMA 2 excavation would be based on removal of soil 

exceeding the subsurface soil cleanup goals, as explained in Section 7. The excavation 

would extend at least one foot into the Lavery till or, in the cases of Lagoon 2 and Lagoon 

3, approximately two feet below the bottom the lagoons, which extend into the Lavery till. 

The configuration of the residual source would therefore be similar to the bottom of the 

excavation shown in the representative cross section in Figure 5-3. 

While the subsurface soil cleanup goals serve as the remediation criteria for the two 

excavations as specified in Section 7, actual residual contamination levels in the Lavery till 

are expected to be well below these criteria. The concentrations of Sr-90 and Cs-137 are 

expected to be of the same order of magnitude as the lower surface soil cleanup goals. 

 

2

 The 26-foot estimate is based on using the ground surface adjacent to Lagoon 3 as a reference point. The 

excavation is expected to extend several feet below the bottoms of Lagoons 2 and 3 to remove sediment 

with radioactivity concentrations above DCGLs. 

Additional Characterization Planned 

The characterization program to be undertaken early in Phase 1 of the 

decommissioning as described in Section 9 would provide additional data on 

radioactivity in subsurface soil in WMA 1 and WMA 2 and lagoon sediment in WMA 2. 

As noted in Section 4, additional characterization measurements being taken in 2008 

are expected to somewhat better define subsurface contamination in both areas. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Rev 0 5-37 

are Sr-90 (due to water independent plant uptake), I-129 (due to water dependent 

pathways), Cs-137 (external radiation dose), and most uranium radionuclides (water 

dependent pathways). 

The sensitivity analysis of the surface soil model, for these radionuclides, indicates the 

following: 

• A lower indoor exposure fraction results in the largest DCGL decrease for U-232 

and no change for I-129. Similarly, a higher indoor exposure fraction results in the 

largest increase for U-232 and no change for I-129 and U-234. However, it is 

unlikely that the indoor fraction is too low based on the local climate. The U-232 

doses are mainly due to external exposure, which accounts for the relative 

sensitivity to this parameter. 

• Decreasing the source thickness increased the DCGL for all radionuclides and 

increasing the source thickness resulted in the most significant DCGL decrease for 

U-235. The sensitivity to this parameter is due to increased/decreased dose from 

the water ingestion and plant pathways (both water dependent and independent). 

• Decreasing the unsaturated zone thickness resulted in an increased DCGL for U235 and a decrease for U-238. Similarly, increasing the unsaturated zone thickness 

decreased the U-235 DCGL and increased the U-238 DCGL. Sensitivity to this 

parameter is mainly due to increased/decreased travel time of contaminants to the 

saturated zone, resulting in water dependent doses occurring earlier/later with 

respect to doses from water independent pathways. 

• Reducing the irrigation/well pump rate increased the DCGL for I-129 most 

significantly. Similarly, increasing the pump rate decreased the DCGL for I-129. This 

is because reducing the pumping rate results in a lower dilution factor, and 

increasing the pumping rate results in more radionuclide inventory available for 

exposure. 

• The most significant effects of varying the Kd values were observed for Sr-90 and U234. 

• Decreasing the hydraulic conductivity significantly increased the DCGL for I-129 due 

to increasing the travel time to the well. Increasing the hydraulic conductivity 

significantly increased the DCGL for U-235 because dilution is greater. 

• Variations in the runoff/evapotranspiration coefficients had the greatest effect on U234 and the least impact on U-232. Radionuclides that are most sensitive to this 

parameter have doses mainly due to water dependent pathways. 

• Decreasing the well intake depth most significantly decreased the DCGL for I-129, 

while increasing this parameter results in significantly increased the DCGL for I-129, 

due to increased/decreased dilution in the well water. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Rev 1 5-38 

• Changes to the parameter for length of contamination parallel to the aquifer flow 

had the most significant effect on the U-235 DCGL, due to increased/decreased 

dilution in the aquifer. 

• Decreasing/increasing the plant transfer factors significantly increased/decreased 

the DCGL for Sr-90, as dose is mainly due to ingestion via plant uptake from soil. 

• Use of the mass balance groundwater model significantly decreases the DCGL for 

U-234 but had no effect on U-232. Radionuclides most sensitive to this parameter 

have doses mainly due to water dependent pathways. 

Table 5-10 summarizes the sensitivity analyses performed for the subsurface soil 

DCGLs, which are detailed in Appendix C. 

Table 5-10. Summary of Parameter Sensitivity Analyses – Subsurface Soil DCGLs(1)

Parameter 

(Base Case) Run Change Made 

Minimum DCGL Change Maximum DCGL Change 

Change Nuclide(s) Change Nuclide(s) 

Indoor/Outdoor 

Fraction (0.66/0.25) 

1 -32% -25% Cs-137 0.1% U-234 

2 21% -1% U-238 35% U-232 

Source Thickness 

(1m) 

3 -67% 10% U-238 193% Sr-90 

4 233% -66% Sr-90 -1% Cs-137 

Unsaturated Zone 

Thickness 

(2 m) 

5 -50% -1% U-238 0% Cs-137, Sr-90, 

U-232, U-235 

6 150% 0% Cs-137 Sr-90 U232 U-235 1% U-238 

Irrigation/Pump 

Rate (0.5 m/y/ 

5720 m3/y) 

7 -57% -36% I-129 0% Cs-137 

8 70% 0% Cs-137 159% U-238 

Soil/Water 

Distribution 

Coefficients (Kd) 

(Table C-2) 

9 lower -85% U-238 9% U-232 

10 higher -27% U-232 3144% U-234 

Hydraulic 

Conductivity 

(1400 m/y) 

11 -99% -1% U-238 3% I-129 

12 150% 0% Cs-137 I-129 Sr-90 

U-232 U-233 U-234 

U-235 U-238 

0% Cs-137, I-129, 

Sr-90, U-232, 

U-233, U-234, 

U-235, U-238 

Runoff/Evapotransporation Coefficient 

(0.6/0.55) 

13 -69% -38% U-234 16% U-232 

14 64% -19% U-232 188% U-234 
WVDP PHASE 1 DECOMMISSIONING PLAN

Rev 1 5-39 

Table 5-10. Summary of Parameter Sensitivity Analyses – Subsurface Soil DCGLs(1)

Parameter 

(Base Case) Run Change Made 

Minimum DCGL Change Maximum DCGL Change 

Change Nuclide(s) Change Nuclide(s) 

Plant Transfer 

Factors 

(RESRAD defaults) 

15 -90% -0.4% U-238 574% Sr-90 

16 900% -89% Sr-90 -1% U-234 

Contaminated Layer 

Area 

(100 m2) 

- Various 

smaller 

areas 

- - - See note (1). 

NOTES: (1) Information from the DCGLEMC calculations was used for evaluation of the sensitivity of the 

contaminated layer area. DCGLs generally increased with smaller areas. Results presented here are 

for radionuclides considered likely to contribute significantly to the overall subsurface soil dose based 

on available characterization data. 

Discussion of Subsurface Soil Results 

The uncertainty results for the subsurface soil source models have been evaluated 

considering those radionuclides that are the primary dose drivers, i.e., those that are likely 

to contribute significantly to predicted dose based on available characterization data (see 

Table 5-1). The radionuclides are Sr-90 (due to water independent plant uptake), I-129 

(due to water dependent pathways), Cs-137 (external radiation dose), and uranium 

radionuclides (water dependent pathways). 

The sensitivity analysis of the subsurface soil model for these radionuclides indicates 

the following: 

• A lower indoor exposure fraction results in a DCGL decrease for Cs-137 and no 

change for U-234. A higher indoor exposure results in a significant increased 

DCGL for U-232. However, it is unlikely that the indoor fraction is too low based on 

the local climate. Doses for these isotopes are mainly due to external exposure, 

which accounts for the relative sensitivity to this parameter. 

• The source thickness parameter sensitivity was most significant for Sr-90 The 

sensitivity to this parameter is due to increased/decreased dose from the water 

ingestion and plant pathways (both water dependent and independent). 

• Decreasing or increasing the unsaturated zone thickness resulted in little change to 

the DCGLs. 

• The I-129 and U-238 DCGLs were sensitive to changes in the irrigation/well pump 

rate but the Cs-137 DCGL was not. This effect is because reducing the pumping 

rate results in a lower dilution factor, and increasing the pumping rate results in 

more dilution for water dependent pathways. 

• The most significant effects of varying the Kd values were observed for U-232, U234, and U-238. 

• Decreasing or increasing the hydraulic conductivity resulted in no change to the 

DCGLs due to use of the mass balance model. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Rev 1 5-40 

• The U-232 and U-234 DCGLs are sensitive to changes in the runoff/ 

evapotranspiration coefficient. Radionuclides that are most sensitive to this 

parameter have doses mainly due to water dependent pathways. 

• The plant transfer factor is most sensitive for Sr-90, as the dose is mainly due to 

ingestion via plant uptake. 

Table 5-11 summarizes the sensitivity analyses performed for the streambed sediment 

DCGLs, which are detailed in Appendix C: 

Table 5-11. Summary of Parameter Sensitivity Analyses – Streambed Sediment 

DCGLs(1)

Parameter 

(Base Case) Run Change Made 

Minimum DCGL Change Maximum DCGL Change 

Change Nuclide(s) Change Nuclide(s) 

Indoor/Outdoor 

Fraction 

(0.00/0.012) 

1 -50% 3% Sr-90 86% Cs-137 

2 100% -48% Cs-137 -5% Sr-90 

Source Thickness 

(1 m) 

3 -50% 1% Cs-137 29% Sr-90 

4 200% -0.2% Sr-90 0% Cs-137 

Unsaturated Zone 

Thickness 

(0.0 m) 

5 0 m to 1m 0.3% Cs-137 8% Sr-90 

6 0 m to 3 m 0.3% Cs-137 8% Sr-90 

Soil/Water 

Distribution 

Coefficients (Kd) 

(Table C-2) 

7 lower 0.5% Cs-137 12% Sr-90 

8 higher 0.3% Cs-137 7% Sr-90 

Runoff/Evapotransporation Coefficient 

(0.6/0.55) 

9 -54% 0% Cs-137 0.4% Sr-90 

10 78% -0.3% Sr-90 0% Cs-137 

Plant Transfer 

Factors 

(RESRAD defaults) 

11 -90% 1% Cs-137 82% Sr-90 

12 900% -82% Sr-90 -9% Cs-137 

Fish Transfer 

Factors 

(RESRAD defaults) 

13 -90% 0.3% Cs-137 7% Sr-90 

14 900% -39% Sr-90 -3% Cs-137 

Contaminated Layer 

Area 

(1000 m2) 

- Various 

smaller 

areas 

- - - See note (1). 

NOTES: (1) Information from the DCGLEMC calculations was used for evaluation of the sensitivity of the 

contaminated layer area. DCGLs generally increased with smaller areas. Results presented here are 

for radionuclides considered likely to contribute significantly to the overall sediment dose based on 

available characterization data. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Rev 1 5-51 

radioactivity concentration in the Lavery till for each radionuclide as summarized in Table 5-

1, and the results of modeling to develop DCGLs for 25 mrem per year as shown in Table 

5-8. The results were as follow: 

WMA 1, a maximum of 1.3 mrem a year 

WMA 2, a maximum of 0.04 mrem a year 

Given the limited data available, these results must be viewed as order-of-magnitude 

estimates. However, they do suggest that actual potential doses from the two remediated 

areas are likely to be substantially below 25 mrem per year. 

 

5.4.5 Final Dose Assessment 

As noted previously, DOE would perform a dose assessment for the residual 

radioactivity in the WMA 1 and WMA 2 excavated areas using Phase 1 final status survey 

data. This assessment would use the same methodology used in development of the 

subsurface soil DCGLs to estimate the potential radiation dose using the actual measured 

residual radioactivity concentrations. The results of the dose assessment would be made 

available to NRC and other stakeholders. Note that a more-comprehensive dose 

assessment that also takes into account the Phase 2 sources may be performed in 

connection with Phase 2 of the proposed decommissioning, depending on the approach 

selected for that phase. 

5.5 References 

Code of Federal Regulations 

10 CFR 20, Subpart E, Radiological Criteria For License Termination (LTR). 

10 CFR 20.1003, Definitions. 

DOE Orders 

DOE Order 450.1, Environmental Protection Program, including Changes 1 and 2. U.S, 

Department of Energy, Washington, D.C. January 15, 2003. 

DOE Order 5400.5, Radiation Protection of the Public and the Environment, Change 2. 

U.S, Department of Energy, Washington, D.C., January 7, 1993. 

NOTE 

The use of maximum rather than average values in these dose estimates adds 

conservatism, as does including values that are simply the highest minimum detectable 

concentrations, especially in the case of Np-237. (There was a wide range of several 

orders of magnitude among the minimum detectable concentrations reported for the 

2008 sample data.) As with the DCGLs, decay of Sr-90 and Cs-137 over 30 years is 

accounted for in the estimate. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Rev 1 5-52 

DOE Technical Standards 

DOE Standard 1153-2002, A Graded Approach for Evaluating Radiation Doses to Aquatic 

and Terrestrial Biota. U.S, Department of Energy, Washington, D.C., July 2002. 

Other References 

Beyeler, et al. 1999, Residual Radioactivity from Decommissioning, Parameter Analysis, 

NUREG/CR-5512, Vol 3, Draft Report for Comment. Beyeler, W. E., W. A. 

Hareland, F. A. Duran, T. J. Brown, E. Kalinina, D. P. Gallegos, and P. A. Davis, 

Sandia National Laboratories, Albuquerque, New Mexico, October 1999. 

Dames and Moore 1994, North Plateau Groundwater Seepage Survey, Letter Report 

D&M:SPV:PJG:11B:0249. Dames and Moore, West Valley New York, August 15, 

1994. 

DOE 2004, Users Guide, RESRAD-BIOTA: A Tool for Implementing a Graded Approach to 

Biota Dose Evaluation, Version 1, DOE/EH0676. Environmental Assessment 

Division, Argonne National Laboratory, Argonne, Illinois, January 2004. 

EPA 1997, Exposure Factors Handbook. National Center for Environmental Assessment, 

Office of Research and Development, U. S. Environmental Protection Agency, 

Washington, D.C., 1997. 

Hemann and Steiner 1999, 1998 Geoprobe Investigation of the Core Area of the North 

Plateau Groundwater Plume, WVDP-346, Revision 0. Hemann, M.R. and R.E. 

Steiner II, West Valley Nuclear Services Company, June 11, 1999. 

NRC 1977, Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor 

Releases for the Purpose of Implementing Appendix I, Regulatory Guide 1.113, 

Rev. 1. U.S. Nuclear Regulatory Commission, Office of Standards Development, 

Washington, D.C., April 1977. 

NRC 1997, Generic Environmental Impact Statement in Support of Rulemaking on 

Radiological Criteria for License Termination of NRC-Licensed Nuclear Facilities; 

Final Policy Statement. NUREG-1496, Vol. 1. U.S. Nuclear Regulatory Commission, 

Office of Regulatory Research, Division of Regulatory Applications, Washington, 

D.C., July 1997. 

NRC 2000, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM), 

NUREG-1575, Revision 1. NRC, Washington, DC, August, 2000. (Also EPA 4-2-R97-016, Revision 1, U.S. Environmental Protection Agency and DOE-EH-0624, 

Revision 1, DOE) 

NRC 2006, Consolidated NMSS Decommissioning Guidance: Characterization, Survey, 

and Determination of Radiological Criteria, Final Report, NUREG 1757 Volume 2, 

Revision 1. NRC, Office of Nuclear Material Safety and Safeguards, Washington, 

DC, September, 2006. 

Willgoose 2000, User Manual for SIBERIA (Version 8.10), University of Newcastle, New 

South Wales, Australia, July 2000. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Rev 1 5-53 

WVES and URS 2008, West Valley Demonstration Project Annual Site Environmental 

Report, Calendar Year 2006. West Valley Environmental Services and URS 

Group, Inc., West Valley, New York, December 2008. 

WVNSCO 1993a. Environmental Information Document Volume III Hydrology Part 4 

Groundwater Hydrology and Geochemistry, WVDP-EIS-009, Revision 0. West 

Valley Nuclear Services Company, West Valley, New York, February 19, 1993. 

WVNSCO 1993b, Environmental Information Document Volume I, Geology, WVDP-EIS004, Revision 0. West Valley Nuclear Services Company, West Valley, New York, 

April 1, 1993. 

WVNSCO 1994, Environmental Information Document, Volume IV: Soils Characterization, 

WVDP-EIS-008, Revision 0. West Valley Nuclear Services Company, West Valley, 

New York, September 15, 1994. 

WVNSCO and D&M 1997, Resource Conservation and Recovery Act Facility Investigation 

Report, Volume 4: Low-level Waste Treatment Facility, West Valley Demonstration 

Project, West Valley, New York, WVDP-RFI-021, Revision 0. West Valley Nuclear 

Services Company, West Valley, New York and Dames and Moore, Orchard Park, 

New York, January 17, 1997. 

Yager 1987, Simulation of Groundwater Flow Near the Nuclear Reprocessing Facility at the 

Western New York Nuclear Service Center, Cattaraugus County, New York, 

Geological Survey Water Resources Investigations Report 85-4308. Yager, R.M, 

U.S. Geological Survey, U.S. Department of Interior, Washington, D.C., 1987. 

Yu, et al. 1993, Data Collection Handbook to Support Modeling the Impacts of Radioactive 

Material in Soil, ANL/EAIS-8. Yu, C., et al., Environmental and Information 

Sciences Division, Argonne National Laboratory, Argonne, Illinois, April 1993. 

Yu, et al. 2000, Development of Probabilistic RESRAD 6.0 and RESRAD-BUILD 3.0 

Computer Codes, NUREG/CR-6697, ANL/EAD/TM-98. Yu, C., et al., 

Environmental Assessment Division, Argonne National Laboratory, Argonne, 

Illinois, November 2000. 

Yu, et al. 2001, User’s Manual for RESRAD Version 6, ANL/EAD-4. Yu, C., et al., 

Environmental Assessment Division, Argonne National Laboratory, Argonne, 

Illinois, July 2001. 
This page is intentionally blank. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 0 7-29 

Neutralization Pit 

The Neutralization Pit would be removed using a process similar to the following: 

Removing any residual water, treating it for disposal via an SPDES-permitted outfall or 

solidifying it for disposal as LLW; and 

Removing the liner, concrete walls, and floor of the pit. 

The underground wastewater lines in the area of the Neutralization Pit would be removed in 

connection with digging the WMA 2 excavation described in Section 7.4.3. Phase 1 final status 

surveys, independent confirmatory surveys, and filling the excavation are also addressed in Section 

7.4.3. 

Old Interceptor 

The Old Interceptor would be demolished using a process similar to that used for the 

Neutralization Pit, with additional radiological controls appropriate to the larger amount of residual 

radioactivity it contains. 

New Interceptors 

The New Interceptors would be demolished using a process similar to that used for the 

Neutralization Pit. 

Concrete Floor Slabs and Foundations 

The concrete floor slabs of the O2 Building, Test and Storage Building, Vitrification Test Facility, 

Maintenance Shop, Maintenance Storage Area, and the Vehicle Maintenance Shop would be 

removed and the building footprints excavated approximately two feet below grade. Phase 1 final 

status surveys would be performed in the excavated areas, and arrangements made for an 

independent verification survey if desired by the regulators. After the surveys have been completed, 

the excavations would be filled with earth. 

7.4.3 Decommissioning the Lagoons 

Decommissioning of Lagoons 1, 2, and 3 would involve constructing a vertical hydraulic barrier 

on the northwest side of the lagoons and digging a single large excavation. Lagoons 4 and 5 would 

be removed separately. Figure 7-10 shows the conceptual plan view of the large excavation and 

the location of the hydraulic barrier wall. Figure 7-11 shows the conceptual cross section. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 7-30 

 

 Figure 7-10. Conceptual Arrangement of WMA 2 Excavation, Plan View 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 7-31 

Figure 7-11. Conceptual Arrangement of WMA 2 Excavation, Cross Section 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 0 7-32 

Hydraulic Barrier Wall Installation 

To isolate the area of WMA 2 to be excavated from the north plateau groundwater plume, a 

vertical hydraulic barrier wall would be installed as shown in Figure 7-10. This hydraulic barrier 

would consist of a soil-cement-bentonite barrier wall that would extend approximately two feet into 

the Lavery till. It would remain in place after the excavation is backfilled. 

Before the hydraulic barrier wall is installed, underground lines in its footprint that carried 

radioactive liquid would be located. Sections of these lines in the area where the wall would be 

constructed would be removed in a controlled manner to avoid unnecessary release of 

contamination. During this process, characterization measurements would be taken in the end of 

each line that would remain in place and the line capped. 

The total length of the barrier wall would be approximate 1100 feet. It would be sufficiently wide 

to provide the stability necessary to permit excavation up to the base of the wall. This barrier wall 

would connect with the WMA 1 hydraulic barrier wall as shown in Figure 7-10. It would be 

constructed in the same manner as the WMA 1 slurry wall and have an in-place maximum 

saturated hydraulic conductivity of approximately 6E-06 cm/s. It would extend to within about three 

feet of grade and be topped with excavated material. Sheet piles on the southeastern side of the 

excavation are not expected to be necessary to control groundwater, except possibly in the Lagoon 

1 area as indicated below. 

Preparations for Removal of Contaminated Lagoon Sediment and Soil 

Detailed planning for the excavation would take into account available information on 

radioactivity in the lagoon sediment, soil, and groundwater as summarized in Section 4, along with 

the results of the soil characterization program. The depth of the water table in the area – typically 

about seven feet below the surface – would also be taken into account. 

Preparations, in addition to installation of the hydraulic barrier wall, would include provisions for 

appropriate radiological controls to minimize airborne radioactivity releases during the excavation 

work, such as a single-span confinement structure for the Lagoon 1 area. 

Removal of Contaminated Soil and Underground Wastewater Lines 

Removal of Lagoons 1, 2, and 3 and the facilities within the area to be excavated as described 

below would be coordinated with removal of soil in other parts of the excavation. Before excavation 

begins, the hydraulic barrier wall would be installed. The excavation process would be 

accomplished in two phases using conventional excavation equipment. 

The first phase would involve removal of soil in the vadose zone. It is expected that 

approximately one-half of the total amount of soil to be removed would be unsaturated. 

The second phase would involve removal of soil in the saturated zone. Wastewater piping 

within the excavated area would be removed. Groundwater accumulating in the excavation would 

be pumped out, treated using a portable treatment system containing ion exchangers and filters, 

and discharged to Erdman Brook through an SPDES-permitted outfall. 

Figure 7-11 shows the planned depth of excavation. The excavation would extend at least one 

foot into the Lavery till and one foot below the sediment in the bottoms of Lagoons 2 and 3 as 

indicated in the figure, with the amount of additional soil removal determined by the use of cleanup 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 0 7-49 

Activity Years from Beginning of Phase 1 Proposed Decommissioning Work 

1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16  31 

1. Complete detailed planning and preparations 

2. Characterize surface soil and sediment 

3. Modify EDR and Load-In/Load-Out Facility 

4. Construct new Canister Interim Storage Facility 

5. Relocate HLW canisters to new facility 

6. Store HLW Canisters in new Interim Storage Facility 

7. Remove WMA 1 facilities to grade 

8. Install WMA 1 hydraulic barrier 

9. Remove WMA 1 underground structures, equip. 

10. Remove source area of north plateau plume 

11. Perform WMA 1 final status surveys, fill excavation 

12. Remove WMA 2 lagoons, other facilities 

13. Perform WMA 2 final surveys, fill excavations 

14. Remove WMA 3 Equipment Shelter 

15. Remove HLW pumps, HLW transfer trench piping 

16. Remove LSA 4 and RHWF in WMA 5 

17. Remove WMA 6 facilities 

18. Remove slabs and gravel pads in WMA 7 

19. Remove Drum Cell in WMA 9 

20. Remove New Warehouse, floor slabs in WMA 10 

21. Perform studies to inform Phase 2 decisions 

Figure 7-15. Conceptual Schedule of Phase 1 Proposed Decommissioning Activities

There is considerable flexibility in the 

sequence for activities 14 through 20. 

One potential sequence is shown. 

LEGEND: EDR = Equipment Decontamination Room 

LSA = Lag Storage Addition 

RHWF = Remote-Handled Waste Facility 

Some studies may take longer. 

The lagoons may remain in service longer 

to allow processing of WMA 1 wastewater. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 7-50 

7.13 References 

Code of Federal Regulations 

40 CFR 61, National Emission Standards for Hazardous Air Pollutants 

DOE Manuals 

DOE Manual 435.1-1, Revision 1, Radioactive Waste Management Manual 

Other References 

EPA, 2007, Clean Air Act Assessment Package, CAP88-PC, Version 3.0. U.S. 

Environmental Protection Agency, Office of Radiation and Indoor Air, Washington, 

D.C., December 9, 2007. 

Hemann and Steiner 1999, 1998 Geoprobe Investigation of the Core Area of the North 

Plateau Groundwater Plume, WVDP-346, Revision 0. Hemann, M.R. and R.E. 

Steiner, III, West Valley Nuclear Services Company, June 11, 1999. 

ISCORS 2005, ISCORS Assessment of Radioactivity in Sewage Sludge: Modeling to 

Assess Radiation Doses, Technical Report 2004-03 (NUREG-1783). Interagency 

Steering Committee on Radiation Standards, Sewage Sludge Subcommittee, 

Washington, D.C., February 2005. 

NRC 1997, Standard Review Plan for Dry Cask Storage Systems NUREG-1536, Final 

Report. U.S. Nuclear Regulatory Commission, Washington, D.C., January 1997. 

NRC 2000, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM),

NUREG-1575, Revision 1. NRC, Washington, DC, August, 2000. (Also EPA 4-2-R97-016, Revision 1, U.S. Environmental Protection Agency and DOE-EH-0624, 

Revision 1, DOE) 

WVNSCO 1994, Environmental Information Document, Volume IV: Soils Characterization,

WVDP-EIS-008, Revision 0. West Valley Nuclear Services Company, West Valley, 

New York, September 15, 1994. 

WVNSCO 2006, Safety Analysis Report for Waste Processing and Support Activities,

WVNS-SAR-001, Revision 11. West Valley Nuclear Services Company, West 

Valley, New York, November 11, 2006. 

WVNSCO and Scientech, 2000, High-Level Waste Canister Shipout from the West Valley 

Demonstration Project, Revision 2. West Valley Nuclear Services Company, West 

Valley, New York and Scientech, Dunedin, Florida, June 30, 2000. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Rev 1 9-3 

Table 9-1 Surface Soil Cleanup Goal Area Factors(1)

Nuclide 

DCGLW

10,000 m2

(pCi/g)

Area Factors (DCGLEMC/DCGLW)

5,000 m2 1,000 m2 500 m2 100 m2 50 m2 10 m2 5 m2 1 m2

Am-241 4.9E+01 1.0E+00 1.0E+00 1.9E+00 7.2E+00 1.1E+01 2.6E+01 3.8E+01 8.1E+01 

C-14 3.1E+01 1.7E+00 4.3E+00 1.2E+01 1.2E+02 3.2E+02 2.9E+03 7.0E+03 4.8E+04

Cm-243 4.2E+01 1.0E+00 1.0E+00 1.4E+00 2.3E+00 2.6E+00 4.2E+00 6.3E+00 1.8E+01 

Cm-244 9.4E+01 1.0E+00 1.0E+00 2.0E+00 9.2E+00 1.7E+01 5.4E+01 7.8E+01 1.3E+02

Cs-137 2.7E+01 1.1E+00 1.1E+00 1.2E+00 1.5E+00 1.6E+00 2.5E+00 3.8E+00 1.1E+01 

I-129 5.8E-01 1.5E+00 3.4E+00 6.1E+00 3.2E+01 6.5E+01 3.2E+02 6.5E+02 3.2E+03

Np-237 9.6E-02 1.3E+00 2.7E+00 4.7E+00 2.4E+01 4.8E+01 2.3E+02 4.6E+02 2.2E+03 

Pu-238 5.8E+01 1.0E+00 1.0E+00 2.0E+00 9.3E+00 1.7E+01 5.5E+01 7.9E+01 1.3E+02

Pu-239 5.2E+01 1.0E+00 1.0E+00 2.0E+00 9.3E+00 1.7E+01 5.5E+01 7.9E+01 1.3E+02 

Pu-240 5.2E+01 1.0E+00 1.0E+00 2.0E+00 9.3E+00 1.7E+01 5.5E+01 7.9E+01 1.3E+02

Pu-241 1.6E+03 1.0E+00 1.0E+00 1.9E+00 7.3E+00 1.2E+01 2.6E+01 3.8E+01 8.2E+01

Sr-90 8.7E+00 1.1E+00 1.1E+00 2.2E+00 1.1E+01 2.2E+01 1.0E+02 2.0E+02 9.2E+02

Tc-99 2.9E+01 1.3E+00 1.7E+00 3.4E+00 1.7E+01 3.4E+01 1.7E+02 3.4E+02 1.7E+03 

U-232 5.6E+00 1.0E+00 1.1E+00 1.1E+00 1.3E+00 1.5E+00 2.3E+00 3.5E+00 1.1E+01

U-233 2.0E+01 1.3E+00 2.6E+00 4.6E+00 2.1E+01 3.9E+01 1.3E+02 2.2E+02 7.1E+02 

U-234 2.1E+01 1.3E+00 2.6E+00 4.7E+00 2.4E+01 4.7E+01 2.2E+02 4.2E+02 1.1E+03

U-235 1.4E+01 1.4E+00 2.9E+00 4.8E+00 5.7E+00 6.3E+00 9.8E+00 1.5E+01 4.3E+01 

U-238 2.2E+01 1.3E+00 2.6E+00 4.5E+00 1.7E+01 2.0E+01 3.2E+01 4.8E+01 1.4E+02

 NOTE: (1) From Table C-16 of Appendix C. The values in the second column are the cleanup goals (CGW) from Table 5-14.

Table 9-2. Subsurface Soil Cleanup Goal Area Factors(1)

Nuclide DCGLW 

100 m2 (pCi/g)

Area Factors (DCGLEMC/DCGLW)

50 m2 10 m2 5 m2 1 m2

Am-241 2.9E+03 1.4E+00 2.5E+00 3.6E+00 7.1E+00 

C-14 1.9E+05 2.6E+00 2.3E+01 5.5E+01 3.4E+02 

Cm-243 5.1E+02 1.1E+00 1.8E+00 2.7E+00 7.9E+00 

Cm-244 8.8E+03 1.7E+00 4.1E+00 5.2E+00 7.5E+00 

Cs-137 2.0E+02 1.1E+00 1.8E+00 2.7E+00 8.5E+00 

I-129 1.9E+02 2.0E+00 1.0E+01 2.0E+01 1.0E+02 

Np-237 1.7E+01 2.0E+00 1.0E+01 2.0E+01 1.0E+02 

Pu-238 5.5E+03 1.7E+00 4.1E+00 5.3E+00 7.5E+00 

Pu-239 5.0E+03 1.7E+00 4.2E+00 5.3E+00 7.6E+00 

Pu-240 5.0E+03 1.7E+00 4.2E+00 5.3E+00 7.6E+00 

Pu-241 9.8E+04 1.4E+00 2.6E+00 3.6E+00 7.1E+00 
WVDP PHASE 1 DECOMMISSIONING PLAN

Rev 1 9-4 

Table 9-2. Subsurface Soil Cleanup Goal Area Factors(1)

Nuclide DCGLW 

100 m2 (pCi/g)

Area Factors (DCGLEMC/DCGLW)

50 m2 10 m2 5 m2 1 m2

Sr-90 1.4E+03 1.9E+00 8.1E+00 1.5E+01 6.5E+01 

Tc-99 5.0E+03 2.0E+00 9.9E+00 2.0E+01 9.8E+01 

U-232 5.3E+01 1.1E+00 1.9E+00 2.8E+00 8.8E+00 

U-233 7.5E+02 2.0E+00 1.0E+01 2.0E+01 9.6E+01 

U-234 7.7E+02 2.0E+00 1.0E+01 2.0E+01 1.0E+02 

U-235 4.3E+02 1.1E+00 1.7E+00 2.6E+00 7.8E+00 

U-238 8.2E+02 2.0E+00 4.7E+00 7.0E+00 2.0E+01 

NOTE: (1) From Table C-47 of Appendix C. The values in the second column are the cleanup goals (CGW) from Table 5-14.

Table 9-3. Streambed Sediment Cleanup Goal Area Factors(1)

Nuclide

DCGLW

1,000 m2

(pCi/g)

Area Factors (DCGLEMC/DCGLW)

500 m2 100 m2 50 m2 10 m2 5 m2 1 m2

Am-241 1.6E+03 1.5E+00 2.9E+00 3.5E+00 5.7E+00 8.5E+00 2.4E+01 

C-14 3.4E+02 2.5E+00 2.0E+01 4.5E+01 2.8E+02 6.1E+02 3.3E+03 

Cm-243 3.6E+02 1.1E+00 1.2E+00 1.3E+00 2.0E+00 3.1E+00 9.1E+00 

Cm-244 4.7E+03 2.0E+00 9.8E+00 1.9E+01 8.5E+01 1.6E+02 6.8E+02 

Cs-137 1.3E+02 1.1E+00 1.2E+00 1.3E+00 2.1E+00 3.1E+00 9.4E+00 

I-129 3.7E+02 2.0E+00 8.6E+00 1.5E+01 4.6E+01 7.7E+01 2.5E+02 

Np-237 5.4E+01 1.6E+00 3.3E+00 4.1E+00 7.1E+00 1.1E+01 3.2E+01 

Pu-238 2.0E+03 2.0E+00 9.9E+00 2.0E+01 9.2E+01 1.8E+02 8.1E+02 

Pu-239 1.8E+03 2.0E+00 9.8E+00 1.9E+01 8.9E+01 1.7E+02 7.7E+02 

Pu-240 1.8E+03 2.0E+00 9.9E+00 2.0E+01 9.3E+01 1.8E+02 8.4E+02 

Pu-241 5.2E+04 1.6E+00 3.0E+00 3.6E+00 5.8E+00 8.7E+00 2.4E+01 

Sr-90 9.5E+02 1.9E+00 7.2E+00 1.1E+01 2.9E+01 4.6E+01 1.5E+02 

Tc-99 2.2E+05 1.8E+00 5.1E+00 7.0E+00 1.4E+01 2.1E+01 6.3E+01 

U-232 2.7E+01 1.0E+00 1.2E+00 1.3E+00 2.0E+00 3.0E+00 9.5E+00 

U-233 5.8E+03 1.9E+00 3.7E+00 4.0E+00 6.2E+00 9.3E+00 2.8E+01 

U-234 6.1E+03 2.0E+00 9.2E+00 1.7E+01 5.2E+01 7.9E+01 2.4E+02 

U-235 2.9E+02 1.0E+00 1.2E+00 1.3E+00 1.9E+00 2.9E+00 8.6E+00 

U-238 1.3E+03 1.1E+00 1.4E+00 1.5E+00 2.3E+00 3.5E+00 1.1E+01 

NOTE: (1) From Table C-75 of Appendix C. The values in the second column are the cleanup goals (CGW) from Table 5-14.
WVDP PHASE 1 DECOMMISSIONING PLAN

Rev 0 9-5 

A surrogate radionuclide is a radionuclide in a mixture of radionuclides whose 

concentration is more easily measured and can be used to infer the concentrations of the 

other radionuclides in the mixture. If actual radioactive contamination levels are below the 

specified concentrations of the surrogate radionuclide, then the sum of doses from all 

radionuclides in the mixture would fall below the dose limit of 25 mrem/y. Tables in Section 5 

do not presently show DCGLW values for a surrogate radionuclide because available data on 

radionuclide distributions in soil and sediment are not sufficient to support this, but Section 5 

may be revised after additional characterization data become available to provide such 

information. 

 

9.2 Types of Surveys and Their Purposes 

Seven types of radiological surveys are associated with the WVDP Phase 1 proposed 

decommissioning project: (1) background surveys, (2) scoping surveys, (3) end-of-task 

surveys taken at the conclusion of deactivation activities, (4) characterization surveys, (5) inprocess or remedial action support surveys, (6) Phase 1 final status surveys, and (7) 

confirmatory surveys. The nature of these surveys and, in some cases, the basic 

requirements are summarized here; more detail is provided further below on background 

surveys (9.3), characterization surveys (9.4), in-process surveys (9.5), and Phase 1 final 

status surveys (9.6). 

9.2.1 Background Surveys 

Background surveys are performed in non-impacted areas around the facility and in nonimpacted buildings of construction similar to those impacted buildings of interest. Background 

surveys establish the baseline levels of radiation and radioactivity from radionuclides 

occurring in the environment or incorporated into the structural materials. Requirements for 

background surveys are summarized in Section 9.3 below. 

9.2.2 Scoping Surveys 

Scoping surveys are conducted (1) to provide preliminary data to supplement historical 

site assessment information needed to guide planning of characterization surveys, (2) to 

identify radionuclide contaminants, (3) to identify relative radionuclide ratios, and (4) to 

identify the general levels and extent of contaminants. As noted in Section 4, much of the 

existing radiological data associated with the WVDP proposed decommissioning project falls 

into the category of scoping survey data, although these data were generally not acquired as 

scoping survey data but were acquired for other operational needs. Additional scoping 

surveys are not planned for Phase 1 of the WVDP proposed decommissioning.

As characterization and in-process surveys are performed, additional data would become 

available that could necessitate re-evaluation of the DCGLs, if, for example, assumptions 

used in development of the DCGLs were found to be incorrect based on the additional 

data. If such a situation develops, revised DCGLs would be calculated and this plan 

changed to incorporate the revised DCGLs and any related changes. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Rev 1 9-6 

9.2.3 End-of-Task Surveys 

As explained in Section 1, additional deactivation work will be completed in certain areas 

of the Process Building during deactivation work to be accomplished before the Phase 1 

proposed decommissioning activities begin, and numerous ancillary project facilities will be 

removed during this period. After each area is deactivated and after each facility is removed, 

end-of-task or “final radiological characterization” surveys will be performed to define the 

resulting radiological conditions. 

Such surveys are not within the scope of this plan since they will be completed before 

proposed decommissioning activities begin. However, their results will be considered in 

connection with defining characterization surveys and Phase 1 final status surveys to be 

performed during the proposed decommissioning. 

9.2.4 Characterization Surveys 

Characterization surveys include facility and site sampling, monitoring, and analysis 

activities to determine the extent and nature of residual contamination. They provide the 

basis for planning decommissioning actions, and providing technical information to develop, 

evaluate, and select appropriate remediation techniques. They also provide information for 

radiation protection purposes and for characterizing waste. 

Four WVDP characterization survey programs have been completed: (1) the 

characterization program for the underground waste tanks, (2) the Facility Characterization 

Project, (3) a series of Resource Conservation and Recovery Act (RCRA) facility 

investigations performed in the 1990s, and (4) investigations of the north plateau 

groundwater plume using a Geoprobe®

.

1

 Additionally, routine groundwater and other 

environmental media sampling and analysis are performed as required by DOE Orders for 

annual monitoring programs. The results of these programs are summarized in Section 4. 

The approaches used are outlined in Section 9.7 below. 

 As indicated in Section 4 and Section 7, additional characterization would be performed 

in connection with proposed decommissioning fieldwork. The requirements for this 

characterization are addressed in Section 9.4. 

9.2.5 In-Process Surveys 

In-process surveys, also referred to as remedial action support surveys, include facility 

and site sampling, monitoring, and analysis activities performed in support of 

decontamination work. They provide information necessary for radiation protection, for 

guiding cleanup work, for determining when field decontamination goals have been attained, 

and to indicate when areas are ready for Phase 1 final status surveys. Requirements for inprocess surveys are discussed in Section 9.5 below. 

1 As indicated in Section 4, additional characterization of subsurface soil in the area of the north plateau 

groundwater plume was accomplished in 2008. The results of this program are summarized in Section 4. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 0 A-11 

CONTENT SECTION PAGE 

The maximum and average radiation levels in mrem/hr in each room or 

work area

NA NA 

A scale drawing or map of the rooms or work areas showing the locations 

of radionuclide material contamination

NA NA 

IV.b. CONTAMINATED SYSTEMS AND EQUIPMENT

A list or description and the location of all systems or equipment at the 

facility that contain residual radioactive material in excess of site 

background levels

NA NA 

A summary of the radionuclides present in each system or on the 

equipment at each location, the maximum and average radionuclide 

activities in dpm/100cm2, and, if multiple radionuclides are present, the 

radionuclide ratios

NA NA 

The maximum and average radiation levels in mrem/hr at the surface of 

each piece of equipment

NA NA 

A summary of the background levels used during scoping or 

characterization surveys

NA NA 

A scale drawing or map of the rooms or work areas showing the locations 

of the contaminated systems or equipment

NA NA 

IV.c. SURFACE SOIL CONTAMINATION 

Information provided focuses on the project premises using existing data, which are not available 

for all locations on the project premises. Contamination in stream sediment is also addressed. 

 A list or description of all locations at the facility where surface soil 

contains residual radioactive material in excess of site background 

levels 

4.2.3 

Figure 4-6 

4-29 

4-31 

 A summary of the background levels used during scoping or 

characterization surveys

4.2.2 

Table 4-11 

Figure B-1 

Table B-1 

4-25

4-26

B-3

B-4

 A summary of the radionuclides present at each location, the maximum 

and average radionuclide activities in pCi/gm, and, if multiple 

radionuclides are present, the radionuclide ratios

4.2.3 

4.2.5 

4-29

4-35 

 The maximum and average radiation levels in mrem/hr at each location 

[Data are not available at sample locations.] 

4.2.6 4-48 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 A-12 

CONTENT SECTION PAGE 

 A scale drawing or map of the site showing the locations of 

radionuclide material contamination in surface soil 

Figure 4-6 4-31 

IV.d. SUBSURFACE SOIL CONTAMINATION 

Information provided focuses on the project premises using existing data, which are not available 

for all locations on the project premises.

 A list or description of all locations at the facility where subsurface soil 

contains residual radioactive material in excess of site background 

levels

4.2.4 

Figure 4-7 

Figure 4-8 

4-30

4-32

4-34 

 A summary of the background levels used during scoping or 

characterization surveys 

4.2.2 4-25 

 A summary of the radionuclides present at each location, the maximum 

and average radionuclide activities in pCi/gm, and, if multiple 

radionuclides are present, the radionuclide ratios 

4.2.4 

4.2.5 

4-30

4-35 

 The depth of the subsurface soil contamination at each location Figure 4-8 

4.2.5 

4-34

4-35 

 A scale drawing or map of the site showing the locations of subsurface 

soil contamination 

Figure 4-7 

Figure 4-8 

4-32 

4-34

IV.e. SURFACE WATER 

[Information provided focuses on the project premises using existing data, which are not available 

for all locations on the project premises.]

 A list or description of all surface water bodies at the facility that contain 

residual radioactive material in excess of site background levels 

4.2.7 

Figure 4-11 

4-54

4-55

 A summary of the background levels used during scoping or 

characterization surveys 

Table 4-11 4-26 

 A summary of the radionuclides present in each surface water body and 

the maximum and average radionuclide activities in becquerel per liter 

(Bq/L) (picocuries per liter (pCi/L) 

Table 4-24 4-56

IV.f. GROUND WATER 

Information provided focuses on the project premises.

 A summary of the aquifer(s) at the facility that contain residual radioactive 

material in excess of site background levels 

4.2.8 4-57

 A summary of the background levels used during scoping or 

characterization surveys 

Table 4-11 4-26 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 A-13 

CONTENT SECTION PAGE 

 A summary of the radionuclides present in each aquifer and the 

maximum and average radionuclide activities in Becquerel per liter 

(Bq/L) (picocuries per liter (pCi/L)) 

Table 4-25 4-58

V. DOSE MODELING 

V.a. UNRESTRICTED RELEASE USING SCREENING CRITERIA 

Screening criteria are not used. 

V.a.1. Unrestricted Release Using Screening Criteria for Building Surface Residual Radioactivity 

The general conceptual model (for both the source term and the 

building environment) of the site

NA NA 

A summary of the screening method (i.e., running DandD or using the 

look-up Tables) used in the DP

NA NA 

V.a.2. Unrestricted Release Using Screening Criteria for Surface Soil Residual Radioactivity 

Justification on the appropriateness of using the screening approach 

(for both the source term and the environment) at the site

NA NA 

A summary of the screening method (i.e., running DandD or using the 

look-up Tables) used in the DP

NA NA 

V.b. UNRESTRICTED RELEASE USING SITE-SPECIFIC INFORMATION 

Although no remediated areas would be released for unrestricted use during Phase 1, 

information specified in this subsection is provided for development of DCGLs and cleanup 

goals for surface soil, subsurface soil, and streambed sediment. The level of detail provided is 

similar to that in the Decommissioning EIS. 

 Source term information including nuclides of interest, configuration of the 

source, and areal variability of the source 

5.1.2 5-2 

 Description of the exposure scenario including a description of the 

critical group 

5.2.1

Figure 5-7 

Figure 5-8 

Figure 5-9 

5-20

5-20

5-24

5-28 

 Description of the conceptual model of the site including the source 

term, physical features important to modeling the transport pathways, 

and the critical group 

5.2.1

Figure 5-7 

Figure 5-8 

Figure 5-9 

5-20

5-20

5-24

5-28 

 Identification/description of the mathematical model used (e.g., hand 

calculations, DandD Screen v1.0, and RESRAD v5.81) 

5.2.2 5-31 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 0 A-14 

CONTENT SECTION PAGE 

 Description of the parameters used in the analysis Table C-1 C-3 

 Discussion about the effect of uncertainty on the results 5.2.4 5-35 

 Input and output files or printouts, if a computer program was used App C 

Related CD 

C-1 

V.c. RESTRICTED RELEASE USING SITE-SPECIFIC INFORMATION 

Although Phase 1 proposed decommissioning activities would not result in a restricted release, this 

plan provides a limited site-wide integrated dose assessment to help place the Phase 1 proposed 

decommissioning activities involving remediation of soil in the WMA 1 and WMA 2 excavations into 

context with regard to supporting potential Phase 2 decommissioning alternatives. Information 

provided on the topics in this subsection is limited to that necessary to support this assessment. 

The level of detail is similar to that in the Decommissioning EIS. 

 Source term information including nuclides of interest, configuration of the 

source, areal variability of the source, and chemical forms 

5.1.2 5-2 

 A description of the exposure scenarios, including a description of the 

critical group for each scenario 

5.2.1

Figure 5-7 

Figure 5-8 

Figure 5-9 

5-20

5-20

5-24

5-28 

 A description of the conceptual model(s) of the site that includes the source 

term, physical features important to modeling the transport pathways, and 

the critical group for each scenario 

5.2.1

Figure 5-7 

Figure 5-8 

Figure 5-9 

5-120 

5-20

5-24

5-28 

 Identification/description of the mathematical model(s) used (e.g., hand 

calculations and RESRAD v5.81) 

5.2.2 5-31 

 A summary of parameters used in the analysis Table C-1 C-3 

 A discussion about the effect of uncertainty on the results 5.2.4 5-35 

 Input and output files or printouts, if a computer program was used App C 

Related CD 

C-1 

V.d. RELEASE INVOLVING ALTERNATE CRITERIA 

DOE would not use alternative criteria. 

Source term information including nuclides of interest, configuration of the 

source, areal variability of the source, and chemical forms

NA NA 

A description of the exposure scenarios, including a description of the 

critical group for each scenario

NA NA 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 0 B-1 

APPENDIX B 

ENVIRONMENTAL RADIOACTIVITY DATA 

PURPOSE OF THIS APPENDIX 

The purpose of this appendix is to provide information on radioactivity in 

environmental media to supplement information in Section 4.2. This appendix 

discusses how radionuclide-specific and media-specific background values were 

developed and describes the methods used to determine whether specific areas of 

the site have been impacted (i.e., contain media with radioactivity concentrations in 

excess of background). 

INFORMATION IN THIS APPENDIX 

This appendix identifies locations used in establishing background radioactivity 

concentrations and methods used for calculating these concentrations. It also 

provides tables of background summary data for each environmental medium, 

explains methods used to evaluate concentrations exceeding background in onsite 

environmental media, provides tables of radionuclide ratios, and provides summary 

data of radioactivity concentrations and status with respect to background at onsite 

routine monitoring locations. Supplementary data for groundwater sampling points 

(e.g., location coordinates, sample depth, geologic unit) are also provided. 

RELATIONSHIP TO OTHER PARTS OF THE PLAN

The information in this appendix supplements that provided in Section 4.2 and 

supports planning for additional characterization of soil and sediment to be 

performed early in Phase 1 of the proposed decommissioning in accordance with 

the Characterization Sample and Analysis Plan described in Section 9. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-2 

1.0 Locations Used for Background Calculations 

Samples of surface soil, sediment, surface water, and groundwater are routinely 

collected from background locations (i.e., “control” or “rference” locations) as part of the 

WVDP Environmental Monitoring Program Plan (WVES 2008a) and the WVDP 

Groundwater Monitoring Plan (WVES 2008b). Environmental radiation measurements are 

also taken with thermoluminescent dosimeters (TLDs) at background locations as 

described in the Environmental Monitoring Program Plan. Location designators beginning 

with a “W” indicate a water sample. Those beginning with an “S” indicate soil or sediment 

samples. A designator beginning with a “D” indicates direct measurement of environmental 

exposure. 

1.1 Surface Soil 

Surface soil samples were collected annually until 2004, when the collection period was 

reduced to once every three years. (In 2008, the frequency was reduced further to once 

every five years, and sampling at most locations was discontinued.) Data from only two 

background locations were available. One (SFGRVAL, located at the air sampling station in 

Great Valley) is the primary (and current) background location. The other (SFNASHV, 

located at the former air sampling station at Nashville) was discontinued in 2003. (See 

Figure B-1.) Therefore, few data points were available to calculate surface soil 

backgrounds. 

To increase the number of data points for estimating background radionuclide 

concentrations, data from soil collected at other offsite sampling locations (i.e., at perimeter 

locations and in the nearby communities of West Valley and Springville) were evaluated for 

the possibility of using data from each in soil background calculations. Data sets for each 

radionuclide from each soil sampling location (1995-2007) were statistically compared with 

the comparable data set from the primary background location, SFGRVAL, using the 

nonparametric Mann-Whitney U-test (Sheskin 1997). The null hypothesis being tested was 

that the median of the test data set was higher than the median at the reference data set 

(SFGRVAL) (one-tailed test, P<0.05). The results are summarized in Table B-1 below, with 

the sample locations shown in Figure B-1 or B-2. (Note that, at the 0.05 level, the 

possibility of making an incorrect decision regarding the status of the location with respect 

to background could have occurred by chance alone five percent of the time.) 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 0 B-3 

Figure B-1. Background Sampling Locations More Than 10 Kilometers From the WVDP 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 0 B-4 

Table B-1. Summary of Comparisons of Radionuclide Data from Test Surface Soil 

Locations vs. SFGRVAL Background 

Location 

Radionuclide Measurement 

Gross 

alpha 

Gross 

Beta Sr-90 Cs-137 U-232 U-233/ 234 

U-235/ 

236 U-238 Pu-238 Pu-239/ 240 Am-241

SFGRVAL vs. 

SFNASHV NS NS NS NS --- --- --- --- NS NS NS 

SFFXVRD NS NS NS NS --- --- --- --- NS NS NS 

SFTCORD NS Higher NS NS --- --- --- --- NS NS NS 

SFRT240 NS NS NS NS --- --- --- --- NS NS NS 

SFSPRVL NS NS NS NS --- --- --- --- NS NS NS 

SFWEVAL NS NS NS NS --- --- --- --- NS NS NS 

SFBOEHN NS NS NS NS NS Higher NS NS NS NS NS 

SFRSPRD NS NS NS Higher NS NS NS NS NS NS NS 

SFBLKST NS Higher NS NS --- --- --- --- NS NS NS 

KEY: Higher = Null hypothesis was not rejected; results higher than background (P<0.05). 

 NS = Null hypothesis was rejected; results were not significantly higher than background. 

 --- = Constituent was not measured at this location. 

LOCATION CODES: SFGRVAL = Background at Great Valley; 

SFNASHV = Background at Nashville in the town of Hanover; 

SFTCORD = Perimeter at Thomas Corners Road; 

SFRT240 = Perimeter at Route 240; 

SFSPRVL = Community at Springville; 

SFWEVAL = Community at West Valley; 

SFBOEHN = Perimeter at Boehn Road; 

SFRSPRD = Perimeter at Rock Springs Road; 

SFBLKST = Perimeter at Bulk Storage Warehouse. 

(Location SFNASHV was discontinued in 2003; locations SFTCORD, SFBOEHN, and SFBLKST 

were discontinued 2005.) 

See Figures B-1 and B-2 for sample locations. 

If data were determined not to be statistically higher than background (i.e., unlikely to 

have been impacted by the WVDP, indicated by “NS” results in the above table), the data 

were pooled with data from Great Valley and included in background calculations. 

As discussed in Section 4.2.1 of this plan, data were extracted from the WVDP 

Laboratory Information Management System. Samples from which the data were taken had 

been collected and analyzed in accordance with controlled sampling plans and defined 

quality assurance protocols. All data used for background calculations were independently 

validated and approved. 

 Although not all analyses were performed by the same laboratories over the years, 

before a laboratory was awarded a contract, analytical procedures were reviewed, 

laboratories were audited by WVDP personnel familiar with radioanalytical methods, and
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-5 

 performance on proficiency samples for the radionuclides of interest were examined for 

acceptability. Analysis of alpha-emitting radionuclides – U-232, U-233/234, U-235/236, U238, Pu-238, Pu-239/240, and Am-241 – was done by alpha spectrometry to meet 

contractual detection limits. After contracts were awarded, laboratories were contractually 

required to participate in formal crosscheck programs and perform acceptably. During the 

term of the contracts, laboratories were routinely audited by WVDP personnel to ensure 

that contractually required standards were maintained. 

1.2 Subsurface soil 

Data from only two boreholes (BH-38 on the north plateau and BH-39 on the south 

plateau) were available for this calculation when Revision 0 to this plan was prepared. The 

boreholes were driven into areas of the WVDP classified as non-impacted as part of a 

Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) soil 

characterization study in 1993. (See Figure B-3.) Although samples were taken from three 

depths at each borehole, the surficial samples (0-2 feet depth) were classified as surface 

soil for the purposes of this plan. Therefore, only two samples from each borehole, a total 

of four samples, were classified as subsurface soil. Although subsurface soil background 

values were calculated from these four data points, they were not used initially as reference 

values because there were too few points. Instead, surface soil background results were 

used to evaluate the presence of radionuclide concentrations in excess of background in 

subsurface soil samples. 

In 2008, subsurface soil background locations in the sand and gravel and unweathered 

Lavery till geological units underlying the site were sampled as part of the North Plateau 

Characterization Program (Michalczak 2007, Klenk 2008). Results from the sand and 

gravel and unweathered Lavery till samples were statistically indistinguishable, so all were 

combined, together with the 1993 results, to produce a subsurface soil background for the 

site. 

1.3 Surface Water and Sediment 

The routine Environmental Monitoring Program background locations were used as the 

source of background data. Both surface water and sediment background data were taken 

from samples collected at Buttermilk Creek upstream of the WVDP (surface water 

monitoring point WFBCBKG and sediment monitoring point SFBCSED) and at Bigelow 

Bridge on Cattaraugus Creek upstream of the point where Buttermilk Creek, containing 

effluent from the WVDP, flows into Cattaraugus Creek (surface water point WFBIGBR and 

sediment point SFBISED). (See Figure B-2.) 

 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 0 B-6 

Figure B-2. Sampling Locations Within 10 Kilometers of the WVDP Used for 

Background Calculations 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 0 B-7 

1.4 Groundwater 

The routine background locations from the Groundwater Monitoring Program were 

used as the source of background data. (See Figure B-3.) Radionuclide concentrations 

were taken from monitoring wells WNWNB1S, WNW0204, WNW0301, WNW0401, 

WNW0405, WNW0706, WNW0901, and WNW0908, which serve(d) as upgradient 

reference locations for the following geologic units: the sand and gravel (S&G) unit 

(WNWNB1S, WNW0301, WNW0401, and WNW0706); the Lavery till sand (LTS) unit 

(WNW0204); the unweathered Lavery till (ULT) unit (WNW0405); the Kent recessional 

sequence (KRS) unit (WNW0901); and the weathered Lavery till (WLT) unit (WNW0908). 

Because few background data points were available for most radionuclides in 

groundwater and no background isotopic data (or very limited data) were available for 

groundwater from some of the geological units (e.g., the Lavery till sand and the Kent 

recessional sequence), data sets for the various units were combined to calculate one 

overall site groundwater background value for each radionuclide. Potential implications of 

pooling the data were considered to be minimal because most of the data sets were 

comprised largely of nondetect values as shown in Table B-7, and because, when positive 

detects were noted (with the exception of naturally occurring radionuclides), they were 

usually below (or slightly higher than) the contractual detection limits. 

1.5 Gamma Radiation Measurements From TLDs

TLD data were taken from four background locations (three no longer active) over the 

1986-2007 time period. (See Figure B-1.) Measurements were taken at: 

(1) The current background location (DFTLD23), located 18 miles (29 km) south of the 

WVDP at the Great Valley air sampler; 

(2) The five-points landfill (DFTLD17), located 12 miles (19 km) southwest of the Site; 

(3) The former air sampling location at Nashville in the town of Hanover (DFTLD37), 

located 23 miles (37 km) northwest of the Site; and 

(4) Sardinia-Savage Road (DFTLD41), 15 miles (24 km) northeast of the Site. 

Quarterly exposure rates (in mR/qtr) and hourly exposure rates (in mR/h) were calculated. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-8 

Figure B-3. Onsite Groundwater and Subsurface Soil Locations Used as Background
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 0 B-9 

2.0 Methods Used for Background Calculations 

Radionuclides for which backgrounds were estimated were selected with consideration 

of (1) radionuclides of interest from the Facility Characterization Project, as listed in 

Decommissioning Plan section 4.1.1, and (2) radionuclides that are routinely monitored in 

environmental media at the WVDP, for which sufficient data were available to develop a 

reliable estimate of background. (See Section 4.2.2 of this plan for a more detailed 

discussion of how background constituents were selected.) 

Once radionuclides and locations applicable to each environmental medium had been 

defined, sample results were extracted from the Laboratory Information Management 

System database using the Environmental Affairs Trend Tool. As part of the extraction 

process, data from duplicate samples (i.e., separate samples of one medium collected at 

the same place and time; co-located samples) were combined into a single result for use in 

calculations, as were data from replicate samples (i.e., recounts or splits of the same 

sample). Calculations to combine results from duplicates and replicates, using protocols 

defined in controlled WVDP Procedure EM-11 (WVNSCO 2004b), were automatically done 

by the Environmental Affairs Trend Tool during data extraction. 

Extracted data files were block copied into Microsoft Excel® spreadsheets and the 

information identified in Table B-2 was summarized for each environmental medium. 

Table B-2. Summary Information for Environmental Medium Background 

Calculations 

Item Explanatory Notes 

Constituent Gross measurement, radionuclide measurement, or direct radiation 

measurement 

Average 

result 

In the LIMS database, individual radionuclide concentration measurements 

are represented by a result term plus or minus an associated uncertainty 

term. The average result is the direct average of result terms from all 

samples in the data set, including negative numbers and zeros. 

Uncertainty 

associated 

with the 

average 

result 

The uncertainty term associated with the average result is calculated from 

the sample uncertainty terms in accordance with Procedure EM-11 per the 

following formula: 

uncertainty = SQRT((uncertainty1

2

 + ... + uncertaintyN

2

) / N) 

where uncertainty1 = the uncertainty term from sample 1 

 uncertaintyN = the uncertainty term from sample N 

 N = the total number of samples 

 SQRT = square root 

Median To estimate the median of each data set, each sample result±uncertainty 

was assigned a single result equal to the larger of the result or the 

uncertainty term. Using the Excel®

 median function, the median was 

selected from the set of single values. If more than half the sample results 

were nondetects, the median was assigned a “<” sign, indicating that the 

median represented a nondetect value. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 0 B-10 

Table B-2. Summary Information for Environmental Medium Background 

Calculations 

Item Explanatory Notes 

Note that if a data set is symmetric, the average and median will be the 

same. However, if the distribution is skewed to the right (that is, it contains 

a large number of low values and a few high values), the average will 

usually be higher than the median. For this reason, with asymmetrically 

distributed data sets (as is often the case with environmental data) the 

median may be the more reliable estimator of central tendency. 

Maximum The maximum was selected from only the results indicating that activity 

had been detected. If no activity had been detected in any of the samples 

from that data set, the maximum was set equal to the highest uncertainty 

term and assigned a “<” sign, indicating that it was a nondetect. 

N Total number of samples. (Duplicate samples were counted as one, as 

were replicate samples.) 

% NDs If the uncertainty term for a sample was larger than the result (i.e., the 

range around the result term included zero), the radionuclide was 

considered not detected (ND) in that sample. Total number of ND samples 

divided by the total number of samples was expressed as a percentage. 

Years The period of years from which the data set was taken. 

Data 

source 

locations 

A listing of the sampling locations from which background data were taken. 

Soil and sediment data, as extracted from the Laboratory Information Management 

System, were in units of μCi/g (dry weight). Surface water and groundwater data were in 

units of μCi/mL. All calculations were performed in units as extracted from the Laboratory 

Information Management System. Environmental dosimetry readings were in mR/qtr. For 

comparisons with onsite sample results, background data were then converted to the units 

specified in the Decommissioning Plan using the following conversion factors: 

Soil and sediment: 1 μCi/g = 1E+06 pCi/g 

Water: 1 μCi/mL = 1E+09 pCi/L 

3.0 Background Summary Data for Each Environmental Medium 

Summary tables of background values (in units of pCi/g per unit dry weight [soil or 

sediment], pCi/L [surface water and groundwater], or mR/quarter [environmental exposure]) 

used to evaluate data from onsite sampling locations are presented in the following tables. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 0 B-11 Table B-3. Surface Soil Background Radionuclide Concentrations for the WVDP(1),(2)

Constituent Avg. Concentration (pCi/g) Median (pCi/g) Maximum (pCi/g) N % NDs Years Data Source Locations Result ± Uncertainty Gross alpha 1.34E+01 ± 3.58E+00 1.29E+01 2.73E+01 104 0% 1995-2007 

SFGRVAL, SFNASHV, SFFSFRT240, SFSPRVL, SFWSFRSPRD, SFBLKST 

Gross beta 2.03E+01 ± 3.11E+00 2.00E+01 4.00E+01 84 0% 1995-2007 SFGRVAL, SFNASHV, SFF

SFSPRVL, SFWEVAL, SFB

Sr-90 1.51E-01 ± 1.46E-01 9.48E-02 3.10E+00 104 25% 1995-2007 

SFGRVAL, SFNASHV, SFFSFRT240, SFSPRVL, SFWSFRSPRD, SFBLKST 

Cs-137 4.50E-01 ± 6.68E-02 4.17E-01 1.21E+00 93 0% 1995-2007 

SFGRVAL, SFNASHV, SFFSFRT240, SFSPRVL, SFWSFBLKST 

U-232 5.52E-03 ± 2.80E-02 < 2.35E-02 1.89E-02 32 97% 1995-2007 SFGRVAL, SFBOEHN, SFRU-233/234 7.79E-01 ± 1.15E-01 7.88E-01 9.39E-01 22 0% 1995-2007 SFGRVAL, SFRSPRD U-235/236 5.98E-02 ± 3.36E-02 5.24E-02 2.18E-01 32 9% 1995-2007 SFGRVAL, SFBOEHN, SFRU-238 7.79E-01 ± 1.13E-01 7.87E-01 9.31E-01 32 0% 1995-2007 SFGRVAL, SFBOEHN, SFRPu-238 5.39E-03 ± 1.38E-02 < 1.21E-02 4.02E-02 92 86% 1996-2007 

SFGRVAL, SFNASHV, SFFSFRT240, SFSPRVL, SVWSFRSPRD, SFBLKST 

Pu-239/240 2.01E-02 ± 1.79E-02 1.55E-02 2.34E-01 104 44% 1995-2007 

SFGRVAL, SFNASHV, SFFSFRT240, SFSPRVL, SFWSFRSPRD, SFBLKST 

Am-241 1.45E-02 ± 1.92E-02 < 1.62E-02 1.93E-01 104 64% 1995-2007 

SFGRVAL, SFNASHV, SFFSFRT240, SFSPRVL, SFWSFRSPRD, SFBLKST 

LEGEND: N = Number of samples  ND = Nondetect NOTES: (1) Soil samples collected at air samplers at background locations (SFGRVAL = Great Valley; SFNASHV = Nashville), perimeter locations (SF

Valley Road; SFTCORD = Thomas Corners Road; SFRT240 = Route 240; SFBOEHN = Boehn Road; SFRSPRD = Rock Springs Road; S

Storage Warehouse), and community locations (SFSPRVL = Springville; SFWEVAL = West Valley). 

 (2) Data from perimeter and community samplers were pooled with data from background locations if they were not statistically higher than ba
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Revision 0 B-12 Table B-4. Sediment Background Radionuclide Concentrations for the WVDP(1)

Constituent Average concentration (pCi/g) Median (pCi/g) Maximum (pCi/g) N % NDs Years Data Sourc

Locations Result ± Uncertainty 

Gross alpha 1.02E+01 ± 3.28E+00 9.21E+00 2.18E+01 22 0% 1995-2006 SFBCSED, Gross beta 1.74E+01 ± 3.01E+00 1.64E+01 2.71E+01 23 0% 1995-2007 SFBCSED, Sr-90 1.49E-02 ± 4.91E-02 < 3.35E-02 1.57E-01 23 65% 1995-2007 SFBCSED, Cs-137 3.50E-02 ± 2.50E-02 3.75E-02 7.84E-02 23 30% 1995-2007 SFBCSED, U-232 1.15E-02 ± 5.50E-02 < 3.10E-02 3.92E-02 23 87% 1995-2007 SFBCSED, U-233/234 5.99E-01 ± 1.19E-01 6.59E-01 8.58E-01 23 4% 1995-2007 SFBCSED, U-235/236 5.31E-02 ± 3.67E-02 4.57E-02 2.78E-01 23 22% 1995-2007 SFBCSED, U-238 6.11E-01 ± 1.19E-01 6.52E-01 9.01E-01 23 4% 1995-2007 SFBCSED, Pu-238 1.67E-02 ± 1.79E-02 < 1.41E-02 1.29E-01 23 74% 1995-2007 SFBCSED, Pu-239/240 1.08E-02 ± 1.37E-02 < 1.22E-02 6.07E-02 23 83% 1995-2007 SFBCSED, Am-241 1.07E-02 ± 1.83E-02 < 1.41E-02 8.60E-02 23 74% 1995-2007 SFBCSED, 

LEGEND: N = Number of samples  ND = Nondetect NOTE: (1) Sediment samples were collected at upstream sampling locations on Buttermilk Creek (SFBCSED) and Cattaraugus Creek (SFBISED). 
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Table B-5. Subsurface Soil Background Radionuclide Concentrations for the WVDP 

Constituent Average concentration (pCi/g) Median (pCi/g) Maximum (pCi/g) N % NDs Years Data Source Locatio

Result ± Uncertainty 

Gross alpha 1.20E+01 ± 4.76E+00 1.26E+01 1.69E+01 18 0% 1993, 2008 BH-38 and 39 (1993); 

GPBG03-08, GPBG04

Gross beta 3.19E+01 ± 3.99E+00 2.86E+01 6.10E+01 18 0% 1993, 2008 BH-38 and 39 (1993); 

GPBG03-08, GPBG04

Sr-90 1.80E-02 ± 2.59E-02 < 2.30E-02 1.24E-01 18 89% 1993, 2008 BH-38 and 39 (1993); 

GPBG03-08, GPBG04

Cs-137 4.51E-03 ± 2.43E-02 < 2.41E-02 1.49E-01 18 94% 1993, 2008 BH-38 and 39 (1993); 

GPBG03-08, GPBG04

U-232 -2.65E-03 ± 2.55E-02 < 2.44E-02 < 4.19E-02 18 100% 1993, 2008 BH-38 and 39 (1993); 

GPBG03-08, GPBG04

U-233/234 6.83E-01 ± 1.19E-01 7.91E-01 1.08E+00 18 0% 1993, 2008 BH-38 and 39 (1993); 

GPBG03-08, GPBG04

U-235/236 5.14E-02 ± 3.47E-02 4.25E-02 1.17E-01 18 33% 1993, 2008 BH-38 and 39 (1993); 

GPBG03-08, GPBG04

U-238 7.19E-01 ± 1.22E-01 8.64E-01 1.11E+00 18 0% 1993, 2008 BH-38 and 39 (1993); 

GPBG03-08, GPBG04

Pu-238 4.32E-04 ± 1.30E-02 < 1.15E-02 < 2.41E-02 18 100% 1993, 2008 BH-38 and 39 (1993); 

GPBG03-08, GPBG04

Pu-239/240 1.72E-03 ± 1.19E-02 < 1.04E-02 < 1.87E-02 18 100% 1993, 2008 BH-38 and 39 (1993); 

GPBG03-08, GPBG04

Am-241 -1.93E-03 ± 1.07E-02 < 1.09E-02 < 1.27E-02 18 100% 1993, 2008 BH-38 and 39 (1993); 

GPBG03-08, GPBG04

LEGEND: N = Number of samples ND = NondetectNOTE: (1) Background locations are shown on Figure B-3. After testing to ensure that subsurface soil results for the sand and gravel unit and the unweathe

statistically indistinguishable, values were combined into a single subsurface soil background value for each radionuclide.
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Table B-6. Surface Water Background Radionuclide Concentrations for the WVDP 

Constituent Average concentration (pCi/L) Median (pCi/L) Maximum (pCi/L) N % NDs Years Data S

Result ± Uncertainty 

Gross alpha 4.74E-01 ± 1.28E+00 < 9.55E-01 5.43E+00 387 74% 1991-2007 WFBCGross beta 2.64E+00 ± 1.43E+00 2.34E+00 2.03E+01 388 12% 1991-2007 WFBCH-3 1.35E+01 ± 8.43E+01 < 8.21E+01 6.33E+02 388 85% 1991-2007 WFBCC-14 1.19E+01 ± 4.44E+01 < 1.33E+01 4.05E+02 68 81% 1991-2007 WFBCSr-90 2.00E+00 ± 1.61E+00 9.04E-01 1.23E+01 251 47% 1991-2007 WFBCTc-99 -4.40E-01 ± 1.80E+00 < 1.80E+00 7.25E+00 52 85% 1995-2007 WFBCI-129 1.39E-01 ± 8.71E-01 < 7.86E-01 2.02E+00 68 90% 1991-2007 WFBCCs-137 6.31E-01 ± 5.98E+00 < 4.15E+00 1.01E+01 250 95% 1991-2007 WFBCU-232 1.81E-02 ± 8.91E-02 < 4.28E-02 2.60E-01 68 87% 1991-2007 WFBCU-233/234 1.10E-01 ± 7.02E-02 9.94E-02 2.98E-01 61 16% 1992-2007 WFBCU-235/236 1.71E-02 ± 4.07E-02 < 3.28E-02 1.00E-01 67 82% 1991-2007 WFBCU-238 7.44E-02 ± 6.35E-02 5.72E-02 4.00E-01 68 35% 1991-2007 WFBCPu-238 1.45E-02 ± 6.24E-02 < 3.10E-02 1.02E-01 68 93% 1991-2007 WFBCPu-239/240 9.17E-03 ± 3.50E-02 < 2.71E-02 1.98E-01 68 91% 1991-2007 WFBCAm-241 5.42E-02 ± 7.15E-02 < 3.27E-02 2.20E+00 68 81% 1991-2007 WFBCLEGEND: N = Number of samples  ND = Nondetect  WFBCBKG = Buttermilk Creek background; WFBIGBR = Cattaraugus Creek background at Bigelow Bridge. 
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Revision 0 B-15 Table B-7. Groundwater Background Radionuclide Concentrations for the WVDP 

Constituent Average concentration (pCi/L) Median (pCi/L) Maximum (pCi/L) N % NDs Years Data Source 

Result ± Uncertainty 

Gross alpha 1.06E+00 ± 5.69E+00 < 2.59E+00 2.19E+01 566 87% 1991-2007 WNW-NB1S

0405, -0706, 

Gross beta 6.19E+00 ± 5.11E+00 4.56E+00 2.82E+01 566 28% 1991-2007 WNW-NB1S

0405, -0706, 

H-3 2.11E+01 ± 8.55E+01 < 8.58E+01 9.41E+02 566 81% 1991-2007 WNW-NB1S

0405, -0706, 

C-14 

-

4.95E+00 ± 2.63E+01 < 2.66E+01 7.43E+00 56 98% 1993-2007 WNW-NB1S

Sr-90 2.69E+00 ± 1.35E+00 2.44E+00 7.38E+00 56 16% 1993-2007 WNW-NB1STc-99 -3.71E-01 ± 1.91E+00 < 1.85E+00 3.98E+00 56 96% 1993-2007 WNW-NB1SI-129 2.39E-01 ± 7.38E-01 < 6.01E-01 1.58E+00 56 86% 1993-2007 WNW-NB1SCs-137 1.75E+00 ± 2.39E+01 < 2.22E+01 1.90E+01 258 98% 1991-2007 WNW-NB1S

0405, -0706, 

U-232 2.28E-02 ± 1.00E-01 < 4.92E-02 3.78E-01 56 88% 1993-2007 WNW-NB1SU-233/234 4.88E-01 ± 1.94E-01 1.60E-01 8.20E+00 56 13% 1993-2007 WNW-NB1SU-235/236 4.52E-02 ± 6.03E-02 < 5.00E-02 1.93E-01 56 71% 1993-2007 WNW-NB1SU-238 3.18E-01 ± 1.48E-01 1.21E-01 5.30E+00 56 21% 1993-2007 WNW-NB1SPu-238 5.94E-02 ± 9.59E-02 < 4.65E-02 2.20E-01 6 83% 1993-1994 WNW-NB1SPu-239/240 4.95E-02 ± 8.35E-02 < 5.28E-02 2.70E-01 6 83% 1993-1994 WNW-NB1SAm-241 4.32E-02 ± 4.76E-02 < 3.81E-02 1.80E-01 6 83% 1993-1994 WNW-NB1SLegend: N = Number of samples  ND = Nondetect  “WNW” locations refer to individual wells that serve as groundwater backgrounds for solid waste management units in the groundwater monito
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Revision 0 B-16 

Table B-8. Background Environmental Radiation Levels at the WVDP 

Constituent Average (mR/quarter) Median Maximum N Years Data So

Result ± Uncertainty 

Environmental radiation 19.3 ± 7.1 19.2 35.0 264 1986-2007 DFTLD23, 

DFTLD41 

NOTE: (1) Background locations: DFTLD17 (Five Point Landfill); DFTLD23 (Great Valley); DFTLD37 (Dunkirk); DFTLD41 (Sardinia-Savage Road
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4.0 Methods for Evaluating Concentrations Above Background in Onsite Environmental 

Media 

Data from onsite sampling were available in three forms: 

(1) Single observations or measurements with no associated uncertainty term (for 

example, a sediment concentration from 1988 presented in a historical report); 

(2) A radionuclide concentration result, plus or minus an associated uncertainty term, 

from a sample collected as part of a one-time sampling project (i.e., the RFI soil, 

sediment, and subsurface soil survey done in 1993; Geoprobe® studies done in 

1994, 1997, 1998, and 2008); and 

(3) Multi-year data sets from samples collected at specified locations as part of the 

routine Environmental Monitoring or Groundwater Monitoring programs. 

4.1 Single-Value Observations 

Single-value observations were directly compared with the maximum result from the 

applicable background radionuclide-medium combination. For example, a Cs-137 

concentration from lagoon sediment, as reported in WVNSCO 1994, was compared directly 

with the maximum Cs-137 concentration observed in background sediment. A value higher 

than the background result was classified as exceeding background. 

4.2 Single Samples With Specified Uncertainty

A single-sample result reported with an associated uncertainty term, such as the result 

from a sample collected as part of the 1993 RFI investigation, was compared with 

background using the relative errors ratio test. This test (as described in WVDP procedure 

EM-74, WVNSCO 2004a) is primarily used as a data validation tool to test the acceptability 

of results from duplicate samples (i.e., to determine the likelihood that the samples could 

have come from the same population). 

In the relative errors ratio test, one sample result (plus or minus its associated 

uncertainty term) is compared another sample result (plus or minus its associated 

uncertainty term). To perform the relative errors ratio calculation, the absolute value of the 

difference between the two sample results is divided by the sum of the squares of the 

estimated standard deviations (as based on the error terms) from each. If the result is not 

greater than 1.96 (approximating a 95 percent confidence interval), the two samples would 

be considered acceptable as duplicates. In other words, the samples could have been 

drawn from the same population (the test sample could have been drawn from the 

background population) if the confidence intervals bracketing the result terms from the two 

samples overlap. 

For purposes of the current evaluation, each onsite sample result was tested against 

the mean (plus or minus the associated uncertainty term) of the applicable radionuclide/ 

medium background value. If the test sample result met the three following conditions, the 

result was classified as exceeding background: 

• The radionuclide was detected 
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• The relative errors ratio value was greater than 1.96, and 

• The result term for the sample was higher than the average result term for the 

background. 

Areas with radiological concentrations exceeding background, as determined by the 

RER calculation, are summarized in Decommissioning Plan Figures 4-6 (surface soil and 

sediment), 4-7 (subsurface soil), and 4-13 (Geoprobe®

 groundwater). Maximum abovebackground concentrations for specific radionuclides at locations in each WMA are 

summarized in Decommissioning Plan Section 4.2.5, Tables 4-12 through 4-22 (surface 

soil, sediment, and subsurface soil), and Decommissioning Plan Section 4.2.8, Table 4-

26 (Geoprobe®

 groundwater). 

4.3 Data From Routine Monitoring Locations 

Radionuclide concentration data sets from routine monitoring locations were compared 

with applicable background data sets using the nonparametric Mann-Whitney “U” test. As 

recommended in MARSSIM, a nonparametric test was used because environmental data 

are usually not normally distributed and because there are often a significant number of 

results lower than detectable concentrations. Both conditions were true of the WVDP data 

sets examined in this evaluation. 

Because of the larger number of observations available for these comparisons, the “U” 

test was more sensitive at detecting concentrations exceeding background at a specific 

location than was the RER test that considered only one measurement. Note that trends 

(i.e., increasing or decreasing radionuclide concentrations) were not evaluated as part of 

this exercise, which focused only on comparisons with background. (Data trends at the 

WVDP are routinely evaluated and conclusions summarized in formal reports associated 

with the Environmental Monitoring and Groundwater Monitoring Programs.) 

The Mann-Whitney U test, similar to the Wilcoxon Rank Sum test used in MARSSIM, is 

a rank-based test. The null hypothesis being tested was that the median of the tested data 

set was higher than the median at the background location (one-tailed test, P<0.05). To 

perform the test, data sets were assembled for radionuclide concentrations at each of the 

onsite routine monitoring points (soil/sediment sampling locations, surface water sampling 

locations, and routine groundwater sampling locations). So that the data could be ranked, 

each radionuclide measurement was assigned a single value. All “detect” values (i.e., the 

result term was larger than the uncertainty term) were set equal to the result term of the 

measurement; all “nondetect” values (i.e., the uncertainty term was larger than the result 

term) were set equal to zero. In this way, all nondetect values received the same rank. 

(Note that summary statistics, such as averages, had already been calculated for each data 

set. The arbitrarily assigned zero values were used only for ranking purposes.) 

The two data sets (test location and background reference location) were then 

combined into one data set and the results ranked in numerical order from the smallest to 

the largest. From the assigned ranks, the test statistic (i.e., “U”) was calculated for each 

(Sheskin 1997). The normal approximation for larger sample sizes (“z”) was also 

calculated. Critical values of “U” and “z” were taken from statistical tables in Sheskin 1997. 
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If the “U” value was lower than the critical value of “U” (or, for larger numbers of 

samples, if the “z” value exceeded the critical level of “z”), and the mean rank from the test 

data set was greater than that from the background data set, then the null hypothesis (i.e., 

that the median of the test data set exceeded that of the background data set) was not 

rejected. In other words, at a 95% confidence level, it was likely that the median of the test 

data set exceeded that of the background data set. 

Locations where results from routine monitoring locations exceeded background are 

summarized by waste management area and radionuclide in section 4.2, Table 4-17 

(sediment from sampling location SNSWAMP), Table 4-18 (sediment from sampling 

location SNSW74A), Table 4-22 (sediment from sampling location SNSP006), Table 4-24 

(routine onsite surface water monitoring locations), and Table 4-25 (routine groundwater 

monitoring locations). 

Direct onsite measurements of environmental radiation (TLD results), for which the 

data sets approximate a normal distribution, were compared with background 

measurements using the one-way analysis of variance (ANOVA) Excel®

 function (p<0.05). 

If the “F” statistic exceeded the critical value of “F,” and the average from the test data set 

exceeded the background average, measurements from the test location were determined 

to exceed background. Results are summarized in section 4.2, Table 4-23. 

5.0 Radionuclide Ratios to Cs-137 

The concentrations of hard-to-measure radionuclides in a medium are often estimated 

on the basis of their relationship to a more easily measured nuclide, such as Cs-137, as 

defined in a well-characterized distribution. As discussed in Section 4.1.4 of this plan, two 

primary distributions have been identified at the WVDP: (1) the Spent Nuclear Fuel 

distribution — applicable to nuclear fuel prior to reprocessing, and (2) the Batch 10 

distribution — applicable to the high-level waste after the uranium and plutonium had been 

extracted. Comparable ratios from the two distributions are presented in Table 4-3. As 

shown in Table 4.3 of this plan, Sr-90 may comprise a larger relative fraction of the total 

radioactivity in the “feed and waste” category (i.e., before waste reprocessing), while a 

larger relative fraction of Am-241 may be more characteristic of the “product” category (i.e., 

after waste reprocessing). 

If surface soil, sediment or subsurface soil samples contained both Cs-137 and other 

radionuclides at above-background concentrations, the ratio of each above-background 

radionuclide to Cs-137 was calculated. Only data from the same discrete samples were 

used to calculate ratios. Ratios in surface soil, sediment, and subsurface soil are 

summarized by WMA in Tables B-9, B-10, and B-11, respectively. For each medium, the 

following information is listed: 

• Number of samples for which each nuclide exceeded background, 

• Minimum ratio, 

• Median ratio, 

• Maximum ratio, 
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• Concentration of Cs-137 (in pCi/g dry) in the sample with the maximum ratio, 

and 

• Location at which the maximum ratio was observed. 

 With respect to environmental concentrations exceeding background, the ratio of a 

radionuclide to Cs-137 may help to better trace the source of the activity. For instance, the 

area of elevated Sr-90 concentrations on the north plateau downgradient of the Process 

Building has been traced to a leak of radioactively contaminated acid in the late 1960s. 

This plume is characterized by high Sr-90-to-Cs-137 ratios. 

6.0 Supplementary Data for Onsite Monitoring Locations 

Summary statistics were calculated for radiological constituents measured at all routine 

monitoring locations on the WVDP site, sediment for the years 1995 through 2007, and 

surface water and groundwater for 1998 through 2007. Constituents exceeding background 

levels at each location are presented in Section 4.2. Complete results, including those from 

locations determined to be non-impacted, are presented in the following tables for onsite 

sediment (Table B-12), surface water (B-13), and groundwater (B-14). 

Supplementary information about routine groundwater monitoring locations (i.e., 

location coordinates, surface elevation, construction material of the well or trench, diameter 

of the well [if applicable], screened interval, and geologic unit monitored) are summarized in 

Table B-15. Similar information for special Geoprobe®

 groundwater sampling points is 

provided in Table B-16. 

Note that only routine monitoring locations included in the current Groundwater 

Monitoring Program were included in the evaluation presented in Section 4.2.8 of this plan. 

A large number of points at which groundwater had been sampled in the past were not 

included in this evaluation. For completeness, information on excluded points is 

summarized in Table B-17. Reasons for exclusion included: 

• The well was dry; 

• No radiological data were available; 

• Data were not validated (e.g., piezometers, surface elevation points, wells for the 

north plateau groundwater recovery system, wells used to evaluate the pilot 

permeable treatment wall); 

• Wells had been dropped from the groundwater program because existing coverage 

was considered sufficient (e.g., more than twenty wells discontinued in 1995); or 

• Sampling points were located in areas outside the scope of the Phase 1 

Decommissioning Plan (e.g., groundwater seeps outside the process premises, 

wells from WMA 8 [New York State-Licensed Disposal Area]). 

7.0 References

Klenk 2008, West Valley Demonstration Project North Plateau Background Soil 

Characterization Report, WVDP-493, Revision 1. Klenk, D.P., West Valley 

Environmental Services LLC, West Valley, New York, December 29, 2008. 
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Michalczak 2007, Sampling and Analysis Plan for Background Subsurface Soil on the 

North Plateau, WVDP-466, Revision 0. Michalczak, L., West Valley Nuclear 

Services Company, West Valley, New York, August 16, 2007. 

Sheskin 1997, Handbook of Parametric and Nonparametric Statistical Procedures. 

Sheskin, D.J., CRC Press LLC, 1997. 

WVES 2008a, Environmental Monitoring Program Plan, WVDP-098, Revision 15. West 

Valley Environmental Services LLC. West Valley, New York, January 7, 2008. 

WVES 2008b, Groundwater Monitoring Plan, WVDP-239, Revision 12. West Valley 

Environmental Services LLC, West Valley, New York, February 12, 2008. 

WVNSCO 1994, Environmental Information Document, Volume IV: Soils Characterization, 

WVDP-EIS-008, Revision 0. West Valley Nuclear Services Company, West Valley, 

New York, September 15, 1994. 

WVNSCO 2004a, Radioanalytical Data Validation, EM-74, Revision 8. West Valley Nuclear 

Services Company, West Valley, New York, November 22, 2004. 

WVNSCO 2004b, Documentation and Reporting of Environmental Data, EM-11, Revision 

8. West Valley Nuclear Services Company, West Valley, New York, December 27, 

2004. 
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Table B-9. Radionuclides in Surface Soil: Ratios to Cs-137(1)

Area(2) Radionuclide N Minimum Median Maximum Cs-137 (pCi/g)(3) Location of Ma

WMA 2 Sr-90 5 0.015 0.28 1.4 8.5E-01 Surface soil near Lagoons 4 and WMA 3 U-238 1 0.047 0.047 0.047 2.2E+01 Surface soil near Waste Tank F Am-241 1 0.011 0.011 0.011 2.2E+01 Surface soil near Waste Tank FWMA 4 Sr-90 3 0.29 0.96 9.5 1.2E+00 CDDL soil (6-12" depth, 1990) WMA 5 Sr-90 2 0.019 0.047 0.075 1.1E+01 Surface soil near RHWF (BH-38 Pu-238 1 0.0033 0.0033 0.0033 1.1E+01 Surface soil near RHWF (BH-38 Pu-239/240 1 0.015 0.015 0.015 1.1E+01 Surface soil near RHWF (BH-38 Am-241 4 0.026 0.033 0.073 1.2E+01 LSA 3 & 4 footers (1990) WMA 6 Sr-90 12 0.036 0.094 1.7 2.9E+00 Rail spur by FRS (1994) WMA 7 Sr-90 8 0.11 1.9 8.3 1.1E+00 NDA Surface Soil (1994)  Pu-238 1 0.021 0.021 0.021 4.1E+00 Surface soil by the NDA Interce Pu-239/240 1 0.022 0.022 0.022 4.1E+00 Surface soil by the NDA Interce Am-241 1 0.037 0.037 0.037 4.1E+00 Surface soil by the NDA InterceWMA 12 Sr-90 4 0.14 0.25 0.29 4.5E+00 Surface soil near WMA 2 and WNOTES: (1) Ratios were calculated from samples for which both Cs-137 and the nuclide of interest exceeded background, with ratios rounded to two sig

integer. 

 (2) No surface soil data were available for WMA 1. No radionuclides exceeded background in WMA 9. Only Cs-137 exceeded background in 

 (3) Cs-137 concentration at the location with the maximum ratio. LEGEND: BH = bore hole CDDL = Construction and Demolition Debris Landfill FRS = Fuel Receiving and Storage LSA = Lag Storage Addition 

RHWF = Remote-Handled Waste Facility. 
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Table B-10. Radionuclides in Sediment: Ratios to Cs-137(1)

Area(2) Radionuclide N Minimum Median Maximum Cs-137 (pCi/g)(3) Location of Maxim

WMA 2 Sr-90 41 0.0063 0.065 144 1.0E+01 Sediment from the Solvent Dike (1986)  U-232 1 0.0054 0.0054 0.0054 1.4E+03 Lagoon 3 sediment (1994)  U-233/234 2 0.0032 0.030 0.056 1.7E+01 Sediment from drainage downgradient o U-235/236 7 0.000010 0.000076 0.011 1.7E+01 Sediment from drainage downgradient o U-238 28 0.000052 0.0014 0.057 2.1E+01 Lagoon 3 sediment (1990)  Pu-238 10 0.00028 0.0015 0.018 4.4E+04 Lagoon 2 shoreline sediment (1990)  Pu-239/240 9 0.00051 0.0011 0.019 1.7E+01 Sediment from drainage downgradient o Am-241 29 0.00058 0.0019 4.2 1.0E+01 Sediment from the Solvent Dike (1986) WMA 4 Sr-90 18 0.041 0.80 16 3.1E+00 Sediment from drainage through CDDL ( U-233/234 9 0.036 0.11 1.4 6.6E-01 Sediment at Northeast Swamp (SNSWA U-235/236 2 0.023 0.14 0.27 6.6E-01 Sediment at Northeast Swamp (SNSWA U-238 9 0.036 0.12 1.3 6.6E-01 Sediment at Northeast Swamp (SNSWA Pu-238 10 0.0057 0.022 0.057 5.2E+00 Sediment at Northeast Swamp (SNSWA Pu-239/240 13 0.0089 0.033 0.21 1.1E+01 Sediment at Northeast Swamp (SNSWA Am-241 14 0.010 0.056 0.22 2.1E+00 Sediment at Northeast Swamp (SNSWAWMA 5 Sr-90 15 0.026 0.13 3.3 6.4E-01 Sediment at North Swamp (SNSW74A)  U-233/234 4 0.12 0.37 0.75 1.1E+00 Sediment at North Swamp (SNSW74A)  U-235/236 1 0.047 0.047 0.047 2.7E+00 Sediment at North Swamp (SNSW74A)  U-238 4 0.15 0.34 2.0 4.7E-01 Sediment at North Swamp (SNSW74A)  Pu-238 1 0.015 0.015 0.015 3.8E+00 Sediment at North Swamp (SNSW74A)  Pu-239/240 9 0.019 0.035 0.096 4.7E-01 Sediment at North Swamp (SNSW74A)  Am-241 11 0.0011 0.057 0.087 6.4E-01 Sediment at North Swamp (SNSW74A) 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 0 B-24 

Table B-10. Radionuclides in Sediment: Ratios to Cs-137(1)

Area(2) Radionuclide N Minimum Median Maximum Cs-137 (pCi/g)(3) Location of Maxim

WMA 6 Sr-90 3 0.062 0.27 0.59 5.9E-01 Sediment from south Demineralizer SludWMA 7 Sr-90 1 3.7 3.7 3.7 9.0E-01 Sediment from drainage near Interceptor  Pu-238 1 0.096 0.096 0.096 9.0E-01 Sediment from drainage near Interceptor  Am-241 1 0.046 0.046 0.046 9.0E-01 Sediment from drainage near Interceptor WMA 12 Sr-90 33 0.022 0.058 0.59 2.7E-01 Sediment from Franks Creek (ST-13) ne U-232 2 0.0010 0.0021 0.0031 3.5E+01 Sediment from Erdman Brook (ST-19) af U-233/234 3 0.034 0.038 0.075 1.1E+01 Sediment from Franks Creek at fence lin U-238 4 0.0094 0.035 0.058 1.4E+01 Sediment from Franks Creek at fence lin Pu-238 10 0.00070 0.0034 0.042 5.9E+01 Sediment from Erdman Brook (ST-20) af Pu-239/240 7 0.00068 0.0029 0.012 5.9E+01 Sediment from Erdman Brook (ST-20) af Am-241 18 0.0012 0.0047 0.033 4.3E+01 Sediment from Erdman Brook (ST-22) doNOTES: (1) Ratios were calculated from samples for which both Cs-137 and the nuclide of interest exceeded background, with the ratios rounded to 

the nearest integer. 

(2) No sediment data were available for WMAs 1, 3, or 9. Only Cs-137 exceeded background in WMA 10. (3) Cs-137 concentration at the location with the maximum ratio. 

LEGEND: CDDL = Construction and Demolition Debris Landfill N = number of samples 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-25 

Table B-11. Radionuclides in Subsurface Soil: Ratios to Cs-137(1)

Area(2) Radionuclide N Minimum Median Maximum Cs-137 (pCi/g)(3) Location of Maxim

WMA 1 Sr-90 45 0.31 303 63,419 5.0E-02 Inside MPPB (GP7898, 21-23’ depth) 

Tc-99 6 0.0027 2.3 5.6 1.1E-01 Outside MPPB, south of FRS (GP7208, 1U-232 1 0.023 0.023 0.023 2.0E+00 Outside southeast corner of MPPB (GP2U-233/234 9 0.0074 0.79 12 7.2E-02 Inside MPPB (GP10008, 30-32’ depth) U-235/236 5 0.013 0.063 1.1 1.4E-01 Outside eastern wall of MPPB (GP3008, U-238 7 0.82 6.1 18 7.2E-02 Outside MPPB, north of FRS (GP10108, Pu-238 5 0.0025 0.019 0.18 1.5E-01 Outside MPPB, south of FRS (GP7208, 4Pu-239/240 8 0.015 0.067 0.80 5.5E-02 East of laundry building (BH-18, 14-16’ dAm-241 16 0.025 0.19 2.7 3.6E-02 Inside MPPB (GP77, 19-23’ depth) Cm-243/244 1 0.015 0.015 0.015 1.0E+01 Inside MPPB (GP8008, 25-27’ depth) 

WMA 2 Sr-90 27 0.037 1.9 750 4.8E-02 Northwest of Lagoon 1 (BH-09, 10-12’ de

U-232 11 0.0050 0.021 1.0 4.8E-02 Northwest of Lagoon 1 (BH-09, 10-12’ deU-233/234 8 0.0046 1.9 7.0 2.7E-01 Solvent dike (BH-11, 10-12’ depth) U-235/236 7 0.000038 0.55 1.1 2.7E-01 Solvent dike (BH-11, 10-12’ depth) U-238 7 0.00052 0.052 4.4 2.7E-01 Solvent dike (BH-11, 10-12’ depth) Pu-238 15 0.0049 0.023 0.089 1.9E+00 Between Interceptors and Lagoon 1 (BH-Pu-239/240 15 0.0046 0.031 0.11 1.6E-01 Maintenance Shop Leach Field (BH-35, 1Pu-241 7 0.030 0.11 0.21 1.6E+01 East of Test and Storage Building (BH-35Am-241 18 0.010 0.051 0.23 2.7E-01 Solvent dike (BH-11, 10-12’ depth) 

WMA 4 Sr-90 2 0.73 0.75 0.77 8.8E-02 Southeast corner of CDDL (BH-28, 6-8’ dWMA 5 Sr-90 1 6.3 6.3 6.3 4.8E-02 Between LSA 3 and LSA 4 (BH-30, 10-12WMA 6 Sr-90 5 1.1 174 1115 1.3E-01 Downgradient of MPPB (GP10208, 16-18

U-232 1 0.087 0.087 0.087 1.1E+00 Downgradient of MPPB (GP10208, 14-16
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-26 

Table B-11. Radionuclides in Subsurface Soil: Ratios to Cs-137(1)

Area(2) Radionuclide N Minimum Median Maximum Cs-137 (pCi/g)(3) Location of Maxim

U-233/234 2 1.2 4.6 8.0 1.3E-01 Downgradient of MPPB (GP10208, 16-18U-235/236 2 0.33 0.82 1.3 1.3E-01 Downgradient of MPPB (GP10208, 16-18U-238 2 1.3 5.2 9.0 1.3E-01 Downgradient of MPPB (GP10208, 16-18Pu-238 2 0.025 0.030 0.035 4.3E+00 Southeast of FRS (BH-19A, 12-14’ depthPu-239/240 3 0.040 0.047 0.047 1.1E+00 Downgradient of MPPB (GP10208, 14-16Pu-241 1 0.35 0.35 0.35 4.3E+00 Southeast of FRS (BH-19A, 12-14’ depthAm-241 4 0.13 0.20 0.33 1.3E-01 Downgradient of MPPB (GP10208, 16-18

WMA 7 Sr-90 1 2.6 2.6 2.6 5.4E-02 Northern corner of NDA (BH-42, 25-27’ dWMA 12 Sr-90 1 1.5 1.5 1.5 4.4E-02 Northwest of the NDA (BH-24, 6-8’ depthNOTES: (1) Ratios were calculated from samples for which both Cs-137 and the nuclide of interest exceeded background, with ratios rounded to two sign

integer. 

 (2) No subsurface soil data were available for WMAs 3 and 9. No Cs-137 results exceeding background were found in WMA 10.  (3) Cs-137 concentration at the location with the maximum ratio. LEGEND: N = Number of Samples; MPPB = Main Plant Process Building; FRS = Fuel Receiving and Storage; CDDL = Construction and Demolition DebStorage Area; NDA = Nuclear Regulatory Commission Licensed Disposal Area
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-27 

Table B-12. Summary of Radionuclide Results from Routine Onsite Sediment Monitoring Locations 

WMA Monitoring Point Constituent N Median (pCi/g) Average (pCi/g) Maximum (pCi/g) 

Result ± Uncertainty 

WMA 4 SNSWAMP Gross alpha 13 1.73E+01 1.68E+01 ± 3.95E+00 2.26E+0 Sediment Gross beta 13 5.43E+01 5.51E+01 ± 4.66E+00 8.98E+0 at northeast Sr-90 17 2.35E+00 5.20E+00 ± 4.97E-01 2.98E+0 swamp Cs-137 17 7.40E+00 9.99E+00 ± 1.39E+00 3.14E+0 drainage U-232 17 <2.19E-02 9.20E-03 ± 3.41E-02 4.79E-0 U-233/234 16 8.21E-01 7.24E-01 ± 1.79E-01 1.13E+0 U-235/236 16 5.82E-02 5.94E-02 ± 5.38E-02 1.76E-0 U-238 16 7.93E-01 7.06E-01 ± 1.65E-01 1.14E+0 Pu-238 10 2.79E-01 2.62E-01 ± 6.87E-02 4.32E-0 Pu-239/240 17 2.26E-01 2.58E-01 ± 7.10E-02 6.42E-0 Am-241 17 4.59E-01 5.13E-01 ± 1.22E-01 1.29E+0WMA 5 SNSW74A Gross alpha 13 1.19E+01 1.29E+01 ± 3.06E+00 2.20E+0 Sediment Gross beta 13 2.33E+01 2.35E+01 ± 2.97E+00 3.47E+0 at north Sr-90 17 3.28E-01 4.67E-01 ± 8.73E-02 2.10E+0 swamp Cs-137 17 2.55E+00 2.83E+00 ± 2.54E-01 8.82E+0 drainage U-232 17 <2.16E-02 8.57E-03 ± 2.53E-02 4.23E-0 U-233/234 16 7.18E-01 6.24E-01 ± 1.74E-01 1.06E+0 U-235/236 16 5.49E-02 5.59E-02 ± 4.05E-02 1.26E-0 U-238 17 6.82E-01 6.36E-01 ± 1.80E-01 1.35E+0 Pu-238 10 2.37E-02 2.30E-02 ± 1.88E-02 5.59E-0 Pu-239/240 17 6.17E-02 6.52E-02 ± 4.13E-02 1.92E-0 Am-241 17 6.10E-02 9.01E-02 ± 5.09E-02 2.58E-0
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-28 

Table B-12. Summary of Radionuclide Results from Routine Onsite Sediment Monitoring Locations 

WMA Monitoring Point Constituent N Median (pCi/g) Average (pCi/g) Maximum (pCi/g) 

Result ± Uncertainty 

WMA 12 SNSP006 Gross alpha 13 1.10E+01 1.01E+01 ± 2.84E+00 1.32E+0 Sediment Gross beta 13 4.27E+01 5.01E+01 ± 4.09E+00 1.60E+0 from Franks Sr-90 17 8.38E-01 1.49E+00 ± 2.29E-01 9.98E+0 Creek at Cs-137 17 1.30E+01 2.10E+01 ± 2.75E+00 9.76E+0 security U-232 17 4.07E-02 4.01E-02 ± 6.81E-02 1.43E-0 fence U-233/234 16 6.40E-01 6.05E-01 ± 1.78E-01 1.02E+0 U-235/236 16 4.56E-02 3.87E-02 ± 5.46E-02 1.04E-0 U-238 17 6.07E-01 5.53E-01 ± 1.68E-01 9.15E-0 Pu-238 10 3.17E-02 4.29E-02 ± 2.58E-02 1.40E-0 Pu-239/240 17 2.60E-02 2.97E-02 ± 2.54E-02 1.08E-0 Am-241 17 4.34E-02 6.51E-02 ± 4.78E-02 2.40E-0

NOTE: (1) Using the nonparametric Mann-Whitney “U” Test, the data set of sediment background results (summarized in Table B-4) was compared with 

the sampling locations. See Appendix B, Section 4.3. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-29 Table B-13. Summary of Radionuclide Results from Routine Onsite Surface Water Monitoring Locations 

WMA Monitoring Point Constituent N Median (pCi/L)(2) Average (pCi/L) Maxim

(pCi/L

Result ± Uncertainty 

WMA 2 WNSP001 Gross alpha 232 1.75E+01 1.92E+01 ± 1.32E+01 1.01E+ Lagoon 3 Gross beta 433 2.56E+02 3.01E+02 ± 2.25E+01 8.18E+ Discharge H-3 231 2.47E+03 2.75E+03 ± 1.42E+02 7.17E+ Weir C-14 62 <2.82E+01 1.35E+01 ± 2.24E+01 4.75E+ Sr-90 231 9.88E+01 1.21E+02 ± 7.42E+00 3.19E+ Tc-99 197 6.53E+01 7.90E+01 ± 4.79E+01 3.36E+ I-129 62 2.13E+00 2.44E+00 ± 1.48E+00 1.04E+ Cs-137 231 6.10E+01 7.57E+01 ± 1.88E+01 3.29E+ U-232 62 8.02E+00 8.98E+00 ± 9.91E-01 2.14E+ U-233/234 62 5.04E+00 5.49E+00 ± 6.20E-01 1.36E+ U-235/236 62 2.62E-01 2.75E-01 ± 1.21E-01 5.84E- U-238 62 3.76E+00 3.82E+00 ± 4.87E-01 7.57E+ Pu-238 62 6.53E-02 1.53E-01 ± 6.78E-02 1.62E+ Pu-239/240 62 5.17E-02 1.34E-01 ± 6.19E-02 1.39E+ Am-241 62 6.79E-02 1.18E-01 ± 6.01E-02 9.74E-WMA 4 WNSWAMP Gross alpha 450 <1.87E+00 2.86E-01 ± 2.28E+00 7.25E+ Northeast Gross beta 451 3.01E+03 3.24E+03 ± 5.33E+01 9.98E+ Swamp H-3 451 1.13E+02 1.13E+02 ± 8.21E+01 5.20E+ Drainage C-14 34 <1.58E+01 2.13E+00 ± 2.09E+01 3.72E+ Sr-90 121 1.52E+03 1.70E+03 ± 3.14E+01 5.16E+ I-129 34 <9.05E-01 5.39E-01 ± 9.28E-01 1.29E+ Cs-137 120 <2.43E+00 6.76E-01 ± 3.33E+00 5.74E+ U-232 34 <6.42E-02 7.47E-03 ± 1.59E-01 9.76E- U-233/234 34 1.73E-01 1.97E-01 ± 1.36E-01 9.27E- U-235/236 34 <4.20E-02 2.54E-02 ± 5.77E-02 8.82E- U-238 34 1.01E-01 1.21E-01 ± 1.07E-01 7.21E- Pu-238 34 <3.11E-02 1.20E-02 ± 9.54E-02 1.50E- Pu-239/240 34 <2.90E-02 1.48E-02 ± 6.65E-02 1.44E- Am-241 34 <3.42E-02 2.86E-02 ± 9.57E-02 1.79E-
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-30 Table B-13. Summary of Radionuclide Results from Routine Onsite Surface Water Monitoring Locations 

WMA Monitoring Point Constituent N Median (pCi/L)(2) Average (pCi/L) Maxim

(pCi/L

Result ± Uncertainty 

WMA 5 WNSW74A Gross alpha 450 <2.17E+00 3.88E-02 ± 3.09E+00 7.89E+ North Gross beta 450 1.17E+01 1.21E+01 ± 4.34E+00 4.24E+ Swamp H-3 450 <8.18E+01 -2.14E+00 ± 8.07E+01 2.80E+ Drainage C-14 34 <1.40E+01 -7.72E-01 ± 1.94E+01 1.50E+ Sr-90 120 5.52E+00 5.46E+00 ± 1.89E+00 1.25E+ I-129 34 <7.10E-01 2.09E-01 ± 7.37E-01 1.31E+ Cs-137 120 <7.08E+00 1.20E+00 ± 8.85E+00 1.18E+ U-232 34 <4.83E-02 8.38E-03 ± 6.79E-02 6.22E- U-233/234 34 1.54E-01 1.64E-01 ± 8.44E-02 3.54E- U-235/236 34 <3.70E-02 1.89E-02 ± 3.99E-02 1.38E- U-238 34 1.01E-01 1.04E-01 ± 6.65E-02 2.00E- Pu-238 34 <2.10E-02 1.43E-02 ± 3.36E-02 1.16E- Pu-239/240 34 <2.39E-02 4.73E-03 ± 2.73E-02 <6.94E Am-241 34 <2.81E-02 1.68E-02 ± 3.17E-01 8.63E-WMA 6 WNSP007 Gross alpha 324 <2.62E+00 1.37E-01 ± 3.32E+00 4.80E+ Sanitary Gross beta 324 1.45E+01 1.53E+01 ± 5.02E+00 4.05E+ Waste H-3 324 <8.25E+01 2.26E+01 ± 8.18E+01 1.53E+ Discharge Sr-90 14 3.11E+00 3.38E+00 ± 1.75E+00 1.17E+ Cs-137 35 <2.92E+00 8.12E-01 ± 3.94E+00 4.44E+ WNCOOLW Gross alpha 73 <1.91E+00 5.65E-01 ± 2.03E+00 5.81E+ Cooling Gross beta 73 6.83E+00 9.05E+00 ± 3.64E+00 3.43E+ Tower Water H-3 73 <8.17E+01 2.86E+00 ± 7.94E+01 4.27E+ Sr-90 10 1.60E+00 1.50E+00 ± 1.40E+00 4.68E+ Cs-137 31 <7.20E+00 8.61E-01 ± 8.32E+00 9.15E+
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-31 Table B-13. Summary of Radionuclide Results from Routine Onsite Surface Water Monitoring Locations 

WMA Monitoring Point Constituent N Median (pCi/L)(2) Average (pCi/L) Maxim

(pCi/L

Result ± Uncertainty 

WMA 12 WNSP006 Gross alpha 471 <1.50E+00 9.49E-01 ± 1.61E+00 1.07E+ Franks Creek Gross beta 471 3.53E+01 4.44E+01 ± 3.99E+00 1.94E+ at security H-3 471 <8.54E+01 1.36E+02 ± 8.33E+01 2.25E+ fence C-14 40 <1.85E+01 -1.31E+00 ± 2.09E+01 2.06E+ Sr-90 120 1.87E+01 1.98E+01 ± 2.99E+00 4.96E+ Tc-99 40 <2.09E+00 3.28E+00 ± 2.15E+00 5.24E+ I-129 40 <7.04E-01 3.26E-01 ± 7.25E-01 1.65E+ Cs-137 120 <8.02E+00 6.32E+00 ± 9.50E+00 7.33E+ U-232 40 3.17E-01 3.16E-01 ± 1.34E-01 7.51E- U-233/234 40 3.66E-01 3.73E-01 ± 1.31E-01 6.87E- U-235/236 40 <4.41E-02 3.26E-02 ± 4.61E-02 9.57E- U-238 40 2.54E-01 2.77E-01 ± 1.12E-01 7.43E- Pu-238 40 <3.36E-02 2.14E-02 ± 3.39E-02 1.36E- Pu-239/240 40 <2.79E-02 1.13E-02 ± 3.02E-02 6.62E- Am-241 40 <3.30E-02 3.23E-02 ± 3.69E-02 1.60E- WNSP005 Gross alpha 140 <2.71E+00 1.22E+00 ± 3.24E+00 1.85E+ Facility yard Gross beta 140 1.50E+02 1.63E+02 ± 9.11E+00 4.53E+ drainage H-3 140 <8.28E+01 3.78E+01 ± 8.23E+01 1.25E+ Sr-90 35 9.61E+01 1.02E+02 ± 6.52E+00 1.98E+ Cs-137 14 <1.91E+00 9.28E-01 ± 2.19E+00 <3.69E WNNDADR Gross alpha 130 <1.34E+00 8.22E-01 ± 1.40E+00 5.84E+ Drainage Gross beta 136 1.74E+02 1.83E+02 ± 6.45E+00 4.06E+ between NDA H-3 546 1.00E+03 1.16E+03 ± 1.02E+02 4.02E+ and SDA Sr-90 41 8.48E+01 8.40E+01 ± 5.45E+00 1.22E+ I-129 34 <8.12E-01 2.62E-01 ± 8.53E-01 1.15E+ Cs-137 120 <6.67E+00 5.99E-01 ± 8.48E+00 1.86E+
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-32 Table B-13. Summary of Radionuclide Results from Routine Onsite Surface Water Monitoring Locations 

WMA Monitoring Point Constituent N Median (pCi/L)(2) Average (pCi/L) Maxim

(pCi/L

Result ± Uncertainty 

 WMA 12 WNERB53 Gross alpha 401 <1.45E+00 1.56E-01 ± 1.65E+00 2.51E+

Erdman Brook Gross beta 401 1.73E+01 1.81E+01 ± 2.92E+00 4.37E+north of burial H-3 403 <8.31E+01 3.08E+01 ± 8.11E+01 3.46E+areas Sr-90 14 8.23E+00 8.04E+00 ± 1.98E+00 9.91E+ Cs-137 14 <2.07E+00 7.52E-01 ± 3.96E+00 2.41E+WNFRC67 Gross alpha 99 <7.00E-01 9.41E-02 ± 7.56E-01 3.89E+Franks Creek Gross beta 99 2.63E+00 2.56E+00 ± 1.50E+00 9.00E+east of burial H-3 99 <8.31E+01 3.08E+01 ± 8.11E+01 3.46E+areas Sr-90 19 <1.17E+00 5.00E-01 ± 1.09E+00 3.42E+ Cs-137 19 <2.13E+00 5.50E-01 ± 2.58E+00 2.26E+

NOTES: (1) Using the nonparametric Mann-Whitney “U” Test, the data set of surface water background results (summarized in Table B-6) was compare

of the above sampling locations. See Appendix B, Section 4.3. 

(2) 1 pCi/L = 3.7E-02 Bq/L 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-33 Table B-14. Summary of Radionuclide Results from Routine Onsite Groundwater Monitoring Locations(1)

WMA Monitoring Point(2) Constituent N Median (pCi/L)(3) Average (pCi/L) Ma

(

Result ± Uncertainty 

WMA 1 WP-A Gross alpha 12 <3.56E-01 1.71E-01 ± 2.12E+00 1. S&G Gross beta 12 2.41E+01 3.09E+01 ± 4.55E+00 5. H-3 12 1.18E+04 1.12E+04 ± 6.24E+02 1.WMA 2 WNW0103 Gross alpha 40 <7.32E+00 1.06E+00 ± 1.01E+01 1. S&G Gross beta 40 1.45E+02 1.85E+02 ± 1.93E+01 5. H-3 40 <8.42E+01 5.19E+01 ± 8.12E+01 2. WNW0104 Gross alpha 40 <3.86E+00 2.23E-01 ± 5.95E+00 5. S&G Gross beta 40 5.88E+04 5.63E+04 ± 1.64E+03 1. H-3 40 3.73E+02 3.91E+02 ± 8.65E+01 7. WNW0105 Gross alpha 41 <4.21E+00 1.04E+00 ± 7.17E+00 4. S&G Gross beta 41 3.88E+04 3.30E+04 ± 1.54E+03 1. H-3 40 3.57E+02 3.72E+02 ± 9.12E+01 7. WNW0106 Gross alpha 40 <2.50E+00 1.94E+00 ± 3.44E+00 1. S&G Gross beta 40 1.64E+01 8.22E+01 ± 7.99E+00 5. H-3 40 9.56E+02 1.04E+03 ± 1.00E+02 1. WNW0107 Gross alpha 40 <1.85E+00 8.97E-01 ± 1.88E+00 5. ULT Gross beta 40 7.00E+00 8.23E+00 ± 2.63E+00 2. H-3 40 3.74E+02 4.78E+02 ± 9.04E+01 9. WNW0108 Gross alpha 40 1.64E+00 1.47E+00 ± 1.46E+00 4. ULT Gross beta 40 2.49E+00 2.42E+00 ± 1.90E+00 5. H-3 40 1.17E+02 1.10E+02 ± 8.38E+01 2. WNW0110 Gross alpha 40 <1.49E+00 1.01E+00 ± 1.61E+00 4. ULT Gross beta 40 2.32E+00 2.23E+00 ± 1.95E+00 7. H-3 40 1.31E+03 1.28E+03 ± 1.08E+02 1. WNW0111 Gross alpha 40 <4.38E+00 3.15E+00 ± 5.06E+00 1. S&G Gross beta 40 5.55E+03 5.87E+03 ± 1.40E+02 1. H-3 40 1.97E+02 2.34E+02 ± 8.39E+01 7.
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-34 Table B-14. Summary of Radionuclide Results from Routine Onsite Groundwater Monitoring Locations(1)

WMA Monitoring Point(2) Constituent N Median (pCi/L)(3) Average (pCi/L) Ma

(

Result ± Uncertainty 

WMA 2 WNW0116 Gross alpha 40 <3.08E+00 8.94E-01 ± 4.35E+00 7. S&G Gross beta 40 8.69E+02 1.98E+03 ± 1.55E+02 9. H-3 40 1.67E+02 1.88E+02 ± 8.24E+01 4. WNW0205 Gross alpha 35 <4.87E+00 4.37E-01 ± 7.67E+00 <2 S&G Gross beta 35 1.61E+01 1.66E+01 ± 8.39E+00 4. H-3 35 <8.14E+01 9.44E+00 ± 8.02E+01 2. WNW0206 Gross alpha 35 <2.47E+00 6.69E-01 ± 3.33E+00 5. LTS Gross beta 35 <3.16E+00 1.95E+00 ± 3.53E+00 6. H-3 35 <8.18E+01 2.94E+01 ± 7.96E+01 2. WNW0408 Gross alpha 40 <3.58E+00 -7.91E+00 ± 9.05E+00 6. S&G Gross beta 39 3.96E+05 4.01E+05 ± 3.04E+03 6. H-3 40 1.52E+02 1.86E+02 ± 1.13E+02 2. C-14 10 <2.16E+01 -7.20E-01 ± 2.27E+01 <3 Sr-90 10 1.54E+05 1.54E+05 ± 1.73E+02 2. Tc-99 10 1.57E+01 1.70E+01 ± 3.28E+00 2. I-129 10 <9.94E-01 7.65E-02 ± 2.53E+00 9. Cs-137 10 <4.01E+00 -3.24E-01 ± 4.29E+00 <6 U-232 10 <6.32E-02 6.31E-02 ± 2.04E-01 5. U-233/234 10 4.51E-01 5.34E-01 ± 2.22E-01 1. U-235/236 10 <5.44E-02 8.34E-02 ± 9.98E-02 3. U-238 10 2.87E-01 3.11E-01 ± 1.57E-01 4. Pu-238 2 <6.83E-02 2.09E-02 ± 7.45E-02 <9 Pu-239/240 2 <6.56E-02 7.70E-03 ± 6.65E-02 <7 Am-241 2 4.60E-02 3.60E-02 ± 4.72E-02 5. WNW0501 Gross alpha 40 <4.79E+00 4.82E-01 ± 8.34E+00 6.
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-35 Table B-14. Summary of Radionuclide Results from Routine Onsite Groundwater Monitoring Locations(1)

WMA Monitoring Point(2) Constituent N Median (pCi/L)(3) Average (pCi/L) Ma

(

Result ± Uncertainty 

 WMA 2 S&G Gross beta 40 1.93E+05 1.91E+05 ± 2.61E+03 3. H-3 40 1.35E+02 1.25E+02 ± 8.37E+01 3. Sr-90 10 9.18E+04 9.33E+04 ± 2.43E+02 1. WNW0502 Gross alpha 40 <4.40E+00 7.94E-01 ± 8.04E+00 1. S&G Gross beta 40 1.68E+05 1.64E+05 ± 2.80E+03 2. H-3 40 1.33E+02 1.44E+02 ± 8.36E+01 4. Sr-90 10 8.36E+04 8.27E+04 ± 2.05E+02 1. WNW8603 Gross alpha 41 <5.02E+00 3.92E-01 ± 7.89E+00 9. S&G Gross beta 41 5.66E+04 4.81E+04 ± 1.20E+03 9. H-3 40 3.37E+02 3.43E+02 ± 8.79E+01 5. WNW8604 Gross alpha 35 <4.68E+00 1.07E+00 ± 7.83E+00 9. S&G Gross beta 35 4.12E+04 4.57E+04 ± 1.12E+03 1. H-3 35 3.48E+02 3.76E+02 ± 8.38E+01 6. WNW8605 Gross alpha 40 9.11E+00 8.46E+00 ± 7.66E+00 2. S&G Gross beta 40 1.09E+04 1.10E+04 ± 1.73E+02 1. H-3 40 3.70E+02 4.19E+02 ± 8.68E+01 1. WP-C Gross alpha 12 <3.95E-01 9.03E-01 ± 2.74E+00 <6 S&G Gross beta 12 2.44E+01 4.16E+01 ± 5.48E+00 1. H-3 12 4.91E+04 4.75E+04 ± 1.56E+03 6. WP-H Gross alpha 13 6.08E+00 7.90E+01 ± 2.33E+01 7. S&G Gross beta 13 6.97E+03 7.23E+03 ± 1.87E+02 1. H-3 13 2.99E+03 3.42E+03 ± 5.00E+02 7.WMA 3 WNW8609 Gross alpha 40 <3.10E+00 -3.75E-01 ± 5.55E+00 3. S&G Gross beta 40 1.51E+03 1.37E+03 ± 4.15E+01 2. H-3 40 4.51E+02 4.66E+02 ± 9.10E+01 7. Sr-90 20 7.99E+02 7.17E+02 ± 2.07E+01 1.WMA 4 WNW0801 Gross alpha 40 <3.85E+00 6.31E-02 ± 6.49E+00 5.
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-36 Table B-14. Summary of Radionuclide Results from Routine Onsite Groundwater Monitoring Locations(1)

WMA Monitoring Point(2) Constituent N Median (pCi/L)(3) Average (pCi/L) Ma

(

Result ± Uncertainty 

 WMA 4 S&G Gross beta 40 7.95E+03 8.59E+03 ± 2.72E+02 1. H-3 40 1.51E+02 1.64E+02 ± 8.24E+01 3. Sr-90 40 4.13E+03 4.33E+03 ± 4.73E+01 7. WNW0802 Gross alpha 40 <1.33E+00 1.05E+00 ± 2.03E+00 1. S&G Gross beta 40 9.94E+00 3.47E+01 ± 5.14E+00 2. H-3 40 <1.05E+02 9.00E+01 ± 8.00E+01 4. WNW0803 Gross alpha 40 <3.01E+00 9.79E-01 ± 3.38E+00 8. S&G Gross beta 40 1.48E+01 1.51E+01 ± 4.69E+00 2. H-3 40 1.84E+02 1.60E+02 ± 8.46E+01 3. WNW0804 Gross alpha 40 <2.04E+00 6.00E-01 ± 2.87E+00 6. S&G Gross beta 40 2.58E+02 2.86E+02 ± 1.07E+01 6. H-3 40 1.19E+02 1.14E+02 ± 7.98E+01 3. WNW8612 Gross alpha 40 <2.62E+00 3.33E-01 ± 3.34E+00 4. S&G Gross beta 41 <3.58E+00 1.57E+00 ± 3.60E+00 5. H-3 40 4.21E+02 4.33E+02 ± 8.88E+01 8.WMA 5 WNW0406 Gross alpha 40 <2.22E+00 1.54E-01 ± 2.58E+00 4. S&G Gross beta 40 7.44E+00 8.08E+00 ± 3.49E+00 1. H-3 40 1.17E+02 1.06E+02 ± 8.42E+01 4. C-14 10 <2.65E+01 -2.04E+00 ± 2.36E+01 2. Sr-90 10 1.92E+00 2.15E+00 ± 1.45E+00 4. Tc-99 11 2.19E+00 2.53E+00 ± 1.91E+00 8. I-129 10 <8.91E-01 3.48E-01 ± 9.17E-01 1. Cs-137 10 <6.41E+00 -9.30E-01 ± 7.35E+00 <1 U-232 10 <4.55E-02 2.47E-02 ± 1.24E-01 <3 U-233/234 10 1.37E-01 1.42E-01 ± 1.05E-01 2. U-235/236 10 <3.97E-02 2.32E-02 ± 5.51E-02 6. U-238 10 8.08E-02 8.87E-02 ± 8.17E-02 1.
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-37 Table B-14. Summary of Radionuclide Results from Routine Onsite Groundwater Monitoring Locations(1)

WMA Monitoring Point(2) Constituent N Median (pCi/L)(3) Average (pCi/L) Ma

(

Result ± Uncertainty 

 WMA 5 WNW0409 Gross alpha 40 <1.01E+00 9.39E-01 ± 9.94E-01 2. ULT Gross beta 40 2.56E+00 2.36E+00 ± 1.37E+00 4. H-3 40 <8.01E+01 -3.82E+00 ± 7.86E+01 2. WNW0602A Gross alpha 35 <1.37E+00 4.04E-01 ± 1.60E+00 2. S&G Gross beta 35 1.21E+01 1.32E+01 ± 2.87E+00 3. H-3 35 2.15E+02 2.18E+02 ± 8.88E+01 4. WNW0604 Gross alpha 41 <2.04E+00 3.35E-01 ± 2.45E+00 3. S&G Gross beta 41 6.06E+00 6.29E+00 ± 2.97E+00 1. H-3 40 <8.14E+01 1.99E+01 ± 8.01E+01 2. WNW0605 Gross alpha 35 <1.54E+00 4.40E-01 ± 1.59E+00 1. S&G Gross beta 35 4.83E+01 5.07E+01 ± 3.98E+00 8. H-3 35 <8.08E+01 1.59E+01 ± 7.86E+01 1. WNW0704 Gross alpha 40 <1.93E+00 1.75E-01 ± 2.25E+00 2. ULT/S&G Gross beta 40 8.05E+00 8.20E+00 ± 3.05E+00 1. H-3 40 <8.20E+01 -1.69E+01 ± 8.24E+01 2. WNW0707 Gross alpha 40 <1.15E+00 3.09E-01 ± 1.35E+00 4. ULT/S&G Gross beta 40 4.17E+00 4.16E+00 ± 1.98E+00 9. H-3 40 <8.22E+01 -1.89E+01 ± 8.11E+01 1. WNW1303 Gross alpha 19 <9.42E-01 1.19E+00 ± 2.06E+00 5. ULT Gross beta 19 2.17E+00 2.24E+00 ± 2.25E+00 9. H-3 19 <8.25E+01 -4.98E+01 ± 2.09E+02 1. WNW1304 Gross alpha 19 <6.14E+00 -8.58E-01 ± 8.32E+00 6. S&G Gross beta 19 <8.20E+00 4.92E+00 ± 8.11E+00 1. H-3 19 <9.44E+01 2.36E+01 ± 2.16E+02 1. C-14 18 <3.03E+01 2.02E+00 ± 2.92E+01 3. Sr-90 18 1.60E+00 1.93E+00 ± 1.28E+00 6. Tc-99 18 <1.94E+00 1.25E-01 ± 1.91E+00 2.
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-38 Table B-14. Summary of Radionuclide Results from Routine Onsite Groundwater Monitoring Locations(1)

WMA Monitoring Point(2) Constituent N Median (pCi/L)(3) Average (pCi/L) Ma

(

Result ± Uncertainty 

 WMA 5 I-129 18 <7.52E-01 3.39E-01 ± 1.33E+00 2. Cs-137 18 <2.77E+00 7.11E-01 ± 4.88E+00 2. U-232 18 <3.73E-02 -1.09E-02 ± 6.74E-02 <2 U-233/234 18 2.66E-01 2.93E-01 ± 1.26E-01 5. U-235/236 18 <4.07E-02 3.85E-02 ± 5.31E-02 1. U-238 18 1.91E-01 2.15E-01 ± 1.05E-01 5. WNW8607 Gross alpha 40 <2.36E+00 -7.83E-02 ± 4.40E+00 9. S&G Gross beta 40 2.57E+01 2.75E+01 ± 5.30E+00 7. H-3 40 <8.47E+01 1.97E+01 ± 8.30E+01 2.WMA 7 WNW0902 Gross alpha 20 1.46E+00 1.34E+00 ± 1.34E+00 5. KRS Gross beta 20 2.70E+00 2.76E+00 ± 1.64E+00 4. H-3 20 <8.08E+01 -3.35E+01 ± 8.18E+01 1. WNW0909 Gross alpha 26 <3.24E+00 1.16E+00 ± 3.83E+00 1. WLT Gross beta 34 3.74E+02 3.70E+02 ± 1.40E+01 6. H-3 30 8.23E+02 1.54E+03 ± 1.20E+02 3. C-14 10 <2.49E+01 7.23E+00 ± 2.39E+01 3. Sr-90 17 1.87E+02 1.83E+02 ± 8.33E+00 2. Tc-99 11 <1.86E+00 1.31E+00 ± 1.82E+00 5. I-129 11 6.21E+00 6.30E+00 ± 1.88E+00 9. Cs-137 10 <5.51E+00 1.09E+00 ± 6.42E+00 <1 U-232 12 <5.99E-02 6.37E-02 ± 1.62E-01 5. U-233/234 12 5.97E-01 7.42E-01 ± 2.40E-01 1. U-235/236 11 6.71E-02 7.66E-02 ± 7.65E-02 2. U-238 12 4.72E-01 5.44E-01 ± 1.97E-01 1.
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-39 Table B-14. Summary of Radionuclide Results from Routine Onsite Groundwater Monitoring Locations(1)

WMA Monitoring Point(2) Constituent N Median (pCi/L)(3) Average (pCi/L) Ma

(

Result ± Uncertainty 

 WMA 7 WNW0910 Gross alpha 25 <2.53E+00 1.88E+00 ± 2.29E+00 3. ULT Gross beta 25 3.80E+01 1.46E+02 ± 8.51E+00 1. H-3 24 <8.06E+01 -1.24E+01 ± 8.05E+01 2. WNNDATR Gross alpha 160 2.22E+00 2.08E+00 ± 2.11E+00 1. WLT Gross beta 166 1.45E+02 1.75E+02 ± 8.36E+00 5. H-3 164 3.65E+03 5.00E+03 ± 2.28E+02 1. C-14 20 <2.18E+01 3.02E-01 ± 2.39E+01 1. Sr-90 28 5.84E+01 7.85E+01 ± 5.55E+00 2. Tc-99 21 <1.94E+00 6.32E-01 ± 1.89E+00 5. I-129 41 <9.14E-01 8.44E-01 ± 9.35E-01 7. Cs-137 140 <6.80E+00 7.20E-01 ± 8.88E+00 1. U-232 21 <7.12E-02 5.11E-02 ± 1.18E-01 4. U-233/234 21 1.67E+00 1.51E+00 ± 2.81E-01 2. U-235/236 21 1.06E-01 1.35E-01 ± 9.47E-02 3. U-238 21 1.30E+00 1.22E+00 ± 2.50E-01 1. WNW8610 Gross alpha 20 <2.21E+00 6.60E-01 ± 2.88E+00 6. KRS Gross beta 20 4.41E+00 4.79E+00 ± 3.09E+00 9. H-3 20 <8.17E+01 -3.80E+01 ± 7.96E+01 1. WNW8611 Gross alpha 21 <1.98E+00 1.23E+00 ± 2.25E+00 4. KRS Gross beta 21 <2.71E+00 2.83E+00 ± 2.81E+00 1. H-3 20 <8.15E+01 -4.98E+01 ± 8.08E+01 8.WMA 9 WNW1005 Gross alpha 20 <2.49E+00 1.97E+00 ± 2.92E+00 4. WLT Gross beta 20 <3.52E+00 2.36E+00 ± 2.98E+00 5. H-3 20 <8.36E+01 1.24E+01 ± 8.14E+01 2.
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-40 Table B-14. Summary of Radionuclide Results from Routine Onsite Groundwater Monitoring Locations(1)

WMA Monitoring Point(2) Constituent N Median (pCi/L)(3) Average (pCi/L) Ma

(

Result ± Uncertainty 

 WMA 9 WNW1006 Gross alpha 20 <5.10E+00 4.24E+00 ± 5.50E+00 1. WLT Gross beta 20 <6.80E+00 4.58E+00 ± 5.68E+00 1. H-3 20 <8.20E+01 -1.81E+01 ± 8.24E+01 1.WMA 10 WNW0302 Gross alpha 36 <5.51E+00 8.24E-01 ± 9.02E+00 1. S&G Gross beta 36 <7.22E+00 4.13E+00 ± 8.13E+00 1. H-3 36 <8.23E+01 3.72E+01 ± 8.11E+01 1. WNW0402 Gross alpha 35 <5.13E+00 5.02E-01 ± 6.93E+00 7. S&G Gross beta 35 <5.64E+00 2.53E+00 ± 6.56E+00 8. H-3 35 <8.21E+01 2.73E+01 ± 8.05E+01 1. WNW0403 Gross alpha 35 <2.11E+00 3.85E-01 ± 2.45E+00 5. S&G Gross beta 35 5.76E+00 6.17E+00 ± 3.26E+00 1. H-3 35 <8.22E+01 2.20E+01 ± 7.97E+01 1. WNW1008B Gross alpha 20 <1.08E+00 7.09E-01 ± 1.12E+00 3. KRS Gross beta 20 2.68E+00 3.15E+00 ± 1.46E+00 9. H-3 20 <8.04E+01 -2.23E+01 ± 7.96E+01 7. WNW1008C Gross alpha 20 <1.51E+00 8.13E-02 ± 1.48E+00 <1 WLT Gross beta 20 <1.86E+00 1.15E+00 ± 2.00E+00 3. H-3 20 <8.15E+01 -1.06E+00 ± 8.10E+01 1. WNW1301 Gross alpha 1 <1.48E+01 1.43E+01 ± 1.48E+01 <1 ULT Gross beta 1 <1.02E+01 -1.04E+01 ± 1.02E+01 <1 H-3 1 <8.61E+02 -6.09E+02 ± 8.61E+02 <8 WNW1302 Gross alpha 19 <3.69E+00 1.00E+00 ± 5.69E+00 4. S&G Gross beta 19 <5.62E+00 2.76E+00 ± 6.44E+00 6. H-3 19 <9.37E+01 -4.07E+01 ± 2.05E+02 1.
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-41 Table B-14. Summary of Radionuclide Results from Routine Onsite Groundwater Monitoring Locations(1)

WMA Monitoring Point(2) Constituent N Median (pCi/L)(3) Average (pCi/L) Ma

(

Result ± Uncertainty 

WMA 12 WNW0903 Gross alpha 20 <1.90E+00 3.35E-01 ± 2.26E+00 4. KRS Gross beta 20 <2.42E+00 2.30E+00 ± 2.62E+00 9. H-3 20 <8.20E+01 -5.34E+01 ± 8.16E+01 1. WNW0906 Gross alpha 20 <1.78E+00 1.47E+00 ± 1.72E+00 4. WLT Gross beta 20 4.50E+00 4.92E+00 ± 2.22E+00 1. H-3 20 <8.43E+01 3.80E+00 ± 8.23E+01 1.

NOTES: (1) See Figure 4-12 in Section 4 of this plan for the locations of monitoring wells where concentrations exceed background. 

 (2) Geologic unit is indicated below each monitoring point. 

 (3) 1 pCi/L = 3.7E-02 Bq/L.  (4) Data sets for radiological constituents in groundwater were compared with data sets from background wells using the nonparametric Man

described in Appendix B, Section 4.3. 

LEGEND: S&G = Sand and Gravel; ULT = unweathered Lavery till; KRS = Kent Recessional Sequence; WLT = weathered Lavery till; LTS = Lavery till s
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-42 

Table B-15. Groundwater Monitoring Locations: Coordinates, Depth, Screened Interval, and Geologic Unit 

Monitoring 

Location(1)

North 

Coordinate(2)

East 

Coordinate(2)

Surface 

Elevation (ft) 

Well 

Construction 

Material 

Well 

Diameter 

(in) 

Depth to 

Screen Top 

(ft) 

Depth to 

Screen Bottom 

(ft) 

WNW0103 893013.68 1129469.99 1399.99 ST. STL. 2 6 21 WNW0104 893295.07 1129574.51 1399.29 ST. STL. 2 8 23 WNW0105 893536.70 1129768.63 1385.59 ST. STL. 2 13 28 WNW0106 893495.37 1129926.24 1383.73 ST. STL. 2 9.5 14.5 WNW0107 893399.05 1130060.32 1376.40 ST. STL. 2 8 28 WNW0108 893110.00 1129915.26 1381.66 ST. STL. 2 13 33 WNW0110 893024.67 1129881.74 1387.74 ST. STL. 2 13 33 WNW0111 892874.91 1129694.33 1392.54 ST. STL. 2 6 11 WNW0116 893518.81 1129560.10 1387.39 ST. STL. 2 6 11 WNW0204 892670.48 1129380.67 1406.83 ST. STL. 2 38 43 WNW0205 892696.37 1129528.87 1398.32 ST. STL. 2 6 11 WNW0206 892705.65 1129535.43 1398.39 ST. STL. 2 32.8 37.8 WNW0301 892593.20 1128914.31 1418.44 ST. STL. 2 6 16 WNW0302 892599.05 1128910.79 1418.46 ST. STL. 2 23 28 WNW0401 892708.28 1128864.51 1418.57 ST. STL. 2 6 16 WNW0402 892702.84 1128867.50 1419.34 ST. STL. 2 24 29 WNW0403 892865.78 1128790.38 1419.66 ST. STL. 2 8 13 WNW0405 893405.48 1128685.08 1408.56 ST. STL. 2 7.5 12.5 WNW0406 893250.04 1128992.47 1405.85 ST. STL. 2 11.8 16.8 WNW0408 893074.34 1129214.81 1405.56 ST. STL. 2 28 38 WNW0409 893256.53 1128988.16 1404.34 ST. STL. 2 44 54 WNW0501 893186.25 1129277.65 1402.18 ST. STL. 2 23 33 WNW0502 893325.38 1129406.73 1397.45 ST. STL. 2 8 18 WNW0602A 893403.75 1129244.07 1397.27 PVC 2 5 15 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-43 

Table B-15. Groundwater Monitoring Locations: Coordinates, Depth, Screened Interval, and Geologic Unit 

Monitoring 

Location(1)

North 

Coordinate(2)

East 

Coordinate(2)

Surface 

Elevation (ft) 

Well 

Construction 

Material 

Well 

Diameter 

(in) 

Depth to 

Screen Top 

(ft) 

Depth to 

Screen Bottom 

(ft) 

WNW0604 893576.30 1128926.84 1398.95 ST. STL. 2 6 11 WNW0605 893815.08 1129254.11 1383.90 ST. STL. 2 6 11 WNW0704 893763.67 1128814.82 1395.36 ST. STL. 2 5.5 15.5 WNW0706 893512.77 1128608.18 1409.03 ST. STL. 2 6 11 WNW0707 893896.47 1128617.53 1396.26 ST. STL. 2 6 11 WNW0801 893679.20 1129555.29 1383.51 ST. STL. 2 7.5 17.5 WNW0802 893904.53 1129687.61 1377.50 ST. STL. 2 6 11 WNW0803 893914.79 1129907.88 1370.17 ST. STL. 2 8 18 WNW0804 893751.72 1129982.56 1373.04 ST. STL. 2 4 9 WNW0901 891449.83 1129923.88 1392.72 ST. STL. 2 121 136 WNW0902 891671.96 1129774.24 1390.46 ST. STL. 2 118 128 WNW0903 892064.50 1129974.91 1380.69 ST. STL. 2 118 133 WNW0906 891945.99 1129796.90 1384.55 ST. STL. 2 5 10 WNW0908 891453.85 1129920.53 1392.94 ST. STL. 2 6 21 WNW0909 892085.66 1130121.37 1372.99 ST. STL. 2 8 23 WNW0910 892088.89 1130128.11 1372.69 PVC 2 25 30 WNW1005 890964.33 1130017.26 1389.68 ST. STL. 2 9 19 WNW1006 891264.17 1130206.69 1392.32 ST. STL. 2 10 20 WNW1008B 890904.46 1129534.09 1402.35 ST. STL. 2 46 51 WNW1008C 890914.13 1129545.20 1402.43 ST. STL. 2 8 18 WNW1301 893111.93 1128386.20 1429.49 PVC 2 20 30 WNW1302 893111.83 1128386.64 1429.47 PVC 2 5 8 WNW1303 893400.10 1128599.38 1414.65 PVC 2 23 38 WNW1304 893405.10 1128595.82 1414.36 PVC 2 6 10 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-44 

Table B-15. Groundwater Monitoring Locations: Coordinates, Depth, Screened Interval, and Geologic Unit 

Monitoring 

Location(1)

North 

Coordinate(2)

East 

Coordinate(2)

Surface 

Elevation (ft) 

Well 

Construction 

Material 

Well 

Diameter 

(in) 

Depth to 

Screen Top 

(ft) 

Depth to 

Screen Bottom 

(ft) 

WNW8603 893537.65 1129716.56 1385.45 PVC 4 8.25 23.25 WNW8604 893396.47 1129624.90 1390.41 PVC 4 6 21 WNW8605 892864.58 1129650.32 1393.19 PVC 4 5.5 10.5 WNW8607 893392.16 1128904.17 1405.03 PVC 4 11 16 WNW8609 893126.56 1129091.64 1407.07 PVC 4 12.7 22.7 WNW8610 891896.52 1130392.29 1376.88 STL. 2 97.33 112.33 WNW8611 892067.89 1130297.10 1376.34 STL. 2 103.5 118.5 WNW8612 893983.30 1130028.31 1367.76 PVC 4 6.6 16.6 WNWNB1S 892513.28 1128353.79 1447.08 ST. STL. 2 8 13 WNNDATR 892068.35 1130126.06 1374.89 CONCRETE 60 0 0 WP-A 892883.92 1129232.58 1408.34 IRON 2 29 33 WP-C 892986.95 1129411.57 1400.89 IRON 2 19 23 WP-H 892925.41 1129367.85 1405.38 IRON 2 13 17 NOTES: (1) Radiological data from the current monitoring locations, as listed in the 2008 Groundwater Monitoring Program, were evaluated for th

Monitoring point WNNDATR is an interceptor trench. 

 (2) Western New York State Planar Coordinate System LEGEND: STL = steel, ST.STL = stainless steel, PVC = polyvinyl chloride, S&G = sand and gravel, TBU = thick bedded unit, SWS = slack wate

ULT = unweathered Lavery till, LTS = Lavery till sand, KRS = Kent recessional sequence, WLT = weathered Lavery till. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-45 

Table B-16. Location, Elevation, and Depth of Geoprobe®

 Groundwater Sampling Points 

Location 

Code 

Year 

Sampled 

North 

Coordinate(1)

East 

Coordinate(1)

Surface 

Elevation 

(ft) 

Sample Depths (ft) and Geologic Units(2)

GP01 1994 893754.94 1129433.58 1375.00 04-06 

GP0197 1997 893527.20 1129733.08 1382.35 00-04, 04-08, 08-12, 12.5-14, 12-16, 16-20, 

17.5-19, 20-24, 22.5-24, 24-28 (ULT) 

GP02 1994 893701.98 1129480.46 1378.95 06-08 

GP0297 1997 893527.37 1129689.35 1383.08 00-04, 04-08, 08-12, 12.5-14, 12-16, 16-20, 

17.5-19, 20-24, 24-28. 25.5-27 

GP03 1994 893684.86 1129546.39 1380.07 08-10, 13-15 

GP0397 1997 893527.23 1129662.34 1383.08 00-04, 04-08, 08-12, 10.5-12, 12-16, 15.5-

17, 16-20, 20.5-22, 20-24, 24.5-26, 24-28, 

28-32 (ULT) 

GP04 1994 893587.10 1129609.73 1381.96 10-12 

GP0497 1997 893529.48 1129630.86 1383.10 08.5-10, 13.5-15, 18.5-20, 23-24.5 

GP05 1994 893556.85 1129746.34 1391.59 15-17, 20-22, 25-27 

GP0597 1997 893531.83 1129600.53 1383.51 08.5-10, 13.5-15 

GP06 1994 893523.31 1129743.01 1382.59 15-17, 20-22, 25-27 

GP0697 1997 893635.51 1129508.65 1381.39 08.5-10, 13.5-15, 17.5-19 

GP07 1994 893623.69 1129777.03 1378.60 07.5-09.5 

GP0797 1997 893633.61 1129535.22 1380.88 08.5-10, 13.5-15, 18.5-20 

GP08 1994 893485.68 1129640.70 1384.66 09-11, 14-16, 19-21 

GP0897 1997 893629.21 1129567.72 1380.15 08.5-10, 12.5-14.5, 17.5-18.5 

GP09 1994 893446.05 1129609.75 1385.81 09-11, 14-16, 19-21 

GP0997 1997 893630.01 1129599.46 1379.30 08.5-10, 13.5-15 

GP10 1994 893495.08 1129514.19 1386.41 09-11 

GP1097 1997 893628.00 1129624.69 1379.01 08.5-10, 13.5-15, 18.5-20 

GP11 1994 893514.96 1129468.64 1386.51 08-10 

GP1197 1997 893625.73 1129664.22 1378.57 08.5-10, 13.5-15, 17.5-19, 23.4-25 

GP12 1994 893594.08 1129526.20 1382.41 07-09 

GP1297 1997 893623.09 1129706.63 1378.15 00-04, 04-08, 07.5-09, 08-12, 12.5-14, 12-

16, 16-20, 17.5-19, 20-24, 22-23.5, 24-28 

(ULT) 

GP13 1994 893422.90 1129419.73 1390.67 10-12 

GP1397 1997 893621.53 1129744.33 1377.93 09-10.5, 13.5-15, 18.5-20 

GP13A 1994 893385.24 1129395.73 1392.97 11-13, 15-17, 16-18 

GP14 1994 893179.41 1129370.33 1399.11 15-17, 20-22, 25-27, 30-32 

GP1497 1997 893619.43 1129784.76 1378.09 00-04, 04-08, 08-09.5, 08-12, 12-16, 16-20 

(ULT) 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-46 

Table B-16. Location, Elevation, and Depth of Geoprobe®

 Groundwater Sampling Points 

Location 

Code 

Year 

Sampled 

North 

Coordinate(1)

East 

Coordinate(1)

Surface 

Elevation 

(ft) 

Sample Depths (ft) and Geologic Units(2)

GP15 1994 893222.77 1129158.76 1402.57 15-17 

GP1597 1997 893662.03 1129761.57 1376.85 08-10, 13-15, 18-20 

GP16 1994 893217.10 1129056.60 1402.66 15-17, 20-22 

GP1697 1997 893662.85 1129707.70 1377.19 08-10, 12-15, 18-20 

GP17 1994 893055.18 1129446.69 1399.01 12-14 

GP1797 1997 893733.87 1130014.29 1370.09 08-10, 13-15 

GP18 1994 892932.47 1129283.29 1404.16 18-20, 21.5-23.5 

GP1897 1997 893666.65 1129642.75 1387.08 08-10, 13-15, 17.5-19.5 

GP1898 1998 892929.53 1129281.76 1403.99 12-14, 16-19, 22-24 

GP1997 1997 893528.51 1129675.56 1383.27 00-04, 04-08, 08-12, 12-16, 14-16, 16-20, 

19-21, 20-22, 22-24, 24-26, 26-28, 28-30 

GP20 1994 893141.44 1129083.93 1403.07 15-17 

GP2097 1997 893529.48 1129645.74 1383.35 00-04, 04-08, 08-12, 12-14, 12-16, 16-20, 

17-19, 20-24, 22-24, 24-28 

GP2197 1997 893531.19 1129615.48 1383.43 00-04, 04-08, 08-12, 12-16, 13-15, 16-20, 

20-24, 23-25, 24-28 (ULT), 28-32 (ULT), 32-

36 (ULT) 

GP2297 1997 893462.46 1129692.02 1384.93 12-14, 17-19, 22-24 

GP23 1994 892960.50 1129165.19 1409.41 20-22, 22.5-24.5, 27-29, 32-34 

GP2397 1997 893512.71 1129715.96 1383.06 12-14, 16-19, 22-24 

GP2397 1998 892980.83 1129165.77 1408.96 17-19, 22-24, 25-29, 32-34 

GP24 1994 893006.32 1129151.08 1408.99 17-19, 22-24, 26-28, 30-32 

GP2497 1997 893506.39 1129771.02 1382.83 00-04, 04-08, 08-12, 12-16, 14-16, 16-20, 

19-21, 20-24, 24-26, 24-28, 28-30, 30-32 

(ULT) 

GP2597 1997 893804.22 1129989.94 1368.40 08-10 

GP26 1994 892992.21 1129084.84 1409.63 17-19 

GP2697 1997 893671.61 1129961.64 1375.36 04.5-06.5, 09-11, 14-16 

GP27 1994 892960.10 1129096.04 1408.86 16-18, 21-23, 26-28 

GP2797 1997 893576.18 1129713.16 1381.18 12-14, 16-19, 22-24 

GP28 1994 892855.87 1129220.94 1408.08 16-18, 21-23, 26-28, 31-33 

GP2897 1997 893579.60 1129663.78 1381.44 12-14, 16-19, 22-24 

GP29 1994 892783.34 1129163.61 1410.01 15-17, 21-23, 27-29, 33-35 

GP2997 1997 893583.58 1129622.59 1381.56 12-14 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-47 

Table B-16. Location, Elevation, and Depth of Geoprobe®

 Groundwater Sampling Points 

Location 

Code 

Year 

Sampled 

North 

Coordinate(1)

East 

Coordinate(1)

Surface 

Elevation 

(ft) 

Sample Depths (ft) and Geologic Units(2)

GP2998 1998 892781.53 1129163.00 1409.81 17-19, 19-21, 21-23, 22-24, 23-25, 25-27, 

27-29, 29-31, 31-33, 33-35, 34-36, 35-37, 

37-38 (ULT), 38-39 (ULT), 39-40 (ULT), 40-

41 (ULT) 

GP2908 2008 892784.10 1129167.91 1410.50 17-19, 29-31, 35-37 

GP30 1994 892835.65 1129144.49 1409.32 18-20, 22-24, 27-29, 32-34 

GP3098 1998 892829.94 1129141.96 1409.18 18-20, 20-22, 22-24, 23-27, 23-37, 24-26, 

26-28, 28-30, 30-32, 32-34, 34-36, 36-36.5, 

36.5-37 (ULT), 37-37.5 (ULT), 37.5-38 

(ULT), 38-38.5 (ULT), 38.5-39 (ULT), 39-

39.5 (ULT), 39.5-40 (ULT) 

GP3008 2008 892837.12 1129147.27 1409.83 20-22, 28-30, 35-37 

GP31 1994 893269.27 1129335.71 1396.59 12-14, 17-19 

GP32 1994 893827.03 1129487.70 1372.83 05-07 

GP32A 1994 893831.75 1129475.59 1372.45 05-07 

GP33 1994 893813.09 1129337.41 1375.73 05-07 

GP33A 1994 893819.60 1129347.72 1375.24 05-07 

GP35 1994 893858.20 1129143.23 1384.48 04-06 

GP36 1994 893815.85 1128971.59 1387.17 03.5-05.5 

GP37 1994 893720.92 1128930.11 1389.11 05-07 

GP38 1994 893594.09 1128959.27 1392.71 06.5-08.5 

GP39 1994 893498.24 1128979.05 1396.44 06-08, 10-12 

GP40 1994 893459.75 1129103.74 1394.08 08-10, 13-15 

GP41 1994 893388.58 1129138.49 1396.59 14-16 

GP42 1994 893362.12 1129180.49 1395.96 11-13 

GP43 1994 893334.39 1129257.32 1396.17 12-14 

GP44 1994 893003.49 1129551.08 1393.29 09-11, 14-16 

GP45 1994 892995.79 1129523.66 1394.34 10-12, 15-17, 18.5-20.5 

GP46 1994 892968.45 1129466.90 1397.24 12-14, 17-19 

GP47 1994 892969.21 1129522.40 1394.24 11-13, 16-18 

GP48 1994 892924.74 1129842.93 1386.88 07-09 

GP50 1994 892833.51 1129852.05 1384.55 08-10 

GP51 1994 893825.87 1129561.74 1374.48 06.5-08.5 

GP52 1994 893859.57 1129634.30 1374.21 08-10 

GP53 1994 893278.77 1128978.62 1401.62 14-16 

GP56 1994 892704.20 1129025.11 1410.49 06-08, 15.5-17.5 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-48 

Table B-16. Location, Elevation, and Depth of Geoprobe®

 Groundwater Sampling Points 

Location 

Code 

Year 

Sampled 

North 

Coordinate(1)

East 

Coordinate(1)

Surface 

Elevation 

(ft) 

Sample Depths (ft) and Geologic Units(2)

GP59 1994 892859.54 1129363.33 1399.83 09-11, 17-19 

GP60 1994 892870.18 1129409.83 1400.01 12-14, 17-19 

GP61 1994 893875.01 1129563.26 1372.91 06-08 

GP62 1994 893933.30 1129567.59 1371.20 04-06 

GP64 1994 893781.92 1129295.55 1379.81 09-11 

GP66 1994 893125.94 1129318.33 1403.62 17-19, 22-24, 26-28, 30-32 

GP67 1994 893186.02 1129410.00 1399.12 15-17, 20-22, 25-27, 30-32 

GP68 1994 893199.21 1129449.59 1398.42 15-17, 20-22, 25-27, 30-32 

GP69 1994 892721.81 1129189.75 1410.10 19-21, 29-31, 34-36 

GP70 1994 892815.80 1129223.19 1409.19 16-18, 21-23, 26-28 

GP71 1994 892845.53 1129242.84 1406.51 16-18, 21-23, 25-27 

GP72 1994 892873.33 1129179.42 1409.41 16-18, 21-23, 20-32 

GP7298 1998 892873.12 1129178.71 1409.17 17-19, 19-21, 21-23, 22-24, 23-25, 25-27, 

27-29, 29-31, 31-33, 32-34, 33-35, 35-37, 

37-39 (ULT), 39-41 (ULT) 

GP7208 2008 892871.89 1129180.55 1410.07 20-22, 25-27, 31-33, 38-40 

GP73 1994 892908.21 1129176.59 1410.51 21-23, 26-28, 30-32 

GP7398 1998 892899.43 1129186.81 1410.00 18-20, 20-22, 22-24, 24-26, 25-27, 26-28, 

28-30, 30-32, 32-34, 34-36, 35-37, 36-38, 

38-40, 40.5-41 (ULT), 40-45.5 (ULT), 41.5-

42 (ULT), 41-41.5 (ULT) 

GP74 1994 892906.72 1129072.17 1409.69 18-20, 23-25, 28-30 

GP75 1994 892804.03 1129071.55 1410.49 19-21, 23-25, 27-29 

GP76 1994 892829.00 1129049.17 1414.49 19-21, 23-25, 27-29 

GP7608 2008 892824.00 1129049.00 1415.00 20-22, 34-36 

GP77 1994 892748.07 1129075.00 1414.49 19-21, 19-23, 27-29, 31-33 

GP78 1994 892841.92 1129109.44 1414.48 19-21, 19-23, 23-25, 27-29, 31-33 

GP7898 1998 892831.03 1129127.81 1409.70 19-21, 20-22, 21-23, 23-25, 24-27, 25-27, 

27-29, 29-31, 30-32, 31-33, 33-35, 35-37 

GP7808 2008 892843.00 1129107.00 1410.21 20-22, 28-30, 34-36 

GP79 1994 892757.54 1129099.11 1414.49 21-23, 25-27, 29-31 

GP80 1994 892809.20 1129126.66 1414.48 25-27, 30-32, 34-39, 35-35, 35-37 

GP8098 1998 892792.03 1129125.21 1414.28 22-24, 24-26, 26-28, 27-29, 28-30, 30-32, 

32-34, 34-36, 36-38, 38-40, 40-42 (ULT) 

GP8008 2008 892812.00 1129141.00 1415.00 25-27, 32-34, 39-41 

GP8198 1998 893048.83 1129217.96 1403.98 15-17, 20-22, 25-27, 30-32, 35-37 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-49 

Table B-16. Location, Elevation, and Depth of Geoprobe®

 Groundwater Sampling Points 

Location 

Code 

Year 

Sampled 

North 

Coordinate(1)

East 

Coordinate(1)

Surface 

Elevation 

(ft) 

Sample Depths (ft) and Geologic Units(2)

GP8298 1998 892996.19 1129315.09 1402.13 12-14, 17-19, 20-24 

GP8398 1998 892982.69 1129187.54 1407.43 17-19, 19-21, 20-22, 21-23, 23-25, 25-27, 

27-29, 29-31, 31-33, 32-34, 33-35, 35-37 

GP8308 2008 892980.71 1129181.86 1409.79 22-24, 30-32, 38-40 

GP8698 1998 892845.57 1129161.24 1409.02 18-20, 20-22, 22-24, 24-26, 24-27, 26-28, 

28-30, 30-32, 32-34, 34-36, 35-37, 36-38, 

38-39, 39-39.5, 39.5-40 (ULT), 40-40.5 

(ULT), 40.5-41 (ULT), 41-41.5 (ULT), 41.5-

42 (ULT) 

GP8798 1998 892813.15 1129225.60 1408.43 15-17, 20-22, 25-27, 28-32 

GP8898 1998 893533.28 1129528.60 1384.14 07-09, 12-14 

GP8998 1998 893722.00 1129516.58 1379.09 06-08, 11-13, 16-18 

GP9098 1998 893826.72 1129596.32 1373.46 03-05, 08-10 

GP9198 1998 893875.44 1129596.20 1372.82 03-05 

GP9298 1998 893811.26 1129533.79 1373.71 04-06, 09-11, 14-16, 18.5-21 

GP9398 1998 893821.48 1129568.33 1372.62 04-06, 09-11, 14-16 

GP9498 1998 893874.66 1129532.98 1372.01 03-05, 08-10, 12-15 

GP10008 2008 892805.00 1129048.00 1415.00 20-22, 35-37 

GP10108 2008 892924.08 1129094.92 1410.30 21-23, 28-30 

GP10208 2008 892838.12 1129224.43 1409.11 27-29 

GP10308 2008 892977.38 1129140.72 1410.53 21-23, 30-32, 35-37 

GP10408 2008 892953.72 1129241.54 1405.91 21-23 

GP10508 2008 893026.27 1129223.72 1405.04 16-18, 28-30, 34-36 

GP10608 2008 893026.76 1129312.67 1403.39 16-18, 20-22, 28-30 

GP10708 2008 893119.33 1129306.52 1403.80 15-17, 22-24, 30-32 

GP10908 2008 893138.89 1129224.21 1402.60 14-16, 28-30, 34-36 

NOTES: (1) Western New York State Planar Coordinate System 

 (2) All screened intervals were within the Sand and Gravel (S&G) unit except for those from the Unweathered 

Lavery Till unit, designated as "ULT." 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-50 

Table B-17. Groundwater Points Excluded from the Evaluation(1)

Sampling 

Location 

North 

Coordinate (2)

East 

Coordinate 

(2)

Surface 

Elevation (ft) 

Elevation at 

Top of 

Screened 

Interval (ft) 

Elevation at 

Bottom of 

Screened 

Interval (ft) 

Geologic 

Unit of 

Screened 

Interval 

NDA WP-A 892047.61 1130117.37 1375.47 1355.27 1348.77 ULT 

NDA WP-B 892045.71 1130112.17 1375.45 1360.25 1357.75 WLT 

NDA WP-C 892006.26 1130115.39 1378.47 1367.67 1362.17 WLT 

NP0101 893602.56 1129427.10 1386.10 1379.60 1374.60 S&G 

NP0102 893577.38 1129428.82 1389.40 1381.90 1376.90 S&G 

NP0103 893586.49 1129466.86 1385.10 1376.60 1371.60 S&G 

NP0104 893621.36 1129460.64 1384.10 1379.60 1369.60 S&G 

NP0105 893528.03 1129853.06 1382.50 1374.50 1359.50 S&G 

NP0106 893598.16 1129779.73 1380.70 1369.70 1364.70 S&G 

NP0107 893542.52 1129601.69 1384.10 1375.60 1370.60 S&G 

NP0108 893518.32 1129601.99 1385.30 1376.30 1371.30 S&G 

NP0109 893543.29 1129552.36 1384.30 1376.30 1369.30 S&G 

NP0110 893573.10 1129628.57 1383.50 1373.50 1370.50 S&G 

NP0111 893609.48 1129621.28 1381.40 1366.40 1363.40 S&G 

NP0112 893605.26 1129622.72 1381.50 1373.50 1368.50 S&G 

NP0113 893578.74 1129574.71 1383.00 1373.00 1368.00 S&G 

NP0114 893564.04 1129564.66 1383.50 1375.50 1370.50 S&G 

NP0115 893484.80 1129685.67 1385.60 1366.60 1359.60 S&G 

NP0116 893490.96 1129688.62 1385.30 1373.80 1368.80 S&G 

NP0117 893446.35 1129634.45 1386.40 1368.40 1363.40 S&G 

NP0118 893439.47 1129630.61 1386.60 1375.60 1370.60 S&G 

NP0119 893526.14 1129664.12 1385.10 1364.10 1359.10 S&G 

NP0120 893526.24 1129655.74 1385.30 1371.30 1366.30 S&G 

NP0121 893518.59 1129668.60 1384.60 1373.60 1358.60 S&G 

NP0122 893512.26 1129663.29 1384.60 1377.60 1362.60 S&G 

NP0123 893513.46 1129649.40 1384.90 1370.90 1365.90 S&G 

NP0124 893512.56 1129653.52 1384.70 1365.70 1360.70 S&G 

NP0125 893518.72 1129631.75 1384.60 1377.60 1362.60 S&G 

NP0126 893513.83 1129634.52 1384.70 1377.70 1362.70 S&G 

NP0127 893561.96 1129508.64 1386.10 1379.60 1369.60 S&G 

NP0128 893611.18 1129516.76 1382.80 1375.80 1365.80 S&G 

NP0129 893585.08 1129529.17 1383.40 1376.40 1366.40 S&G 

NP0130 893629.71 1129576.60 1381.00 1374.00 1364.00 S&G 

NP0131 893535.80 1129735.81 1383.00 1366.00 1356.00 S&G 

NP0132 893556.54 1129690.68 1383.70 1364.70 1360.70 S&G 

NP0133 893616.82 1129670.92 1379.90 1364.90 1354.90 S&G 

PTWRP 893516.03 1129663.87 1384.88 1380.88 1360.88 S&G 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-51 

Table B-17. Groundwater Points Excluded from the Evaluation(1)

Sampling 

Location 

North 

Coordinate (2)

East 

Coordinate 

(2)

Surface 

Elevation (ft) 

Elevation at 

Top of 

Screened 

Interval (ft) 

Elevation at 

Bottom of 

Screened 

Interval (ft) 

Geologic 

Unit of 

Screened 

Interval 

PZ01 893501.64 1129644.29 1385.10 1378.10 1363.10 S&G 

PZ02 893502.55 1129658.76 1385.10 1378.10 1363.10 S&G 

PZ03 893509.15 1129639.29 1384.60 1377.60 1362.60 S&G 

PZ04 893508.56 1129664.33 1384.70 1377.70 1362.70 S&G 

PZ05 893519.11 1129676.77 1384.40 1377.40 1362.40 S&G 

PZ06 893538.60 1129638.19 1384.30 1377.30 1362.30 S&G 

PZ07 893537.58 1129663.80 1384.00 1377.00 1362.00 S&G 

PZ08 893516.74 1129643.87 1385.40 1368.40 1365.40 S&G 

PZ09 893516.34 1129651.79 1385.40 1367.90 1365.40 S&G 

PZ10 893521.60 1129632.18 1384.60 1375.60 1372.60 S&G 

RW01 893556.21 1129506.87 1384.43 1379.43 1369.43 S&G 

RW02 893559.26 1129478.22 1384.38 1380.38 1370.38 S&G 

RW03 893565.07 1129493.51 1385.28 1380.28 1370.28 S&G 

WNGSEEP 893765.77 1130322.30 1356.89 NA NA S&G 

WNGSP04 893866.63 1130309.52 NA NA NA S&G 

WNGSP06 893960.73 1130283.50 NA NA NA S&G 

WNGSP11 894065.05 1130090.45 NA NA NA S&G 

WNGSP12 894171.90 1130050.85 NA NA NA S&G 

WNNDATR 892068.35 1130126.06 1372.49 NA NA WLT 

WNSE007 893850.15 1129578.86 1371.11 NA NA S&G 

WNSE008 893791.04 1130002.44 1368.52 NA NA S&G 

WNSE009 893683.63 1129699.74 1378.11 NA NA S&G 

WNSE011 893838.93 1129534.25 1373.08 NA NA S&G 

WNW0109 892972.05 1129830.09 1386.84 1373.84 1353.84 ULT 

WNW0114 893452.77 1129988.66 1377.01 1368.01 1348.01 ULT 

WNW0115 893525.49 1129564.84 1384.19 1366.19 1356.19 ULT 

WNW0201 892419.73 1129383.16 1408.19 1398.19 1388.19 S&G 

WNW0202 892407.19 1129390.47 1407.95 1374.95 1369.95 LTS 

WNW0203 892670.42 1129376.09 1404.62 1396.62 1386.62 S&G 

WNW0207 892503.34 1129677.53 1396.11 1390.11 1385.11 S&G 

WNW0208 892488.90 1129674.25 1396.26 1378.26 1373.26 LTS 

WNW0305 892630.33 1129176.24 1410.38 1394.38 1379.38 S&G 

WNW0306 892633.70 1129174.87 1410.32 1344.32 1329.32 KRS 

WNW0307 892634.87 1129177.55 1410.53 1404.53 1394.53 S&G 

WNW0404 892871.77 1128786.30 1416.69 1390.19 1380.19 S&G 

WNW0407 893250.92 1128996.78 1402.40 1336.90 1326.90 ULT 

WNW0410 892868.61 1128789.26 1416.64 1348.64 1338.64 KRS 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-52 

Table B-17. Groundwater Points Excluded from the Evaluation(1)

Sampling 

Location 

North 

Coordinate (2)

East 

Coordinate 

(2)

Surface 

Elevation (ft) 

Elevation at 

Top of 

Screened 

Interval (ft) 

Elevation at 

Bottom of 

Screened 

Interval (ft) 

Geologic 

Unit of 

Screened 

Interval 

WNW0411 892694.15 1128869.23 1416.27 1370.27 1350.27 KRS 

WNW0601 893810.70 1129256.11 1381.14 1377.14 1375.14 S&G 

WNW0603 893519.08 1128736.33 1401.14 1393.14 1388.14 S&G 

WNW0701 893501.78 1128611.97 1406.52 1383.52 1378.52 ULT 

WNW0702 893775.67 1128516.08 1397.68 1369.68 1359.68 ULT 

WNW0703 893887.50 1128622.76 1393.12 1382.12 1372.12 ULT 

WNW0705 893779.24 1128509.78 1397.87 1391.87 1376.87 ULT 

WNW0904 892066.15 1129984.19 1377.95 1361.95 1351.95 ULT 

WNW0905 892131.67 1130069.18 1373.56 1355.56 1350.56 S&G 

WNW0907 891901.62 1129774.48 1382.27 1376.27 1366.27 WLT 

WNW1001 890969.42 1130010.26 1387.55 1281.55 1271.55 KRS 

WNW1002 891267.67 1130208.43 1389.76 1291.76 1276.76 KRS 

WNW1003 891303.20 1130437.01 1387.65 1259.65 1249.65 KRS 

WNW1004 891085.15 1130459.09 1383.89 1290.89 1275.89 KRS 

WNW1007 891306.41 1130433.26 1387.55 1374.55 1364.55 WLT 

WNW1101A 891062.41 1130830.41 1379.37 1373.37 1363.37 WLT 

WNW1101B 891060.33 1130826.90 1379.42 1359.42 1349.42 ULT 

WNW1101C 891058.61 1130823.07 1379.13 1285.13 1270.13 KRS 

WNW1102A 891508.74 1131146.27 1382.71 1375.71 1365.71 WLT 

WNW1102B 891514.11 1131142.06 1382.59 1361.59 1351.59 ULT 

WNW1103A 891925.14 1130822.28 1379.90 1373.90 1363.90 WLT 

WNW1103B 891929.54 1130818.73 1379.83 1358.83 1343.83 ULT 

WNW1103C 891934.64 1130815.86 1379.51 1273.51 1258.51 KRS 

WNW1104A 892289.10 1130545.05 1376.12 1372.12 1357.12 WLT 

WNW1104B 892285.42 1130549.21 1376.10 1355.10 1340.10 ULT 

WNW1104C 892282.05 1130553.29 1375.96 1261.96 1251.96 KRS 

WNW1105A 892608.51 1130294.17 1365.80 1354.80 1344.80 ULT 

WNW1105B 892608.20 1130289.77 1366.01 1345.01 1330.01 ULT 

WNW1106A 891960.87 1130374.92 1374.36 1368.36 1358.36 WLT 

WNW1106B 891964.09 1130372.02 1374.32 1353.62 1343.62 ULT 

WNW1107A 892368.58 1130256.16 1377.16 1373.16 1358.16 WLT 

WNW1108A 891312.43 1130600.10 1380.93 1374.93 1364.93 WLT 

WNW1109A 891929.92 1130329.31 1374.86 1368.86 1358.86 WLT 

WNW1109B 891934.27 1130326.01 1374.02 1358.02 1343.02 ULT 

WNW1110A 892100.29 1130691.11 1377.05 1367.05 1357.05 WLT 

WNW1111A 891654.21 1131042.28 1380.22 1369.22 1359.22 ULT 

WNW80-4 893687.98 1129428.98 1386.55 1373.98 1368.98 S&G 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-53 

Table B-17. Groundwater Points Excluded from the Evaluation(1)

Sampling 

Location 

North 

Coordinate (2)

East 

Coordinate 

(2)

Surface 

Elevation (ft) 

Elevation at 

Top of 

Screened 

Interval (ft) 

Elevation at 

Bottom of 

Screened 

Interval (ft) 

Geologic 

Unit of 

Screened 

Interval 

WNW834D 893670.95 1129435.35 1380.48 1256.18 1249.98 KRS 

WNW834E 893670.95 1129435.35 1381.64 NA NA BR 

WNW8606 892694.89 1129523.46 1396.49 1390.89 1385.89 S&G 

WNW8608 893250.67 1128985.62 1401.59 1394.59 1384.59 S&G 

WNW90I7 891913.54 1130323.78 NA NA NA WLT 

WNW96I1 891991.27 1130117.11 1379.89 1374.89 1369.89 WLT 

WNW96I2 891915.18 1130305.03 1380.41 1374.91 1369.91 WLT 

WNW96I3 891898.75 1129901.48 1380.32 1372.32 1367.32 WLT 

WNW96I4 891872.40 1129910.29 1381.36 1374.36 1369.36 WLT 

WNWEW-1 893578.98 1129453.22 1384.91 1379.91 1371.91 S&G 

WNWEW-4 893546.14 1129515.19 1384.17 1380.17 1368.17 S&G 

WNWWP-4 893486.96 1129473.70 1387.63 1379.63 1377.63 S&G 

WP01 893485.51 1129520.87 1386.57 1378.57 1376.57 S&G 

WP02 893566.19 1129521.75 1383.10 1376.10 1373.10 S&G 

WP03 893513.64 1129490.62 1385.88 1377.88 1375.88 S&G 

WP05 893584.51 1129490.37 1383.91 1376.91 1373.91 S&G 

WP06 893548.40 1129479.09 1384.94 1377.94 1374.94 S&G 

WP07 893520.93 1129467.36 1386.08 1378.08 1376.08 S&G 

WP08 893500.03 1129447.32 1387.34 1379.34 1377.34 S&G 

WP09 893591.43 1129438.20 1384.81 1377.81 1374.81 S&G 

WP10 893533.21 1129414.87 1390.47 1383.47 1380.47 S&G 

WP11 893537.89 1129741.98 1382.08 1370.08 1367.08 S&G 

WP12 893552.47 1129785.92 1381.68 1369.68 1366.68 S&G 

WP13 893603.74 1129840.46 1379.78 1367.78 1364.78 S&G 

WP14 893561.33 1129744.79 1381.38 1369.38 1366.38 S&G 

WP15 893530.52 1129536.70 1384.08 1377.08 1374.08 S&G 

WP16 893591.77 1129669.06 1381.61 1365.61 1362.61 S&G 

WP17 893631.05 1129660.29 1379.01 1371.01 1368.01 S&G 

WP18 893627.96 1129702.66 1378.66 1370.66 1367.66 S&G 

WP20D 892845.95 1129162.30 1409.60 1379.60 1376.6 S&G 

WP20S 892844.41 1129162.58 1409.60 1388.60 1385.60 S&G 

WP21 893534.74 1129529.93 1384.50 1377.50 1374.50 S&G 

WP22 893723.11 1129517.68 1379.80 1365.80 1362.80 S&G 

WP23 893809.43 1129533.65 1374.60 1366.60 1363.60 S&G 

WP24 893874.64 1129534.13 1372.50 1364.50 1361.50 S&G 

WP25 893522.25 1129629.76 1384.70 1377.70 1362.70 S&G 

WP26 893511.05 1129650.65 1384.50 1377.50 1362.50 S&G 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 B-54 

Table B-17. Groundwater Points Excluded from the Evaluation(1)

Sampling 

Location 

North 

Coordinate (2)

East 

Coordinate 

(2)

Surface 

Elevation (ft) 

Elevation at 

Top of 

Screened 

Interval (ft) 

Elevation at 

Bottom of 

Screened 

Interval (ft) 

Geologic 

Unit of 

Screened 

Interval 

WP27 893519.23 1129672.49 1384.40 1377.40 1362.40 S&G 

WP28 893513.60 1129644.17 1384.60 1377.60 1362.60 S&G 

WP29 893519.34 1129643.90 1385.10 1378.10 1363.10 S&G 

WP30 893526.35 1129644.34 1385.20 1378.20 1363.20 S&G 

WP31 893519.50 1129651.73 1385.40 1378.40 1363.40 S&G 

WP32 893520.70 1129651.71 1385.40 1378.40 1363.40 S&G 

WP33 893522.25 1129651.70 1385.40 1378.40 1363.40 S&G 

WP34 893526.13 1129651.67 1385.40 1378.40 1363.40 S&G 

WP35 893538.42 1129651.63 1384.00 1377.00 1362.00 S&G 

WP36 893513.55 1129659.28 1384.70 1377.70 1362.70 S&G 

WP37 893519.29 1129659.11 1385.30 1378.30 1363.30 S&G 

WP38 893520.62 1129659.08 1385.40 1378.40 1363.40 S&G 

WP39 893522.08 1129659.00 1385.40 1378.40 1363.40 S&G 

WP40 893526.27 1129659.35 1385.30 1378.30 1363.30 S&G 

NOTES: (1) This table lists points that were not included in the evaluation for DP section 4.2 because: a) no 

radiological data were available; b) data from that point were not validated (e.g., piezometers, surface 

elevation points, wells for the north plateau groundwater recovery system, wells for evaluation of the 

permeable treatment wall); c) sampling was dropped from the groundwater program because coverage 

was considered sufficient and no additional sampling was required (e.g., several points discontinued in 

1995); d) the well was dry; or e) the sampling point was from an area outside the scope of the Phase 1 

DP (e.g., groundwater seeps outside the process premises, wells from WMA 8). 

(2) Western New York State Planar Coordinate System 

LEGEND: S&G = sand and gravel, ULT = unweathered Lavery till, WLT = weathered Lavery till, LTS = Lavery till 

sand, KRS = Kent recessional sequence, BR = bedrock. 

 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 C-1 

APPENDIX C 

DETAILS OF DCGL DEVELOPMENT

AND THE INTEGRATED DOSE ASSESSMENT 

PURPOSE OF THIS APPENDIX 

The purpose of this appendix is to provide supporting information related to 

development of derived concentration guideline levels (DCGLs) and the limited 

integrated dose assessment performed to ensure that cleanup criteria for surface 

soil, subsurface soil, and streambed sediment used in Phase 1 of the proposed 

decommissioning would support any decommissioning approach that may be 

selected for Phase 2. 

INFORMATION IN THIS APPENDIX

This appendix provides the following information: 

Table C-1 in Section 1 provides a complete list of RESRAD input 

parameters, except for distribution coefficients, and the bases for these 

parameters. 

Table C-2 in Section 1 provides a list of distribution coefficients and their 

bases. 

Table C-3 in Section 1 provides the exposure pathways considered in the 

analysis. 

Table C-4 in Section 1 provides data on measured radionuclide 

concentrations in the Lavery till in the area of the large excavations in 

Waste Management Area 1 and Waste Management Area 2. 

Section 2 describes the information that comprises Attachment 1, which 

supports the calculation of DCGL and Cleanup Goal values presented in 

Section 5 of the Decommissioning Plan. 

Attachment 1 provides electronic RESRAD input and output files for the 

three base cases (surface soil, subsurface soil, and streambed sediment), 

the limited integrated dose analysis, and the input parameter sensitivity 

analyses performed, along with the associated Microsoft Excel 

spreadsheets. 

Attachment 2 provides an additional electronic file (a Microsoft Excel 

spreadsheet) used in the preliminary dose assessments. 

RELATIONSHIP TO OTHER PLAN SECTIONS 

This appendix provides supporting information for Section 5. Information provided in 

Section 5 and in Section 1 on the project background will help place the information 

in this appendix into context. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 C-2 

1.0 Tabulated Data 

Table C-1 identifies input parameters used in the RESRAD models, except for the 

distribution coefficients, which are included in Table C-2. Input parameters are provided for 

the three source exposure scenarios: surface soil (SS), subsurface soil (SB), and stream 

bank sediment (SD). The RESRAD input parameters presented in Table C-1 were selected 

as discussed in Section 5. 

Distribution coefficients (Kd) are presented in Table C-2 for chemical elements of the 18 

radionuclides and their decay progeny for each of the three analyses (SS, SB and SD) for 

each of the modeled media (contaminated zone, unsaturated zone and saturated zone) 

used in RESRAD. The conceptual models assume the sand and gravel unit is 

representative of the three RESRAD zones, except that in the SB and SD analyses, the 

contaminated zone is assumed to be represented by the Lavery till. The table includes the 

RESRAD default value, the specific value input into the RESRAD model for DCGLW

calculations, either measured site-specific or reference values (as identified in Note 1 to 

table C-2), and the range of values used in the sensitivity analysis. The Kd values were 

selected to represent the central tendency of the site-specific data or were based on 

specific soil strata characteristics where available. Variability/uncertainty in the Kd values 

was addressed through the sensitivity analysis. 

The exposure pathways presented in Table C-3 were based on the critical groups 

identified for each of the source media. The resident farmer was the critical receptor for 

soil exposure and the recreationist was identified as the critical receptor for stream bank 

sediment exposure. 

The data in Table C-4 are the basis for the maximum radionuclide concentration data in 

Table 5-1. These data comprise the available characterization data for radionuclides in the 

Lavery till within the footprints of the large excavations for the Process Building-Vitrification 

area and the Low-Level Waste Treatment Facility area that are described in Section 7. 

Preliminary dose assessments have been performed for the remediated WMA 1 and 

WMA 2 excavations. These assessments made use of the maximum measured 

radioactivity concentration in the Lavery till for each radionuclide as summarized in Table 

C-4, and the maximum detection level concentration for non-detected radionuclides. (It 

should be noted that the minimum detection levels for non-detected radionuclides may 

range several orders of magnitude. Use of the maximum detection level concentration for 

non-detected radionuclides results in added conservatism in the reported preliminary dose 

assessment.) The results were as follow: 

WMA 1, a maximum of 1.3 mrem a year 

WMA 2, a maximum of 0.04 mrem a year 

Given the limited data available, these results must be viewed as order-of-magnitude 

estimates. However, they do suggest that actual potential doses from the two remediated 

areas are likely to be substantially below 25 mrem per year. Table C-4B in Attachment 2 

shows how these doses were estimated. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 0 C-11 

Table C-2. Soil/Water Distribution Coefficients 

Radionuclide 

RESRAD 

Default 

(mL/g) 

Surface Soil DCGL 

Contaminated 

Zone (mL/g) 

Subsurface Soil DCGL

Contaminated 

Zone (mL/g) 

Sediment DCGL 

Contaminated 

Zone (mL/g) 

Unsaturated(2) 

Zone (mL/g) 

Saturated(3) 

Zone (mL/g) 

Strontium 30 6.16(8) 15(5) 15(5) 6.16(8) 6.16(8)

 (1 - 32) (1 - 32) (1 - 32) (1 - 32) (1 - 32) 

Technetium 0 0.1(4) 4.1(7) 4.1(7) 0.1(4) 0.1(4)

 (0.01 - 4.1) (1 - 10) (1 - 10) (0.01 - 4.1) (0.01 - 4.1) 

Uranium 50 35(4) 10(7) 10(7) 35(4) 35(4)

 (15 - 350) (1 - 100) (1 - 100) (15 - 350) (15 - 350) 

Progeny Elements(9)

Actinium 20 20 20 20 20 20 

Lead 100 100 100 100 100 100 

Protactinium 50 50 50 50 50 50 

Radium 70 70 70 70 70 70 

Thorium 60,000 60,000 60,000 60,000 60,000 60,000 

NOTES: (1) Sources of Kd values considered included Table 3-20; NUREG-5512 (Beyeler, et al. 1999), Table 6.7; RESRAD User's Guide (Yu, et al. 2001), Tables E-3, E-4; and 

Sheppard and Thibault 1990. Values in parentheses are the bounds used in the sensitivity evaluation, selected considering site-specific and literature values to reflect 

a reasonable range. 

 (2) Sediment model assumes no unsaturated zone. Values used for surface and subsurface soil evaluation only. 

 (3) Values presented here are those used for surface soil DCGLs based on the non-dispersion model. Saturated zone distribution coefficients are not utilized by RESRAD 

for the mass-balance groundwater model. 

 (4) From Sheppard and Thibault 1990, for sand. 

 (5) Site specific value for the unweathered Lavery till (see Section 3.7.8, Table 3-20). 

 (6) RESRAD default for this radionuclide is to allow the code to calculate the distribution coefficient based on correlation with plant root uptake transfer factor. 

 (7) Site specific value for the Lavery till (see Section 3.7.8, Table 3-20). 

 (8) Site specific value for the sand and gravel unit (see Section 3.7.8, Table 3-20). 

 (9) Progeny Kds were not included in the sensitivity analysis; RESRAD default values were used in all cases. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 C-12 

Table C-3 Scenario exposure pathways for WVDP DCGL development 

Exposure Pathways 

Resident Farmer 

(surface soil and 

Lavery Till source) 

Recreationist 

(sediment 

source) 

Incidental ingestion of source 

External exposure to source 

Inhalation of airborne source  

Ingestion of groundwater impacted by source x 

Ingestion of milk impacted by soil and water sources x 

Ingestion of beef impacted by soil and water sources x 

Ingestion of produce impacted by soil and water 

sources 

x 

Incidental ingestion of surface water impacted by 

source 

 

Ingestion of fish impacted by source  

Ingestion of venison impacted by sediment and water 

sources 

 

LEGEND: 

- Pathway is considered complete and is included in DCGL development. 

 - Pathway is considered potentially complete but unlikely, and is not included in DCGL development. 

x - Pathway is considered incomplete and is not included in DCGL development. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 C-13 

Table C-4. Radiological Concentrations from Soil Samples Containing Lavery Till in the 

WMA 1 and WMA 2 Excavation Areas(1)

Location Nuclide Result (pCi/g) Sample Depth 

Interval (ft) 

BH-17 (WMA 6, 1993) 

Depth to Lavery till - 27 ft 

 

 

 

 

 

 

 

 

Sr-90 1.1E-01 26-28 

Cs-137 2.6E-02 26-28 

U-232 < 3.2E-03 26-28 

U-233/234 1.6E-01 26-28 

U-235 < 5.8E-03 26-28 

U-235/236 < 6.9E-03 26-28 

U-238 1.1E-01 26-28 

Pu-238 < 4.3E-03 26-28 

Pu-239/240 < 4.3E-03 26-28 

Pu-241 1.3E+00 26-28 

Am-241 < 9.6E-03 26-28 

BH-21A (WMA 1, 1993) 

Depth to Lavery till - 37.5 ft 

Sr-90 4.5E+02 36-38 

Cs-137 < 3.0E-02 36-38 

U-232 < 7.4E-03 36-38 

U-233/234 8.6E-02 36-38 

U-235 < 5.1E-03 36-38 

U-235/236 < 7.2E-03 36-38 

U-238 7.1E-02 36-38 

Pu-238 < 4.8E-03 36-38 

Pu-239/240 < 4.8E-03 36-38 

Pu-241 < 1.1E+00 36-38 

Am-241 < 7.2E-03 36-38 

GP3098 (WMA 1, 1998) 

Depth to Lavery till - 37 ft 

 

 

 

 

 

Sr-90 6.6E+00 36.5-37 

Sr-90 4.2E+00 37-37.5 

Sr-90 6.3E+00 37.5-38 

Sr-90 5.5E+01 38-38.5 

Sr-90 5.9E+01 38.5-39 

Sr-90 3.4E+01 39-39.5 

Sr-90 2.9E+01 39.5-40 

GP3008 (WMA 1, 2008) 

Depth to Lavery till - 37 ft 

C-14 < 3.0E-01 37-39

Sr-90 1.7E+00 37-39

Tc-99 < 5.5E-01 37-39

I-129 < 1.1E-01 37-39

Cs-137 < 2.0E-02 37-39

U-232 < 2.2E-02 37-39

U-233/234 9.7E-01 37-39

U-235/236 1.3E-01 37-39
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 C-14 

Table C-4. Radiological Concentrations from Soil Samples Containing Lavery Till in the 

WMA 1 and WMA 2 Excavation Areas(1)

Location Nuclide Result (pCi/g) Sample Depth 

Interval (ft) 

U-238 1.1E+00 37-39

Np-237 < 9.8E-03 37-39

Pu-238 < 1.1E-02 37-39

Pu-239/240 < 1.2E-02 37-39

Pu-241 < 4.8E-01 37-39

Am-241 < 1.2E-02 37-39

Cm-243/244 < 1.2E-02 37-39

GP7398 (WMA 1, 1998) 

Depth to Lavery till - 39 ft 

 

Sr-90 1.9E+00 40-40.5 

Sr-90 1.8E+00 40.5-41 

Sr-90 5.2E+00 41-41.5 

Sr-90 8.4E+00 41.5-42 

GP7608 (WMA 1, 2008) 

Depth to Lavery till - 38 ft 

C-14 < 3.4E-01 38-40

Sr-90 1.8E+01 38-40

Tc-99 < 3.9E-01 38-40

I-129 < 2.3E-01 38-40

Cs-137 7.9E+00 38-40

U-232 < 2.8E-01 38-40

U-233/234 1.9E+00 38-40

U-235/236 < 4.2E-01 38-40

U-238 8.8E-01 38-40

Np-237 < 3.6E-01 38-40

Pu-238 < 3.4E-01 38-40

Pu-239/240 < 3.1E-01 38-40

Pu-241 < 3.4E+01 38-40

Am-241 < 2.0E-01 38-40

Cm-243/244 < 2.2E-01 38-40

GP7808 (WMA 1, 2008) 

Depth to Lavery till - 37 ft 

C-14 < 2.9E-01 37-39

Sr-90 8.6E+00 37-39

Tc-99 < 4.4E-01 37-39

I-129 < 2.3E-01 37-39

Cs-137 < 2.2E-02 37-39

U-232 < 1.3E-02 37-39

U-233/234 8.2E-01 37-39

U-235/236 9.2E-02 37-39

U-238 1.1E+00 37-39

Np-237 < 2.1E-02 37-39

Pu-238 < 1.1E-02 37-39

Pu-239/240 < 1.5E-02 37-39

Pu-241 < 4.9E-01 37-39

Am-241 < 1.7E-02 37-39

Cm-243/244 < 1.6E-02 37-39
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 C-15 

Table C-4. Radiological Concentrations from Soil Samples Containing Lavery Till in the 

WMA 1 and WMA 2 Excavation Areas(1)

Location Nuclide Result (pCi/g) Sample Depth 

Interval (ft) 

GP8098 (WMA 1, 1998) 

Depth to Lavery till - 41 ft 

 

 

 

C-14 < 8.6E-02 40-42 

Sr-90 1.3E+01 40-42

Tc-99 < 2.6E-01 40-42

I-129 < 2.3E-01 40-42

Cs-137 < 2.2E-02 40-42

Pu-241 < 2.1E+00 40-42

GP8008 (WMA 1, 2008) 

Depth to Lavery till - 40 ft 

C-14 < 2.8E-01 39-41

C-14 < 2.8E-01 41-43

Sr-90 5.3E+00 39-41

Sr-90 1.4E+00 41-43

Tc-99 < 3.4E-01 39-41

Tc-99 < 3.7E-01 41-43

I-129 < 1.2E-01 39-41

I-129 < 1.2E-01 41-43

Cs-137 < 2.3E-02 39-41

Cs-137 < 2.8E-02 41-43

U-232 < 1.0E-02 39-41

U-232 < 1.3E-02 41-43

U-233/234 5.2E-01 39-41

U-233/234 1.1E+00 41-43

U-235/236 3.9E-02 39-41

U-235/236 1.1E-01 41-43

U-238 8.2E-01 39-41

U-238 1.4E+00 41-43

Np-237 < 1.1E-02 39-41

Np-237 < 1.2E-02 41-43

Pu-238 < 1.5E-02 39-41

Pu-238 < 1.5E-02 41-43

Pu-239/240 < 1.6E-02 39-41

Pu-239/240 < 1.5E-02 41-43

Pu-241 < 4.4E-01 39-41

Pu-241 < 5.2E-01 41-43

Am-241 < 1.2E-02 39-41

Am-241 < 1.5E-02 41-43

Cm-243/244 < 1.3E-02 39-41

Cm-243/244 < 1.6E-02 41-43

GP8308 (WMA 1, 2008) 

Depth to Lavery till - 41.5 ft 

C-14 < 3.5E-01 40-42

Sr-90 1.5E+00 40-42

Tc-99 < 3.6E-01 40-42

I-129 2.4E-01 40-42

Cs-137 < 2.7E-02 40-42

U-232 < 2.4E-02 40-42
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 C-16 

Table C-4. Radiological Concentrations from Soil Samples Containing Lavery Till in the 

WMA 1 and WMA 2 Excavation Areas(1)

Location Nuclide Result (pCi/g) Sample Depth 

Interval (ft) 

U-233/234 9.8E-01 40-42

U-235/236 2.2E-01 40-42

U-238 1.1E+00 40-42

Np-237 < 1.3E-02 40-42

Pu-238 < 1.1E-02 40-42

Pu-239/240 < 1.1E-02 40-42

Pu-241 < 2.7E-01 40-42

Am-241 < 1.2E-02 40-42

Cm-243/244 < 1.8E-02 40-42

GP8698 (WMA 1, 1998) 

Depth to Lavery till - 39 ft 

 

 

 

Sr-90 2.2E+00 39-39.5 

Sr-90 1.0E+00 39.5-40 

Sr-90 3.0E+00 40-40.5 

Sr-90 1.0E+01 40.5-41 

Sr-90 4.1E+01 41-41.5 

Sr-90 3.0E+01 41.5-42 

GP10008 (WMA 1, 2008) 

Depth to Lavery till - 37 ft 

C-14 < 3.0E-01 37-39

Sr-90 6.7E+00 37-39

Tc-99 < 4.0E-01 37-39

I-129 < 1.4E-01 37-39

Cs-137 < 2.7E-02 37-39

U-232 < 1.3E-02 37-39

U-233/234 7.6E-01 37-39

U-235/236 7.5E-02 37-39

U-238 9.5E-01 37-39

Np-237 < 1.2E-02 37-39

Pu-238 < 2.2E-02 37-39

Pu-239/240 < 1.1E-02 37-39

Pu-241 < 4.3E-01 37-39

Am-241 < 1.4E-02 37-39

Cm-243/244 < 2.3E-02 37-39

GP10108 (WMA 1, 2008) 

Depth to Lavery till - 33 ft 

C-14 < 3.1E-01 32-34

Sr-90 6.3E-01 32-34

Tc-99 < 5.4E-01 32-34

I-129 < 9.1E-02 32-34

Cs-137 < 2.6E-02 32-34

U-232 < 1.6E-01 32-34

U-233/234 6.0E-01 32-34

U-235/236 5.0E-02 32-34

U-238 7.3E-01 32-34

Np-237 < 1.0E-02 32-34

Pu-238 < 9.5E-03 32-34
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 C-17 

Table C-4. Radiological Concentrations from Soil Samples Containing Lavery Till in the 

WMA 1 and WMA 2 Excavation Areas(1)

Location Nuclide Result (pCi/g) Sample Depth 

Interval (ft) 

Pu-239/240 < 8.8E-03 32-34

Pu-241 < 4.7E-01 32-34

Am-241 < 1.1E-02 32-34

Cm-243/244 < 1.1E-02 32-34

GP10408 (WMA 1, on border of WMA 2) 

Depth to Lavery till - 24 ft 

C-14 < 3.6E-01 24-26

Sr-90 7.4E+00 24-26

Tc-99 < 5.1E-01 24-26

I-129 < 1.1E-01 24-26

Cs-137 < 5.5E-02 24-26

U-232 4.1E-02 24-26

U-233/234 8.8E-01 24-26

U-235/236 1.4E-01 24-26

U-238 7.9E-01 24-26

Np-237 < 6.9E-03 24-26

Pu-238 < 1.2E-02 24-26

Pu-239/240 < 1.2E-02 24-26

Pu-241 < 3.1E-01 24-26

Am-241 < 1.3E-02 24-26

Cm-243/244 < 1.4E-02 24-26

BH-05 (WMA 2, 1993), located 

downgradient of Lagoon 1 

Depth to Lavery till - 12 ft 

Sr-90 8.5E-01 12-14 

Cs-137 4.5E-01 12-14 

U-232 1.2E-02 12-14 

U-233/234 1.8E-01 12-14 

U-235 < 5.9E-03 12-14 

U-235/236 < 8.3E-03 12-14 

U-238 1.1E-01 12-14 

Pu-238 1.0E-02 12-14 

Pu-239/240 < 5.9E-03 12-14 

Pu-241 < 1.3E+00 12-14 

Am-241 3.0E-02 12-14 

BH-07 (WMA 2, 1993) 

Depth to Lavery till - 13 ft 

Sr-90 1.3E-01 12-14 

Cs-137 7.5E-02 12-14 

U-232 < 8.7E-03 12-14 

U-233/234 2.2E-01 12-14 

U-235 < 6.6E-03 12-14 

U-235/236 < 7.6E-03 12-14 

U-238 1.5E-01 12-14 

Pu-238 < 4.7E-03 12-14 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 C-18 

Table C-4. Radiological Concentrations from Soil Samples Containing Lavery Till in the 

WMA 1 and WMA 2 Excavation Areas(1)

Location Nuclide Result (pCi/g) Sample Depth 

Interval (ft) 

 Pu-239/240 < 6.2E-03 12-14 

Pu-241 9.5E-01 12-14 

Am-241 < 5.1E-03 12-14 

BH-08 (WMA 2, 1993), located 

downgradient of Lagoon 1 

Depth to Lavery till - 11.5 ft 

 

 

 

 

 

 

 

 

Sr-90 1.8E+02 10-12 

Cs-137 2.5E+02 10-12 

U-232 1.9E+01 10-12 

U-233/234 9.7E+00 10-12 

U-235 3.2E-01 10-12 

U-235/236 5.0E-01 10-12 

U-238 1.3E+01 10-12 

Pu-238 3.9E+00 10-12 

Pu-239/240 7.6E+00 10-12 

Pu-241 2.7E+01 10-12 

Am-241 1.1E+01 10-12 

BH-12 (WMA 2, 1993) 

Depth to Lavery till - 15.5 ft 

 

 

 

 

 

 

 

 

Sr-90 1.8E-01 14-16 

Cs-137 < 2.2E-02 14-16 

U-232 < 6.0E-03 14-16 

U-233/234 1.1E-01 14-16 

U-235 < 7.0E-03 14-16 

U-235/236 1.3E-02 14-16 

U-238 9.7E-02 14-16 

Pu-238 < 4.9E-03 14-16 

Pu-239/240 < 4.9E-03 14-16 

Pu-241 < 1.0E+00 14-16 

Am-241 < 4.6E-03 14-16

BH-13 (WMA 2, 1993) 

Depth to Lavery till - 19 ft 

 

 

 

 

 

 

 

 

Sr-90 1.8E-01 18-20 

Cs-137 2.7E+00 18-20 

U-232 1.6E-02 18-20 

U-233/234 8.5E-02 18-20 

U-235 < 5.1E-03 18-20 

U-235/236 < 8.2E-03 18-20 

U-238 5.3E-02 18-20 

Pu-238 2.4E-02 18-20 

Pu-239/240 2.6E-02 18-20 

Pu-241 < 8.1E-01 18-20 

Am-241 9.5E-02 18-20 
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Revision 1 C-19 

Table C-4. Radiological Concentrations from Soil Samples Containing Lavery Till in the 

WMA 1 and WMA 2 Excavation Areas(1)

Location Nuclide Result (pCi/g) Sample Depth 

Interval (ft) 

BH-14 (WMA 2, 1993) 

Depth to Lavery till - 15 ft 

 

 

 

 

 

 

 

 

Sr-90 1.8E+01 14-16 

Cs-137 1.9E+00 14-16 

U-232 2.0E-02 14-16 

U-233/234 1.9E-01 14-16 

U-235 < 7.9E-03 14-16 

U-235/236 < 1.1E-02 14-16 

U-238 2.8E-01 14-16 

Pu-238 1.7E-01 14-16 

Pu-239/240 1.6E-01 14-16 

Pu-241 < 1.1E+00 14-16 

Am-241 1.1E-01 14-16 

NOTE: (1) Data are from the 1993 RCRA facility investigation and the other Geoprobe studies described in Section 4.

2.0 Information Provided in Attachment 1 

Other information associated with the dose modeling is provided in Attachment 1. As 

explained in Section 5, the dose calculations were performed using RESRAD 6.4 and the 

results were exported to Microsoft Excel for post-processing. Attachment 1 provides: 

RESRAD input files to verify input parameters and model setup, 

RESRAD output files to verify input parameters and results, 

Excel result files containing (1) RESRAD output results (exported from the 

RESRAD summary report), (2) summaries of data [maximum dose-source ratios 

(DSRs) and times of maxima], (3) calculation of DCGLW values from the maximum 

DSRs, (4) calculation of area factors and DCGLEMC values, and (5) summary of 

sensitivity results 

DCGL development was based on entering unit source concentrations (1pCi/g) for 18 

radionuclides into RESRAD to generate DSRs in units of mrem/y per pCi/g (RESRAD output 

results based on unit concentrations can be interpreted as either the dose or DSR, and the terms 

are used interchangeably in this document). The individual, peak DSRs are then used to 

generate DCGLs for each radionuclide based on the following equation: 

DCGL (pCi/g) = Dose Limit (mrem/y) / Maximum DSR (mrem/y per pCi/g) (Eq.1) 

The dose limit of 25 mrem/y and maximum DSRs were used as the basis for 

developing the DCGLs. Further details regarding the Attachment 1 files are presented 

below. Because of the uncertainty in the actual distributions and mixtures of radionuclides 

in the environmental media, the DCGL for each radionuclide is calculated individually. 

Following characterization, the working cleanup levels for mixtures can be developed using 

the sum of fractions method discussed in Chapter 5 of the MARSSIM. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 C-20 

2.1 Input Parameters Tables 

The parameters input to the RESRAD model include: 

Base case values for the DCGLW calculations, 

Modification of source area only for DCGLEMC calculations, and 

Variation of key parameters to evaluate model sensitivity 

The Excel file “WV Sensitivity Parameters Table.xls” (Table C.5) provides a summary 

of the following parameters which were varied to evaluate model sensitivity. 

Surface Soil Sources 

- Indoor/outdoor time fraction 

- Source thickness 

- Unsaturated zone thickness 

- Irrigation/well pumping rate 

- Soil/water distribution coefficients 

- Hydraulic conductivity (Vertical/Horizontal) 

- Runoff/Evapotranspiration coefficients/ Infiltration rate 

- Depth of well intake 

- Length of contaminated area parallel to aquifer flow 

- Plant transfer factors 

- Use of mass balance instead of non-dispersion groundwater model 

Subsurface Soil Sources (subsurface soil distributed on the surface): 

- Indoor/outdoor time fraction 

- Source thickness 

- Unsaturated zone thickness 

- Irrigation/well pumping rate 

- Soil/water distribution coefficients 

- Hydraulic conductivity (Vertical/Horizontal) 

- Runoff/Evapotranspiration coefficients/ Infiltration rate 

- Plant transfer factors 

Stream Bank Sediment sources: 

- Outdoor time fraction 

- Source thickness 

- Unsaturated zone thickness 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 C-21 

- Soil/water distribution coefficients 

- Runoff/Evapotranspiration coefficients/ Infiltration rate 

- Plant transfer factors 

- Fish transfer factors 

These sensitivity parameters were selected based on preliminary model simulations 

and consideration of parameter priorities presented in Table 4.2 of NUREG-6697, 

Attachment B (Yu, et al. 2000). The parameters selected for analysis are discussed further 

below. 

Sensitivity parameter values were selected to represent a reasonable range in order 

to provide bounds on the uncertainty in the DCGL calculations. The basis for particular 

parameter values are discussed below. 

Indoor/Outdoor fraction – varied from 0.45/0.45 to 0.8/0.1 from the base case values 

of 0.66/0.25. The lower indoor fraction represents equal time indoors and outdoors, 

while the higher fraction was selected to represent a farmer spending inordinate 

amounts of time indoors. 

Source thickness – for surface soil and sediment, varied from 0.5 to 3m to bound the 

base case value of 1m with potential thicknesses resulting from remedial activities and 

to account for potential source erosion uncertainty. For subsurface soil, varied from 0.1 

to 1 m to bound the base case value of 0.3 m. The subsurface source thickness is 

dependent on the amount of material excavated during well/cistern installation, and 

depths less than the base case would correspond with a smaller source area for a 

given excavated volume. 

Unsaturated zone thickness – varied from 1 to 5 m to bound the 2 m base case value 

with the range possible for the site. The range of results also provides an assessment 

of potential source erosion uncertainty. 

Irrigation/well pumping rate - varied from 0.2/2720 to 0.8/8720 (m/y)/(m3

/y) to bound 

the base case of 0.5/5720 (m/y)/(m3

/y). The irrigation rate and well pump rate are 

directly related and the range reflects changes in crop irrigation only. For all cases, the 

assumed household and livestock water ingestion rates were held constant. This 

parameter is applicable to soil exposure only, not to sediment exposure 

Soil/Water distribution coefficients – varied for each radionuclide based on sitespecific data where available. If a range of site-specific distribution coefficients was not 

available (as was the case for the majority of radionuclides), values were selected from 

the literature to provide a bound on the base case uncertainty. The conceptual models 

assume the sand and gravel unit is representative of the three RESRAD zones 

(contaminated, unsaturated and saturated), except that in the SB and SD analyses, the 

contaminated zone is assumed to be represented by the Lavery till. 

Hydraulic conductivity – for the contaminated and unsaturated zone, varied the 

vertical conductivity from 1 m/y (3.2E-06 cm/s) to 350 m/y (1.1E-03 cm/s) to bound the 

base case value of 140 m/y (4.4E-04 cm/s) which is the average for the sand and 

gravel unit divided by 10 to account for anisotropy (DEIS Appendix E, Table E-3). 
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Revision 1 C-22 

Similarly for the saturated zone, the horizontal conductivity was varied from 10 to 3500 

m/yr from the base case of 1400 m/y. The conceptual model assumes the sand and 

gravel unit is representative of the unsaturated and saturated zone. The upper bound 

value is that used in the DEIS and is included for comparison. 

Runoff/evapotranspiration coefficient – varied from 0.2/0.5 to 0.8/0.8 to bound the 

base case of 0.6/0.55. The base case was selected to achieve infiltration rate of 0.42 

m/y which corresponds to 25% of the applied water (DEIS Appendix E). The upper 

bounds are assumed values and the lower bounds for these parameters represent the 

RESRAD defaults. 

Depth of well intake – applicable to non-dispersion model only (surface soil base 

case). Varied from 3 to 10 m to bound the base case value of 5m. The lower bound 

represents the minimum for a 1 m contaminated thickness and 2 m unsaturated zone. 

The upper bound represents the upper end of observed thickness of the saturated 

zone on site. 

Length of contaminated area parallel to aquifer flow - applicable to non-dispersion 

model only (surface soil base case). Varied from 50 m to 200 m to bound the base 

case of 100 m. 

Plant transfer factors – varied from the constituent specific base cases by increasing 

and decreasing each parameter an order of magnitude. 

Fish transfer factors – applicable for sediment source evaluation. Values varied from 

the constituent specific base cases by increasing and decreasing each parameter an 

order of magnitude. 

Groundwater model – the surface soil base case non-dispersion model is varied to 

provide results for the mass balance model for comparison. The RESRAD User’s 

Manual suggests the non-dispersion model for areas >1,000 m2

 (Yu et al. 2001, p.E18). 

2.2 RESRAD Input Files

The following RESRAD input files are provided to allow verification of input parameters 

and reproduction of the output files and summary graphics: 

DCGLW input files: 

- WV Surface – 10k Base.RAD (Surface soil source of 10,000 m2

) 

- WV Subsurface – 100 Base.RAD (Subsurface material as a surface source of 

100 m2

) 

- WV Sediment - 1k Base.RAD (Sediment source of 1,000 m2

) 

DCGLEMC input files (varying only source area from DCGLW files): 

- Surface Soil Source 

WV Surface - 5k EMC.RAD (5,000 m2

 source) 

WV Surface - 1k EMC.RAD (1,000 m2

 source) 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 C-23 

WV Surface - 500 EMC.RAD (500 m2

 source) 

WV Surface - 100 EMC.RAD (100 m2

 source) 

WV Surface - 50 EMC.RAD (50 m2 source) 

WV Surface - 10 EMC.RAD (10 m2

 source) 

WV Surface - 5 EMC.RAD (5 m2

 source) 

WV Surface - 1 EMC.RAD (1 m2 source) 

- Subsurface Source 

WV Subsurface - 50 EMC.RAD (50 m2

 source) 

WV Subsurface - 10 EMC.RAD (10 m2 source) 

WV Subsurface - 5 EMC.RAD (5 m2

 source) 

WV Subsurface - 1 EMC.RAD (1 m2

 source) 

- Stream Bank Sediment Source 

WV Sediment - 500 EMC.RAD (500 m2

 source) 

WV Sediment - 100 EMC.RAD (100 m2

 source) 

WV Sediment - 50 EMC.RAD (50 m2

 source) 

WV Sediment - 10 EMC.RAD (10 m2

 source) 

WV Sediment - 5 EMC.RAD (5 m2

 source) 

WV Sediment - 1 EMC.RAD (1 m2

 source) 

Note: sediment source area width was maintained at 3 m when varying areas to 

represent assumed stream bank configuration. 

Sensitivity analysis input files: 

- Surface soil Source 

WV Surface - SENS1.RAD (decreased indoor fraction) 

WV Surface - SENS2.RAD (increased indoor fraction) 

WV Surface - SENS3.RAD (decreased source layer thickness) 

WV Surface - SENS4.RAD (increased source layer thickness) 

WV Surface - SENS5.RAD (decreased unsaturated zone thickness) 

WV Surface - SENS6.RAD (increased unsaturated zone thickness) 

WV Surface - SENS7.RAD (decreased well pumping rate) 

WV Surface - SENS8.RAD (increased well pumping rate) 

WV Surface - SENS9.RAD (decreased Kd values) 

WV Surface - SENS10.RAD (increased Kd values) 
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Revision 1 C-24 

WV Surface - SENS11.RAD (decreased K value) 

WV Surface - SENS12.RAD (increased K value) 

WV Surface - SENS13.RAD (decreased runoff/evapotranspiration) 

WV Surface - SENS14.RAD (increased runoff/evapotranspiration) 

WV Surface - SENS15.RAD (decreased well intake depth) 

WV Surface - SENS16.RAD (increased well intake depth) 

WV Surface - SENS17.RAD (decreased length parallel to flow) 

WV Surface - SENS18.RAD (increased length parallel to flow) 

WV Surface - SENS19.RAD (decreased plant transfer factors) 

WV Surface – SENS20.RAD (increased plant transfer factors) 

WV Surface - SENS21.RAD (mass balance groundwater model) 

- Subsurface Soil Source 

WV Subsurface - SENS1.RAD (decreased indoor fraction) 

WV Subsurface - SENS2.RAD (increased indoor fraction) 

WV Subsurface - SENS3.RAD (decreased source layer thickness) 

WV Subsurface - SENS4.RAD (increased source layer thickness) 

WV Subsurface - SENS5.RAD (decreased unsaturated zone thickness) 

WV Subsurface - SENS6.RAD (increased unsaturated zone thickness) 

WV Subsurface - SENS7.RAD (decreased well pumping rate) 

WV Subsurface - SENS8.RAD (increased well pumping rate) 

WV Subsurface - SENS9.RAD (decreased Kd values) 

WV Subsurface - SENS10.RAD (increased Kd values) 

WV Subsurface - SENS11.RAD (decreased K value) 

WV Subsurface - SENS12.RAD (increased K value) 

WV Subsurface - SENS13.RAD (decreased runoff/evapotranspiration) 

WV Subsurface - SENS14.RAD (increased runoff/evapotranspiration) 

WV Subsurface - SENS15.RAD (decreased plant transfer factors) 

WV Subsurface – SENS16.RAD (increased plant transfer factors) 

- Sediment Source 

WV Sediment - SENS1.RAD (decreased outdoor fraction) 

WV Sediment - SENS2.RAD (increased outdoor fraction) 

WV Sediment - SENS3.RAD (decreased source layer thickness) 
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Revision 1 C-25 

WV Sediment - SENS4.RAD (increased source layer thickness) 

WV Sediment - SENS5.RAD (increased unsaturated zone thickness) 

WV Sediment - SENS6.RAD (largest unsaturated zone thickness) 

WV Sediment - SENS7.RAD (decreased Kd values) 

WV Sediment - SENS8.RAD (increased Kd values) 

WV Sediment – SENS9.RAD (decreased runoff/evapotranspiration) 

WV Sediment – SENS10.RAD (increased runoff/evapotranspiration) 

WV Sediment - SENS11.RAD (decreased plant transfer factors) 

WV Sediment – SENS12.RAD (increased plant transfer factors) 

WV Sediment - SENS13.RAD (decreased fish transfer factors) 

WV Sediment – SENS14.RAD (increased fish transfer factors) 

 

The dose results from the above input files were the basis for calculation of DCGLW

and DCGLEMC values. The DCGLs were calculated in Excel spreadsheets, based on 

exported data from the RESRAD summary output report. The following section describes 

the RESRAD output files, which are provided for informational purposes. 

2.3 RESRAD Output Files

The RESRAD output files are provided to allow review of results without running the 

simulations. For the DCGLW simulations, summary, detailed, daughter, and concentration 

reports are included in the QA files. The summary report is also available for the DCGLEMC

simulations. As indicated in the previous section, DCGL calculations are based on data 

exported from the RESRAD summary output report. RESRAD output files generated are 

as follows; 

DCGLW output files: 

- Surface Soil Source 

WV Surface – 10k Base_sum.TXT (summary report) 

WV Surface – 10k Base_ det.TXT (detailed report) 

WV Surface – 10k Base _dtr.TXT (daughter report) 

WV Surface – 10k Base _conc.TXT (concentration report) 

- Subsurface Soil Source 

WV Subsurface – 100 Base_sum.TXT (summary report) 

WV Subsurface – 100 Base_det.TXT (detailed report) 

WV Subsurface – 100 Base_dtr.TXT (daughter report) 

WV Subsurface – 100 Base_conc.TXT (concentration report) 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 C-26 

- Sediment Source 

WV Sediment – 1k Base_sum.TXT (summary report) 

WV Sediment – 1k Base_det.TXT (detailed report) 

WV Sediment – 1k Base_dtr.TXT (daughter report) 

WV Sediment – 1k Base_conc.TXT (concentration report) 

DCGLEMC output files (varying only source area from DCGLw files): 

- Surface Soil Source 

WV Surface - 5k EMC_sum.TXT (5,000 m2

 source) 

WV Surface - 1k EMC_ sum.TXT (1,000 m2 source) 

WV Surface - 500 EMC_sum.TXT (500 m2

 source) 

WV Surface - 100 EMC_sum.TXT (100 m2

 source) 

WV Surface - 50 EMC_sum.TXT (50 m2

 source) 

WV Surface - 10 EMC_sum.TXT (10 m2

 source) 

WV Surface - 5 EMC_sum.TXT (5 m2

 source) 

WV Surface - 1 EMC_sum.TXT (1 m2

 source) 

- Subsurface Soil Source 

WV Subsurface - 50 EMC_sum.TXT (50 m2

 source) 

WV Subsurface - 10 EMC_sum.TXT (10 m2

 source) 

WV Subsurface - 5 EMC_sum.TXT (5 m2

 source) 

WV Subsurface - 1 EMC_sum.TXT (1 m2

 source) 

- Sediment Source 

WV Sediment - 500 EMC_sum.TXT (500 m2

 source) 

WV Sediment - 100 EMC_sum.TXT (100 m2

 source) 

WV Sediment - 50 EMC_sum.TXT (50 m2

 source) 

WV Sediment - 10 EMC_sum.TXT (10 m2

 source) 

WV Sediment - 5 EMC_sum.TXT (5 m2

 source) 

WV Sediment - 1 EMC_sum.TXT (1 m2

 source) 

Sensitivity analysis output files: 

- Surface Soil Source 

WV Surface - SENS1_sum.TXT (decreased indoor fraction) 

WV Surface - SENS2_sum.TXT (increased indoor fraction) 

WV Surface - SENS3_sum.TXT (decreased source layer thickness) 
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Revision 1 C-27 

WV Surface - SENS4_sum.TXT (increased source layer thickness) 

WV Surface - SENS5_sum.TXT (decreased unsaturated zone thickness) 

WV Surface - SENS6_sum.TXT (increased unsaturated zone thickness) 

WV Surface - SENS7_sum.TXT (decreased well pumping rate) 

WV Surface - SENS8_sum.TXT (increased well pumping rate) 

WV Surface - SENS9_sum.TXT (decreased Kd values) 

WV Surface - SENS10_sum.TXT (increased Kd values) 

WV Surface - SENS11_sum.TXT (decreased K value) 

WV Surface - SENS12_sum.TXT (increased K value) 

WV Surface - SENS13_sum.TXT (decreased runoff/evapotranspiration) 

WV Surface - SENS14_sum.TXT (increased runoff/evapotranspiration) 

WV Surface - SENS15_sum.TXT (decreased well intake depth) 

WV Surface - SENS16_sum.TXT (increased well intake depth) 

WV Surface - SENS17_sum.TXT (decreased length parallel to flow) 

WV Surface - SENS18_sum.TXT (increased length parallel to flow) 

WV Surface - SENS19_sum.TXT (decreased plant transfer factors) 

WV Surface – SENS20_sum.TXT (increased plant transfer factors) 

WV Surface - SENS21_sum.TXT (mass balance groundwater model) 

- Subsurface Soil Source 

WV Subsurface - SENS1_sum.TXT (decreased indoor fraction) 

WV Subsurface - SENS2_sum.TXT (increased indoor fraction) 

WV Subsurface - SENS3_sum.TXT (decreased source layer thickness) 

WV Subsurface - SENS4_sum.TXT (increased source layer thickness) 

WV Subsurface - SENS5_sum.TXT (decreased unsaturated zone 

thickness) 

WV Subsurface - SENS6_sum.TXT (increased unsaturated zone 

thickness) 

WV Subsurface - SENS7_sum.TXT (decreased well pumping rate) 

WV Subsurface - SENS8_sum.TXT (increased well pumping rate) 

WV Subsurface - SENS9_sum.TXT (decreased Kd values) 

WV Subsurface - SENS10_sum.TXT (increased Kd values) 

WV Subsurface - SENS11_sum.TXT (decreased K value) 

WV Subsurface - SENS12_sum.TXT (increased K value) 
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Revision 1 C-28 

WV Subsurface - SENS13_sum.TXT (decreased runoff/evapotranspiration) 

WV Subsurface - SENS14_sum.TXT (increased runoff/evapotranspiration) 

WV Subsurface - SENS15_sum.TXT (decreased plant transfer factors) 

WV Subsurface – SENS16_sum.TXT (increased plant transfer factors) 

- Stream Bank Sediment Source 

WV Sediment - SENS1_sum.TXT (decreased outdoor fraction) 

WV Sediment - SENS2_sum.TXT (increased outdoor fraction) 

WV Sediment - SENS3_sum.TXT (decreased source layer thickness) 

WV Sediment - SENS4_sum.TXT (increased source layer thickness) 

WV Sediment - SENS5_sum.TXT (increased unsaturated zone thickness) 

WV Sediment - SENS6_sum.TXT (largest unsaturated zone thickness) 

WV Sediment - SENS7_sum.TXT (decreased Kd values) 

WV Sediment - SENS8_sum.TXT (increased Kd values) 

WV Sediment – SENS9_sum.TXT (decreased runoff/evapotranspiration) 

WV Sediment – SENS10_sum.TXT (increased runoff/evapotranspiration) 

WV Sediment - SENS11_sum.TXT (decreased plant transfer factors) 

WV Sediment – SENS12_sum.TXT (increased plant transfer factors) 

WV Sediment - SENS13_sum.TXT (decreased fish transfer factors) 

WV Sediment – SENS14_sum.TXT (increased fish transfer factors) 

The following section presents the methods used to generate DCGLs from the 

RESRAD model output previously described. 

2.4 Excel Result Files

The outputs of the RESRAD simulations (the DSR for each of the radionuclides at 

various future times) were exported to Excel from the RESRAD summary output report 

(specifically, the DSR values in the table presented at the bottom of page 45 of each 

RESRAD summary report). For each simulation, dose results were exported for each of the 

18 radionuclides, which includes the simulation year and dose (for that year) for each 

radionuclide. These have been generated for DCGLW, DCGLEMC, and sensitivity simulations 

for each source media and isotope. The peak dose for each radionuclide is identified and 

used as the basis for the DCGL calculation as follows; 

DCGLw = Dose Limit / Peak radionuclide DSR (Eq.2) 

Specific Excel result files are described below. 

2.4.1 Surface Soil DCGLs 

Surface soil DCGLs were calculated to conform with the annual dose limit for large 

areas (DCGLW), smaller areas of elevated concentrations (DCGLEMC), and to evaluate the 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 C-29 

sensitivity of the model to variations in specific parameters. The files associated with these 

calculations are described below. 

Surface Soil DCGLW Values

The soil DCGLW values were calculated based on resident farmer exposure for a 

10,000 m2

 source area and results from the RESRAD summary output report are presented 

in the Excel file “WVDP Surface DCGLs.XLS” in the sheet “Base” (Table C-6). The input 

files for the surface soil evaluation are presented in Section 2.2. These surface soil DCGLW

values are the basis for calculation of surface soil area factors and DCGLEMC values. 

Surface Soil DCGLEMC Values 

The DCGLW values calculated on the Excel summary sheet previously discussed serve 

as the base case for subsequent DCGLEMC development; DCGLEMC values are based on 

varying the source area from the 10,000 m2

 value used for the DCGLW as discussed in 

Chapter 5 of the MARSSIM. The Excel file “WVDP Surface DCGLs.XLS” has sheets for 

each of the source areas used to generate the DCGLEMC (Tables C-7 to C-14). The sheet 

“Summary” in the Excel file “WV Surface DCGLs.XLS” summarizes the DCGLEMC (Table C15) and Soil Area Factors (TableC-16) for each of the 18 radionuclides and selected source 

areas (ranging from 1 to 10,000 m2

). 

Surface Soil DCGLW Sensitivity Analysis 

The surface soil DCGLW sensitivity to key parameters was assessed by varying the 

input values for specific parameters and tabulating the results. The Excel file “WV Surface 

DCGL Sensitivity.XLS” contains the DSRs and DCGLs for each of 18 radionuclides from 

the RESRAD summary report output for each of the sensitivity simulations. Results of each 

run are in sheets SENS1 through SENS21 (Tables C-17 to C-37). Also included in the file 

are a summarization of the calculated DCGLs (Table C-38) and a summary of the percent 

change from the base case (Table C-39) for each of the sensitivity runs (also presented in 

Table 5-9). Table C-40 below presents a summary of the surface soil sensitivity results. 

Table C-40 Summary of Surface Soil DCGL Sensitivity Analysis 

Parameter Run 

Change in 

Sensitivity 

Parameter

Minimum Maximum

Change Nuclide(s) Change Nuclide(s)

Indoor/Outdoor 

Fraction 1 -32% -23% U-232 0% C-14 I-129 

Np-237 Tc-99 

2 21% 0% 

 C-14 I-129 Np237 Tc-99 U234 

30% U-232 

Source 

Thickness 

3 -50% 9% Cs-137 238% C-14 

4 200% -58% C-14 0% 

 Am-241 Cm243 Cm-244 

Pu-239 Pu240 

Unsaturated 

Zone Thickness 5 -50% -10% Tc-99 6% U-235 

6 150% -4% U-235 10% Tc-99 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 C-30 

Table C-40 Summary of Surface Soil DCGL Sensitivity Analysis 

Parameter Run 

Change in 

Sensitivity 

Parameter

Minimum Maximum

Change Nuclide(s) Change Nuclide(s)

Irrigation/Pump 

Rate 

7 -57% -1% U-232 52% I-129 

8 70% -31% I-129 2% U-232 

Distribution 

Coefficients 

(Kd) 

9 lower -100% Pu-239 6% U-232 

10 higher -4% U-232 1146% U-234 

Hydraulic 

Conductivity 

11 -99% 0% Sr-90 1873% I-129 

12 150% 0% 

 Am-241 C-14 

Cm-243 Cm244 Cs-137 Pu238 Pu-239 Pu240 Sr-90 U232 

122% U-235 

Runoff/Evapotransporation 

Coefficient 

13 -69% -28% U-234 3% U-232 

14 64% -3% U-232 123% Np-237 

Depth of Well 

Intake 

15 -40% -42% I-129 0.1% U-232 

16 100% 0% 

 Am-241 Cm243 Cm-244 

Cs-137 Pu-238 

Pu-239 Pu-240 

93% Np-237 

Length Parallel 

to Aquifer Flow 17 -50% 0% 

 Am-241 Cm243 Cm-244 

Cs-137 Pu-238 

Pu-239 Pu-240 

78% U-235 

18 100% -44% U-235 0.1% U-232 

Plant Transfer 

Factors 

19 -90% -4% I-129 387% Sr-90 

20 900% -90% Sr-90 -6% I-129 

Mass Balance 

Model 21 -69% -81% U-234 0% U-232 

2.4.2 Subsurface Soil (Lavery till) DCGLs 

To evaluate an excavation that would expose the resident farmer to subsurface 

material, DCGLs were developed to address this potential future source. It is possible that 

a farmer may install a cistern or well to access groundwater, and in the excavation process, 

contaminated Lavery till material from the subsurface may be spread on the ground surface 

and be a source of exposure. The following subsections discuss the files associated with 

this calculation. 

Subsurface Soil DCGLW Values

The subsurface DCGLw values are presented in the Excel file “WV Subsurface 

DCGLs.XLS” in the sheet “Base” (TableC-41), and are based on the RESRAD input file 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 C-31 

“WV Subsurface – 100 Base.RAD” and results from page 45 of the RESRAD summary 

output report “WV Subsurface – 100 Base.TXT”. 

For calculation of the distributed soil, DCGLW values for a 100 m2 source area of Lavery 

till on the surface were increased by a factor of 10 to account for an assumed blending of 

residually contaminated till with clean overlying soil in the excavation process (assuming 

0.5 m of till for each 5 m of total excavation). This factor is applied to the final RESRAD 

generated DCGLw as presented in the overall summary table (See “DCGL Summary” 

section). 

The input files for the subsurface soil evaluation are discussed in Section 2.2. These 

Lavery Till DCGLW values are used as the basis for calculation of the subsurface soil 

DCGLEMC values and for sensitivity analysis as described below. 

Subsurface Soil DCGLEMC Values

Calculation of DCGLEMC values for the subsurface Lavery till was based on the base 

case area of 100 m2

 used for development of the DCGLW values (after accounting for 

blending). The DCGLEMC values were generated by varying the source area. The RESRAD 

output for these simulations are presented and summarized in the Excel file “WV 

Subsurface DCGLs.XLS”. The results for each source area are presented in individual 

sheets (Tables C-42 to C-45). The sheet “Summary” presents the DCGLEMC values (Table 

C-46) and subsurface soil area factors (Table C-47) for each of the 18 radionuclides and 

selected source areas (ranging from 1 to 100 m2

). 

Subsurface Soil Sensitivity Analysis 

The subsurface soil DCGLW sensitivity to key parameters was assessed by varying the 

input values for specific parameters and tabulating the results. The Excel file “WV 

Subsurface DCGL Sensitivity.XLS” contains the DSRs and DCGLs for each of 18 

radionuclides from the RESRAD summary report output for each of the sensitivity 

simulations. Results of each run are in sheets SENS1 through SENS16 (Tables C-48 to C63). Also included in the file is a summarization of the calculated DCGLs (Table C-64) and 

a summary of the percent change from the base case (Table C-65) for each of the 

sensitivity runs (also presented in Table 5-10). Table C-66 below presents a summary of 

the subsurface soil sensitivity results. 

Table C-66 Summary of Subsurface Soil DCGL Sensitivity Analysis

Parameter Run 

Change in 

Sensitivity 

Parameter

Minimum Maximum

Change Nuclide(s) Change Nuclide(s)

Indoor/Outdoor 

Fraction 

1 -32% -25% Cs-137 0.1% U-234 

2 21% -1% U-238 35% U-232 

Source 

Thickness 

3 -67% 10% U-238 255% Tc-99 

4 233% -90% C-14 -1% Cs-137 

Unsaturated 

Zone Thickness 

5 -50% -3% Tc-99 0% 

 Am-241 C-14 

Cm-243 Cm-244 

Cs-137 Pu-238 

Pu-239 Pu-240 

Pu-241 Sr-90 U232 U-235 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 C-32 

Table C-66 Summary of Subsurface Soil DCGL Sensitivity Analysis

Parameter Run 

Change in 

Sensitivity 

Parameter

Minimum Maximum

Change Nuclide(s) Change Nuclide(s)

6 150% 0% 

 Am-241 C-14 

Cm-243 Cm-244 

Cs-137 Pu-238 

Pu-239 Pu-240 

Pu-241 Sr-90 

Tc-99 U-232 U235 

1% U-238 

Irrigation/Pump 

Rate 7 -57% -36% I-129 0% 

 Am-241 Cm243 Cm-244 Cs137 Pu-238 Pu239 Pu-240 

8 70% 0% Cm-243 Pu-238 

Pu-239 Pu-240 159% U-238 

Distribution 

Coefficients 

(Kd) 

9 lower -99% Pu-239 16% Tc-99 

10 higher -27% U-232 3144% U-234 

Hydraulic 

Conductivity 

11 -99% -1% U-238 3% I-129 

12 150% 0% 

 Am-241 C-14 

Cm-243 Cm-244 

Cs-137 I-129 

Np-237 Pu-238 

Pu-239 Pu-240 

Pu-241 Sr-90 

Tc-99 U-232 U233 U-234 U235 U-238 

0% 

 Am-241 C-14 

Cm-243 Cm-244 

Cs-137 I-129 

Np-237 Pu-238 

Pu-239 Pu-240 

Pu-241 Sr-90 

Tc-99 U-232 U233 U-234 U235 U-238 

Runoff/Evapotransporation 

Coefficient 

13 -69% -38% U-234 16% U-232 

14 64% -19% U-232 188% U-234 

Plant Transfer 

Factors 

15 -90% -0.4% U-238 574% Sr-90 

16 900% -90% Tc-99 -1% U-234 

2.4.3 Streambed Sediment DCGLs 

DCGLs were also developed to account for potential exposure associated with stream 

bank sediment (including direct pathways, fish ingestion, and venison ingestion). The 

stream bank rather than the streambed was the focus of the analysis because the 

recreationist is assumed to be in direct contact with the stream bank, and not the stream 

bed. 

Files associated with the calculations are discussed below and presented in the files 

attachment. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 C-33 

Streambed Sediment DCGLW Values

The sediment DCGLW values were calculated based on a recreationist exposure for a 

1,000 m2

 source area and results from the RESRAD summary output report are presented 

in the Excel file “WVDP Surface DCGLs.XLS” in the sheet “Base” (Table C-67). The input 

files for the sediment evaluation are discussed in Section 2.2. These sediment DCGLW

values are the basis for calculation of Sediment Area Factors and DCGLEMC values. 

Streambed Sediment DCGLEMC Values

The DCGLW values calculated on the Excel summary sheet previously discussed serve 

as the base case for subsequent DCGLEMC development, which are based on varying the 

source area from the 1,000 m2

 value used for the DCGLW values. The RESRAD output for 

these simulations are presented and summarized in the Excel file “WV Sediment 

DCGLs.XLS”. The results for each source area are presented in individual sheets (Tables 

C-68 to C-73). The sheet “Summary” presents the DCGLEMC values (Table C-74) and 

sediment area factors (Table C-75) the 18 radionuclides and selected source areas 

(ranging from 1 to 1,000 m2

). 

Streambed Sediment Sensitivity Analysis 

The sediment DCGLW sensitivity to key parameters was assessed by varying the input 

values and tabulating the results. The Excel file “WV Sediment DCGL Sensitivity.XLS” 

contains the RESRAD summary report output for each of the sensitivity simulations. 

Results of each run are in sheets SENS1 through SENS14 (Tables C-76 to C-89). Also 

included in the file is a summarization of the calculated DCGLs (Table C-90) and percent 

change from the base case (Table C-91) for each of the sensitivity runs (also presented in 

Table 5-11). Table C-92 below presents a summary of the sediment sensitivity analysis. 

Table C-92 Summary of Sediment DCGL Sensitivity Analysis 

Parameter Run 

Change in 

Sensitivity 

Parameter

Minimum Maximum

Change Nuclide(s) Change Nuclide(s)

Outdoor Fraction 1 -50% 0% C-14 97% U-232 

2 100% -50% Cm-243 0% C-14 

Source Thickness 3 -50% 0% Cm-243 157% C-14 

4 200% -52% C-14 0% 

 Am-241 Cm243 Cm-244 

Cs-137 Pu238 Pu-239 

Pu-240 

Unsaturated Zone 

Thickness 

5 0 m to 1m 0.3% Cs-137 83% U-234 

6 0 m to 3 m 0.3% Cs-137 83% U-234 

Soil/Water 

Distribution 

Coefficients (Kd) 

7 lower -90% Pu-239 47% Pu-241 

8 higher -59% U-233 127% Np-237 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 C-34 

Table C-92 Summary of Sediment DCGL Sensitivity Analysis 

Parameter Run 

Change in 

Sensitivity 

Parameter

Minimum Maximum

Change Nuclide(s) Change Nuclide(s)

Runoff/Evapotransporation 

Coefficient 9 -54% 0% 

 Am-241 

Cm-243 Pu238 Pu-239 

Pu-240 

8% U-232 

10 78% -29% U-233 0% 

 Am-241 Cm243 Cm-244 

Pu-238 Pu239 Pu-240 

Plant Transfer 

Factors 

11 -90% -29% U-233 82% Sr-90 

12 900% -82% Sr-90 -1% U-235 

Fish Transfer 

Factors 

13 -90% -28% U-233 99% Np-237 

14 900% -84% Np-237 -3% Cs-137 

Consideration of Subsurface Lavery till as a Continuing Source to Groundwater

An evaluation of the potential for the Lavery till to act as a continuing source to 

groundwater was conducted and concluded the following (See section 3.7 and Table 3-19 

of the body of the plan): 

A well screened entirely in the Lavery Till could not produce enough groundwater 

for the resident farmer scenario. 

A well screened in both the sand and gravel unit and Lavery till would likely pump 

mostly groundwater from the sand and gravel unit due to the much higher relative 

hydraulic conductivity and subsequent development of preferential flowpaths, and 

contain highly diluted contributions of contaminated groundwater from the Lavery 

Till. 

Advective movement from the Lavery Till to the overlying Sand and Gravel Unit is 

unlikely considering the vertical downward groundwater gradient. 

Diffusive movement from the Lavery Till to the Sand and Gravel Unit is unlikely 

considering the very low diffusion coefficients for radionuclides. 

Migration vertically upward from the till through the aquifer and into a well that is 

screened several meters above the till is unlikely. 

DCGL Summary 

The Excel File “WV DCGL Summary Tables.xls” (Table C-93) summarizes the DCGLs 

for the surface soil, subsurface soil and sediment, and presents DCGLW and DCGLEMC for a 

1 m2

 area (also presented in Table 5-8). 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 C-35 

Integrated Dose Assessment 

In order to account for potential exposure to multiple sources, a combined dose 

assessment was conducted. The assessment considered which combination of exposures 

was likely, and concluded that the resident farmer may also spend time in recreation along 

the stream bank. 

The Excel File “WV DCGL Summary Tables.xls” presents the calculated DCGLW and 

DCGLEMC values when considering the combined doses from surface soil (90% x 25 

mrem/yr = 22.5 mrem/y) and sediment sources (10% x 25 mrem/y = 2.5 mrem/y), which are 

summarized in Tables C-94, C-95, and C-96 (also presented in Table 5-13). In the same 

Excel file, Table C-96 presents the cleanup goals to be used as the criteria for the 

proposed remediation activities. Values in Table C-97 represent the DCGLW and DCGLEMC

values for surface soil and sediment (considering the combined dose), as well as cleanup 

goals for subsurface soil (which are 50% of the DCGLW and DCGLEMC values adjusted to 

provide a margin of confidence/safety factor for excavation success for each radionuclide 

(also presented in Table 5-12). 

Evaluation of Institutional Control Period 

After Phase 1 proposed remediation there is assumed to be a 30 year period of 

institutional controls (associated with storage of the HLW canisters until 2041), prior to site 

access by the critical receptors. During this period, radionuclide inventories will be subject 

to decay and leaching, which will result in site concentrations at the time of exposure that 

are reduced from the initial concentrations left at the time of proposed remediation. With the 

exception of Sr-90 and Cs-137, DCGLs were developed neglecting the effects of decay and 

leaching from the source during the 30 year institutional control period. The ratio of the 

initial concentrations in soil to the RESRAD generated soil concentration after a 30 year 

simulation was used to provide an evaluation of uncertainty associated with the assumption 

of neglecting decay/leaching. A RESRAD simulation was run using the surface soil base 

case without irrigation, well pumping, or plant/animal/human uptake from soil (see 

RESRAD input file “WV SURFACE – 10k – LCH_DCAY.RAD” and output file “WV 

SURFACE – 10k – LCH_DCAY_sum.txt”. The RESRAD concentration output summary file 

(see page 8 of the file “WV SURFACE – 10k – LCH_DCAY_conc.txt”) provides the soil 

concentration at year 30, which is then related to the initial soil concentration to quantify the 

effects of leaching/decay (see Excel file “WV Institutional Control.xls” Table C-98). 

Evaluation of Potential Dose Drivers and Sensitivity Parameters 

The impact of specific sensitivity parameters is dependent on the radionuclides that 

contribute the majority of the dose to the receptor. Due to limited site data, a full evaluation 

can not be performed until additional site characterization data is available. In the interim, 

Table C-99 presented below identifies the primary dose pathways for each radionuclide 

and indicates which of the sensitivity parameters have significant impact on the dose. This 

evaluation would be refined as additional site data are collected. 
WVDP PHASE 1 DECOMMISSIONING PLAN

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Table C-99 Summary of Primary Dose Pathways 

Nuclide Primary Pathway for Dose Key Parameters(1) Year of 

Peak Dose 

Surface Soil 

Am-241 Water independent (plant uptake) plant transfer factors, source thickness 0.00E+00

C-14 Water independent (plant uptake) source thickness 0.00E+00 

Cm-243 External Exposure, Water independent 

(plant uptake) 

plant transfer factors, source thickness 0.00E+00

Cm-244 Water independent (plant uptake) plant transfer factors, source thickness 0.00E+00 

Cs-137 External Exposure outdoor fraction, plant transfer factors 0.00E+00

I-129 Water dependent (water ingestion, plant 

and milk uptake) 

K, Kd, runoff/evap coefficients, well intake 

depth, groundwater model 

9.21E+00

Np-237 Water dependent (water ingestion, plant 

uptake)

hydraulic conductivity, Kd, runoff/evap 

coefficients, well intake depth, groundwater 

model

2.01E+01

Pu-238 Water independent (plant uptake) Kd, plant transfer factors 0.00E+00 

Pu-239 Water independent (plant uptake) Kd, plant transfer factors 0.00E+00

Pu-240 Water independent (plant uptake) Kd, plant transfer factors 0.00E+00 

Pu-241 Water independent (plant uptake) Kd, plant transfer factors 5.52E+01

Sr-90 Water independent (plant uptake) source thickness, plant transfer factors, Kd, 

groundwater model 

0.00E+00

Tc-99 Water dependent (water ingestion, plant 

uptake), independent (plant uptake) 

source thickness, well intake depth, plant 

transfer factors, length parallel to flow, Kd, K, 

groundwater model 

1.54E+00

U-232 External Exposure outdoor fraction, plant transfer factors 8.17E+00 

U-233 Water dependent (water ingestion, plant 

uptake)

irrigation/pump rate, Kd, runoff/evap 

coefficients, groundwater model 

2.96E+02

U-234 Water dependent (water ingestion, plant 

uptake)

irrigation/pump rate, Kd, runoff/evap 

coefficients, groundwater model 

2.96E+02

U-235 Water dependent (water ingestion, plant 

uptake)

irrigation/pump rate, Kd, runoff/evap 

coefficients, groundwater model 

2.96E+02

U-238 Water dependent (water ingestion, plant 

uptake)

irrigation/pump rate, Kd, runoff/evap 

coefficients, groundwater model 

2.96E+02

Subsurface Soil 

Am-241 External Exposure, Water independent 

(plant uptake) 

source thickness, plant transfer factors 0.00E+00

C-14 Water independent (plant uptake) source thickness 0.00E+00 

Cm-243 External Exposure outdoor fraction, source thickness 0.00E+00

Cm-244 Water independent (plant uptake) source thickness, plant transfer factors 0.00E+00 

Cs-137 External Exposure outdoor fraction, source thickness 0.00E+00
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 C-37 

Table C-99 Summary of Primary Dose Pathways 

Nuclide Primary Pathway for Dose Key Parameters(1) Year of 

Peak Dose 

I-129 Water dependent (water ingestion) source thickness, irrigation/pump rate, Kd, 

runoff/evap coefficients 

6.32E+00

Np-237 Water independent (soil ingestion, plant 

uptake)

source thickness, Kd, runoff/evap coefficients 1.37E+01

Pu-238 Water independent (plant uptake, soil 

ingestion and inhalation) 

source thickness, Kd, plant transfer factors 0.00E+00 

Pu-239 Water independent (plant uptake, soil 

ingestion and inhalation) 

source thickness, Kd, plant transfer factors 0.00E+00

Pu-240 Water independent (plant uptake, soil 

ingestion and inhalation) 

source thickness, Kd, plant transfer factors 0.00E+00 

Pu-241 Water independent (plant uptake) source thickness, Kd, plant transfer factors 6.14E+01

Sr-90 Water independent (plant uptake) source thickness, Kd, plant transfer factors 0.00E+00 

Tc-99 Water dependent (plant uptake) source thickness, plant transfer factors 0.00E+00

U-232 External Exposure outdoor fraction, source thickness 4.60E+00 

U-233 Water dependent (water ingestion) Kd, runoff/evap coefficients 1.97E+02

U-234 Water dependent (water ingestion) Kd, runoff/evap coefficients 1.97E+02 

U-235 External Exposure outdoor fraction, source thickness, Kd 0.00E+00

U-238 Water dependent (water ingestion) source thickness, irrigation/pump rate, Kd, 

runoff/evap coefficients, groundwater model 

1.98E+02

 Sediment 

Am-241 External Exposure, Soil ingestion, Water 

independent (meat uptake) 

outdoor fraction 0.00E+00

C-14 Water independent (meat uptake), Water 

dependent (fish uptake) 

source thickness, unsaturated thickness, Kd 0.00E+00 

Cm-243 External Exposure outdoor fraction 0.00E+00

Cm-244 Soil ingestion outdoor fraction 0.00E+00 

Cs-137 External Exposure outdoor fraction 0.00E+00

I-129 Water independent (meat uptake), Water 

dependent (fish uptake) 

unsaturated thickness, Kd, fish transfer 

factors 

0.00E+00

Np-237 External Exposure, Water independent 

(meat uptake), Water dependent (fish 

uptake)

unsaturated thickness, Kd, fish transfer 

factors 

0.00E+00

Pu-238 Water independent (meat uptake), Soil 

ingestion 

outdoor fraction, Kd 0.00E+00 

Pu-239 Water independent (meat uptake), Soil 

ingestion 

outdoor fraction, Kd 2.82E-01

Pu-240 Water independent (meat uptake), Soil 

ingestion 

outdoor fraction, Kd 1.18E-01
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 C-38 

Table C-99 Summary of Primary Dose Pathways 

Nuclide Primary Pathway for Dose Key Parameters(1) Year of 

Peak Dose 

Pu-241 External Exposure, Water independent 

(meat uptake), Soil ingestion 

outdoor fraction, Kd 5.78E+01

Sr-90 Water independent (meat uptake) plant and fish transfer factors 0.00E+00 

Tc-99 Water independent (meat uptake) Kd, plant and fish transfer factors 0.00E+00

U-232 External Exposure outdoor fraction, Kd 7.72E+00 

U-233 External Exposure, Water independent 

(meat uptake), Water dependent (fish 

uptake)

outdoor fraction, unsaturated thickness, Kd, 

plant and fish transfer factors 

1.56E-01

U-234 Water independent (meat uptake), Water 

dependent (fish uptake) 

outdoor fraction, unsaturated thickness, Kd, 

fish transfer factors 

1.81E-01

U-235 External Exposure outdoor fraction 0.00E+00

U-238 External Exposure outdoor fraction, fish transfer factors 0.00E+00 

 NOTE: (1) Key parameters identified in sensitivity runs. As additional site characterization data becomes available, the 

radionuclides driving dose and parameters most critical to calculating dose can be used to refine the sensitivity 

analysis. 

3.0 References 

Beyeler, et al. 1999, Residual Radioactivity from Decommissioning, Parameter Analysis, 

NUREG/CR-5512, Vol 3, Draft Report for Comment. Beyeler, W. E., W. A. 

Hareland, F. A. Duran, T. J. Brown, E. Kalinina, D. P. Gallegos, and P. A. Davis, 

Sandia National Laboratories, Albuquerque, New Mexico, October 1999. 

EPA 1997, Exposure Factors Handbook. National Center for Environmental Assessment, 

Office of Research and Development, U. S. Environmental Protection Agency, 

Washington, D.C., 1997. 

NRC 1997, Generic Environmental Impact Statement in Support of Rulemaking on 

Radiological Criteria for License Termination of NRC-Licensed Nuclear Facilities; 

Final Policy Statement. NUREG-1496, Vol. 1. U.S. Nuclear Regulatory Commission, 

Office of Regulatory Research, Division of Regulatory Applications, Washington, 

D.C., July 1997. 

Sheppard and Thibault 1990, "Default Soil Solid/Liquid Partition Coefficients, Kds, for Four 

Major Soil Types: A Compendium," Sheppard, M.I., and D.H. Thibault, Health

Physics, 59:471-482, 1990. 

Yu, et al. 1993, Data Collection Handbook to Support Modeling Impacts of Radioactive 

Material in Soil. Yu, C., et al., Environmental Assessment and Information Sciences 

Division, Argonne National Laboratory, Argonne, Illinois, April 1993. 

Yu, et al. 2000, Development of Probabilistic RESRAD 6.0 and RESRAD-BUILD 3.0 

Computer Codes, NUREG/CR-6697, ANL/EAD/TM-98. Yu, C., et al., 

Environmental Assessment Division, Argonne National Laboratory, Argonne, 

Illinois, November 2000. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 C-39 

Yu, et al. 2001, User’s Manual for RESRAD Version 6, ANL/EAD-4. Yu, C., et al., 

Environmental Assessment Division, Argonne National Laboratory, Argonne, 

Illinois, July 2001. 

WVNSCO 1993a, Environmental Information Document, Volume I, Geology, WVDP-EIS004, Rev. 0. West Valley Nuclear Services Company, West Valley, New York, 

1993.

WVNSCO 1993b, Environmental Information Document, Volume III, Hydrology: Part 4, 

Groundwater Hydrology and Geochemistry, WVDP-EIS-009, Rev. 0. West Valley 

Nuclear Services Company, West Valley, New York, 1993.

WVNSCO 1993c, Environmental Information Document, Volume III, Hydrology: Part 5, 

Vadose Zone Hydrology, WVDP-EIS-009, Rev. 0. West Valley Nuclear Services 

Company, West Valley, New York, 1993.

WVNSCO 1993d, Environmental Information Document, Volume VIII, Air Resources: Part 

2, Meteorology, WVDP-EIS-014, Rev. 0. West Valley Nuclear Services Company, 

West Valley, New York, 1993.

Attachments 

1. Electronic Files Described in Section 2 (provided separately) 

2. Electronic File Described in Section 1 (provided separately) 
This page is intentionally blank. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 0 D-3 

permanent hydraulic barrier of slurry wall type construction would be installed on the 

downgradient side of the excavation in soil contaminated by the north plateau groundwater 

plume to act as an intrusion barrier to prevent the migration of Sr-90 contaminated groundwater 

from the non-source area of the north plateau groundwater plume into the WMA 1 excavation. 

The permanent downgradient hydraulic barrier would: 

Prevent recontamination of the remediated and backfilled WMA 1 excavation from the 

non-source area of the plume until a Phase 2 decommissioning decision is made, and 

Minimize groundwater recharge to the non-source area of the plume, thereby 

minimizing hydraulic heads and groundwater velocity. 

A French drain system would be installed adjacent and hydraulically upgradient of the 

permanent hydraulic barrier wall once the WMA 1 excavation has been backfilled to maintain 

groundwater elevations near there current levels. The French drain system would: 

Prevent groundwater mounding against, and potential overtopping of, the permanent 

downgradient hydraulic barrier wall; 

Maintain hydraulic heads on the upgradient side of the barrier wall that coincide with 

the elevation of the French drain system, that are higher than groundwater levels 

downgradient of the barrier wall. This would create a hydraulic gradient towards the 

non-source area of the north plateau groundwater plume, preventing seepage from the 

plume through the wall into the backfilled excavation; and 

In conjunction with the permanent downgradient hydraulic barrier, minimize 

groundwater recharge to the non-source area of the North Plateau Plume thereby 

minimizing hydraulic heads and groundwater velocity across the North Plateau. 

1.1.2 Hydraulic Barrier Walls and French Drain System

The WMA 1 excavation would require the installation of approximately 2,250 linear feet of 

subsurface hydraulic barrier wall comprised of temporary interlocking steel sheet piling on the 

upgradient and cross-gradient sides of the excavation and a permanent hydraulic barrier wall 

on the downgradient side of the excavation before excavation begins as shown on Figure D-1. 

Temporary Sheet Pile Barrier Walls

Approximately 1,500 feet of conventional interlocking sheet piles would be installed in 

uncontaminated soils along the upgradient and cross-gradient sides of the excavation boundary 

before excavation begins (Figure D-1). The piles would be driven a minimum of two feet into the 

underlying Lavery till to prevent groundwater from migrating beneath the piles into the WMA 1 

excavation.

Contaminated soil exceeding the subsurface soil cleanup criteria specified in Section 5 

would be excavated leaving a soil cut-back slope against the sheet pile walls containing soil 

with radionuclide concentrations below the subsurface soil clean-up criteria.2The soil cut-backs 

along the sheet pile walls would be surveyed during the Phase 1 final status surveys as 

specified in Sections 7 and 9 of this plan. The sheet pile barrier wall would be removed as

2

 Figure 7-8 in Section 7 of this plan shows typical excavation slopes. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 D-4 

 specified in Section 7 once the final status survey, the independent verification survey, and 

backfilling of the WMA 1 excavation is completed to allow a return to typical groundwater flow 

patterns within the sand and gravel unit.

Figure D-1. Plan View of the WMA 1 Excavation 

Permanent Downgradient Hydraulic Barrier Wall

The permanent hydraulic barrier wall constructed on the downgradient side of the WMA 1 

excavation (Figure D-1) would be a vertical soil-cement-bentonite slurry wall installed using 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 D-5 

slurry wall trenching technology. This hydraulic barrier technology was selected because of its 

long history of successful usage. This wall would prevent migration of Sr-90 contaminated 

groundwater from the non-source area of the North Plateau Plume into the WMA 1 excavation 

both during excavation and after backfilling the excavation with clean fill.

The hydraulic barrier wall downgradient of the WMA 1 excavation would be installed under 

a carefully planned and rigorous quality control-quality assurance program as described in 

Section 8. 

The soil-cement-bentonite barrier wall would be a mixture of 85 percent soil, five percent 

Portland cement, and 10 percent bentonite. The Portland cement would provide internal 

stability to the barrier wall and it would have an initial maximum design hydraulic conductivity of 

6.0 E-06 cm/s.

The soil-cement-bentonite barrier wall would be approximately 750 feet long, two to 13 feet 

wide, and would be up to 50 feet deep with an average depth of 27 feet. The wall would extend 

through the sand and gravel unit and a minimum of two feet into the Lavery till to minimize 

groundwater flow beneath the bottom of the wall.

Approximately 225 feet of barrier wall outside of the excavation boundary would be two to 

three feet thick. The remaining 525 feet of barrier wall within the boundary of the excavation 

would be at least 13 feet thick to allow the excavation of subsurface soils up to and into the 

barrier wall. The proposed thickness would allow an excavation cut back slope of 1:2 

(horizontal to vertical), which is typical of what can be achieved in most stiff clayey soils. The 

barrier wall material within the excavation cut-back slope would be surveyed during the Phase 1 

final status survey.3

The upper three feet of the barrier wall would be constructed of clean backfill similar to the 

surrounding sand and gravel unit. This material would allow vehicular traffic over the barrier 

wall without damaging the underlying barrier wall.

French Drain System

A French drain system would be installed upgradient of the permanent hydraulic barrier 

wall during the backfilling of the WMA 1 excavation (Figure D-1). The French drain would be 

installed to keep groundwater levels at their current level on the upgradient side of the barrier 

wall to prevent groundwater mounding against the wall, prevent potential overtopping of the 

wall, and promote groundwater flow towards the non-source area of the north plateau 

groundwater plume.

The French drain would be constructed by excavating a trench, approximately four feet 

wide and 10 feet deep, placing perforated pipe into the bottom of the trench, and backfilling the 

trench with permeable granular materials. The northwest and southeast portions of the French 

drain would meet at a concrete manhole located near the mid-point of the barrier wall. The 

French drain would be sloped to the southeast to discharge by gravity flow to a surface water 

drainage discharging to Erdman Brook.

3 As explained in Section 7 of this plan, any soil found to exceed cleanup goals would be removed only within 

the confines of the planned excavation, that is, within the confines of the downgradient hydraulic barrier wall 

and the sheet piles.
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 D-6 

1.2 Waste Management Area 2

The Phase 1 proposed decommissioning activities in WMA 2 would include the removal of 

Lagoons 1 through 3, the Neutralization Pit, Interceptors, Solvent Dike, and surrounding 

contaminated soils within a single excavation down into the underlying Lavery till. Most of this 

excavation is cross gradient to the non-source area of the North Plateau Plume (Figure D-2).

The removal of the lagoons, sub-grade structures, and surrounding soils would require the 

installation of a permanent subsurface hydraulic barrier wall prior to excavation to facilitate 

removal activities and to prevent potential recontamination of the area from the non-source area 

of the north plateau groundwater plume as described in Section 7. The barrier wall for WMA 2 

is described in greater detail below.

1.2.1 Need for Subsurface Engineered Barriers 

Lagoons 1 through 3, sub-grade structures, and surrounding contaminated vadose and 

saturated soils would be removed to a depth of approximately 14 feet to meet the unrestricted 

release criteria in 10 CFR 20.1402. Most of the WMA 2 excavation may be impacted by 

migration of Sr-90 contaminated groundwater from the adjacent non-source area of the north 

plateau groundwater plume. The need for a subsurface hydraulic barrier wall for the 4.2-acre 

excavation area across WMA 2 is the same as the rationale described earlier in Section 1.1.1 of 

this Appendix for the excavation of WMA 1. 

A permanent hydraulic barrier of slurry wall type construction would be installed on the 

northwest side of the WMA 2 excavation to act as an intrusion barrier to prevent the migration 

of Sr-90 contaminated groundwater from the non-source area of the north plateau groundwater 

plume into the WMA 2 excavation. This permanent downgradient hydraulic barrier would 

prevent recontamination of the remediated and backfilled WMA 2 excavation from the nonsource area of the north plateau plume until a Phase 2 decommissioning decision is made.

1.2.2 Hydraulic Barrier Wall

Before excavation activities begin in WMA 2 a permanent subsurface hydraulic barrier wall 

would be installed on the northwest side of the WMA 2 excavation as shown on Figure D-3.

Permanent Hydraulic Barrier Wall 

The permanent hydraulic barrier wall constructed on the northwest side of the WMA 2 

excavation would be a vertical soil-cement-bentonite slurry wall installed using slurry wall 

trenching technology. This hydraulic barrier technology was selected because of its long history 

of successful usage. This wall would prevent migration of Sr-90 contaminated groundwater 

from the non-source area of the north plateau plume into the WMA 2 excavation both during 

excavation and after the excavation has been backfilled with clean fill.

The hydraulic barrier wall installed northwest of the WMA 2 excavation would be installed 

under a carefully planned and rigorous quality control-quality assurance program as described 

in Section 8. The barrier wall would be approximately 1,100 feet long, sufficiently wide to 

provide the stability necessary to permit excavation close to the edge of the excavation, and up 

to 20 feet deep, with an average depth of 16 feet. The wall would extend through the sand and 

gravel unit and a minimum of two feet into the Lavery till to minimize groundwater flow beneath 

the bottom of the wall.
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 D-7 

 Figure D-2. Plan View of the WMA 2 Excavation 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 D-8 

The upper three feet of the barrier wall would be constructed of clean backfill similar to the 

surrounding sand and gravel unit. This material would allow vehicular traffic over the barrier 

wall without damaging the underlying barrier wall.

1.3 Durability of Engineered Barriers

The materials used in the construction of the soil-cement-bentonite slurry walls are 

common natural geologic construction materials that exhibit long-term durability within the 

natural environment. The engineered barriers are expected to retain their design effectiveness 

until the start of Phase 2 of the decommissioning at a minimum. Their continued use would be 

among the factors evaluated in determining the approach to Phase 2 of the decommissioning. 

The low-permeability bentonite used in the slurry wall construction is a natural geologic 

material exhibiting demonstrated long-term mineralogical and geologic stability (Mitchell 1986 

and Mitchell 1993). Chemical contaminants that might degrade the physical characteristics 

and/or compromise the hydraulic conductivity of soil-bentonite slurry walls include: 

Concentrated solutions of organic fluids (Mille, et al. 1992 and Khera and Tirumala 

1992),

Organic groundwater contaminants (Evans, et al. 1985b and Grube 1992), and 

Acidic or highly alkaline solutions (Evans, et al. 1985a and Fang et al. 1992). 

However, these conditions are not present within the project premises. 

The backfill to be used for slurry wall construction would be a mixture of soil, Portland

cement, and commercial sodium bentonite. The soil can be any material that could be classified 

as CL, CL/ML or ML/CL by the Unified Soil Classification System. The soil backfill would be 

natural geologic materials similar to the sand and gravel unit in the North Plateau. 

Uncontaminated sand and gravel from the trench excavation may also be used as soil backfill 

for the slurry wall. The sodium bentonite would be added at a rate recommended by the vendor 

to achieve a hydraulic conductivity on the order of 1 E-08 to 1 E-06 cm/s.

The geotechnical stability of the soil-cement-bentonite slurry wall has been evaluated under 

combined static and seismic loading conditions. The evaluation results indicate that the 

proposed soil-cement-bentonite slurry wall would provide the necessary strength to withstand 

damage from static and seismic loads predicted to occur during a hypothetical earthquake 

generating a horizontal acceleration of 0.20 g in the soil, with an approximate factor of safety of 

greater than 1.3 to greater than 3.0 (URS 2000). 

The French drain would be constructed of natural (stone backfill) and man-made 

(perforated drain pipe, geotextile) materials. The French drain trench backfill would be designed 

to minimize silting of the drainpipe. The French drain would be periodically monitored and 

maintained until the start of Phase 2 decommissioning to ensure it is functioning properly.

1.4 Engineered Barriers and Groundwater Flow 

Groundwater flow in the sand and gravel unit is currently to the northeast across the north 

plateau through WMA 1 and parallel to WMA 2 (Figure D-2). The permanent hydraulic barrier 

wall and French drain to be installed on the downgradient side of the WMA 1 excavation would

be nearly perpendicular to the current groundwater flow path in the sand and gravel unit in the 

north plateau.
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 D-9 

1.4.1 Conceptual Model 

A three-dimensional near-field groundwater model was developed to simulate groundwater 

flow conditions near the engineered barriers installed at WMA 1 and WMA 2 using the STOMP 

computer code (Nichols, et al. 1997)4. This model is a revised version of the near-field model 

described in Appendix E to the Revised Draft Environmental Impact Statement for 

Decommissioning and/or Long-Term Stewardship at the West Valley Demonstration Project 

and Western New York Nuclear Service Center. Figure D-3 shows the boundaries of the north 

plateau near-field model.

Figure D-3. North Plateau Groundwater Flow Model Boundary 

The north plateau model mimics the shape of the lateral extent of the sand and gravel unit. 

It is oriented from the southwest to the northeast and extends downward from the ground 

surface to the top of the Kent Recessional Sequence.

Hydrogeologic units represented in the model are the thick-bedded unit, the slack-water 

sequence and the unweathered Lavery till. Together, the thick-bedded unit and the slack-water 

sequence comprise the surficial sand and gravel unit. The thick-bedded unit comprises 

glaciofluvial gravel and alluvial deposits that range from one to five meters in thickness 

overlying the unweathered Lavery till. The slack-water sequence is a depositional sequence 

with layers of gravel, sand and silt filling a southwest-to-northeast trending channel in the upper 

portion of the unweathered Lavery till. The slack-water sequence varies in thickness from zero 

to five meters with the thickest portions beneath the Process Building. The unweathered Lavery 

4 STOMP (Subsurface Transport Over Multiple Phases) solves the relevant conservation equations for the 

flow of both liquid and gas (air with water vapor) phases in a porous matrix confined in a cylindrical shape. 

This computer code was developed by DOE’s Pacific Northwest National Laboratory. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 D-10 

till is a glacial till with a thickness range of 10 to 17 meters in the model volume.

The hydrogeologic units incorporated into the north plateau near-field flow model are 

represented in Figures D-4 through D–8. The slack-water sequence appears in the 

northeastern portion of the model as shown in Figures D-6 through D–8. The hydraulic 

conductivities of these units are assumed constant over the model domain with values of 2.5 E03, 5.3 E-03, and 6.0 E-08 centimeters per second for the thick-bedded unit, slack-water 

sequence, and unweathered Lavery till, respectively. Two variants of the north plateau nearfield model were developed to simulate current north plateau groundwater flow conditions and 

to evaluate north plateau groundwater flow conditions associated with the proposed hydraulic 

barriers to be installed during Phase 1.

Figure D-4. Cross Section of North Plateau Near-Field Model – Northwest to Southeast, 

Distance of 0 to 80 Meters 

Figure D-5. Cross Section of North Plateau Near-Field Model – Northwest to 

Southeast, Distance of 80 to 120 Meters
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 D-11 

Figure D-6. Cross Section of North Plateau Near-Field Model – Northwest to 

Southeast, Distance of 120 to 250 Meters

Figure D-7. Cross Section of North Plateau Near-Field Model – Northwest to 

Southeast, Distance of 250 to 310 Meters
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 D-12 

Figure D-8. Cross Section of North Plateau Near-Field Model – Northwest to Southeast, 

Distance of 310 to 820 Meters 

1.4.2 Modeling Current Conditions 

To simulate current conditions, the horizontal portion of the near-field groundwater model 

grid comprised rectangular blocks with 81 blocks in the northwest-to-southeast direction and 64 

blocks in the southwest-to-northeast direction. Grid blocks with horizontal dimension as large 

as 50 meters were used along the west and north boundaries while grid block horizontal 

dimensions range from 1 to 10 meters over most of the model domain. For the vertical 

direction, the upper three meters were represented using 15 0.2-meter-thick layers, the next 

three meters were represented using six 0.5-meter-thick layers, and the bottom 17 meters were 

represented using 17 1.0-meter-thick layers. With these dimensions, the model utilized 

approximately 200,000 grid blocks.

Boundary conditions applied for the near-field model are consistent with site observations 

and with those applied for the site-wide model. At the bottom of the unweathered Lavery till, 

atmospheric pressure was applied representing the presence of a water table in the Kent 

Recessional Sequence. On the sides of the model, no flow conditions were applied for the 

unweathered Lavery till. On the southwest side of the model, lateral recharge into the thickbedded unit of 20 cubic meters per day was applied. On the northwest, southeast, and 

northeast sides of the model, atmospheric pressure conditions were applied for the thickbedded unit and slack-water sequence to represent seepage to Quarry Creek, Erdman Brook, 

and Franks Creek.

Evaluation of simulated pressures and measured conditions in target groundwater wells 

showed that a uniform recharge of 26 centimeters per year produced the closest match to 

existing conditions. Table D-1 compares measured hydraulic heads in wells screened in the 

sand and gravel unit from the north plateau with predicted hydraulic heads generated by the 

near-field model for three different recharge rates. Figure D-9 shows the resulting plot of water 

table elevation in the thick bedded unit for a recharge of 26 centimeters per year. These water 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 D-13 

table elevations are consistent with the measured heads and the predictions of the site-wide 

groundwater model described in Appendix E to the Revised Draft Environmental Impact 

Statement for Decommissioning and/or Long-Term Stewardship at the West Valley 

Demonstration Project and Western New York Nuclear Service Center. Table D-2 shows the 

modeled flow balance.

Table D-1. North Plateau Near-field Flow Model Calibration for Head(1)

Groundwater 

Well

Measured

Head (ft) 

Predicted Head (ft) at Specified Recharge 

18 cm/y 26 cm/y 34 cm/y 

103 1391.4 1386.8 1391.6 1394.5 

104 1385.5 1379.6 1383.1 1385.7 

116 1380.5 1372.4 1376.8 1379.4 

203 1394.4 1400.2 1401.6 1404.2 

205 1393.1 1397.9 1399.2 1401.2 

301 1410.7 1401.9 1406.8 1410.6 

401 1410.3 1401.5 1406.4 1409.5 

406/86-08 1393.45 1394.1 1397.4 1400.0 

601 1377.3 1376.9 1378.9 1380.9 

603 1391.9 1395.0 1397.0 1399.6 

604 1391.6 1389.7 1391.9 1394.6 

86-09 1391.8 1391.6 1396.5 1399.8 

86-12 1364.8 1343.6 1345.2 1346.8 

408 1391.8 1391.0 1394.8 1398.4 

501 1391.3 1386.8 1391.5 1394.5 

403 1408.0 1401.1 1405.8 1409.1 

801 1376.6 1369.3 1373.1 1375.7 

804 1369.9 1391.6 1396.5 1399.8 

Sum of Squared Residuals (ft2)

(2) 1111.4 730.1 831.4 

NOTES: (1) This specified recharge is the net inflow at the ground surface that results from the balance of 

precipitation, evapotranspiration, and run-off. 

 (2) Sum of squared residuals = (Measured Head – Predicted Head)2

 for each location, then summed. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 D-14 

Table D-2. Summary of Sand and Gravel Unit Flow Balance(1)

Inflow Outflow 

Location Rate (m3/y) Location Rate (m3/y) 

Ground Surface 107,624 Down to ULT 9,060 

Bedrock leakage 7,304 Quarry Creek 8,456 

Erdman Brook 15,238 

Frank’s Creek 66,713 

North Plateau Ditch 15,445 

Totals 114,928 114,912 

NOTE: (1) For a recharge rate of 26 centimeters per year 

LEGEND: ULT = unweathered Lavery till 

The relationship between rate of flow in the slack-water sequence and the thick-bedded 

unit above the slack-water sequence was investigated through tabulation of groundwater 

velocities along a flow path extending from the location of the Process Building to the north 

plateau ditch. Average linear velocities predicted by the near-field model for this path are 

presented in Table D-3. An effective porosity value of 0.225 was used for the thick-bedded unit 

and an effective porosity value of 0.35 for the slack-water sequence. For the slack-water 

sequence and thick-bedded unit above the slack-water sequence, the travel time and average 

velocity along the flow path are 2.26 years and 141 meters per year and 3.07 years and 

104 meters per year, respectively.

Table D-3. Average Linear Velocity for Flow Path Originating at the Process Building 

Distance Along Flow 

Path (m) 

Average Linear Velocity (m/y) 

Slack-water Sequence Thick-bedded Unit 

0 to 40 107.4 78.6 

40 to 80 117.7 86.6 

80 to 120 127.9 96.5 

120 to 160 139.8 102.5 

160 to 200 150.4 110.3 

200 to 240 161.5 118.4 

240 to 280 174.9 128.5 

280 to 320 191.8 140.9 

NOTE: To convert meters per year to feet per year, multiply by 3.2803.

1.4.3 Modeling Conditions Following Phase 1 of the Decommissioning 

The near-field groundwater flow model developed to assess current groundwater flow 

conditions was used to evaluate groundwater flow following the installation of the Phase 1 

hydraulic barriers and WMA 1 French drain. The WMA 1 and WMA 2 slurry walls are modeled 

as one-meter thick extending downward to the unweathered Lavery till with a hydraulic 

conductivity of 1.0 E-06 cm/s. The WMA 1 hydraulic barrier wall downgradient of the Process 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 D-15 

Building is oriented parallel to the groundwater elevation contours and perpendicular to 

groundwater flow as shown in Figure D-9. The segment of barrier wall between the Process 

Building and the Waste Tank Farm has been modeled parallel to groundwater flow due to the 

model constraints. The French drain for WMA 1 was modeled as one-meter thick with a depth 

of three meters and a hydraulic conductivity of 10 cm/s.

The cross-sectional structure of the aquifer is that represented in Figures D-4, D-5, D-6, D7, and D-8 with the same vertical discretization as the current conditions case.

Figure D-9 shows the distribution of hydraulic heads predicted following completion of 

Phase 1 of the decommissioning. The results indicate an overall increase of approximately four 

feet in water table elevation across the large backfilled WMA 1 and WMA 2 excavations 

formerly occupied by the Process Building and the lagoons, respectively.

The higher groundwater elevations in the backfilled WMA 1 excavation suggest that 

groundwater would flow through the WMA 1 slurry wall to the northwest, towards the Waste 

Tank Farm, and to the northeast, towards the non-source area of the north plateau groundwater 

plume. However, a significant volume of this flow would be diverted by the French drain and 

discharged to Erdman Brook (Table D-4).

Groundwater elevations coincide with the bottom of the French drain near the WMA 1 

barrier wall. Groundwater elevations on the downgradient side of the WMA 1 barrier wall are 

over 10 feet lower than on the upgradient side, resulting in a steep hydraulic gradient across 

the barrier wall and a shallower gradient along the non-source area of the north plateau 

groundwater plume.

Groundwater levels in the backfilled WMA 2 excavation are several feet higher than 

modeled in the current conditions scenario and would be below grade across the backfilled 

WMA 2 excavation. Groundwater elevations are up to 10 feet lower on the north plateau plume 

side of the WMA 2 barrier wall, suggesting groundwater flow to the northwest and northeast 

through the WMA 2 slurry wall towards the non-source area of the north plateau groundwater 

plume and to the southeast towards Erdman Brook.

 Table D-4 summarizes the modeled flow balance. Table D-5 shows the average linear 

velocities predicted by the near-field model for conditions after Phase 1. 

Table D-4. Summary of Sand and Gravel Unit Flow Balance After Phase 1(1)

Inflow Outflow 

Location Rate (m3/y) Location Rate (m3/y) 

Ground Surface 107,624 Down to ULT 8,884 

Bedrock leakage 7,304 Quarry Creek 8,659 

 Erdman Brook (TBU) 14,881 

 Erdman Brook 

(French drain) 

21,700

 Frank’s Creek 47,117 

 North Plateau Ditch 13,664 

Total 114,928 114,905 

NOTE: (1) For a recharge rate of 26 centimeters per year.
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 D-16 

Distance, Northwest to Southeast (m) Distance, Northwest to Southeast (m)

CURRENT CONDITION AFTER PHASE 1

1390

Distance, Southwest to Northeast(m)

1410

1390

1370

Modeled Barrier 

Designed Hydraulic Barrier 

Figure D-9. Groundwater Flow Associated with the WMA 1 and WMA 2 Engineered Barriers 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 D-17 

Table D-5. Average Linear Velocity for Flow Path Originating at the Process Building 

Area After Phase 1 

Distance Along Flow 

Path (m) 

Average Linear Velocity (m/y) 

Slack-water Sequence Thick-bedded Unit 

0 to 40 89.5 65.9 

40 to 80 84.6 67.8 

80 to 120 13.1 1.9 

120 to 160 45.3 1.8 

160 to 200 73.5 2.0 

200 to 240 99.0 7.6 

240 to 280 115.4 88.2 

280 to 320 133.3 119.0 

NOTE: To convert meters per year to feet per year, multiply by 3.2803. 

In calculation of linear velocities shown in Table D-5, the value of effective porosity of 0.35 

was used for the slack-water sequence while the moisture content of the thick-bedded unit was 

used to reflect unsaturated conditions that develop along the flow path north of the location of 

the slurry wall. For the slack-water sequence and thick-bedded unit above the slack-water 

sequence, the travel time and average velocity along the flow path are 6.37 years and 

50 meters per year and 70 years and 4.6 meters per year, respectively. 

1.4.4 Groundwater Modeling Predictions for Conditions Following Phase 1 

The revised near-field groundwater model for the north plateau suggests that the 

engineered barriers to be installed during Phase 1 decommissioning would have the following 

effect on groundwater flow in the north plateau: 

Groundwater flow patterns upgradient of the WMA 1 barrier wall and French drain 

would be similar to current flow patterns in the sand and gravel unit shown in Figure D9.

Water table elevations in WMA 1 would be approximately 15 feet higher on the 

upgradient side of the WMA 1 barrier wall compared to water levels immediately 

downgradient of the wall. 

This steep hydraulic gradient suggests that groundwater would preferentially flow from 

the backfilled WMA 1 excavation across the barrier wall into the non-source area of the 

north plateau plume, rather than from the non-source area of the plume into the 

backfilled WMA 1 excavation.

Higher groundwater elevations would also be found on the upgradient side of the 

barrier wall separating the WMA 1 excavation from the Waste Tank Farm, suggesting 

potential flow from WMA 1 into the Waste Tank Farm area.

Flow contours southeast of the WMA 1 barrier wall suggest that groundwater would 

flow to the east into the area of the backfilled WMA 2 excavation, as discussed in 

Section 1.4.3 of this appendix. 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 D-18 

Downgradient of the WMA 1 barrier wall groundwater flow in the sand and gravel unit 

would continue to the northeast across the north plateau. However, the upgradient 

diversion of groundwater flow by the barrier wall system would result in an overall 

reduction in the hydraulic gradient of the non-source area of the north plateau 

groundwater plume. 

Groundwater elevations in the backfilled WMA 2 excavation are expected to be up to 

10 feet higher than present in the non-source area of the north plateau groundwater 

plume.

Higher groundwater elevations within the backfilled WMA 2 excavation suggests 

groundwater would flow across the WMA 2 barrier wall to the northwest and northeast 

toward the non-source area of the north plateau groundwater plume and also to the 

southeast toward Erdman Brook.

2.0 Post-Remediation Site Monitoring and Maintenance 

This section describes the post-remediation site monitoring and maintenance program to be 

implemented by the DOE at the project premises following the completion of Phase 1 of the 

proposed decommissioning. The program would include monitoring and maintenance 

associated with engineered barriers installed within the project premises and monitoring of 

environmental media within and outside the project premises. This monitoring and maintenance 

program would continue until the start of Phase 2 of the decommissioning, when the program 

requirements would be re-evaluated. DOE concludes that this program would be adequate to 

control and maintain the project premises because it is similar to the successful program 

currently in use and because it appropriately addresses all facilities of importance. 

2.1 Monitoring and Maintenance of Engineered Barriers and Systems 

The performance of the engineered barriers installed at WMA 1 and WMA 2 during Phase 1 

proposed decommissioning would be routinely monitored up to the start of Phase 2 of the 

decommissioning to ensure they function as designed. Systems and engineered barriers 

installed during work leading to the interim end state, such the Tank and Vault Drying System at 

WMA 3 and the geomembrane cover and slurry wall at WMA 7, would also be routinely 

monitored and maintained as part of the DOE monitoring and maintenance program. Corrective 

actions would be implemented to correct any observed defects or irregularities with these 

engineered barrier and systems. 

2.1.1 North Plateau Subsurface Barrier Walls and French Drain 

The monitoring and maintenance program would monitor the performance and condition of 

the subsurface hydraulic barriers installed at WMA 1 and WMA 2, and the French drain at WMA 

1. This program would include routine inspections of these systems for signs of degradation or 

loss of performance.

Hydraulic Barrier Walls

Piezometers would be installed upgradient and downgradient of the permanent hydraulic 

barrier walls installed downgradient of the WMA 1 and northwest of the WMA 2 excavations 

(Figure D-10). These piezometers would be spaced at intervals at least equal to the maximum 

lateral spacing recommended by the U.S. Environmental Protection Agency (EPA 1998). Water 

levels in these piezometers would be routinely monitored to evaluate the performance of these 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 D-19 

hydraulic barriers. Groundwater would be sampled and analyzed semi-annually for the 

radiological indicator parameters (gross alpha, gross beta, tritium) and for Sr-90 to evaluate the 

effectiveness of the barrier walls in preventing recontamination of WMA 1 and WMA 2.

If groundwater monitoring suggests repairs to the walls are required, these repairs would be 

accomplished through grouting, consistent with past industry experience and practice (e.g., 

EPA 1998).

French Drain

Monitoring and maintenance activities associated with the French drain installed upgradient 

of the WMA 1 hydraulic barrier wall would include monitoring of groundwater levels in 

piezometers installed on the upgradient and downgradient sides of the French drain following 

installation.

The need for and extent of repairs to the French drain, if any, would be determined based 

on analysis of the groundwater level data, which would be evaluated to identify evidence for any 

localized defect(s) in the French drain.

2.1.2 Waste Tank Farm Tank and Vault Drying System 

The Tank and Vault Drying System installed in WMA 3 during the work to establish the 

interim end state would be routinely monitored and maintained during the Phase 1 period to 

ensure its continued operation as designed. The major components of the system – such as the 

blowers, heaters, and dehumidifier units – would be inspected and repaired or replaced as 

necessary to ensure continued operation of the system.

2.1.3 Waste Tank Farm Dewatering Well 

As specified in Section 7 of this plan, the existing dewatering well would continue to be 

used to artificially lower the water table to minimize in-leakage of groundwater into the tank 

vaults. The water from this well would be collected, sampled, treated if necessary using a 

portable wastewater treatment system, and released to Erdman Brook through a State Pollutant 

Discharge Elimination System-permitted outfall. 

2.1.4 NRC-licensed Disposal Area Engineered Barriers 

The geomembrane cover and the hydraulic barrier wall installed at the NDA during work to 

establish the interim end state would be routinely monitored and maintained throughout Phase 

Geomembrane Cover 

The geomembrane cover would be routinely inspected for signs of deterioration or damage 

to the membrane. The seams connecting the geomembrane panels would be inspected to 

evaluate their condition. The geomembrane cover would be repaired to remedy any defects or 

irregularities identified during these inspections.

Hydraulic Barrier Wall 

A monitoring and maintenance program similar to that described for the barrier walls 

installed at WMA 1 and WMA 2 would be implemented for the hydraulic barrier wall installed 

upgradient of the NDA. Twenty-one piezometers were installed upgradient and downgradient of 

the barrier wall during its construction. Water levels in these piezometers would be routinely 

monitored during Phase 1 to evaluate the performance of the barrier wall in limiting 

groundwater flow into the NDA.
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 D-20 

Figure D-10. Groundwater Monitoring Locations within the Project Premises during the 

Phase 1 Institutional Control Period
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 D-21 

2.1.4 Security Features 

The features important to security on the project premises and to security of the new 

Canister Interim Storage Facility during the period before Phase 2 of the decommissioning 

would be periodically inspected and maintained in good repair. These features include the 

security fences, signs, and security lighting described in Section 3.2 of this appendix.

2.2 Environmental Monitoring 

The Phase 1 proposed decommissioning activities would include the removal of the 

following facilities: 

Above-ground and below-grade facilities in WMA 1 and the underlying source area of 

the north plateau groundwater plume within a single excavation down into the 

underlying Lavery till; 

Lagoons 1, 2, and 3, the Neutralization Pit, Interceptors, Solvent Dike, and surrounding 

contaminated soils in WMA 2 within a single excavation down into the underlying 

Lavery till; and 

Most remaining facilities and concrete slabs down to a maximum depth of two feet. 

The following facilities and contamination areas within the project premises would not be 

considered during Phase 1 of the proposed decommissioning but would be addressed during 

Phase 2:

The Waste Tank Farm in WMA 3, including the Permanent Ventilation System Building 

and the Supernatant Treatment System Support Building; 

The Construction Demolition Debris Landfill in WMA 4; 

The NDA in WMA 7; and 

The non-source area of the north plateau groundwater plume. 

The DOE would implement an environmental monitoring program to monitor closed and 

remaining facilities and the non-source area of the north plateau groundwater plume as part of 

its management of the project premises during the Phase 1 institutional control period. 

Environmental monitoring would include onsite groundwater, storm water, and air monitoring, 

and both onsite and offsite surface water, sediment, and radiation monitoring as described 

below. Annual reports would be issued summarizing the monitoring results. These reports 

would include analyses of the data collected, along with conclusions about trends and 

compliance with regulatory limits.

2.2.1 Groundwater Monitoring Within the Project Premises

Groundwater within the project premises would be monitored during the Phase 1 

institutional control period in accordance with the DOE WVDP Groundwater Monitoring Plan in 

effect at the time. Offsite groundwater monitoring would not be performed as this monitoring 

program was discontinued in 2007. The onsite grounding monitoring program for the project 

premises is described below and shown on Figure D-4. A total of 36 groundwater wells would 

be routinely monitored along with 59 piezometers.

WMA 1 - Process Building and Vitrification Facility Area 

Groundwater in the sand and gravel unit in the backfilled WMA 1 excavation would be 
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 D-22 

monitored using the network of piezometers installed to monitor the effectiveness of the 

hydraulic barrier wall and French drain described in Section 2.1.1 of this Appendix. A 

monitoring well screened in the sand and gravel unit would also be installed in the upgradient 

portion of the WMA 1 excavation to provide information on groundwater quality flowing into the 

backfilled excavation.

An additional monitoring well screened in the Kent Recessional Sequence would be 

installed immediately upgradient of the WMA 1 hydraulic barrier wall to monitor groundwater in 

this unit and to evaluate potential migration of groundwater from the source area of the north 

plateau groundwater plume that was removed during Phase 1 of the proposed 

decommissioning.

Groundwater from these piezometers and monitoring wells would be sampled semiannually 

for radiological indicator parameters (gross alpha, gross beta, and tritium) and for Sr-90 during 

the Phase 1 institutional control period.

WMA 2 - Low-Level Waste Treatment Facility Area 

Groundwater in the sand and gravel unit in the backfilled WMA 2 excavation would be 

monitored using the network of piezometers installed to monitor the effectiveness of the 

hydraulic barrier wall and French drain described in Section 2.1.1 of this Appendix. Three 

monitoring wells screened in the sand and gravel unit would also be installed on the 

southeastern boundary of the WMA 2 excavation to provide information on groundwater flow 

and quality in this area.

Groundwater from these piezometers and monitoring wells would be sampled semiannually 

for radiological indicator parameters (gross alpha, gross beta, and tritium) and for Sr-90 during 

the Phase 1 institutional control period. 

WMA 3 - Waste Tank Farm Area

Groundwater in the sand and gravel unit and the Kent Recessional Sequence would be 

routinely monitored at WMA 3 during the Phase 1 institutional control period. Four wells would 

be screened in the sand and gravel unit with one well upgradient and three wells downgradient 

of the Waste Tank Farm. Two wells screened in the Kent Recessional Sequence would be 

installed downgradient of the Waste Tank Farm.

 Groundwater from these wells would be sampled semiannually for radiological indicator 

parameters (gross alpha, gross beta, and tritium) and for Sr-90 during the Phase 1 institutional 

control period. 

WMA 4 - Construction Demolition Debris Landfill Area 

Groundwater in the sand and gravel unit at WMA 4 would be routinely monitored at six 

locations, including four monitoring wells around the Construction and Demolition Debris 

Landfill, and at two groundwater seep locations along the edge of the north plateau outside of 

the WVDP fence line. 

Groundwater at WMA 4 would be sampled semiannually for radiological indicator 

parameters (gross alpha, gross beta, and tritium) and for Sr-90.

WMA 6 - Central Project Premises 

Groundwater in the sand and gravel unit at WMA 6 would be routinely monitored at two well 
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Revision 1 D-23 

locations, including one well upgradient of the rail spur and the other well downgradient of the 

rail spur and the removed Demineralizer Sludge Ponds and Equalization Basin. 

Groundwater at these locations would be sampled semiannually for radiological indicator 

parameters (gross alpha, gross beta, and tritium).

WMA 7 – NDA 

Groundwater in the weathered Lavery till and Kent recessional unit at WMA 7 would be 

routinely monitored by five wells screened in the weathered Lavery till and three wells screened 

in the Kent Recessional Sequence. One well cluster would be located upgradient of the NDA 

and would include a well screened in the weathered Lavery till and one screened in the Kent 

Recessional Sequence. Two well clusters, each with a well screened in the weathered Lavery 

till and Kent Recessional Sequence, would be located downgradient of the burial area. The two 

remaining wells screened in the weathered Lavery till would be located downgradient of the 

burial area. 

Groundwater at WMA 7 would be sampled semiannually for radiological indicator 

parameters (gross alpha, gross beta, and tritium) and annually for specific radionuclides (Cs137, Sr-90, Am-241, and Pu isotopes).

Non-Source Area of the North Plateau Plume 

Groundwater in the sand and gravel unit would be routinely monitored at 11 well locations 

within the non-source area of the north plateau groundwater plume. These wells are located 

along the length of the plume from the WMA 1 barrier wall to the Construction and Demolition 

Debris Landfill in WMA 4. Three wells are located downgradient of the Permeable Treatment 

Wall to evaluate its effectiveness in reducing Sr-90 concentrations in groundwater from the 

sand and gravel unit.

Groundwater in the non-source area of the north plateau groundwater plume would be 

sampled semiannually for radiological indicator parameters (gross alpha, gross beta, and 

tritium) and for Sr-90. 

2.2.2 Surface Water, Sediment, and Storm Water Monitoring 

Surface water and associated stream sediments would be routinely monitored both within 

and outside the project premises during the Phase 1 institutional control period. The proposed 

monitoring locations are currently part of the DOE WVDP annual environmental monitoring 

program. These locations have been uniquely sited to monitor surface water releases from the 

WVDP and the Center. Several of the locations have been actively monitored since the 

implementation of the program in 1982 providing a significant historical record of surface waters 

leaving the WVDP and the Center.

Eight surface water-sampling locations within the project premises would be routinely 

monitored during the Phase 1 institutional control period (Figure D-11). These locations monitor 

streams both within (WNDNKEL, WNSP005, WNNDADR, WNFRC67, WNERB53) and leaving 

the project premises (WNSW74A, WNSWAMP, and WNSP006). Sediment samples would be 

collected from three locations where surface waters leave the project premises (SNSW74A, 

SNSWAMP, and SNSP006).
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Surface water would be routinely collected and analyzed from three sampling locations 

outside of the project premises (Figure D-12). These locations would monitor surface water 

quality in Buttermilk Creek and Cattaraugus Creek where these streams leave the Center 

(WFFELBR, WFBCTCB) and where Buttermilk Creek enters the Center (WFBCBKG). 

Sediment samples would be collected from all three off-site locations (SFBCSED, SFTCSED, 

SFCCSED).

Surface water and sediment samples would be collected from these locations semiannually and would be analyzed for radiological indicator parameters (gross alpha, gross beta, 

and tritium). 
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Revision 1 D-25 

Figure D-11. Surface Water and Sediment Sampling Locations on the Project 

Premises during the Phase 1 Institutional Control Period
WVDP PHASE 1 DECOMMISSIONING PLAN

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Figure D-12 – Offsite Surface Water and Sediment Sampling Locations during the Phase 1 

Institutional Control Period
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The New York State Pollutant Discharge Elimination System permit issued to the DOE 

WVDP requires periodic sampling from storm water outfalls located within the project premises. 

Sampling from these outfalls during storm events is designed to assess specific chemicals in 

storm water discharges that may originate from industrial or construction activity runoff from 

locations within the project premises. The planned storm water sampling locations are identified 

on Figure D-13. Sampling would be performed semi-annually for the non-radiological 

parameters specified in the New York State Pollutant Discharge Elimination System permit. 

2.2.3 Air Monitoring 

The stack discharge from the Permanent Ventilation System Building in the Waste Tank 

Farm in WMA 3 would be the only air monitoring location to be routinely monitored within and 

outside of the project premises during the Phase 1 institutional control period (Figure D-14).

The Permanent Ventilation System ventilates the Supernatant Treatment System Valve 

Aisle and Tanks 8D-1, 8D-2, 8D-3, and 8D-4 in WMA 3. The air discharged from these facilities 

passes though high-efficiency particulate air filters before discharge through the Permanent 

Ventilation System Building stack. Air discharged from the Tank and Vault Drying System would 

also be treated in the Permanent Ventilation System Building.

Air discharges from this location would be analyzed for radiological indicator parameters 

(gross alpha, gross beta, and tritium) and specific radionuclides (Cs-137, Sr-90, I-129, Am-241, 

and U and Pu isotopes). 

2.2.4 Direct Radiation Monitoring 

Direct radiation monitoring using thermoluminescent dosimeters would be performed at 19 

locations within and outside of the project premises. These monitoring locations are currently 

part of the DOE WVDP annual environmental monitoring program and were sited to monitor 

both on-site and off-site radiation exposure from facilities within the project premises and the 

State-Licensed Disposal Area. Several of these locations have been actively monitored since 

1982.

Eight monitoring locations would be within the project premises (Figure D-15) and eleven 

stations would be located on the perimeter of the Center (Figure D-16). All locations would be 

routinely monitored for gamma radiation exposure on a quarterly monitoring schedule.
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Revision 1 D-28 

Figure D-13. Storm Water Sampling Locations on the Project Premises during the Phase 1 

Institutional Control Period
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 D-29 

Figure D-14. Air Monitoring Locations on the Project Premises during the Phase 1 

Institutional Control Period
WVDP PHASE 1 DECOMMISSIONING PLAN

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Figure D-15 – Direct Radiation Monitoring Locations on the Project Premises during the 

Phase 1 Institutional Control Period
WVDP PHASE 1 DECOMMISSIONING PLAN

Revision 1 D-31 

Figure D-16. Offsite Direct Radiation Monitoring Locations during the Phase 1 Institutional 

Control Period
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3.0 Phase 1 Institutional Control Program

This section describes the institutional control program that would be implemented for the 

project premises following the completion of the Phase 1 remedial activities.

3.1 Government Control of the Project Premises

NYSERDA is the current owner of the project premises property and would remain owner 

following Phase 1 activities. As stipulated in the Cooperative Agreement with NYSERDA, DOE 

shall remain in exclusive use and possession of the project premises and project facilities 

throughout the remainder of the project term (DOE and NYSERDA 1981). DOE would therefore 

continue control of the project premises during the implementation of the Phase 1 proposed 

decommissioning activities and during the Phase 1 institutional control period. In this capacity, 

DOE carries the full authority of the federal government in enforcing institutional controls over 

the project premises.

DOE would be responsible for operating and maintaining facilities within the project 

premises such as the Waste Tank Farm, the NDA, and the non-source area of the north 

plateau groundwater plume in a safe manner. DOE would continue to implement the 

environmental radiation protection program for the project premises as required by DOE Order 

5400.5, Radiation Protection of the Public and the Environment. NRC would also be involved in 

a regulatory oversight capacity over the project premises, which would remain under NRC 

license.

3.2 Institutional Control Design Features 

The institutional control program for the project premises would prevent its unacceptable 

use and protect against inadvertent intrusion into the site. DOE in its capacity as the steward of 

the site would ensure that institutional controls are maintained at the project premises during 

Phase 1 proposed decommissioning and during the Phase 1 institutional control period. These 

institutional controls would include: 

Security fencing and signage along the perimeter of the project premises to prevent 

inadvertent intrusion into the site and to notify individuals that access is forbidden 

without permission from the DOE, 

A full time security force to prevent unauthorized access into the project premises, 

Authorized personnel and vehicle access into the project premises would be limited to 

designated gateways through the perimeter security fence 

The environmental monitoring program implemented at the project premises during the 

Phase 1 institutional control period would ensure that operations at the site protect 

members of the public and the environment from radiation risk. 

Additional institutional controls would be provided for the new Canister Interim Storage 

Facility on the south plateau. These would include measures such as security fencing around 

the area and appropriate security lighting.
WVDP PHASE 1 DECOMMISSIONING PLAN

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 4.0 References

Code of Federal Regulations and Federal Register Notices 

10 CFR 20 Subpart E, Radiological Criteria for License Termination.

67 FR 22, Decommissioning Criteria for the West valley Demonstration Project (M-32) at the 

West Valley Site; Final Policy Statement, U.S. Nuclear Regulatory Commission, 

Washington, D.C., February 1, 2002. 

DOE Orders 

DOE Order 5400.5, Change 2, Radiation Protection of the Public and the Environment. U.S. 

Department of Energy, Washington, D.C., January 7, 1993.

Other References 

DOE and NYSERDA 1981, Cooperative Agreement between the United States Department of 

Energy and New York State Energy Research and Development Authority on the 

Western New York Nuclear Service Center at West Valley, New York. Signed November 

3, 1980, amended September 18, 1981.

EPA 1998, Evaluation of Subsurface Engineered Barriers at Waste Sites, EPA 542-R-98-005. 

U.S. Environmental Protection Agency, Office of Solid Waste and Emergency 

Response, Washington, D.C., August 1998.

Evans, et al. 1985a, “Organic Fluid Effects on the Permeability of Soil-Bentonite Slurry Walls,”

Evans, J.C., et al. Proceedings of the National Conference on Hazardous Wastes and 

Environmental Emergencies, pp. 267-271, Cincinnati, Ohio, 1985.

Evans, et al. 1985b, “Containment of Hazardous Materials with Soil Bentonite Slurry Walls,” 

Evans, J.C., et al. Proceedings of the 6th National Conference on Management of 

Uncontrolled Hazardous Waste Sites, pp. 369-373, Washington, D.C. November 1985. 

Fang, et al. 1992, “Soil-Pollution Effects on Geotextile Composite Walls,” Fang, H. et al. in 

Slurry-Walls Design, Construction, and Quality Control, ASTM Special Technical 

Publication STP 1129, pp. 103-116, ASTM, Philadelphia, Pennsylvania, 1992.

Grube 1992, “Slurry Wall Trench Cut-off Walls for Environmental Pollution Control,” Grube, W. 

in Slurry Walls - Design, Construction, and Quality Control, ASTM Special Technical 

Publication STP 1129, pp. 69-77, ASTM, Philadelphia, Pennsylvania, 1992.

Khera and Tirumala 1992, “Materials for Slurry Walls in Waste Chemicals,” Khera, R.P., and 

Tirumala, R.K.. in Slurry Walls - Design, Construction, and Quality Control, ASTM 

Special Technical Publication STP 1129, pp. 172-180, ASTM International, West 

Conshohocken, Pennsylvania, 1992.

Millet, et al. 1992, USA Practice Slurry Wall Specifications 10 Years Later, in Slurry Walls - 

Design, Construction, and Quality Control. Millet, R.A., et al., ASTM Special Technical 

Publication STP 1129, pp. 42-66, ASTM International, West Conshohocken, 

Pennsylvania, 1992.
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Mitchell 1986, “Hazardous Waste Containment,” Mitchell, J. K., in Groundwater in Engineering 

Geology, Mitchell, J. K., J.C Cripps, F.G. Bell, and M.G. Culshaw (eds.). Geological 

Society Engineering Geology Special Publication No. 3, pp. 145-157, 1986.

Mitchell 1993. Fundamentals of Soil Behavior, Second Edition, Mitchell, J. K. John Wiley & 

Sons, Inc., New York, New York, 1993.

Nichols, et al. 1997, STOMP Subsurface Transport Over Multiple Phases: Application Guide,

PNNL-11216 (UC-2010). Nichols, W.E., N.J. Aimo, M. Oostrom, and M.D. White, 

Pacific Northwest National Laboratory, Richland, Washington. 1997.

URS 2000, Evaluation of Stability of Proposed WMA1&3/WMA7 Slurry Walls Under 

Hypothetical Seismically-induced Horizontal Acceleration of 0.2g, Calculation BUF2000-069, Rev. 0. URS Corp., Orchard Park, New York, July 17, 2000.