ML20217H069
| ML20217H069 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 10/31/1999 |
| From: | NUCLEAR FUEL SERVICES, INC. |
| To: | |
| Shared Package | |
| ML20217H044 | List: |
| References | |
| NUDOCS 9910220047 | |
| Download: ML20217H069 (200) | |
Text
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LQ FINAL STATUS SURVEY REPORT FOR THE NORTIIWEST CaF STORAGE AREA 2
(USNRC Material License SNM-1097, Docket No. 70-1113) l October 1999 Prepared by Nuclear Fuel Services,Inc.
1205 Banner Hill Road Erwin,TN 37650 l
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Prepared for l
General Liectric Nuclear Energy Castle Hayne Road l
Wilmington,NC 28403 -
/ 'i 9910220047 991015 U
PDR ADOCK 07001113 B
PDR j
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FinalStatus Survey Report Northwest CaF Storage Area October 1999 TABLE OF CONTENTS
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- i EXECUTIVE
SUMMARY
......................................................................................................... v 1.0 - INTRODU CT10N...............................................................................................................
L.1: Purpose................................................................................................................................1-1
-1.2 Scope...................................................................................................................................1-t1.3' Objectives..........................................................................................................................2.
2.01 SITE INFORMATION......................................................................................................... 3
. 2.1. I Site Description and History................................................................................................ 3
' 2.2 Identification of Contaminant and Analysis Method........................................................... 6
' 2.3 T Area Rel ease Criteri a.......................................................................................................... 6 3.0 / SOIL S AMPLING METHODOLOGY............................................................................. 7
" 3.1 Soil Sampling Obj ectives.....................................................................................................;7 3.2 : : Sampling Locations............................................................................................................ 7 f
3.3 S amplin g Method s......................................................................................................... 7 A
3.4 S ample Designations.......................................................................................................... 8
- 3.5_ : Sample Types and. Number of Samples................................................................................ 9 13.6 ' L Sample Volumes and Containers....................................................................................... 9
' 3.7f S ample Labelin g.................................................................................................................. 9 3.8 ' Fon ns for Sample Collection.......................................................................................... 1 1
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3.9 S ample Preservatio n............................................................................................................ 1 1 3.10 ; Duplicate S ampl es............................................................................................................... 1 1
- 3.1 1 Decontamination Process.................................................................................................... 1 1 J 3.12 Transfer of Custody and Shipment..................................................................................... 12
' 3.13 Documentation of Field Operations................................................................................ 12.
[4.0 FIELD ACTIVITIES
SUMMARY
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4.11 Soil Sampling aad Additional Excavation Activities..........................................................14 4.2 i Gamma Scanning Survey.;................................................................................................. 19 e
' 4.3 Exposure Rate S urvey......................................................................................................... 21
- 4.4 Groundwater S ampling....................................................................................................... 2 2 5,0 HEALTH AND S AFETY................................................................................................... 24
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i 6.0 QUALITY AS S URANCE................................................................................................... 2 5 6.1 Field Activities Quality Assurance....................................................................................... 25 6.2 Laboratory Quality Assurance............................................................................................. 26 7.0. PRESENTATION OF RESULTS AND DISCUSSION................................................... 28 L 7.1 B ackgro und Determination............................................................................................ 2 8 1 7.2 Un affec t ed Area.....................................................................................................
. 7.3 Affect ed Area.................................................................................................... I 7.4 Gamma Walkover S urvey Results..................................................................................... 3 0
. 7.5 Exposure Rate Survey........................................................................................................ 31 -
7.6 Gro mdwater S ampling and Analysis................................................................................ 3 2
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8.0 CONCLUSION
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...............................................................34 9.0 RE FE RENC E S...................................................................................................
n-LIST OF TABLES
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Table 3.1 Sample Collection Summary.................................................................................... 10 l
j Table 4.1 Sample Results from the Elevated Area in the Unaffected Area (pCi/g)............... 15 j
Table 4.2 Confirmatory Sample Results from the Elevated Area in the Unaffected Area (pCi/g)................................................... 16 Table 4.3 Sample Results/ Averages Prior to Dredging Operations.......................................17 i
Table 4.4 Sample Results/ Averages Following Dredging Operations......................................18 Table 4.5 Sample Results/ Averages Following Additional Excavation.................................... 20 Table 4.6 Gamma Scanning Survey Equipment......................................................................... 21 l
Table 6.1 - Equipment Rinse and Rinse Water Sample Results (pCi/l)...................................... 25 L Table 6.2. Identification ofBlind Field Duplicate Samples and Associated RERs.................. 27 Table 7.1 Exposure Rate Survey Summary............................................................................... 31 LIST OF FIGURES Figure 2-1 CaF S ite Location Map.............................................................................................. 5 2
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APPENDICES.
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> APPENDIX A-DRAWINGS '
7 nitial Sampling Locations and Results above NRC Criteria............................................... Sheet 1 I
4 h Trapezoidal Grids for Averaging......................................................................................... Sheet 2 L
. Additional Areas Requiring Corrective Action................................................................... Sheet 3 4 Post - Dredging and Excavation Sampling Activities.................................................... Sheet 4
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L Affected Area Sampling Results -- Post Excavation................................................_.......... Sheet 5
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Final S ta tus............................................................................................................ 1 l
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- APPENDIX B - PHOTOGRAPHS' l
1 > Site view of the affected area near the northwest comer looking east............................B-1 L 2.
Site view of the affected area near the northwest comer looking southeast....................B-1
'3.
Site view from near the northeast comer looking west, the soil piles are in' th e b a c k grou nd.............................................................................................................. B-2 i
4.
Site view from near the southeast comer looking west, the soil piles are L
i n the b ack gro u nd................................................................................................................ B -2
- 5. Soil pile view to the north near the westem site boundary.............................................B-3 g
- 6. Soil pile view toward the west............................................................................................ B-3 L Q
- 7. A pontoon boat.was used as the sampling platform for most of the affected area...........B-4 8.
PVC pipe was driven into the pond and labeled for sample location control.................B-4
- 9.
- Clear PVC tubes were driven into the sediment from the pontoon boat......................B e
- 10. Clear PVC tubes were also driven into the soil from the land surface.............................B-6 l
- 11. Sample ~ cores were measured to ensure adequate sample recovery..................................B-7
- 12. Excess water recovered from the core was decanted back into the basin...............
......B
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I 13. ' Samples material was deposited into' stainless steel bowls fo'r mixing............................B-8 L,
'14.' Filled and labeled sample container ready for placement into a sample cooler.................B-8
! 151 Steam pressure washer used for decontamination activities.............................................B-9 '
- 16. Decontamination tubs were used in_the multi-step decontamination process.................B-9 L
- 17. fall sample bottles were radiologically surveyed prior to sample shipment.................B-10..
_181Several swipe samples were counted for de.. contamination. assessment.........................B-10
- 19. Sample cooler with'samplejars and chain-of-custody form ready for shipment.............B-11 APPENDIX C-TABLES =
1 (Table C.1 j Isotopic Sample Results for Unaffected Area and Soil Piles................................C-1 K
Table C.2 2 Isotopic Sample Results for AfTected Area......................................................C-10 1 Table C.3a Backpound Sample Results (pCi/g)- Surface Samplcs (0 - 6).........................C-22 Table C.3b : Background Sample Results (pCi/g)- Surface Samples (6 - 36).....................C-22 oTable C.4 L Unaffected Area Sample Results (Sample Locations at Center of 10m Grids)....C-23 e
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i Table C.5f Soil Pile Overburden Sample Results....................................................................C-24
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Final Status Survey Report Northwest CaF Storage Area 2
October 1999 APPENDICES Table C.6. Soil Pile Sample Results/frapezoid Averages......................................................C-25
- Table C.7 AfTected Area Sample Results...............................................................................C-2 7
- Table C.8 Affected Area Sample Averages............................................................................C-31
.. APPENDIX D - REPORT OF FINAL STATUS SURVEY GROUNDWATER SAMPLING AND ANALYSIS ACTIVITIES
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Final Status Survey Report i
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October 1999 r
' y $h EXECUTIVE
SUMMARY
(The former northwest calcium fluoride (CaF ) storage area consist'ed of seven shallow trenches 2
. located in a 1-acre fenced area in the remote northwest quadrant of the General Electric Nuclear o
Energy Proddction '(GE NEP) facility in Wilmington, North Carolina. CaF was placed in the 2
storageLtrenchAs beginning in late 1968 through 1972._ The seven trenches were located within
' a fenced area and were estimated to contain approximately 70,000 cubic feet of CaF material.
2 The maximum; depth of the. trenches was~ estimated at approximately 9 feet with an average
' depth ' f 5 t'o 6 feet.
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- From the period of February 1996 'to August 1996, Nuclear Fuels Services, Inc. (NFS) removed
/ approximately; 200,000 cubic feet of CaF and CaF contaminated soil from the seven shallow 2
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- pits. ' In summer 1997, NFS conducted a scoping survey to determine if the site was ready to implement the Final Status Survey and Release Plan (FSSRP) prepared by NFS and approved -
by the Nuclear Regulatory. Commission (NRC). Based on the sampling results, it was determined that additional material would need to be removed to meet the release criterion for residual total uranium activity in soil, established for thic project to be 30 picocuries per gram
'_(pCi/g) above background.
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In December 1997, NFS initiated excavation and removal of the additional material exc Ming the 30 pCi/g release criterion. App wately 115,000 cubic feet of material was removu. from the former northwest CaF storage area and transported by truck to the' central process lagoons 2
- area,'also ~on the GElNEP site, where it was placed with material of similar total uranium
- activities. The" remaining material, consisting primarily of soil excavated from between the trenches,"was placed'into several piles located adjacent to and just south of the excavated area.
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1 After completion of these. secondary excavation activities, preparations were made for final-
' status survey sampling activities.
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{ During December 1998 to January 1999, NFS obtained a total of 533 soil samples from the fonner northwest CaF storage area.' These samples were collected from both the area 2
containing the. storage trenches (referred'to;as the affected area) and the surrounding area l(refhrred to as the unaffected area). The soil piles present within the unafTected area from the excavation activities were also sampled. All samples were analyzed using alpha spectroscopy to yield activities' for three uranium isotopes,2"U,2"U and "U, expressed in terms of pCi/g.
2 LThe three uranium isotope activity values are summed to yield a total uranium content (pCi/g)
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J lPer sample. 'All samples were analyzed using an external contract laboratory (O'Brien and l Nuclear Fuel Services,Inc.=
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W h-Final Status Survey Report Northwest CaF: Storage Area October 1999
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Gere,Inc of Syracuse, NY)..
.M-N Because removal 'of the' CaFf material and surrounding soils created an excavation extending below the. water table, the majority of soil samples obtained from the affected area were collected using a pontoon boat as a sampling platform. A total of 312 samples were initially takSn at various del ths from the affected area. All soil samples collected from'the affected area i
Lwere obtained from the nodes of a 5-meter by 5-meter triangular grid established at the site by a North Carolina registered land surveying firm.. In addition to the 312 soil samples initially I. collected, fourteen blind field duplicate samples were collected and analyzed for quality control.
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Soil samples collected from the unafrected area were obtained from 0 - 6 inches in depth.. Of the 199_ total samples initially taken from the unaffected area,130 were collected from soil t excavated fmm the affected area and stored in piles adjacent to the excavation. These 130 t samples were also collected from the 5-meter by 5-meter grid nodes. The remaining 69 sample locations represent unaffected area, non-soil pile regions where a 10-meter by 10-meter grid was used to locate the sampling points. In addition to the 199 samples initially obtained from L the unafrected area,8 blind field duplicate samples were collected and analyzed for QC.
Results from both the affected and unaffected areas were ' veraged within the proper grid a
~ overlay _as 'specified in the FSSRP. The entire unaffected area met the release criteria with two
-exceptions. First, twelve individual soil pile samples exceeded 75% of the release criterion or l 22.5 pCi/g. These areas were reclassified as "afrected per the FSSRP. Because the average of the five sample points within each applicable trapezoid-shaped grid was below the 30 pCi/g release criterion, no further action was necessary. Second, an area adjacent to soil pile exhibited 1
an average of 33.4 pCi/g, exceeding the 30 pCi/g release criterion. This area was excavated on -
- March ' 15, L1999.~ Confirmatory. sampling of the soils confirmed that this area met the unrestricted release criterion.~
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A two areas near the center of the affected area exhibited an average total uranium activity,37.4
_. pCi/g' and 53.4 pCi/g, exceeding the 30 pCi/g release criterion.' Three other areas within the -
- affected area exhibited an average total uranium activities of 12.6,26.9 and 29.6 pCi/g. As a
. result, on March'12,1999,.a portion of these five contiguous areas was excavated using a diesel-hydraulic dredge and sampled.' This confirmatory sampling indicated that for all but one of these five areas, the uranium content was still above the release criterion, thereby indicating
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. that all of the uranium contamination had not been successfully removed and further excavation 3Q Nuclear Fuel Services,'Inc.:
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Final Status Survey Report Northwest CaF Storage Area October 1999 was required.
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In September 1999, soil from the soil piles adjacent to the westem edge of the unaffected area was used to construct a ramp that extended out from the eastern bank of the affected area to each area requiring additional excavation. Wooden equipment mats were placed on the ramp to provide a stable platform for the excavator. Approximately 2 - 3 feet of soil was removed from each area and stockpiled in the unaiTected area. Samples collected from the excavation area and stockpiled soils indicated the unrestricted release criterion was met.
Gamma scanning and exposure rate surve'ys were performed as directed by the FSSRP. The gamma scanning survey indicated one area of elevated activity. This area, adjacent to a soil pile, was excavated and surveyed. No areas with an audible count rate above background were found on resurvey. The exposure rate survey found no areas exceeding 10 pR/hr above background.
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The data indicates that uranium contaminated soils exceeding the unconditional release criterion have been removed from both the unaffected and affected areas, including the various soil piles within the unaffected area. The gamma scanning surveys indicated no
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detectable increase in activity between the accessible survey points within the affected and unaffected areas. The exposure rate survey found no area greater than 10 pR/In above I
background. Based upon these results, the criteria for unconditional release of the former nodhwest CaF storage area have been met.
2 Groundwater samples were collected from the 17 CAF-series monitoring wells located on GENE property in the vicinity of the former northwest CaF storage area. The Research 2
Triangle Institute (RTI) collected both filtered and unfiltered groundwater samples in January j
1999. Uranium activities were below US Environmental Protection Agency's (EPA's)
. proposed drinking-water maximum contaminant level (MCL) of 30 pCi/L, except the samples from CAF-6A and CAF-7A. These two monitoring wells are directly downgradient of the former northwest CaF storage area and on GE NEP property. Groundwater from the 2
next downgradient well, CAF-12A, also on GE NEP property, exhibited a uranium activity below the proposed MCL, as did the deeper monitoring points adjacent to CAF-6A and CAF-7A (CAF-6B and CAF-7B). These monitoring data indicate that the impacts are limited to the shallow groundwater in the immediate vicinity of the former northwest CaF: storage area.
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In accordance with the Classifications and Water Quality Standards Applicable to the t/
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October 1999 Groundwaters ofNorth Carolina (North Carolina Administrative Code Title 15A, Subchapter 2L), RTI prepared a Comprehensive Site Assessment (CSA) summarizing the
'd assessment and monitoring activities for groundwater in the former northwest CaF storage 2
The CSA was reviewed and approved by the North Carolina Department of area.
' Environment and Natural Resources (DENR), Division of Water Quality and Division of Radiation Protection. In addition, a natural attenuation Corrective Action Plan (CAP) was prepared by RTI to address the localized groundwater impacts in the area and was submitted to DENR in 1999. Consistent with the recommendations of the CAP and the verbal approval of the CAP monitoring plan by DENR, routine monitoring of groundwater quality in the area is underway and will continue. Periodic updates of groundwater sampling and analysis activities will be provided to DENR.
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Final Status Survey Report Northwest CaF Storage Area October 1999
1.0 INTRODUCTION
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V 9e General Electric Nuclear Energy Production (GE NEP) facility at Wilmington, NC, through Ps contractor, Nuclear Fuel Services, Inc., (NFS) has co npleted removal of the calcium fluoride (CaF ) material from the site designated as the former northwest CaF 2
2 storage area. This report presents the results of sampling activities at the excavated site and surrounding areas conducted in accordance with the Nuclear Regulatory Commission (NRC) approved Final Status Survey and Release Planfor the Northwest CaF Storvye Area, Rev. 2 (FSSRP) (NFS 1996a) and subsequent correspondence 2
dated Octooerl,1998 (GE NEP 1998)'and November 24,1998 (GE NEP 1998b).
1.1 Purpose The purpose of this report is to summarize the implementation of the FSSRP and present the results of the survey and associated activities for NRC review. It is intended that this report will provide, in accordance with the FSSRP, sufficient documentation that the residual uranium concentration in the soil meets the unrestricted release criterion of 30 picoCuries/ gram (pCi/g) above background total uranium for both the (l
affected and unaffected areas of the former northwest CaF storage area and an exposure 2
rate less than 10 microRoentgens per hour ( R/hr) above background. This report also describes the results of groundwater sampling and analysis activities conducted in accordance with the FSSRP and describes activities completed to address total uranium activities greater than the threshold level of 30 picoCurries per liter (pCill).'
1.2 Scope The sampling area was divided into two areas, affected and unaffected. The affected area comprised approximately 5,600 square meters (m ) and is defined by the former 2
fence that surrounded the northwest CaF storage area. For the purpose of the final 2
status survey, the unaffected area includes the area outside the affected area bounded by the existing chain-link fence along the north, south and west sides of the area and by the ten 10-meter grids contiguous to the castem edge of the affected area. Several soil piles 1
Based on the proposed drinking water naximum contaminant level established by the US Environmental Protection Agency in National Primary Drinking Witer Regulations; Radionuclides; Proposed Rule. Federal llegister pp. 33050 33127. July I 8,1991 (v)
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- - containing materials removed from ths affected area are located in the unaffected area.
Samples from the' affected area,~. unaffected areas and excavated soil piles were collected."
L.3 ~. Objectives ;
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. The' objectives of the fir # status survey conducted during December 1998 and January 1999 (with additional samples collected in March and' September 1999) were to demonstrate that:
~ 1. : Residual. soil contamination concentrations are less than the NRC unrestricted micase limit of 30 pCi/g, above background, as specified in NRC Branch Technical Position, Disposal or Onsite Storage of Residual Thorium or Uraniumfrom Past Operations, Option 1 (NRC 1981).
2.-
Exposure rates due to site contamination are less thar. the NRC unrestricted release limit of 10 pR/hr, above background, as specified in NRC Branch Technical Position, Disposal or Onsite Storage of Residual Thorium or-Uraniumfrom Past Operations, Option 1, anci;
- 3. Reasonable effotts have been made to identify and remove areas of elevated activity.
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Final Status Survey Report Northwest CaF Storage Area 2
October 1999 2.0 SITE INFORMATION 7V 2.1-Site Description and Illstory The northwest CaF storage area consisted of seven shallow trenches located in a 1-acre 2
area in the remote northwest quadrant of the GE NEP facility. CaF was placed in the 2
storage trenches beginning in late 1968 through 1972. The seven trenches were located within a fenced area and were estimated to contain approximately 70,000 cubic feet (ft')
of CaF, material. The maximum depth of the trenches was estimated at approximately nine feet with an average depth of 5 to'6 feet.
The fenced and contiguous areas were, until 1996, covered with varying age classes of pine trees and scrub vegetation. All vegetation was cleared from the site before excavation activities commenced. Natural ground elevations in this area typically ranged from 20 to 26 feet above mean sea level. The pre-excavation and surface generally sloped from west to east.
Soils in the area are chiefly composed of fine-to-medium grain sands, distributed in
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strata, which generally become finer and siltier with depth. The sands vary in silt
'd content, color and percent of natural organic material. The approximate depth to groundwater beneath the surface ranged from approximately 4 feet in the southeast comer of the site to 11 feet in the northwest comer (based on water level mesurements performed in 1995 by others).
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Radiological surveys were completed for the area surrounding the former northwest CaF storage area by NFS and were presumed, with a single exception, to be unaffected
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2 by prior CaF operations. One area of eleva;ed activity was identified along the access
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2 road during this survey. This area was excavated; hence the source of elevated activity was removed prior to excavation of CaF material.
2 From the period of February 1996 to August 1996 approximately 200,000 ft' of CaF2 and CaF contaminated soil was removed from the seven shallow pits. Of this total, 2
approximately 125,000 ft' of CaF material was transported to a secure onsite 2
warehouse for interim storage. The remaining 75,000 ft' consisted of soils containing visible CaF at a total uranium concentration less than 200 pCi/g. This material we.s 2
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Final Status Survey Report Northwest CaF Storage Area 2
October 1999 disposed of at Safety Kleen's Pinewood, South Carolina facility. Following removal of
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fm the CaF, materials, the excavation has remained open pending release of the site for
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unrestricted use.
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l Figure 2-1 shows the post excavation CaF Project area as of September 1997. The project area is defined by the pioject area fence to the north, south and west and by the control line fence to the east. The project area is divided into two areas: affected and unaffected. The affected area is bounded by the old storage area fence, which was partially removed during excavation, but is shown on Figure 2-1 to help clarify the boundaries. The unaffected area is delined as all the remaining area within the project area. The soil pile area consisted of the overburden soil which had been placed over the CaF material and had to be removed.
2 1
In summer 1997, a scoping survey was conducted to detennine if the site was ready to l
implement the NRC approved FSSRP and to establish background uranium activities for area soils (NFS 1997). Based upon the sampling results, it was determined that additional material would need to be removed to meet the release criterion for residual total uranium activity in soil. Although the overburden soil pile and unaffected area met
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the unrestricted release criterion, the level ofresidual uranium in portions of the affected area, primarily the bottom of the t:enches, exceeded 30 pCi/g total uranium.
In December 1997, removal of the remaining material exceeding 30 pCi/g began.
Periodic samples were taken and analyzed for total uranium via gamma spectroscopy to segregate materials that were beMw the unrestricted release criterion and could remain at the northwest storage area and materials that exceeded the unrestricted release criterion and must be removed from the area. Approximately 115,000 ft' of material exceeding the release critericn was removed from the former northwest storage area and transported by truck to the process lagoons area on the GE NEP site where it was deposited with CaF material of similar total uranium activities.
2 The remaining soil consisting primarily of soil excavated from between the trenches was placed into several soil piles located adjacent to and just south of the excavated rea. These piles consist of overburden material removed prior to the start of excavation activities and " clean" soils removed from, primarily, between the former trenches afler the CaF had been excavated and removed. The only vegetation remaining consists of 73 Nuclear Fuel Senices,Inc.
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semb grasses, weeds, etc. 'Several different pictures of the site are presented in
. Appendix B (Photographs 1 through 6).
Because removal of the CaF material and surrounding soils created an excavation extending below the water table, most of the affected area is inundated under 4 to 5 feet
- ofwater, i
2.2-Identification of Contaminant and Analysis Method CaF 'is a by-product of the anunonium 'diuranate process and contains low concentrations of enriched uranium. Consistent'with the FSSRP, uranium comprises the sole contaminant of interest at the site, specifically the uranium radionuclides of 2"U,2"U and "U. The average 2nU enrichment in the fomier northwest storage area is 2
approximately 2% by weight.
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- For all soil and aqueous rinse blank samples, alpha spectroscopy was the sole analysis 2
conducted. Results from the contract laboratory and summary data presented within i
this report are all expressed in terms ofpCi/g.
'2.3 ' - Area Release Criteria The applicable radiological criteria for release of the former northwest CaF storage area 2
for unrestricted use, as approved by the NRC in the FSSRP, is 30 pCi/g total uranium in soil above background and un exposure rate no greater than 10 R/ hour above
- background. Residual activity at any sample location exceeding 90 pCi/g total uranium will be remediated as directed by GE NEP after which follow-up samples will be taken I
to confirm that no location exceeds 90 pCi/g.
2 EPA 907.0 (modified). Prescribed Procedures for the Measurement of Radioactivity in Drinking Water. EPA-600/4 %
032, August 1980.
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Final Status Survey Repon 7
Northwest CaF Storage Area October 1999
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13.0:
SOIL SAMPLING METHOD 01,0GY
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.l g iSoil Sampling Objectives -
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- Soil samples were collected in a manner to ensure that:
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( Samples were representative and free of cross contamination, 4
12;
- Prger sampling, sample handling, preservation, and' quality control (QC)
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. techniques were performed, -
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~ Samples.were properly identified, and
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Sample chain-of-custody procedures were followed and documented.
" 3.2 ! ! Sampling Loea' tions h
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. Geodetic control'(horizontal and vertical) was first established for all sample locations M
in the unaffected and affected areas. Every accessible land surface location was flagged
.: an' labeled. For inaccessible (i.e., underwater) locations, every other point was flagged '
d and labeled (Appendix B, Photograph 7). Following additional excavation activities,
- samplh locations were established using ' tape measure and an existing sample location a
for reference. Refer to Sheets I thmugh 6 of Appendix'A for the layout of the sampling points based upon the 5-meter x 5-meter triangular grid and the 10-meter x 10-meter square grid.
- 3.3 :. Sampling Methods.
4, Surface samples (0 to 6 inches below land surface) were taken using a stainless steel
. spoon or stainless steel scoop. Vegetation was cleared from the sample area prior to
' sampling to avoid including extraneous material in the sample. The 6-inch depth was determined using a plastic ruler as a guide for proper depth. The sample hole generally
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measthed 2 to 4 inches in diameter. Each sample was placed in a stainless steel bowl and then homogenized using a stainless steel spoon. Any remaining sample material L was plabed back in each respective sam %ing location h' le.
{
o Subsurface sediment sampling (0 to 36 inches below land surface) wa
.,mplished in
+
the pond area u' sing a pontoon boat as a sampling platform (Photograph 8). Because of Nucicar Fuel Services,'Inc.'
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Final Status Survey Report Northwest CaF Storage Area 2
October 1999 difficulties distinguishing sample depths from above the water surface, a single 1
sampling horizon was chosen for all samples collected from the pontoon boat.
<m O
Furthermore, due to the sandy soil conditions and the lack of sufficient sample recovery, the stainless steel auger could not be used for the subsurface sampling. A 10-foot clear polyvinyl chloride (PVC) sampling tube was driven from the boat into the sediment.
The tube was driven into the sediment with a rubber mallet or a metal hammer with a block of wood atop the tube. Once the tube was driven to the proper depth, a rubber stopper was placed inside the top of the tube to create a vacuum to retain the sample core. The core was then retrieved, the water decanted from the top of the tube, and the core was measured to make sure that the proper depth had been reached. The core was placed in a stainless steel bowl and homogenized with a stainless steel spoon before a subsample was obtained. This sampling method is shown in Photograph 9.
Subsurface samples from locations outside the pond area were collected from the 6 to 36 inch depth interval. The 10-foot sample tubes were cut in half, measured and taped 1
off to 36 inches in length from the bottom.' The tubes were driven and the cores recovered in the manner described above. A rubber stopper was also used with these tubes to create a vacuum to retain the sample core. Samples were homogenized in a
(]
stainless steel container using a stainless steel spoon or scoop. Photograph 10 shows sampling from land surface. Sample interval verification and excess water removal i
fmm the sampling tubes is shown in Photographs 11 and 12. Sample extrusion into the stainless steel bowls is shown in Photographs 13.
3.4 Sample Designations The sample designations were derived from the geodetic survey map generated prior tc the sampling event. Points labeled from the survey corresponded to the sampk identification designation. Prior to sampling tables were created that depic: J the sample numberr associated with the affected, unaffected, and soil piles. These tables were used as a check to assure all samples were collected. A field survey map was also used to check accuracy of sampling points.
Samples were labeled in the unaffected area as "U" followed by the sample number.
Samples for the affected area were prefixed with the letter "A" folloived by the sample number. In the affected area where samples were collected at different depths, samples wJ Nuclear Fuel Senices,Inc.
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were labeled "A" followed by the sample number. Confirmatory samples taken after re-
,rS excavation activities were conducted were labeled as before but were suflixed with the U
letter "F" For example, sample A325 was re-labeled as sample A325F for the post-excavatipn/ confirmatory sampling. Where a second confirmatory sample was required, a second F" was affixed to the previous sample number, e.g. A325FF. The "laydown area", which was a small area adjz cent to the affected area, was used to temporarily stage and drain the excavated soil. Samples were collected from the laydown area after soil removal. These samples, taken from 0 to 6 inches in depth, were labeled as LA-1 through LA-9.
The field QC equipment rinse and decontamination rinse water samples were labeled ER and DRW, respectively, followed by consecutive numbers.
The blind field duplicates were prefixed with the letters "U" or "A" depending on the area and depth from which they were collected.
3.5 Sample Types and Number ofSamples Single, vertical-specific samples were taken at each sampling location. Recovered soil
(~]
material from the sampling device was homogenized in a stainless steel container. The number of samples collected is shown in Table 3.1.
3.6 Sample Volumes and Containers All soil samples were placed into 125-mL wide-mouth glass sample jars. Aqueous samples obtained from equipment blanks and rinse water samples were put into standard 1-L plastic sample containers and were preserved with nitric acid to a pH of less than 2. Photograph 14 pmvides a representative picture of a labeled samplejar, l
3.7 Sample Labeling All samples were labeled approprSely with a waterproof, indelible ink marker.
Information recorded on each sample label included the sample identification number including depths if needed, date and time sampled, analysis, project name, and the sampler (s) initials.
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TABLE 3.1 Sample Collection Summary 3
I
- 7... 7. #..,,s.,w,.
.,y
. /'.M k Affected Area hccessible areas) 0-6 48 i
l Affected Area (accessible areas).
l 6-36 48 l Affected Area 0-36 216 (inaccessible areas) l Unaffected Area, soil piles l
0-6 130 l Unaffected Area, non-soil pile area l
0-6 69 l
Subtotal: 511 samples.sent to contract laboratory Note: 22 blind field duplicate samples,6 equipment rinse samples, and 6 decontamination water samples were obtained and analyzed by the contract laboratory.
,e_ctetAresF%g%%s#3lgW Unaffected Area, soil piles C-6 4
l Unaffected Area, non-soil pile area 0-6 1
l~
Subtotal: 5 samples sent to contract laboratory, no field duplicates
~~ T C1 21WAaHfplelt
__ _ _______- 1.%b)1R99 W W W K t"' Z a MPAW Affected Area 0-36 18 (inaccessible areas)
I Area Laydown Area in the Unafrected 0-6 9
l Unaffected Area near soil pile 0-6 4
p(/
l Subtotal: 31 samples sent to contract laboratory l were:obtained and analyzed by the contract laboratory. Note 2 blind field du l
,C.li.!5571121 ZE.,72-?f'? ^^A23999M3WN4MWWMWik Affected Area 0-36 25 (inaccessible areas)
Excavated Soils Placed in the 0-6 22 Unaffected Area l
Subtotal: 45 samples sent to contract laboratory Note: 2 blind field duplicate samples,1 equipment rinse sample were obtained and analyzed by the contractlaboratory BLS - Below Land Surface n)
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Final Status Survey Report
. Northwest CaF, Storage Area October 1999 3.8 Forms for Sample Collection Standard sample labels and chain-of-custody forms were used for all samples sent to the contract laboratory. Additionally, custody seals were affixed to the sample coolers and a soil-sampling log was maintained which recorded information includirg: facility / site identification, sample identification, sample collection times and dates, and the depth intervals of samples taken. These logs are maintained within the project file.
. 3.9 Sample Preservation j
3 No sample preservation or sample cooling was required for alpha spectroscopy analyses on the soil samples; however, all aqueous samples (equipment rinse, rinse-water) were preserved with nitric acid to a pH ofless than 2.
'3.10 Duplicate Samples Duplicate samples were taken after sample homogenization at an approximate rate of one duplicate per twenty samples collected. These duplicate samples were labeled so that the contract laboratory did not realize that they were duplicates (i.e. blind field I
-duplicates).
3.11 Decontamination Process A pressure-rinse decontamination station was established to decontaminate the PVC sampling tubes. Water containerized within portable tubs was used to clean all other sampling equipment with a two-step process. The first step involved the equipment being rinsed until any visible sands or soil was removed. The second step involved a general water rinse using spray bottles. Equipment was then hand-dried with towels.
Gross swipes of equipment were canducted and surveyed with field instrumentation to provide an indication of any gross deficiencies in decontamination effectiveness. All decontamination process water was retumed to the basin. All swipe sample results and field screening indicated that the decontamination process was successful. Photographs 15 and 16 depict the typical decontamination process. While examples of radiological field screening ofsample bottles and swipe counting are shown in Photographs 17 and 18, respectively.
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October 1999 3.12 Transfer of Custody and Shipment l
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When transferring possession of the samples, the transferee signed and recorded the date l
and time on the chain-of-custod." record. Samples collected during this program were always transferred as a group of1amples. Every person who took custody filled in the appropriate section of the chain-of-custody record. To prevent undue proliferation of custody records, the namber of persons involved in the chain-of-custody possession was minimized to the extent possil;le.
The Project Enviromnental Scientist was responsible for and successful in ensuring that all samples were properly labeled, packaged, and dispatched to the contract laboratory.
This responsibility included completing and verifying data accuracy, and then dating and signing the appropriate section of the chain-of-custody record.
The chain-of-custody record accompanied'all shipments sent to the laboratory. A copy of these forms was retained by the Project Environmental Scientist and transferred to
' the project file. Samples were delivered to the contract laboratory in a timely manner, and no chain-of-custody violations or discrepancies were noted. Tamper-proof custody Qb seals were attached to the lids of each cooler shipped.
3.13-Documentation of Field Operations I
3.13.1 Field Lochook l\\
A bound log book was maintained to record the names of the sample collector (s),
general descriptions of the day's activities, documentation of general weather conditions, unique sample collection characteristics (special cases), project name or identification, date and time of sampling, source / location of sample, and method of sample collection. A field notebook was used to derument sample designations, time and date of collection, sample depths and W.tions, sampler (s) initials, scheduled
- contract laboratory tumaround time for dna receipt, and shipping date. Entries were made in waterproofink. A sepote log was maintained for the gamma scanning and exposure rate surveys that is also maintained in the project files. The bound log and field notebook are maintained in the project file.
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- 3.13.2 Chain-of-Custody--
l Each sample was properly _ documented to ensure timely, correct, and complete analysis.
The documentation system provided the means to individually identify, track, and
~
monitor each individual sample from the point of collection through final data reporting.
- A sample or evidence file was considered to be under custody if: it was in possession; it was in ~ constant view after being in the site manager's possession; it was in possession
' and was placed in a secure area: or it was placed in a designated secure area; Photograph 19 depicts several samples contained within a sample cooler with chain-of-custody forms supplied."
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l 4.0 FIELD ACITIVITIES
SUMMARY
/^')
U The FSRRP required sampling aciivities for both soil and groundwater. These sampling activities are discussed below.
4.1 SoilSampling and AdditionalExcavation Activities To implement the FSSRP, NFS prepared a work plan (NFS 1998) to provide detailed instructions for the soil sampling activities. This work plan was reviewed with all sampling personnel prior to the stab of sampling activities.
From the period from December 15,1998 to January 11,1999,533 samples, including 22 blind field duplicates, were submitted for analysis to the contract laboratory.
Sampling was conducted under the guidance of the Project Environmental Scientist by four field samplers and a radiation technician. Based upon the sample results, two areas were identified for additional action. Sheet 1 of Appendix A shows the initial sample locations.
Sheet 2 of Appendix A presents the initial sampling locations with corresponding averaging trapezoids.
n Surface samples (0 to 6 inches) were collected from the unaffected area at the center of each 10-meter x 10-meter square grid. Because the soil piles contained soil removed from the affected area, sampling locations were determined using a 5-meter triangular grid. A surface sample was collected at each node of the triangular grid. Because the soil was mixed during excavation, no stratification within the soil pile was expected.
Thus, no subsurface samples were collected. For accessible areas within the affected-j area, a surface and subsurface (6 to 36 inches) sample was collected. Because an accurate distinction between the two sampling horizons was unable to accurately be made for samples collected from the pontoon boat, a single subsurface sample (0 to 36 inches) was collected at each of these points within the affected area.
. 4.1.li Additional Excavation in the' Unaffected Area Indvidual data received from the unaffected area indicated that sample number U416 contained 39.0 pCi/g of total uranium. The area in the immediate vicinity of this sample was reclassified as an affected area. Sample locations U403A, U403B, U403C and A.
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E U35A were identified to provide the required sample density. Samples (0 to 6 inches) were collected at these points. The sample locations and corresponding total uranium
- C concentrations for the trapezoidal survey unit are shown in Table 4.1. Sample locations i
U403C (11.5 pCi/g) and U35A (0.66 pCi/g) were collected to verify the elevated activities did not extend outside the unaffected area.
1 TABLE 4.1 Sample Results from the Elevated Area in the Unaffected Area (pCi/g) j gjgstalDN remum i
,;;3 ffThlinlitatifk l
r U403 11.4 U34 15.5 U416 39.0 1
U403A 2.43 U403B 98.9 Average = 33.4 As shown in Table 4.1, the trapezoidal grid averaged 33.4 pCi/g which was above the release criterion of 30 pCi/g. In addition, sample U403B exceeded the action limit of 90 g.
pCi/g. All of these samples were obtained from 0 to 6 inches in depth. The initial
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gamma scanning survey indicated this area was above the audible background count rate. The location with the highest audible count rate was labeled EA-1. Due to the distance this area was from the affected area and the sample results from nearby locations, these elevated samples (points U416 and U403B) were considered outliers and indicative of surface contamination. Therefore, no 6 to 36 inch samples were collected. Because the average total uranium concentration for the survey unit exceeded 30 pCi/g, a decision was made to implement corrective action through additional excavation and confirmatory sampling and surveying.
On March 12, 1999, additional excavation was conducted within the unaffected area bounded roughly by sampling points U406A, U406B, U35, EAl, and U418. Two to four inches of soil was excavated and removed from the site. Four additional samples were obtained as indicators whether all uranium contaminated soil above the 30 pCi/g release limit had been removed. These four samples were labeled as U35F, U416F, U403BF, and U403AF. Whether the data were considered individually or in cluster average fonn, the release criterion for this particular area was met. Table 4-2 shows the O
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TABLE 4.2 Confirmatory Sample Results from the Elevated Area in the Unaffected Area (pCilg)
U403 11.4 U34 15.7 U416F-2.69 U403AF-28.6 U403BF 3.50 Average = 12 4 The sample locations U403 and U34 were not affected by excavation activities.
Therefore, confirmatory samples were not collected at these locations and the original total uranium-concentration was used in calculating the average total uranium concentration for the survey unit. ' A confirmatory sample was collected at sample location UJ5F (1.18 pCi/g total uranium). The gamma scanning survey conducted after excavation indicated no increase in the audible count rate above background. Sheet 4 of
()
Appendix A shows the excavated boundary area and associated confirmatmy sampling i
locations.
4.1.2 Dredeine Operations in the AfTected Arc Individual data within trapezoid numbers 33, and 40, indicated that uranium activity was sufficient to increase the calculated survey unit averages (using five data points per cluster) above 30 pCi/g. In addition, two sample locations (A324 and A326) exceeded the 90 pCi/g action limit defined in the FSSRP. Averages for two areas were above the
- release criterion while the averages for three adjacent areas, trapezoid numbers 26,38 and 39, contained elevated individual sample results. Table 4.3 presents the sample results for these areas. All samples were obtained from the bottom of the pit dowTi to three feet in depth. Because both individual results exceed 90 pCi/g and these five cluster averages exceeded or nearly exceeded 30 pCi/g total uranium, a decision was made to implement corrective action through excavation and confirmatory sampling.
On March 12,1999, the elevated area within the affected area was excavated using a (D
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n Table 4.3 Sample Results/ Averages Prior to Dredging Operations v
~_9
.:; 3 ;
~
y 26 A310 55.1 39 A277 6.19 A311 5.42 A278 13.9 A312 9.73 29.6 A279 9.70 12.6 l
A321 7.94 A288 3.49 A322 b75 A289 30.0 33 A308
.22.9 40 A305 12.1 A309 16.9
'A306 7.88 A323 28.3 53.4 A307 37.4 E.
A324 A326 II A325 56.7 A327 19.8 38 A244 10.4 j l A245 10.9
- [
A246 21.5 26.9 i
A255
[$
h A256 16.6 6
diesel-hydraulic dredge. Removed soils were temporarily placed to the south of the
)
affected area within the unaffected area and allowed to padially dewater before site removal This temporary soil storage area was referred to as the laydown area. A total of nine samples, taken from 0 to 6 inches in depth after the excavated soil was removed, were obtained from the laydown and water mnoff areas to ensure that the surface soils in contact with the re<:xcavated soils did not become contaminated. Sampling results indicates that the laydown area meets the release criterion. A scanning survey of the laydown area indicated no increase in audible count rate above background.
After dredging, the affected area was sampled to assess whether this area met the release criterion. The sample results are presented in Table 4.4 and Sheet 4 of Appendix A.
.Two sample locations (A307 and A327) exceeded the 90 pCi/g action limit defined in the FSSRP. Averages foi three areas were above the release criterion while the two
- other areas'still contained elevated samples.
4.1.3 Additional Excavation Activitiesin the Affected Area As shown in Table 4.3, the uranium activity was sufficient to increase the calculated
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Table 4.4 Sample Results/ Averages Following Dredging Operations 26 A310F 54.7.
39 A277F 24.3 A311F-3.88 A278F 83.3 A312 9.73*
20.4 A279F 61.9 46.3 A321 7.94*
A288F 56.5 A322F 25.5 A289F 5.56 33 A308F 21.9 40 A305 12.l*
A309F 50.6 A306 7.88*
A323F 10.3 44.1 2
A307F 139.0 68.9 A324F 77.7 A326F 84.5
'A325F 59.9 A327F 101.0 38 A244 10.5*
lp Laydown LA-1 2.97 A245 10.9*
j i Area LA-2 1.17 h
A246 21.5*
25.8 LA-3 3.44 A255F 69.80 g
LA-4 9.70 A256F 16.2 Wi LA-5 2.72 5.7 bg LA-6 2.45 LA-7 11.2 b
h O
LA-8 8.36 g
LA-9 3.66
- indicates prior sample used to calculate average, cluster averages above 30 pCi/g for three of the five areas. All samples were obtained from the bottom of the pit down to 3 feet in depth. As a result, a decision was made to excavate additional soil from these areas.
In September 1999, soil from the soil pile located along the westem edge of the unaffected area was used to construct a ramp that extended out from the tastern bank of the affected area to each area requiring additional excavation. Wooden equipment mats were placed on the ramp to provide a stable platform for the excavator. Approximately 2 - 3 feet of material was removed from each cluster and stockpiled in the previous laydown area. Samples were collected fmm the excavation area and the stockpiled soils. All averages for the trapezoids were below the release criterion. One soil pile sample, A493, exceeded 90 pCi/g at 111.0 pCi/g. While awaiting sample results, Hurricane Floyd deposited over 15 inches of rain on the area that caused the contours of
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Final Status Survey Report Northwest CaF Storage Area October 1999 the soil pile to change. As result, sample location A493 was resampled to determine if further action was necessary. The resample result, A493F, was 11.0 pCi/g indicating no fyV further action was necessary. The sample results are shown in Table 4.5 and Sheet 5 of Appendix A.
4.2 Gamma Scanning Survey A gamma scanning survey was performed as described in the NRC approved FSSRP and subsequent conespondence for the former northwest CaF storage area. The survey 2
was performed by the Project He'alth Physicist and Technician each using a system comprised of a Ludlum Model 2221 scaler-ratemeter with a Ludlum Model 44-10 4
NaI(Th) detector to identify the presence of elevated direct radiation.
System information is presented in Table 4.6. The survey instruments were checked each moming and every 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> thereafter, during instrument use, for the following: battery status, high voltage applied to the detector, threshold shift, and background response. A Cs-137 source and uranium source were used to check the equipment response as measured in counts per second (cps). The results of the instrument check indicate that no observable drift of the detector occurred while performing the gamma p
scanning survey. The scaler-ratemeter and detector combination indicated in the table U
was used in performing all surveys. The range of equipment response was 60 - 80 cps for background when performing the scanning survey.
Personnel performed the gamma scanning survey by moving the survey meter from righ, to left in a 1-meter wide path while walking at a rate less than the FSSRP stated scanning rate of 0.5 m/s. Cord handles were attached to the detector to permit personnel to maintain a consistent 6 inch height of the detector to the soil surface when scanning.
Walking rates were slowest for the gamma survey scan of the soil pile slopes and excavation banks surrounding the underwater affected area. A more consistent walking rate was noted for open level areas but still less than the 0.5 m/s rate.
In areas where survey personnel detected an increase in the audible count rate, personnel paused over the area where an increase was noted. Personnel performed a stationary I
gamma scan survey for 4 to 8 seconds to determine if the count rate did increase. For all cases when personnel paused, no increase in audible count rate was observed except 2
for an approximately 10 m area located 2 m from sample locations U416. After
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l Final Status Survey Report Northwest CaF Storage Area October 1999 (D
Table 4.5 Sample Results/ Averages Following Additional Excavation 5
(
26 A310FF 5.07 f.3 39 A277FF-14.3 A311F 10.4
. s A278FF 26.1 A312F 4.30 15.1 g
A279FF 24.9 18.0 A322F 48.3 M
A289F 4.07 A321F 7.52'
'6 A288FF 20.8 33 A308FF 10.3 y
40 A305F 5.20 A309FF 24.4 A306F 13.3 A325FF 13.9 14.45 E
A307F 18.0 18.8 A324FF 15.2 A327F 21.8 A323FF 8.49 A326F 35.9 38 A256FF 51.6 g
Soil A485 12.7 A255FF 10.4 M/
Pile A486 7.20 A244F-17.5 24.0 I
A487 8.35 A488 7.88
)4 A245F 21.1 A246F 19.5 A489 10.5 fff A490 22.7 A491 1.76 h~
h A492 10.9 g
A493F 11.0 12.1 A494 7.97 f
A495 54.8 W
A496 10.1
[h.
A497 9.99 A498 6.62
!!i A499 3.82 A500 8.82 i
A501 9.40 i
A502 10.3 Y2 A503 10.3 N
A504 17.1 o0 Nuclear Fuel Services,Inc.
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Final Status Survey Report Northwest CaF Storage Area 2
October 1999 Table 4.6 V
Gamma Scanning Survey Equipment b. n:.L W i l
Wil2%
1 2221 126508 Scaler-Ratemeter Ludlum l
44-10 l PR128459 2" x 2" NaI(Th) Detector 2
l 2221 l
126519 Scaler-Ratemeter Ludlum l 44-10 l PR120262 2" x 2" NaI(Th) Detector j
scanning the area where an increase in' audible count rate was observed, the boundaries of the elevated area (based on increase in audible count rate) were marked on the survey map and a sample flag was located at the center of the circular area. This sample location was marked as EA-1. Refer to section 4.1.1 for a discussion of the additional excavation of this area. A final gamma scanning survey for this area indicated no audible count rate above background.
The gamma scan survey locations for the affected and unaffected area used the existing grid system established for the soil sampling. The entire soil surface of the 10-meter O
gria i# the rreeted ree t e vered 67 - ter a the ever8"rae" ti ere - -
surveyed. The 1-meter wide path surveyed for the unaffected area was performed ia a straight line that intersected the marked center points of the 10-m grid. The initial 2
gamma survey scan was perfomied over a 2-day period, Febmary 15 and 17,1999.
Weather was clear both days with temperatures from 50 to 65 degrees Fahrenheit. A follow-up gamma scan survey was performed on the laydown area and unaffected area east of the soil piles after the re-excavations were completed. The location of the laydown area and the excavated area is indicated on Sheet 3 of Appendix A. After completion of the final excavation of these areas, the gamma scanning survey indicated no elevated activity based upon audible count rate.
4.3 Exposure Rate Survey The exposure rate survey was performed using a Ludlum Model 2221 scaler /ratemeter with a Ludlum Model 44-10 NaI detector to identify the presence of elevated direct radiation influence. The instrument was calibrated to read in pR per hour. The detector
~
and ratemeter were placed on a monopod (staff) to provide a consistent distance of one (V)
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meter from the land surface. A 1-minute count was perfomied to determine an q
integrated exposure rate. The survey instruments were checked with a Cs-137 source l
each morning and every 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> thereafter, during instrument use, for the following:
battery status, high voltage applied to the detector, threshold shift, background r esponse.
The results of the instrument check indicated that no observable drift of the detector occurred while performing the exposure rate suney.
The systematic series of exposure rate measurements were performed using the existing 5-meter triangular grid and 10-meter square grid used for the soil sampling. Exposure rate measurements were taken at each' marked grid location. The detector was attached to a monopod,,1 meter from the ground. When performing the exposure rate survey on the soil pile slopes or banks near the underwater area, the pole was kept perpendicular to the surface being surveyed. Refer to Sheet 1 of Appendix A for the grid point location and numbering layout for the March survey and Sheet 5 of Appendix A for the September survey of the soil pile.
The exposure rate survey was performed on March 5 and 6,1999 with the weather being fair and the temperature 60 - 65 degrees Fahrenheit. Photograph 18 shows the
[]
Ludlum system use during the survey process. The exposure rate survey readings and background were counted for one minute. Background was determined at the NFS field office and at the entrance to the former northwest CaF, storage area on March 6,1999, the weather being fair and in the upper 50's. An exposure rate survey was performed September 27,1999 for the soil pile generated during final excavation of the affected area, weather being fair and temperature in the mid 70's Fahrenheit.
A measurement was taken at the center point of the square from each 10-meter grid square present within the unaffected area. In the affected area and the overburden soil piles, exposure rate measurements were taken at each sample point on the 5-meter triangular grid system. All accessibic grid locations were surveyed.
4.4 Groundwater Sampling Groundwater samples were collected from the 17 CAF-series monitoring wells located on GENE property in the vicinity of the former northwest CaF storage area.
2 The Research Triangle Institute (RTI) collected both filtered and unfiltered gb Nuclear Fuel Services,Inc.
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I5 Final Status Survey Report Northwest CaF Storage Area October 1999 i
' groundwater samples in ' January 1999. Teledyne Brown Engineering - and
.O' Environmental Services in Westbrook, New Jersey, analyzed the groundwater samples -for isotopic-uranium using alpha spectroscopy. Documentation of the 1-groundwater sampling activities, including a description of the sampling locations, methodology, and analytical results, is provided in Appendix D. Appendix D also includes supplemental information on groundwater flow characteristics and velocity calcula'tions.
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5.0 IIEALTII AND SAFETY l
f3,
'(/-
All members of the field crew were trained to bot client and NFS requirements before starting the project. : The work was conducted pursuant to the NFS Health and Safety Plan for the GE NEP Wilmington site. Thejob activities and associated hazards were discussed with personnel prior to the start of any fieldwork. A GE NEP Radiation Work Permit was not issued for the FSSRP field sampling activities. New disposable gloves were donned prior to the sampling of each survey point. Field personnel wore
. safety glasses and steel-toed boots throughout the sampling program. Life vests were worn by all personnel that used'the pontoon boat. Periodic radiation surveys of sampling cquipment, sample containers and personnel founn no detectable contamination.
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6.0 QUA.LITY ASSURANCE
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l
'v Quality assurance (QA) was achieved throughout the project by following written plans and procedures and US Environmental Protection Agency (EPA) protocols. Data validation performed on all alpha spectroscopy data indicated that no problems were noted with precision, accuracy, representativeness, completeness or accuracy. QC samples collected and analyzed as part of field and laboratory QA are discussed below.
6.1 Field Activities Quality Assurance.
As evidence to demonstrate that the decontamination process was sufficient, seven equipment rinse samples and seven samples of the rinse water itself were collected and analyzed by alpha spectroscopy.
The sample results were all representative of background conditions at the site, thereby indicating that no cross contamination was present and that the decontamination process was successful. Data from the equipment rinse and rinse water samples are summarized in Table 6-1.
TABLE 6.1
,o Equipment Rinse and Rinse Water Sample Results (pCi/I)
\\m.)
a c ERI 0.118 0.0237 0.107 0.249 EPd 0.193 0.209 2.46 2.86 ER3 0.0897 0.0268 0.166 0.282 ER4 0.0510 0.0503 0.138 0.239 ER5 0.0309 0.0519 0.129 0.212 ER6 0.0685 0.0676 0.194 0.330 ER7 0.0573 0.106 0.122 0.0416 DWR1 0.0953 0.0380 0.0953 0.229 DWR2 0.0205 0.0289 0.I61 0.210 DWR3 0.0507 0.0487 0.138 0.237 DWR4 0.0936 0.000 0.0688 0.162 DWR5 0.118 0.0875 0.16]
0.366 DWR6 0.0300 0.0586 0.145 0.234 DWR7 0.0435 0.0181 0.153 0.214 (O
3 Nuclear Fuel Services,Inc.
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i Final Status Survey Report i
Northwest CaF, Storage Area October 1999 6.2 Laboratory Quality Assurance j
pg V
A total of 33 method / preparation blanks were run for each analyte (224U,2"U,2"U). The activity concentrations for all method blanks met acceptance criterion ofless than three times the minimum detectable level and were thus all acceptable. All samples were prepared and analyzed within the method specified holding time. Laboratory contml sample (LCS) recoveries are considered acceptable if found between 75% and 125%. A total of 31 LCS were analyzed for the uranium isotopes; two LCS were noted with both having a 59% batch recovery, both samples had a higher than normal FWHM (poor resolution) which interfered with resolving low-energy peaks such as U-238. However, for these two batches, normal to better-than-normal resolution was observed in samples and spike recoveries were good; therefore, both batches were considered acceptable.
Thirty-three laboratory duplicates were analyzed, and all duplicate analyses data met the acceptance criterion of a replicate error ratio (RER) criterion ofless than 2.0 which is considered fully acceptable (results between 2.0 and 3.0 are considered conditionally acceptable). All.RERs for U-235 and U-238 were less than 2.0. One of the laboratory duplicates performed on sample U118 showed a RER of 2.9 for U. However, for this 234 c'D particular sample, the total uranium activity was 3.4 pCi/g indicating background i
/
activities. Another one of the laboratory duplicates performed on sample A321 showed 234 a RER of 6.3 for U. The total uranium content for this sample was again low at 7.9 pCi/g. A total of thirty-three blank spikes and thirty-three matrix spikes were un run for each uranium isotope. Blank spike and matrix spike recoveries were all within the 75% to 125% trace criterion with the exception of four samples (no corrective action was taken since for these particular batches, tracer recoveries were acceptable and consistent with the parent samples). Matrix spike duplicates all demonstrated good precision.
A total of 24 blind field duplicate samples (8 unaffected area and 16 affected area samples) were obtained and analyzed for each analyte (234U,2"U, '"U). These data are provided in Table 6-2 and indicate excellent correlation. All blind field duplicates were within the acceptance criterion (a replicate error ratio of less than 3.0) with three 2
2 exceptions out of 72 (two for "U, one for "U). Given the heterogeneity of the CaF,
2 some exceptions where the RER is greater than 3.0 is normal and would be expected especially at low levels where background activities are common, and at the relatively Li Nuclear Fuel Services,Inc.
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Final Status Survey Report Northwest CaF Storage Area
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2 October 1999 i
higher activities. Variables such as lack of optimal field sample homogenization also i
73 contribute to higher sample RERs.
,V TABLE 6.2 Identification of Blind Field Duplicate Samples and Associated RERs U133 3.16 U486 4.86 0.37 0.07 1.62 unaffected area U122 2.98 U487 5.26 0.49 0.09 2.09 unaffected area U120 5.46 U488 2.35 0.40 0.39 3.96 unaffected area U427 9.0 U489 9.14 0.27 0.29 0.72 unaffected area U436 13.3 U490 14.1 0.59 1.28 0.14 unaffected area U461 18.0 U491 18.5 0
0.42 0.32 unaffected area U94 13.5 U492 11.4 1.27 0.27 0.71 unaffected area U78 6.8 U493 8.22 1.09 0.15 0.48 unaffected area A150 0-6" 1.03 A494*
1.01 0
0.16 0.24 affected area A147 0-6" 0.70 A495*
0.74 0.18 0.03 0.04 affected area A263 0-36" 7.0 A496*
5.73 1.00 0.53 0.90 afTected area A205 0-36" 9.12 A497*
8.71 0.48 0.72 0.05 affected area A214 0-36" 14.5 A498*
15.3 0.41 1.09 0.30 affected area A 280 0-36" 11.2 A499*
10.5 0.53 0.15 0.19 affected area A346 0-36" 3.76 A500*
4.27 0.60 1.47 0.47 affected area A199 0-36" 1.10 A50l*
0.76 0.47 0.01 0.22 affected area A315 0-36" 7.71 A502*
6.23 0.48 0.24 1.47 affected area A151( 36" 0.38 A503*
0.31 0.09 0.04 0.35 affected area A266 6-36" 8.98 A504*
8.16 0.87 0.40 0.29 affected area A398 0-36" 1.27 A505 0.96 0.10 0.20 0.22 affected area A374 0-36" 84.8 A506 56.9 2.85 3.02 3.16 afrected area A187 0-36" 1.28 A507 2.08 0.33 0.23 0.73 effected area A324F 0-36" 77.3 A508 75.1 0.27 0.23 0.25 affected area A278F 0-36" 83.7 A509 62.3 2.10 0.49 2.59 affected area
- Sample number duplicated with the sample numbers collected from the soil pile generated l
during additional excavation of the affected area.
1 Instrument primary calibrations are performed annually using National Institute of l
Standards and Technology (NIST) -traceable standards. During this project, secondary l
calibrations were performed weekly using in-house prepared standards. The contract laboratory performed daily checks to verify the electronia reproducibility of the counting system.
- Q U
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Final Status Survey Report Northwest CaF, Storage Area October 1999 7.0 PRESENTATION OF RESULTS AND DISCUSSION
'n U
Tables C.1 and C.2 present the isotopic sample results for the unaffected and affected areas. The total uranium activity is determined by summing measured activity for each isotope (2uU,2"U, and "U). Because the release criterion is based upon total uranium 2
activity, i..e presentation and discussion ofsaraple results refers to total uranium activity rather than the activity of the individual isotopes. Sheet 6 of Appendix A presents the final sampling results.
7.1 Background Determination
~
Twenty background samples, consistir'g of ten surface (0 to 6 inches) and ten subsurface samples (6 to 36 inches in depth) were taken from an area with similar geology as the former northwest CaF storage area (NFS 1997). This background area, located about 2
500 yards south of the project area was identified as an area not affected by GE hTP plant operations or by the CaF storage area excavation activities. Table C.3a lists the 2
background sample results from the ten surface samples. The average total uranium activity for surface samples was 0.26 pCilg. Table C.3b lists the background sample results from the ten subsurface samples. The average total uranium activity for the subsurface samples was 0.31 pCi/g. Because the background activities are low with respect to the 30 pCi/g release criterion, a background correction to the samples collected during this program was considered unnecessary.
7.2 Unaffected Area Table C.4 presents the results of samples taken on 10-meter grid increments in the unaffected area. This table is divided into two sections. First, the results from samples collected at the center of the 10-meter grids bordering the affected area are shown.
These grids comprise the unaffected area as defined by the FSSRP. As identified in Section 2.0, the area immediately adjacent to the west and south of the unaffected area, as defined in the FSSRP, was part of the operations aref during CaF removal and 2
therefore should also be considered an unaffected area. The second part of Table C.3 presents the results of samples collected from the center of 10-meter grids within this expanded unaffected area. As shown, all sample results are less than 75% of the unrestricted release criterion of 30 pCi/g. Therefore, no further sampling or excavation Nuclear Fuel Services,Inc.
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Final Status Survey Report Northwest CaF Storage Area 2
October 1999 is necessary. These areas meet the unrestricted release criterion for the total uranium (3
activity,30 pCi/g, defined by the FSSRP.
LJ Table C.5 presents the sample results collected from overburden soil pile. This pile consisted of the soil removed from the top surface of the trenches prior to the start of CaF removal. Samples were collected during the scoping survey (NFS,1997) by 2
dividing the soil pile into 3 zones and collected 3 core samples from each zone. These samples were analyzed by NFS' onsite laboratory using gamma spectroscopy. Two samples SP-06 and SP-09 were also analyzed via alpha spectroscopy by a contract laboratory, as a QA check, at 4.93 pCI/g and 9.09 pCi/g, respectively. In the period of time since these samples were collected, additional soil has been removed from the affected area and placed over this overburden soil. As shown, all sample results from the overburden pile met the unrestricted release criterion.
The various soil piles within the unaffected area contain soil removed from the affected area. This soil consists primarily of soils removed from between the trenches during the excavation activities beginning in December 1997. Process control samples were collected and analyzed for total uranium, via gamma spectroscopy, during excavation to (o) verify the soil placed in these piles was below the 30 pCi/g release criterion. The soil pile located in the laydown area consists of soil removed from the affected area during the additional excavation activities conducted during September 1999. All soil piles were sampled on a 5-meter triangular grid.
Table C.6 presents the individual sample results and trapezoidal grid averages for the soil piles. Four samples (U29, U451, U417 and A495) exceeded the unrestricted release criterion at 30.5 pCi/g,35.9 pCi/g,55.6 pCi/g and 54.8 pCi/g, respectively. However, because all trapezoidal grid averages were below the 30 pCi/g, the unrestricted release criterion for total uranium activity was met for all soil piles. Because the soil was well mixed during excavation, no stratification of uranium within the soil pile was expected j
and thus, no subsurface samples were collected.
7.3 Affected Area 1
Table C.7 presents the final individual sample results and trapezoidal grid ave: ages for the affected area samples. No sample result exceeded the immediate remediation level C/
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Final Status Survey Report Northwest CaF Storage /rea 2
October 1999 of 90 pCi/g. Twelve individual results exceeded the unrestricted release criterion.
O Because samples from nearby sample locations are below the release criterion, these V
elevated samples were considered isolated examples of contamination and no further sampling at these locations was conducted.
Table C.8 presents the trapezoidal survey unit averages for the aff;cted area. Because site conditions dictated varying sampling depths within a survey unit, the survey unit average was calculated using the maximum total uranium concentration at that sample location regardless of sample depth. As shown, all averages were below the release criterion. In addition, the calculated 95% upper confidence limit for these averages was also below the release criterion.
7.4 Gamma Scanning Survey Results For the gamma scanning survey, a comparison of the observed increase i udible count rate to the known uranium soil activities can be used to empirically determine the sensitivity of the Ludlum survey systems. Background count rates observed were
'60 to 80 counts per second for the walkover survey. Results of the walkover survey
(')
identified only one accessible area with a discernible increase in audible count rate that can used to evaluate the detector response. When passing over the area the count rate increased to approximately 120 cps. The location of the area and an associated sampling point, EA-1,is indicated on Sheet 3 of Appendix A.
A 0 to 6-inch sample was taken from the grid location EA-1 to evaluate the soil uranium activity. Laboratory analysis indicated that the EA-1 sample is 13 pCi/g so a direct correlation could not be made for the area having an increase in the audible count rate. Review of the soil sample results indicates that the sample locations U416 and U417 have total uranium activities of 38 and 68 pCi/g respectively.
1 After completion of the excavation activities for the undenvater affected area and the area east of the soil piles, the gamma scanning survey was repeated for those areas.
Final results of the survey indicate no areas are present above the audible count rate observed for background.
I
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Final Status Survey Report Northwest CaF Storage Area 2
October 1999 7.5 Exposure Rate Survey t
l V
The same Ludlum scaler-ratemeter detector system used for the gamma scanning survey was used for the exposure rate survey. The Project Health Physicist and Radiological Technician who suppo*ted the soil sampling a id gamma scanning survey performed the survey. Calibration of the Ludlum scaler-raten eter detector system was performed by the Ludlum Measurements. The calibration set a threshold of 100 kiloelectron-volts (kev) for the model 2221 scaler-ratemeter and 44-10 detector with the window open and with the window in for the Cs-137 photopeak. The window in mode was used to evaluate if any system drift occurr'ed in relation to the well-defined Cs-137 photopeak.
The exposure rate smvey measurements were perfonned with window open to detect all photoemissions greater than 100 kev.
The Ludlum system response can be confirmed by comparison to information for this detector published in NUREG/CR-1507, " Minimum Detectable Concentrations with Typical Radiation Survey Instrument for Various Contaminants and Field Conditions" (1995), that establishes guidance for radiological surveys to demonstrate compliance with applicable guidelines. Based on the discussion in NUREG-1507, Section 6, a Ludlum model 44-10 detector system with an open window and a threshold of 60 kev is 4520 cpm /pR/hr for 3% enriched uranium at 50 pCi/g concentration. Two factors that change the response characteristics for this project are the threshold value and uranium enrichment.' Using an open window with a 100 kev threshold meter response reduces the detector response by 15% (NUREG/CR-1507). The uranium enrichment is nominally 2%, so the detector response is reduced by approximately 10% further to
- 3500 cpm / R/hr at 50 pCi/g. The results of the Exposure Rate survey are presented in Table 7.1. 'Ihe number of survey points include points from the soil pile created during final excavation of the affected area. Results for the exposure rate survey indicate all measurements are below the 10 pR/hr over background release criterion.
TABLE 7.1 Exposure Rate Survey Summary
===.
Background===
10 3.0 0.18 0.12 l Affected Area l
273 l
4.0 l
1.72 0.21 l Unaffected Area l 76 l
3.9 l
0.57 0.13 f'
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l Final Status Survey Report Northwest CaF Storage Area 2
October 1999 Comparison of the background exposure rate to the two areas ofinterest indicates that
_/\\U the both the affected area and unaffected areas are less than 10 pR/hr above the background value. Exposure rate survey data for the soil piles are included in both the affected area and unaffected area average reading because the 5-meter triangular grid lo:ations and 10-meter square grid center point locations are superimposed in this area.
The greatest exposure rate of 6 R/hr was obtained at EA-1,2 meters off grid location 1
416 on a line to grid location 417. After soil scraping from the affected area, the exposure rate is consistent with other readings at 4.2 pR/hr. Survey of the soil pile after the final excavation of the affected areas indicated the soil averages of 4.5 pR/hr.
7.6 Groundwater Sampling and Analysis Total uranium activities for unfiltered groundwater samples ranged from below minimum detectable activity (MDA) to 157.7 pCi/L. Mean and median activities for unfiltered groundwater samples were 15.3 and 2.16 pCi/L, respectively'. Total i
uranium activities for filtered groundwater samples ranged from below MDA to 145.7 pCi/L. Mean and median activities for filtered groundwater samples were 12.5 and p
0.7 pCi/L, respectively. Uranium activities were below US Environmental Protection U
Agency's (EPA's) proposed drinking-water maximum contaminant level (MCL) of 30 pCi/L, except the samples from CAF-6A and CAF-7A. These two monitoring wells are directly downgradient of the former northwest CaF storage area and on GE 2
property. Groundwater from the next downgradient well, CAF-12A, exhibited a uranium activity below the proposed MCL, as did the deeper monitoring points adjacent to CAF-6A and CAF-7A (CAF-6B and CAF-7B). These monitoring data indicate that the impacts are limited to the shallow groundwater in the immediate vicinity of the former northwest CaF2 storage area.
Documentation of the groundwater sampling activities, including a description of the sampling locations, methodology, and analytical results, is provided in Appendix D. Appendix D also includes supplemental information on groundwater flow characteristics and velocity calculations.
In accordance with the Classifications and Water Quality Standards Applicable to the 3 For samples with activities below the minimum detectable activity (MDA), one-half of the MDA (0.1 pCi/L) was used to calculate mean and median activities.
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Final Status Survey Report Nonhwest CaF Storage Area 2
- October 1999 Groundwaters ofNorth Carolina (North Carolina Administrative Code Title 15A, Subchapter 2L), RTI prepared a Comprehensive Site Assessment (CSA) summarizing
- f. s\\
'u/
the assessment and monitoring activities for groundwater in the former northwest CaF storage area. The CSA was reviewed and approved by the North Carolina 2
Department of Environment and Natural Resources (DENR), Division of Water Quality and Division of Radiation Protection. In addition, a natural attenuation Corrective Action Plan (CAP) was prepared by RTI to address the localized groundwater -
acts in the area and was submitted DENR in 1999. Development of the CAP involved data collection and analysis, including delineation of the horizontal and vertical extent of non-natural'tiranium in groundwater, and evaluation of the fate and transport of the constituents of concern and potential impacts to human and ecological receptors. There are no human drinking-water receptors downgradient of the former source area and future development of the area is not expected. The groundwater impacts will continue to attenuate via natural processes and are not predicted to pose significant human or ecological risks currently or in the future. The i
adjacent property owner has been notified of the groundwater impacts and of the monitored natural-attenuation corrective action. Evaluation of existing geochemical and hydrogeologic data and the results of fate and transport modeling of the groundwater contamination indicate that monitored natural attenuation is the appropriate corrective action for this area. Consistent with the recommendations of the CAP and the verbal approval of the CAP monitoring plan by DENR, routine monitoring of groundwater quality in the area is underway and will continue. Periodic l
updates of groundwater sampling and analysis activities will be provided to DENR.
l l
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Final Status Survey Report Northwest CaF Storage Area l
2 October 1999
8.0 CONCLUSION
S (U
Based upon several soil samples analyzed for uranium activi+. the former northwest CaF storage area has. been extensively characterized per the FSSRP.
This 2
characterization has been conducted with the objective to provide documentation that the site meets the criteria for unconditional release under NRC regulation. The data inicates uranium contaminated soils exceeding the unconditional release criterion have been removed from both the unaffected and affected areas, including the various soil piles within the unaffected area. For the affected area, all trapezoidal grouping averages are below the release crite'rion with 95% confidence. In addition, no individual sample result exceeds the threshold activity of 90 pCi/g. The gamma scanning surveys indicated no detectable increase in activity between the accessible survey points within the affected and unaffected areas. The exposure rate survey found no area greater than 10 pR/hr above background. Based upon these results, the criteria for unconditional release of the former northwest CaF storage area have been met.
2 A natural attenuation Corrective Action Plan (CAP) was prepared by RTI to address the localized groundwater impacts in the area and was submitted DENR in 1999.
/7 Evaluation of existing geochemical and hydrogeologic data and the results of fate and i
transport modeling of the groundwater contamination indicate that monitored natural attenuation is the appropriate corrective action for this area. The groundwater impacts will continue to attenuate via natural processes and are not predicted to pose significant human or ecological risks currently or in the fu'ure. Consistent with the recommendations of the CAP and the verbal approval of the CAP monitoring plan by DENR, routine monitoring of groundwater quality in the area is underway and will continue. Periodic updates of groundwater sampling and analysis activities will be 1
provided to DENR.
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Final Stitus Survey Report
. Northwest CaF Storage Area 2
October 1999
9.0 REFERENCES
m
)
GE NEP 1998. Letter CMV-98-035, C. M. Vaughan (GE NEP) to M. Lamastra
~
(USNRC) dated November 24,1998.
GE NEP 1998a. Letter SPM-98-046, S. P. Murray (GE NEP) to H. Astwood (USNRC) dated October 8,1998.
I NFS,1998. Final Status Surny Workplan for the Northwest CaF Storage Area.
2
. November 1998. Nuclear Fuel Services, Inc., Envin, Tennessee.
NFS,1996. Final Status Survey and Release Plan for the Northwest CaF Storage 2
Area, February 28,1996, Rev. 02. Nuclear Fuel Services, Inc., Erwin, Tennessee.
NFS,1996a. CaF Soil Boring Characterization Report. July 1996. Nuclear Fuel 2
. Services, Inc., Erwin, Tennessee.
NFS,1997. Northwest CaF Storage Area Scoping Survey Report. September 1997.
2
'O Nuclear Fuel Services, Inc., Envin, Tennessee.
C/
NFS,1998. Final Status Survey Work Planfor the Northwest CaF Storage Area.
2 December 1998. Nuclear Fuel Services,Inc., Erwin, Tennessee.
NRC 1981. U. S. Nuclear Regulatory Commission (NRC). 1981. Bran:h Technical Position. Disposal or Onsite Storage of Residual Thorium or Uranium from Past Operations. 46FR2061.
L NRC Manual for conducting Radiological Surveys in Support of License Termination l
(Draft NUREG/CR-05849).
i r
O Nuclear Fuel Services,Inc.-
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Nuclear Fuel Services,Inc.
B-6
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i Final Status Survey Report j
Northwest CaF Storage Area 2
October 1999 9'
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Nuclear Fuel Services,Inc.
B-7
Final Status Survey Report Northwest CaF Storage Area 2
October 1999
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Nuclear Fuel Services,Inc.
B-8
Final Status Suney Report Northwest CaF Storage Area 2
October 1999
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i Nuclear Fuel Services,Inc.
B-9
I Final Status Survey Report Northwest CaF2 Storage Area October 1999 Q
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Nuclear Fuel Services,Inc.
B-10
Final Status Survey Report l
Northwest CaF Storage Area i
2 October 1999 I
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l i
p 0
O 0 4 O 0
0 O
O 0
0 0
O O
O 0
O o
+
- +
E E E E E E E E
E E E E E E E E E t
- 2 o.
D 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 s
A 7 0
8 6
6 0
7 0
7 2
9 0
5 J
6 6
I 9
1 2
5 6
3 9
5 2
1 3
2 6
5 7
I 1
2 "6
C..
ljlllllllllllllj 3
e 1
2 l
2 l
1 1
l l
2 1
l l
1 l
1 l
l 0
0 O 4 O 0
0 O
O 0
0 O
O 0
O 0
O 0
b, a
E E E E E E E E E E E E E E E E E t
T
-,- 0 0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
a 6 A 0
9 2
0 6
1 2
2 1
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2 2
2 1
d 1
9 1
9 1
1 1
1 1
9 1
1 1
1 1
1 1
e r
t c
0 lllllljll)llllll h e l
t l 0
0 0
0 l
0 l
0 0
0 0
0 0
0 l
1 0
O 0
0 0
0 0
O 0
O 9 0
0 0
0 0
0 h po t
e c
+
- + + + +
+
+
+ + + + + +
pd E E E E E E E E E E E E E E E E E e ees
.. 0 G
0 0
0 0
0 0
0 G
0 0
0 0
0 0
0 dl 0
A 9 8
5 5
5 A A 1
2 2
3 1
8
- 8. _8 l
7 8
8 8
epp 3
1 2
1 3
1 1
6 1
2 1
4 2 pmm l
aa ms s a
r s "6 lllllllllllllllj "6
e 1
0 0
0 1
0 1
0 0
0 0
1 0
1 0
1 l
3 h t
c
,0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 n
w.E+ + + + + + + + + + + + + + + + +
O I
E E E E E E E
E E E E E E E E E
- 6l
,s 0
0 0
0 0
0 0
0 0
0 G
0 0
0 0
0 0
0*
l e
5 9
7 3 J 5
8 2
6 2
A 5 J 6
6 5 *
- A 1
c i
1 2
3 9
I 7
1 3
6 3
5 3
6 1
9 2
1 vre S
llllllllllllllll le F
F F F
F F
F F F F F F F F F u
A F
F F
F F
F F
F F
F F
F F
F F
F 5
6 2
1 8
9 0
0 7
8 9
0 1
1 2
2 3
4 5
6 7
r 8
8 a
3 3
0 0
0 1
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2 2
2 e
3 3
2 2
3 3 3
3 3
3 3 3 3
3 3
A A A A A A A A A A A A A A A A A lcu llllllllllllllll N
7f
Final Status Survey Report Northwest CaF Storage Area 2
October 1999 TABLE C.3a Background Sample Results (pCi/g)- Surface Samples (0 - 6 inches)
. ill
)
k Nbk $
INmi Bl-1 0.07 0.01 0.11 0.19 B2-1 0.10 0.01 0.10 0.21 B3-1 0.06 0.01 0.08 0.15 B4-1 0.15
-0.01 0.15 0.29 B5-1 0.12 0.00 0.08 0.20 B6-1 0.19 0.00 0.23 0.42 B7-1 0.23 0.00 0.19 0.42 B8-1 0.14 0.01 0.10 0.25 B9-1 0.10.
0.01 0.08 0.19 B10-1 0.12 0.00 0.11 0.23 Total Uranium Mean = 0.26 pCi/g Total Uranium Standard Deviation = 0.10 Total Uranium 95% UCL ( mean) = 0.31 pCi/g Samples were analyzed using alpha spectroscopy TABLE C.3b Background Sample Results (pCi/g)- Subsurface Samples (6 -36 inches) en h
f
()
B1-2 0.12 0.02 0.12 0.26 B2-2 0.13 0.01 0.11 0.25 B3-2 0.11 0.00 0.08 0.19 B4-2 0.13 0.01 0.14 0.28 B5-2 0.19 0.03 0.20 0.42 B6-2 0.20 0.01 0.18 0.39 B7-2 0.18 0.02 0.19 0.39 B8-2 0.15 0.00 0.12 0.27 B9-2 0.15 0.01 0.11 0.27 B10-2 0.16 0.01 0.19 0.36 Total Uranium Mean = 0.31 pCi/g Total Uranium Standard Deviation = 0.076 Total Uranium 95% UCL ( mean) = 0.35 pCi/g Samples were analyzed using alpha spectroscopy (J
u Nuclear Fuel Services,Inc.
C-22
Final Status Survey Report Northwest CaF Storage Area 2
October 1999 l
l
)
TABLE C.4 Unaffected Area Sample Results
~
(Sample Locations at Center of 10m Grids)
T@!W $m)l$$fhiMkiMAYgM3NilmedbytheFSSRih ' %
1 U101 1.30
?
Ull2 0.88 W
U123 9.26 U102 4.80 Ull3 1.99 U124 3.02 g
U103 2.37 U114 6.89 b
U125 22.4 U104 2.06 6
U115 7.41 x
U126 2.91 U105 3.57 T@
Ull6 17.7 U127 3.11 U106 7.18 D
Ull7 3.37 U128 0.31 U107 6.51 b
U118 3.44 U129 2.71 U108 4.69 U119 4.98
+
U130 6.27 U109 6.02 U120 5.47 U131 3.05 U110 4.95 U121 3.18 a
U132 3.03 Ulll 0.83 U122 3.01 U133 3.21 1
H U134 1.04 Total Uranium Mean = 4.79 pCi/g Total Uranium Standard Deviation = 4.45 Total Uranium 95% Confidence Limit (one side, mean) = 6.08 pCi/g
,_sC i n'
'N S84tpkE44m3*pasqg(Ugglbeted Areas? g@ >Na U10 2.71
- 1 U22 4.32 e
U48 2.77 i
Ull 7.96 F
U23 21.9 7
U49 3.68 U12 8.03 Ef(
U24 7.17 U50 4.67 U13 2.98 U25 3.64 U51 3.64 U14 8.63 a
U26 5.09 U52 6.55 U15 4.88 g
U27 5.01 g
U53 2.43
~
U16 9.53 U30 3.16 9
U54 2.26 U17 5.36 Jd
~U31 12.2 en U5!
5.11 U18 7.74 in U35 17.8 U56 7.54 U19 18.1 a
U35A 0.66 U57 10.5 U20 16.4 s
U46 7.75 U58 3.14 U21 4.51 U47 3.69 L
Total Uranium Mcan = 6.91 pCi/g Total Uranium Standard Deviation = 5.00 Total Uranium 95% Confidence Limit (one side, mean) = 8.34 pCi/g U
Nuclear Fuel Services,Inc.
C-23 l
Final Status Survey Report Northwest CaF Storage Area 2
October 1999 f3 C/
TABLE C.5 Soil Pile Overburden Sample Results a 7gwymwt,7.44
. w ' g-- -..
,- aggg
.m%. gu.', 3 a.,
~ in, a, t. L e.AlL, i.A O
p
-Q (.% "n"mngy;p....; P1 ' gy a.t -
g;.yy;;:';p.,g.;.;y;.y c,;.
' "g. A
, qjy;..
.~,pe [yf,.ng g.
y; ;. p_.
....~.,.gs,
.er.
.. ~..
<l.83 N/A 1.83 SP-03 '
<l.75 N/A 1.75 SP-04 12.18 1.27 1.64 i
SP-05 9.65 1.38 1.86 SP-06 7.00 1.16 1.90 SP-07 9.53 1.28 1.79 SP-08 14.54 1.20 1.84 SP-09 13.65 1.90 1.64 Total Uranium Mean = 9.15 pCi/g Total Uranium Standard Deviation = 5.28 Total Uranium 95% CL ( one side, mean) = 12.43 pCi/g Note: Where the sample result was <MDA, one-half the MDA was used in the calculations.
i 1
.,n b
l l
i t'~1 V
Nuclent Fuel Services, Inc.
C-24 k
Final Status Survey Report Northwest CaF Storage Arca 2
October 1999
(].
L Table C.6 Soil Pile Sample Results/ Trapezoid Averages 4g h(Tot 4W y
V
- +
w W
JV@
w nTotala hI f N[z y1lj #P8Ph) y m
k !NN, [ NhPesold{ fSamg$1_el'JUranihhk IMerages pCl/g)d ?(pCl/t),
" MNo.i?% EOIDt%
c(pCi/g)1, 1(pCi/g)1 g5kM 4kJD?O 57 0 96 8.52 Mi 65 U448 10.1 U95 8.88 M
U447 13.7 U94 13.6 7.25 U465 17.4 16.26 U98 22.9 U466 15.1 U99 23.2 U467 25.0 58 U410 15.3 g
66 U421 18.9 U409 4.57 U420 14.4 y
U408 9.12 16.44 h
U438 13.6 14.05 l129 E
U439 16.3 2
U412 22.7 U440 7.05 59 U429 3.78 g
67 U405 6.62 U428 12.7 P
U404 10.9 U427 9.04 10.70 U414 10.3 10.00 U431 3.09 T
U33 10.7 U432 24.9 U415 11.5 60 U456 15.1 s
68 U419 25.1 U455 13.2 U418 23.8
(,)
U454 21.2 12.73 g
E gj 24.42 U458 7.49 f
U441 5.18 U459 6.67 h
U442 12.4 61 U426 8.98 69 U446 10.1 U425 9.69 k
U445 9.73 U433 11.7 12.00 U444 14.3 11.46 U434 8.65
[
U468 13.7 U435 21.0 i
U469 9.49 62 U453 7.72 1
70 U67 7.50 U452 10.1 N
U68 12.6 U460 16.3 13.14 U69 7.45 8.88 U461 18.0 h
U73 8.27 U462 13.6 0 72 8.56 63 U424 15.1 71 U75 18.5 U423 18.1 U76 9.93
'U422 9.50 12.91 U77 4.84 11.60 U436 13.3 s
U81 8.44 U437 8.53 I
U80 16.3 64 l14(l gj 72 U83 5.83 U450 3.97 U84 14.0 U449 16.4 16.75 U85 4.99 8.09 U463 15.0 i
U88 6.33 (m)
U464 12.5 U87 9.31 Nuclear Fuel Senices,Inc.
C-25
Final Status Survey Report Northwest CaF Storage Area 2
1 i
October 1999 Table C.6 Soil Pile Sample Results/frapezoid Averages T
- EB 43 otala. um I f
& g% y
_ ; Totals J,
4 Trapezold iSa$ls) iUraniusai jAerage':
{irrapezoid' iSanifie' (Uranlun4(pC1/g)){'
$peragec j
JNo.9, d@!
1(pCi/g)y
- (pC1/g)k
- ; 4No.? W ' !. ID i (pci/g) K 73 U34 15.5 Misc. Soil U399 9.81 g
U406 8.49 n
Pile U401 0.98 U403AF 28.6 11.8 Samples U403 11.4 U403BF 3.50 (continued)
U406 8.49 U416F 2.69 U407 6.14 74 A489 10.5 U411 4.46 A490 22.7 b
U413 6.07 A491 1.76 10.8 U430 10.2 A493F 11.0 U443 6.70 A494 7.97 U457 1.95 75 A487 8.35 U470 1,05 A488 7.88 I
U471 1.52 7.31 M
g 18.2 4
U472 13.1
)
A496 10.1 U473 15.5 A497 9.99 d
U474 9.45 Misc. Soil U32 14.0 j
U475 8.81 Pile U59 15.3 J
U476 1.13 U477 4.70 Samples U60 8.94 p
U61 11.5 N
U478 1.09 V
U62 1.06 U479 0.92 U64 8.50 U480 3.30 U65 7.65 J
U481 0.51 U66 7.43 E
U482 0.44 U70 8.42 U483 0.56 U.71 10.8 A485 12.7 A486 7.20 U74 3.20 u
U78 6.82 A498 10.9 U79 13.7 A499 6.62 y
U82 13.9
.A500 3.82 U86 6.82 A501 8.82 U89 0.45 A502 9.40 U90 2.47 A503 10.3 U91 19.7 C
A504 17.1 U92 7.09 U93 10.9 e
U97 1.13 R
p Total Uranium Mean (Trapezoids Only) = 13.03 pCi/g Total Uranium Standard Deviation (Trapezoids Only) = 4.05 Total Uranium 95% CL ( one side, mean) (Trapezoids Only) = 14.64 pCi/g n
- 0 - 6" sample depth U
Nudear Fuel Services, Inc.
C-26
Final Status Survey Report Northwest CaF Storage Area 2
October 1999 OV Table C.7 Affected Area Sample Results l
's 3 Md
- > Tota,l. Uranium 34
,m
.s,p 4 Total Uranium, y; iT@ripez:id
,9 Sample?
"(pCi/g);
a m
l Jrapezoidf (Samplet M sw 7(pCFi)? O o
GNo? -
iID/. ;: 6"< - 6 f36"- 0.-. 36" -
" 7Non 9 J+1IDis 0K6"F J-36'!! 0:- 36"' g
- w; m4 wm u,-
u w yy; i a
<s 1
A135 1.15 0.15 1.
9 A171 1.07 A136 14.6 0.49
[f A172 3.89 A137 7.23 0.96 A196 28.5 A166 1.38 A197 24.5 A167 0.79 0.29 A198 4.43 2
A138 4.59 0.75 10 A173 6.92 A139 8.06 1.07 A174 9.43 A163 2.61 I
A175 7.80 A164 1.31 A194 23.4 A165 0.58 A195 15.2 3
A140 3.25 0.87 11 A176 0.91 A141
- 9. ),
1.01 A177 1.99 A142 9.44 0.82 A191 10.4 A161 7.37 A192 5.70 A162 5.31 A193 8.88 4
A143 0.33 0.62 p
12 A178 1.63 A144 0.99 0.76 A179 2,06
)
A158 0.65 A180 1.70 A159 3.22 A189 11.8 4
A160 5.43 A190 14.3 5
A145 1.08 1.74 13 A181 0.79 A146 1.81 0.66 7
A182 0.46 A147 0.71 0.67 S
A186 0.89 A156 0.45 A187 2.09 0.81 E
A188 30.1 A157 6
A148 1.72 0.54 14 A183
.11 A149 0.90 0.54 hii A184 0.71 0.78 0.82 4
A185 0.65 0.68 A153 A154 0.80 A155 0.61 m
7 A150 1.03 0.40 15 A201 3.03 1.00 A151 0.72 0.32 A202 1.05 g
A152 0.89 0.55 5'
A203 5.04 4
A232 4.53 A233 1.05 0.34
~
8 A168 7.38 5.40 E
16 A204 4.26 A169 2.41 A205 9.09
^
0.57 A229 5.39 A170 0.76 f,2_3J
!Q A199
[]
A200 6.53 2.53 A231 3.18 w
Nuclear Fuel Services, Inc.
C-27
Final Status Survey Repot1 Northwest CaF Storage Area 2
October 1999 Table C.7 Affected Area Sample Results q
.,e n,.
3 z: Tot.al Ura.nium.;.
,J y~ n.5,.
sTotal Uranium 9
.w iTrapezoid! { Sample : M5..
1/g)/
Trapezold
!. Sample l(pCi/g))
.M, Mb <
' q, DT,,
es 6"
- 6436't <0 h36",
. t:No.T f ID:-
10,6"',6.36't c 0 - 36'.' -
l i
1 sw g,
3 17 A206 8.20 25 2,
41;3 n-A207
~
3.51 31.4 A208 8.99 g
A257 3.67 A227 12.6 h
A258 22.3 A228 2.06 A259 1.35 18 A209 7.02 26 A310FF 5.07 A210 13.2 A31IFF 10.4 A224 25.9 A312F 4.30 A225 7.05
%322FE
- 83 A226 15.5 A321F 7.52
!A2 ]
]
19 g2.]
27 A247 18.1
- 3...
A212 4.49 A248 12.4 A213 11.6 A252 1.80 A222 9.58 A253 8.46 A223 11.1 A254 19.3 20 A214 14.2 s
28 A249 3.) 1 A215 20.4 A250 1.36 2.10 A219 3.81 A251 3.54 1.67 p
O s;:
^22o 9 24 A221 27.2 3
21 A216 1.14 g
29 A267 10.1 11.9 A217 0.98 1.24 A268 6.94 A218 2.40 0.88
,i A270 5.38 A298 7.01
.r A299 7.85 22 A234 17.4 8.77 30 A269 1.66 A235 7.70 h
A271 3.72 h
A236 6.69 A295 2.27 2.40 A265 7.26 A296 A266 8.17 10.1 A297 3.73 23 A237 50.5 31 A272 10.1 A238 24.6 A273 21.3 A262 12.7 1
A274 15.5 7.02 I
A293 28.O A263 A264 7.20 t
A294 6.06 24 Q
llj 32 A275 5.46 g
6.21 A276 2.34 A240 20.7 8
A290 7.61 A241 A260 14.4 A291 3.26 A261 3.04 A292 5.95 Nuclear Fuel Services,Inc.
C-28
1 Final Status Survey Report Northwest CaF Storage Area 2
October 1999 l
Table C.7 Affected Area Sample Results O
+ v 'or +=
~nt iu i-n r
- i or i -
)wn,
Trapezoid.) ;:Samplei %:
!(pdi/s)C : E Trapezoidj i Sample!
- W f(pCi/g)1 No! ~ _.
- ID2E 0 - 6"
- ;6?36" 0-36" e No."H -
' TIDc '
0 -' 6"- 6-36" 36" -
.stWul l;. " &'
3 s
L M
r ta ua ma.a 33 A308FF 10.3
?
41 A313 2.85 l
A309FF 24.4 A314 7.00 A325FF 13.9 A318 22.1 1
A324FF 15.2 M
A319 25.3 A323FF 8.49 A320 14.5 34 A280 11.3 42 A315 6.23 g
A281 5.84 4
A316 0.90 3.45 A285 12.6 A317 2.23 3.16 l
A286 10.0 A287 6.36 35 A282 15.1 43 A333 21.2 15.5 A281 1.88 6.76 A334 3.54 A284 2.14 2.92 A335 2.35 A364 5.15 A365 4.78 36 A300 7.42 4.60 44 A336 6.44 A301 7.27 A337 6.63 A302 6.68 A361 27.8 O
^332 8.62 i3e2 19.4 A332 11.6 A363 5.93 37 A303 18.2 45 A338 1.90 12.1 x#
A339 12.7 A304 A328 7.53 A340 6.90 A329 4.64 A359 7.84 A330 4.59 A360 8.61 38 M56FE gl j 46 A341 10.9 a
A255FF 10.4 A342 4.61 A244F 17.5 A356 5.98 21.1 A357 6.88 A245F A246F 19.5 A358 6.53 39 A277FF 14.3 47 A343 4
11.6 A278FF 26.1 A344 5.73 A279FF 24.9 A345 9.72 A289FF 4.07 F;
A354 8.68 A288FF 20.8 A355 6.26 40 A305F 5.21 48 A346 4.22 A306F 13.3 A347 4.34 A307FF 18.0 A351 19.9 A327FF 21.8 A352 5.23 W326FE
$5~9 A353 3.86 Nuclear Fuel Services,Inc.
C-29 l
I Final Status Survey Report i
Northwest CaF Storage Area 2
October 1999 Table C.7 Affected Area Sample Results T
' 9 otal Ura,ntum4' 3,3) M
,. 7,,
y JTotal Uranium i-91 4 lTrapezoidi ! Sample;.a - J(pCi/g)1 tTrapezoid' i Samplei L(pCi/g)/
" h Non
'ID T 0-6" l6536"c.0. 36" -
- No/
lID!
0-6":
'6 - 36" - 36" isMa 6. n ;.. b&& Lan ab.,
,hLm b
sg Kna
_ au
.'s j/
a 53 M74 56.8 49 A348 5.43 j
lM 1349 1.54 2.77 A375 10.0 A389 1.19
" 50 2.75 6.72 l
{
A390 0.82 A391 3.40 50 M(j pf.]
3.29 54 A376 5.66 A367 10.3 A377 2.59 A368 5.47 A378 10.7 A397 3.05 A387 4.87 1.02 A398 0.97 A388 3.09 0.84 51 A369 10.3 4
55 M72
@8.50 A370 5.69 4
A380 2.10 A394 7.00 A384 15.3 8.27 A395 4.21 A385 6.79 4.31 A396 1.55 A386 2.99 0.79 52 A371 9.73 q.
56 A381 17.4 A372 9.61 A382 2.64 2.08 M.]
A383 22.7 5.59 A392 2.36 A393 1.36
\\
Nuclear Fuel Services,Inc.
C-30
Final Status Survey Report Northwest CaF Storage Area 2
October 1999 O
Table C.8 Affected Area Sample Averages U
m E
w v
>t 4Totale T-NM<sW '
Nbhlb fh8NE.tk hNh. !;Bk
[-
K.
'e
, sS]s e 1SapplM j%ium[ l Ave'ra@
w Totale -a N
m old FN
%@/4 ' (pCFg)s gjpCFg)I (No.i IDnk
%(pCi/g)9 L:(pCi/g)9 1
A135 1.15*
y 9
A171 1.07 A136 14.6*
}.
A172 3.89 A137 7.23*
5.03 A196 28.5 12.48 A166 1.37 Y
A197 24.5 A167 0.79*
A198 4.43 2
A138 4.59*
10 A173 6.92 A139 8.06*
A174 9.43 A163 2.61 3.43 A175 7.80 12.57 A164 1.31 A194 23.4 A165 0.58 A195 15.3 3
A140 3.25*
1 11 A176 0.91 A141 9.11*
A177 1.99 A142 9.44*
6.90 Y
A191 10.4 5.58 A161 7.37 A192 5.70 A162 5.31 A193 8.88 4
A143 0.62 *
- Sr 12 A178 1.63 A144 0.99*
7 A179 2.06 A158 0.65 2.18 Y
A180 1.70 6.30 A159 3.22 A189 11.8 A160 5.43 A190 14.3 5
A145 1.74**
13 A181 0.79 A146 1.81*
A182 0.46 A147 0.71*
1.10 A186 0.89 6.87 A156 0.45 A187 2.09 4
A157 0.81 h
A188 30.1 6
A148 1.72*
14 A183 0.11 A149 0.90*
F A184 0.78 *
- A153 0.82 0.97 A185 0.68 *
- 0.52 A154 0.80 4
A155 0.61 N
7 A150 1.03*
15 A201 3.03*
A151 0.72*
A202 1.05 A152 0.89*
0.88 A203 5.04 2.94 A232 4.53 a
A233 1.05*
8 A168 7.38*
16 A204 4.26 A169 2.41 A205 9.09 p
A170 0.57 3.53 w
A229 5.39 10.58 A199 0.76 K230
[ff s
p A200 6.53*
A231 3.18 G
Nuclear Fuel Senices,Inc.
C-31
Final Status Survey Report Northwest CaF Storage Area 2
October 1999 Table C.8 Affected Area Sample Averages O
1; a
r e il
.. 4;
- m 11 < i -
h"reamylej
~
a%inni3Verigf Trapezold Samb. ole ).
- Uran.ium;-
fAverageD
~
lU
! Trapezoid d5ESm, MID b a(pg/g)2 1(pCi/g)1 4N6.tw 11Df s
~ (pCilg)@
/(giCi/g) 25 p2 41.3 17 A206 8.20 A207 3.51 d
kN A208 8.99 7.07 A257 3.67 20.00 A227 12.6 A258 22.3 s.
A228 2.06 A259 1.35 18 A'm 7.02 C
26 A310FF 5.07 A21(
13.2 ii A311FF 10.4 A224 25.9 13.73 A312F 4.30 15.12 A225 7.05 K322FE A226 15.5 A321F 7.52 27 A247 18.1 j
19 MJU M
A212 4.49 A248 12.4 A213 11.6 13.87 A252 1.80 12.01 A222 9.58 A253 8.46 A223 11.0 A254 19.3 20 A214 14.2 28 A249 3.11 A215 20.4 A250 2.10*
- A219 3.81 14.97
^
A251 3.54*
2.92 i
g s
A220 9.24
\\
A221 27.2 21 A216 1.14 29 A267 1 1.9 *
- A217 1.24*
- A268 6.94 A218 2.40' l.59 A270 5.38 7.82 A298 7.01 t
A299 7.85 22 A234 17.4*
r 30 A269 1.66 A235 7.70 P
A271 3.72 A236 6.69 9.83 A295 2.27 2.76 A265 7.26 A296 2.40 A266
- 10. l *
- A297 3.73 23 M)]
g 31 A272 10.1 c
A238 24.6 3)
A273 21.3 A262 12.7 20.40 A274 15.5 16.19 A263 7.02 A293 28.0 A264 7.20 W
A294 6.06 24 Mjg W
j.
32 A275 5.46 A240 6.29 A276 2.34 A241 20.7 16.59 A290 7.61 4.92 A260 14.4 A291 3.26 A261 3.04 A292 5.95 f^b Nuclear Fuel Services,Inc.
C-32
Final Status Survey Report Northwest CaF Storage Area 2
October 1999 Table C.8 Affected Area Sample Averages T
A otalp g gf 4 gg ;
. yfy '
gTotal4 7;g 4Z-p.e,
>Trapezoidi eSample?,: Uranium;JAverage Jrapesold
, 3 Sample =
iUraniumj
- Average u
- ONobg, SID i(pg/g)1 g(pC1/g)1
- $No.J JIDi n(pCilg)i d(p,Ci/g)1 y
33 A308FF 10.3 a
41 A313 2.85 A309FF 24.4 I
A314 7.00 A325FF 13.9 14.44 0
A318 22.1 14.35 A324FF 15.2 i
A319 25.3 A323FF 8.49 A320 14.5 34 A280 11.3 42 A315 6.23 A281 5.84 A316 3.45 *
- A285 12.6 9.20 A317 3.17 *
- 4.28 A286 10.0 p
A287 6.36 A
35 A282 15.1 43 A333 21.2 g
A283 6.76* *
'e A334 3.54 A284 2.92 *
- 8.12 l
A335 2.35 7.40 3
A364 5.15 N
A365 4.78 36 A300 7.42*
44 A336 6.44 A301 7.27 A337 6.63 m"
A302 6.68 7.72 A361 27.8 13.24 A331 8.62 g
A362 19.4 v
A332 11.6 A363 5.93 37 A303 18.2 45 A338 1.90 A304 12.1 E
A339 12.7 A328 7.53 9.33 M
A340 6.90 7.58 A329 4.64 E
A359 7.81 A330 4.59 A360 8.61 38 M56FE Sg 46 A341 10.9 A255FF 10.4 A342 4.61 y
A244F 17.5 23.70 J
A356 5.98 6.98 A245F 21.1 A357 6.88 A246F 19.5 A358 6.53 39 A277FF 14.3 47 A343 11.6 A278FF 26.1 E
A344 5.73 A279FF 24.9 18.21 A345 9.72 8.40 A289FF 4.07 h
A354 8.68 A288FF 20.8 A355 6.26 40 A305F 5.21 g
48 A346 4.22 A306F 13.3 A347 4.34 A307FF 18.0 18.90 c
A351 19.9 7.51 A327FF 21.8 A352 5.23
$323FE SQ A353 3.86
^
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C-33
Final Status Survey Report Northwest CaF Storage Area 2
October 1999 l
Table C.8 Affected Area Sample Averages
)
, a g.i 1,
w Totalf,
' i
, eTotalc s
l iTrag!dj [Sa$ple; (Urantami { Average; $ lTrM*dl Sanipisl
- Urlaning; Average!
t EN C l WIDE L(pC#g)1 (pCi/gP h
,1Noh
?ID(
j(pCi/g) 4
- (pCi/g)1 49 A348 5.43 53 A37f
[6J A349 2.77*
- A375 10.0 A350 6.72*
- 4.97 A389 1.19 14.44 A390 0.82 A391 3.40 50 A366
@J{jj 54 A376 5.66 A367 10.3 A377 2.59 A368 5.47 10.32 A378 10.7 5.38 i
A397 3.05 A387 4.87*
A398 0.97 A388 3.09*
51 A369 10.3 55 M))
}_84 A370 5.69 4
A380 2.10 A394 7.00 5.75 A384 15.3*
13.14 A395 4.21 1
A385 6.79*
A396 1.55 A386 2.99*
52 A371 9.73 4
56 A381 17.4 A372 9.61 A382 2.64*
Q7J
[Q 12.13 A383 22.7*
12.67 o
A392 2.36 t
L.)
A393 1.36 E
Total Uranium Mean = 10.1 pCi/g Total Uranium Standard Deviation = 5.47 Total Uranium 95% Confidence Limit ( one side, mean) = 11.43 pCi/g Note: Only the averages from the trapezoids containing 5 sampling points were used to estimate the mean, standard deviation and 95% Upper Confidence Limit.
- 0 - 6" sample depth
- 6 - 36" sample depth All Other samples collected at 0 - 36" Nuclear Fuel Services,Inc.
C-34
(9) ESEARCH TRIANGLE INSTITUTE c
RTI Report No. 6448-018/007/01F October 12,1999 Report of Final Status Survey Groundwater Sampling and Analysis Activities -
Former Northwest CaF Storage Area 2
General Electric - Wilmington, NC o()
Prepared for:
General Electric Company Wilmington, North Carolina Prepared by:
Jeff W. Reynolds, P.G., P.HG.
Michael I. Lowry O
V Geosciences Department Center for Environmental Measurements and Quality Assurance 3040 Cornwallis Road. Post Office Box 12194. Resea cn Err .r-Narn Carohna 27709-2194 USA
'4%
i
.O aTi aenort wo. e448-o'8'oo7/o's October 12,1999 Report of Final Status Survey Groundwater Sampling and Analysis Activities -
Former Northwest CaF Storage Area 2
j General Electric - Wilmington, NC Research Triangle Institute Geosciences Department q
PO Box 12194 kJ Research Triangle Park, NC 27709 (919)S41-8758 Reviewed by:
4 Andrew D. Stahl, P.G., C.P.G.
Jeff W. Reynolds, P.G., P.HG.
Hydrogeologist Project Hydrogeologist and Manager, Hydrogeologic Assessments Program Hydrogeologic Assessments Program Licensed NC Geologist No.1650 Licensed NC Geologist No.1075 AIPG Professional Geologist No. 9070 AlH Professional Hydrogeologist No.1467
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1 Final Status Survey Groundwater Sampling and \\nalysis October 12,1999 Table of Contents 1.0 Introduction 1
2.0 S ample Location s.............................................
1 3.0 Sampling and Analysis Methods................................
- 3.1 Sampling Methods.........................................
1 3.2 Sample Analysis...........................................
1 l
3 i
l
- 4. 0 Re s u lt s...........................................
l 3
5.0 Quality Assurance / Quality Control....................................
4 5.1 Laboratory Quality Assurance........................
5.2 Field Quality-Control Activities.................................
4 l
l 5.3 Quality-Control Data Review..............................
4 -
i 4
l
, 6.0 G roundwater Flow...............................................
5
-. 7. 0 D i scu s s io n.....................................................
6 l
l List of Figures i
1.
Monitoring Well Location Map
' 2.
Total Uranium in Groundwater - Filtered Samples - January 1999 3.
Total Uranium in Groundwater - Unfiltered Samples - January 1999 List of Tables t
i 1.
' Well Construction Data - CAF-Series Monitoring Wells
. 2.
Summary of Analytical Results - Final Survey Groundwater Sampling Attachments i
1 A.
.Teledyne Brown Engineering Isotopic Uranium Analytical Data Report i
S.
GroundwaterVelocity Calculations in the Vicinity of the Former NW-CaF Storage I
2 Area - GE-Wilmington
-[-q,'j '
1 GY448-018. Survey _ Release \\Surv&Rel. GW(Finaf).wpd
/RTI i
I
[
1-
{,
Final Status Survey Groundwater Sampling and Analysis October 12,1999 l.
1.0 Introduction This document presents the results of the final status survey sampling of groundwater in the former northwest calcium fluoride (NW-CaF ) storage area of the General Electric (GE) 2
-Wilmington, North Carolina, site. Information on the sampling locations and procedures, analytical method,' quality-control (QC) measures, and groundwater-flow characterization are also provided in this document.
2.0 Sample Locations For the final status survey sampling event, groundwater samples were collected from the
[
17 CAF-series monitoring wells located on the GE-Wilmington property in the vicinity of
\\
, the former NW-CaF storage area. Figure 1 shows the locations of these CAF-series 2
wells. Construction data for the wells, including land-surface and measuring-point elevation data; are provided in Table 1. Elevation data were proviJed by North Carolina Registered Land Surveyors employed by CENTURY /vonOesen, Inc, of Wilmington, North -
Carolina.
1 '
3.0 Sampling and Analysis Methods 3.1 Sampling Methods Final status survey groundwater sampling was performed in January 1999 in accordance with Revision 02 of the Final Status Survey and Release Plan (FSSRP) for the former l
. NW-CaF Storage Area (February 28,1996), prepared by Nuclear Fuel Services (NFS).
2
. Groundwater sampling was performed by Research Triangle Institute (RTI) staff familiar with groundwater sampling procedures at the GE-Wilmington site. The sampling was performed in general accordance with EPA Region IV Environmental Investigations Standard Operating Procedures and Quality Assurance Manual (May 1996). Samples
).
GM448-018\\ Survey _ Release \\Surv&Rel GW(Final)wpd
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l l
l' l)
Final Status Survey Groundwater Sampling and Analysts October 12,1999 were collected using dedicated pneumatic bladder pumps that have been installed in each well. A summary description of the sampling method is provided below.
Prior to sampling each well, the static water level was measured to the nearest 0.01 foct After the purge volume was calculated, the air source to the pump was attached and the well was purged of standing water. Purge water was containerized in 55-gallon steel drums for later testing and appropriate disposal. For monitoring wells with screens placed across orjust below the water table, the bladder-pump intake was set in the lower portion of the well screen. The purge volume was three times the volui,7 of the water column standing in the well. For monitoring wells with screens submerged beneath the static water level, the bladder-pump intake was set approximately 1 foot below the top of the weli screen. The purge volume for these wells was three times the volume of water in the screened section of the well. For these wells, the purge rats is reduced to minimize the total drawdown in the well (<1.5 feet) so that standing water from above the screen is not introduced into the screened interval.
pG
' Due to the geologic conditions in the area, groundwater samples collected from the CAF-series wells occasionally exhibit elevated turbidity. In accordance with EPA procedures, a low-flow / low-stress sampling procedure was used to collect the samples to minimize the turbidity. Groundwater parameters (e.g., specific conductance, pH, dissolved oxygen, oxidation-reduction potential [ORP], and temperature) were measured before each groundwater sample was collected.
After the requisite purging was completed, both unfiltered and filtered groundwater samples were collected for laboratory analysis. Filtered samples were collected by
' attaching an in-line,0.45-m pore-size filter capsule to the discharge line. After the samples were collected, nitric acid preservative was added to lower the sample pH to j
below 2 pH units.
1 The samples were prepared (each bottle sealed and individually wrapped) and shipped to the analytical laboratory in a secure cooler. A completed chain-of-custody form accompanied the samples to document the sample number, collection date and time, container and preservative used, and requested analyses. The form also documented I.
l G:T>448 018\\ Survey _ Release \\Surv&Ref - GW(Rnal).wpd
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I l
l l-l Final Status Survey Groundwater Sampling and Analysis October 12,1999 sample custody and the transfer of the samples from the originator to the analytical laboratory.
l 3.2 Sample Analysis The samples were analyzed by Teledyne Brown Engineering and Environmental Services (Teledyne) in Westbrook, New Jersey. Both the filtered and unfiltered samples were l
analyzed for isotopic uranium using Teledyne's procedure No. PRO-062-110, l
Determination of Uranium by Alpha Spectroscopy. Results were reported for nach isotope
' in picocuries per liter (pCi/L).
4.0 Results l
Table 2 summarizes the results of the final status survey groundwater sampling. Results for the uranium isotopes (2 "U,23sU,23eU) were summed to give the total uranium activity
]
(in pCi/L). Figures 2 and 3 show the distribution of total uranium in filtered and unfiltered
/
, groundwater samples, respectively.
Teledyne's report of analysis is provided as
. Attachment A.
Total uranium activities for unfiltered groundwater samples ranged from below minimum detectable activity (MDA) of 0.2 pCi/L to 157.7 pCi/L. Mean and median activities for unfiltered groundwater samples were 15.3 and 2.16 pCi/L, respectively'. Total uranium l
activities for filtered groundwater samples ranged from below MDA to 145.7 pCi/L. Mean and median activities for filtered groundwater samples were 12.5 and 0.7 pCi/L, respectively. Uranium activities'were below US Environmental Protection Agency's
' (EPA's) proposed drinking-water maximum contaminant level (MCL) of 30 pCi/L, except the samples from CAF-6A and CAF-7A. These two monitoring wells are directly i
downgradient of the former NW-CaF storage area and on GE property. Groundwater from 2
the next downgradient well (CAF-12A), also on GE property, exhibited a uranium activity below the proposed MCL, as did the deeper monitoring points adjacent to CAF-6A and CAF-7A-(CAF-6B and CAF-7B). These monitoring data indicate that the impacts are
' For samples with activitias below the minimum detectable activity (MDA), one-half of the MDA
/~N
~b (0.1 pCl/L) was used as the sample result to calculate mean and median activities.
j GY>448-0181 Survey Release \\surv&Rel.GW(Final).wpd I
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N l
F
]
(]
Final Status Survey Groundwater Sampling and Analysis October 12,1999 limited to the shallow groundwater in the immediate vicinity of the former NW-CaF storage 2
area.
5.0 Quality AssurancelQuality Control 5.1 Laboratory Quality Assurance Teledyne performs the analysis in accordance with a Quality Assurance Manual (Document no. lWL-0032-395, Rev. O, March 7,1997) developed for their Environmental Analysis Department. This manual establishes the criteria for quality sssurance applied to analytical measurement of radioactive materials as specified in 10 CFR 50, Appendix B and the Nuclear Regulatory Commission'(NRC) Regulatory Guide 4.15 (Quality Assurance for Radiological Monitoring Programs).
Expanded quality-assurance (QA) data were requested for the final status survey samples.
t)
Teledyne provided copies of data sheets, matrix-spike sample results, and instrument calibration data. Results of RTI's review of Teledyne's expanded QA data are described in Section 5.3.
5.2 Field Quality-Control Activities Duplicate groundwater samples (both filtered and unfiltered) were collected from two of the l
CAF-series monitoring wells and submitted as blind QC samples to evaluate laboratory precision. In addition, two ambient field blanks were collected during the sampling activities to evaluate potential biases due to atmospheric or other sampling conditions.
Additional samples were collected from well CAF-8A for Teledyne to use as a matrix for spiking.
5.3 Quality-Control Data Review All analyses were performed as requested within the 180-day technical holding time.
j Control charts for calibration data from September 1,1998, to February 16,1999, were
{
provided. Calibration data were within the control limits for all of the detectors during the j
time frame of the analyses.
i i
b G:'6448-018\\ Survey _ Release \\Surv&Rel. GW(Final).wpd 3
Page 4 j
m s
f h
Final Status Survey Groundwater Sampling and Analysis October 12,1999
! Uranium was not detected in either of the field blanks submitted. Matrix-spike analyses L were provided for "U and 23sU. jThe recoveries for234U were 126 percent (unfiltered) and 2
- fdB percent (filtered).: Relative percent differences'for total uranium in the field duplicate sampiss ranged from 9.2 to 34 percent. Although data-quality objectives (with respect to precis;on and_ accuracy). were not. established for groundwater in.the FSSRP, the grounc. water data are~ considered to be representative indicators of groundwater quality
~
at the time of sample col'ection, l
5 6.0. Groundwater Flow The former NW-CaF storage area is positioned on the eastern flank of a relic sand done 2
that forms a topographically prominent sandy peninsula that is surrounded on three sides by low-lying swampy areas. In the study area, the subsurface is composed primarily of
- undifferentiated sands down to approximately 30 feet. There are no continuous and extensive clay layers or distinct confining units in the immediate vicinity of the former NW-i
, ' CaF storage areat A rocky zone is present below this layer, indicating a transition to the 2
~
,. Peedee Formation. This formation consists of a mixture of semi-consolidated sandstone
-and unconsolidated, glauconitic, fine, silty sand.
Groundwater in the area of the former NW-CaF storage ~ area flows toward the north, 2
discharging offsite into a swampy area located approximately 700 feet north of the former NW-CaF storage area! ' Groundwater velocity for the area was calculated along the 3 '
2
' L transeciextending from the former NW-CaF storage area nodh-northeast to the swampy 2
l area based on the equation:
v = Kiln where:
- v. = line' r groundwater; velocity (ft/d);
a K = hydraulic conductivity'(ft/d);-
"i = hydraulic gradient (unitiess); and =
n =; effective porosity (percent)..
I
. in Exhibit A-8 of the FSSRP, the average linear groundwater velocity in the vicinity of the former NW-CaF storage area was reported as approximately 0.31 feet / day (ft/d), based 2
}
- G:5448 018\\ Survey _Reissee\\Surv&Rei GW(Final).wpd -
Page 5
Final Status Survey Groundwater Sampling and Analysis October 12,1999 on the following values for the above equation: K = 25.5 ft/d, i = 0.005, and n = 41 percent.
For this calculation, the hydraulic conductivity values were obtained from historical results of slug tests and short-term pumping tests performed in wells located southeast of the fcirmer NW-CaF storage area and from laboratory grain-size analyses. Porosity (reported 2
as total porosity) was based on an empirical calculation using a single bulk density measurement from a sample collected from the central GE site.
Revised average linear groundwater velocity estimates for the area were reported in 199P
- and 1999 and included more recent hydraulic data from wells closer to the former Fw CaF storage area. Based on these subsequent tests, the hydraulic conductivity estimuu s 2
calculated for the area range approximately over one order of magnitude between 0.4 and S.7 ft/d, the minimum and maximum estimates for the slug tests conducted in the former NW-CaF storage area, respectively. Using the highest directly measured (i.e., excluding 2
grain-size analyses) hydraulic conductivity value (6.7 ft/d,), a hydraulic gradient of 0.005, and a porosity of 30 percent (typical of silty fine to niedium sand and a better q
representation of the effective porosity of the aquifer), a conservative estimate of the 2
D, average linear groundwater velocity in the vicinity of the former NW-CaF storage are 2
' L on the order of 0.1 to 0.15 ft/d. Additional discussion of hydraulic testing activities and calculation of groundwater velocity in the vicinity of the former NW-CaF storage area are 2
provided in Attachment B.
7.0 Discussion In accordance with the Classifications and Water Quality Standards Applicable to the Groundwaters of North Carolina (North Carolina Administrative Code Title 15A, i
Subchapter 2L), RTI prepared a Comprehensive Site Assessment (CSA) report
- summarizing the assessment and monitoring ~ activities for groundwater in the former NW-CaF storage area (Comprehensive Site Assessment (CSA) Report for the Northwest Site 2
Area, RTI Report No. 6448-018/012/003/01F, December 11, 1998). The CSA was 2
The effective porosity (instead of total porosity) should be used to calculate average linear groundwater velocity. Effective porosity takes into consideration non-interconnecting (dead-end) spaces f'i in the aquifer and is consequently typically less than total porosity.
G:E448-018\\ Survey _, Release \\Surv&Rei GW(Final).wpd
/RTI Page 6
)
fl Final Status Survey Groundwater Sampling and Analysis J
October 12,1999 reviewed and approved by the North Carolina Department of Environment and Natural Resources'(DENR), Division of Water' Quality and Division of Radiation Protection. In I
' addition, a monitored natural-attenuation corrective action plan (CAP) was prepared by RTI to address the localized groundwater impacts in the area and submitted to DENR (Corrective Action Plan (CAP) for the Northwest Site Area, RTI Report No. 6448-018/004/01F, April 27,1999). Development of the CAP involved data collection and.
analysis, including delineation of the horizontal and vertical extent of non-natural uranium
'in groundwater, and evaluation of fate and transport of the constituents of concern. In addition, the potential risks associated with the groundwater impacts on human and ecological receptors were evaluated.
To summarize, the evaluation activities described in the CAP indicated that there are no j
human drinking-water receptors downgradient of the former source area, and future j
development of the area is not expected. The groundwater contamination will continue to attenuate via natural processes'and is not predicted to pose significant human or ecological risks currently or in the future. The adjacent property owner has been notified V, of the groundwater impacts and of the monitored natural-attenuation corrective action.
Evaluation of existing geochemical and hydrogeologic data and the results of fate and i
~
transport medeling of the groundwater contamination indicate that monitored natural 4
attenuation is the appropriate corrective action for this area. Consistent with the recomme ndations in the CAP and the verbal approval of the CAP monitoring plan by DENR, routine monitoring of groundwater quality in the area is underway and will continue.
Periodic updates of groundwater sampling and analysis activities will be provided to 1
DENR.
l G Y>448418\\ Survey _ Release \\Surv&Rel - GW(FiriaQ.wpd
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Table 2. Final Survey and Release Groundwater Sampling Results i
Groundwater Uranium Results (pCl/L)
{
fellID Date Sampled Elevation
)
i Filtration 2
228 U st22' U'"
U Total (ft MSL)
Unfiltered
<0.2
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<0.2 1.9 4.3 Unfiltered 120 4.7 33 157.7 CAF-6A 1/12/99 17.27 Filtered 110 3.7 32 145.7 CAF-6A Unfiltered 100 3.4 30 133.4 1/12/99 Duplicate Filtered 100 3.9 29 132.9
(
Unfiltered 8.5 0.42 5
13.9 CAF-6B 1/12/99 17.23 Filtered 2
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<0.3 2
4.4 CAF-7B 1/14/99 16.79 Filtered 1.8
<0.2 1.2 3
l Unfiltered 0.35
<0.1 0.27 0.6 CAF-8A 1/14/99 17.11 Filtered 0.26
<0.2
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< 0. 3 0.35 0.7 l
~ CAF-8B Unfiltered 1.1
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<0.2 1.2 3.3 "AF-9A 1/15/99 16.76 Filtered 0.36
< 0.1
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< 0.1 1.2 2.6 CAP-98 1/15/99 16.64 Filtered 0.66
<0.1 0.74 1.4 UnMered 0.94
<0.1 0.32 1.3 CAF-10A 1/14/99 17.35 Filtered 1
<0.1 0.66 1.7 n ered
<0.2 42
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<0.1
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<0.2
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<0.3
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< 0.1 41
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<0.2
<0.2
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<0.3
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<0.2
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<0.3
<0.2
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<0.2
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< 0.1 BMDA BMDA - Indicates total uranium activities were below isotopic minimum detectable activities shown.
I Summary of Total Uranium Analyses (pCi/L)
Unfiltered Filtered n
Minimum 0.1 Minimum 0.1
()
Maximum 157.7 Maximum 145.7 Average 15.3 Average 12.5 Median 2.2 Median 0.7 Standard Standard Deviation 37.6 Deviation 35.0 l
Not7 One-half of the largest isotopic MDA was used to calculate mean, median, and standard deviation.
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O ocioeer,2.1999 Attachment B Groundwater Velocity Calculations in the Vicinity of the Former NW-CaF Storage Area 2 GE-Wilmington Background Information Estimations of groundwater velocity in the northwest GE site area developed by the Research Triangle Institute (RTI) have been reported in the following three documents:
- 1. Final Status Survey andRelease Plan (FSSRP) prepared by Nuclear Fuels Services (NFS) (Rev. 02, dated February 28,1996),
- 2. Comprehensive Site Assessment (CSA) Report forthe Northwest Site Area prepared by RTI (Report No. 6448-018/012/003/01F dated December 11,1998), and
- 3. Corrective Action Plan (CAP) for the Northwest Site Area prepared by RTI (Report No. 6Ai8-018/004/01F dated April 27,1999),
r3 V Based on the most recent data, the average linear groundwater velocity in the northwest site area has been revised from the 0.31 foot / day (ft/d) estimate provided in the FSSRP to approximately 0.1 to 0.15 ft/d. Descriptions of how the groundwater velocity estimations were calculated in these three documents are presented in the following sections. Groundwater Velocity Average linear groundwater velocity is calculated based on the following equation: 1 v = Ki/n where: l v = linear groundwater velocity (ft/d); K = hydraulic conductivity (ft/d); 3 i = hydraulic gradient (unitiess); and ' n = effective porosity (percent). v(D \\ /RTI Attachment B - Page 1 of 7
p ' Attachment B - Groundwater Velocity Estimates October 12,1999 ' Calculation of: the hydraulic: gradient is fairly straightforward. The difference in f groundwater elevation is divided by the horizontal distance between two wells aligned approximately parallel to 'the groundwater flow direction. Default values are typically used ifor effective porosity, depending on the predominant grain size of the' aquifer media. The variability of these two components of the equation is fairly limited. Values for aquifer K, however, are much mo're variable (over several orders of magnitude), and there are- ~ numerous; methods by which K can be, calculated. Technical details pertaining to l development of the K values reported in these documents are described in the following se'ctions.: Final Status Survey and Release Plan (FSSRP) The initial estimate of groundwater velocity in the vicinity of the former NW-CaF storage 2 area was provided in Exhibit A-8 of the FSSRP In that document, the average linear ' groundwater velocity in the vicinity of the former.NW-CaF storage area was reported as 2 approximately 0.31 feet / day (ft/d), based on the following values for the equation above: h K = 25.5 ft/d, i = 0.005, and n =_41 percent. For this calculation, the K value selected was obtained from historical results of slug tests and short-term pumping tests performed by + ~other' consultants in wells located southeast of the former NW-CaF storage area. This 2 -value f was' similar to the valuesi calculated from laboratory grain-size analyses (approximately 26 ft/d) performed for this project. The, porosity' component of the groundwater velocity equation was reported as total porosity and was based on.an empirical calculation using a single bulk density measurement from a sample collected from the central GE site as shown below: .n = 1 - p,/p, Jwhere:' .n = porosity; ' p3 = soil bulk density (g/cm ) [mean of 1.56 g/cm'] p, = particle density (g/cm') (assumed to be 2.65 g/cm', typical of quartz) a Af g Attachment B - Page 2 of 7
) l QQ Attachment B - Grcundwater Velocity Estimates October 12,1999 The bulk density was measured for a sand sample collected from the central region of the t GE site (similar to the soils encountered in the northwest site area) using the American Society for Testing and Materials (ASTM) Method D2937-94 Standard Test Method for Density of Soilin Place by the Drive Cylinder Method. Comprehensive Site Assessment (CSA) An estimated linear groundwater velocity of 0.15 ftIday was reported in the CSA based on a K value calculated using three different methods: instantaneous response (slug) testing, . regional water balance calculations, and approximation from grain-size analyses. The l t representative K value used to estimate the average linear velocity based on the three methods is shown below: l l Method Representative K Geometric mean of l (ft/ day) selected K values l q Slug testing 5.47 (maximum) U Grain size analysis 26.6 (geometric mean) g l Regional water balance 5 (75% of calculated value) In addition, an effective porosity of 30 percent (typical of silty fine to medium sand and a better representation of the effective porosity of the aquifer) was used. The slug testing and water-balance K calculations are described below. Slug Tecting Two rounds of slug tests were performed on seven CAF-B series monitoring wells on l March 5 and 11,1996. The CAF-B series wells were selected in that they are all screened l completely below the water table and are spatially distributed around the former NW-CaF 2 storage area. Prior to beginning the slug testing, dedicated sampling pumps were removed and stored in clean polyethylene bags, and the water levels in the wells were allowed to equilibrate for several days. An InSitu pressure transducer and Hermit 1000 data logger wer < " sed to monitor water level changes atter insertion of a decontaminated solid plastic slu, a displace the water in the well (' slug in'). Logarithmic readings were -n d' y Attachment B-Page 3 of 7
r 1 1 ) Attachment B - Groundwater Velocity Estimates October 12,1999 collected by the data logger until the water level stabilized to approximately static conditions. The data logger was reset, and water level measurements were collected after removal of the slug (' slug out'). Dedicated sampling equipment was replaced after testing. Water level measurements were downloaded and two solution methods, both designed for analysis of slug tests in unconfined aquifers, were used to calculate K for the upper portion of the aquifer: rahods developed by Hvorslev (1951) and Bouwer and Rice (1976). Both of these methods assume a homogeneous isotropic aquifer, radial flow to the well, no drawdown in the water table, and no frictional losses. The Bouwer and Rice method, however, takes more detailed account of the flow geometry and as a result yields lower K values. The K values resulting from the analysis of the initial slug tests are provided on Table B-1. K values ranged from 0.41 to 5.47 ft/d, with higher estimates from the Hvorslev analytical method. There were no significant differences between the ' slug in' and ' slug out' phases of the testing, nor between the tests run on different days. The geometric means of K for the Hvorslev and Bouwer and Rice methods were 1.61 and 1.02 ft/ day, respectively. ([) However, considering the scale of the slug-test evaluation method, the maximum K value ' of 5.47 ft/ day was selected for comparison to other evaluation methods. Grain-Size Analysis A 9 emirical method was developed by Hazen (18D2) to estimate K based on grain-size analyses. With this method, an effective grain size is squared and multiplied by a factor dependent on the uniformity of the sediment. The equation used to make this approximation is: K = Ad o i where: K = hydraulic conductivity (in cm/sec); A = Hazen's coefficient (1 = uniformly graded sands, fine to coarse); and d o= diameter at which 10 percent of the soil particles are finer by weig tmm). i /RTI Attachment B - Page 4 of 7
r I Attachment B - Groundwater Velocity Estimates October 12,1999 Measurements of the d value for three soil samples collected from approximately 20 to w 30 feet below land surface in borings CB-1, CB-2, and CB-4 are 0.085 mm, 0.085 mm, and 0.12 mm, respectively. Using a Hazen's approximatie of 1, these grain sizes correspond . to K values of 7.2e-3, 7.2e-3, and 1.4 e-2 cNnte TL geometric mean of these ( measurements is 9.4e-3 cm/sec, or 26.6 ft/d. Regional Water-Balance Method l t With the regional water balance method, K was estimated based on the recharge between two constant head boundaries (i.e., the swampy area surrouniing the peninsular relic sand i dune on which the former NW-CaF storage area is loca'.ed) similar to the method for 2 calculating K between two parallel canals as described by Ferris, et al. (1962). However, because the peninsula is bounded on three of four sides instead of just two, the solution based on this method may be overestimated. Based on the equation: 1 2 Kb = N x /2h O
- nere:
K = hydraulic conductivity (ft/ day); N = area recharge rate (used 3.42e-3 ft/d; based on 30% of 50 in/yr); x = distance from divide to constant head boundaries ('s,500 feet); b = thickness of saturated zone (used 40 feet); and ~' $eight of water table mounding (5.1 feet); the caiculated K for the peninsular geometry is on the order of 6.4 ft/ day (2.3e-3 cm/sec). Considering that this rnethod may overestimate the K as a result of the peninsular orientation, the effective thickness of the saturated zone may be greater than 40 feet, and i there is some uncertainty in the actual recharge to the aquifer; a reasonable estimate of average K for the peninsular region is probably on the order of about 5 ft/d. Corrective Action Plan Additional slug testing was performod in January of 1999 to evaluate the hydraulic characteristics of the deeper, semi-consolidated sandstone and to evaluate conditions in 2n Attachment B - Page 5 of 7
r-Attachment B - Groundwater Velocity Estimates October 12,1999 a larger area of the northwest site area. The additional hydraulic testing indicated slightly lower permeability estimations than those described in the CSA; therefore, the average linear groundwater velocity is expected to be only slighily lower than that presented in the CSA. Based on the cumulative K estimates for the area, the average linear groundwater velocity was reported in the CGA to be on the order of 0.1 to 0.15 ft/d. f Pneumatic Slug Tests The additional slug tests were performed using a pneumatic displacement method rather than displacement with a solid slug. With the pneumatic method, the water level in a well i is depressed by pressurizing the well casing with an inert gas (nitrogen was used for the testing described herein). The pneumatic slug 2est typically provides superior data quality relative to the typical displacement methods as it avoids problems such as:
- Insufficient and uncontrolled displaceme' ' of water,
- Non-instantaneous slug removal, and 4
> Interference with the pressure transducer cable. L) After measuring the static water level in the well, an air-tight wellhead fitting is attached to top of the well casing. This wellhead fitting contains a pressure gauge, gas injection port, a sealed pressure transducer inlet, and a large (2-inch) ball valve for instantaneously releasing the pressure at the start of the slug test. The pressure transducer is lowered into the well casing below the anticipated displacement water level, connected to a data logger, referenced to zero, and programmed for data collection. After ensuring that the ball valve 4 is closed, the well is pressurized to lower the water to the desired level (as measured on the pressure gauge reading inches of water pressure). The pre' mure is adjusted to the desired level (typically approximately 100 inches of water pressure), ensuring that the water level is not pushed below the top of the screened interval of the well. Prior to initiating the actual slug test, the water level measured by the data logger is allowed to re-equilibrate to zero. After the water level stabilizes, the slug test is started by instantaneously releasing the pressure from the casing by opening the ball valve. The data logger is started a fraction of time prior to depressurization, so that all early-time data are collected. The compressed air supply is then turned off, and data logging continues until the water level is near the initial, static condition. After testing, the transdent cable is removed and decontaminated (as necessary) and the weli is resecured. The data were /RTI Attachment B - Page 6 of 7
r j Attachment B - Groundwater Velocity Estimates October 12,1999 downloaded from the data logger onto a laptop PC and were plotted using Microsoft Excel. For the unconfined aquifer in the northwest site area, the Bouwer and Rice (1976) and the Hvorslev (1951) analysis methods were used to obtain K estimates. Results from the additional slug testing activities were remarkably similar to earlier results (Table B-2). The minimum and maximum K values for the additional testing were 0.82 and 6.7 ft/d, respectively. The geometric mean K values for the Hvorslev and Bouwer-Rice analysis methods were 2.4 and 2.0 ft/d, respectively. In the deeper zones, the geometric mean K values were 1.05 and 0.96 ft/d for the Hvorslev and Bouwer-Rice methods, respectively. The maximum K value of 6.7 ft/ day was sele 'd for comparison to other evaluation methods. References i Bouwer, H. and R.C. Rice.1976. A slug test for determining hydraulic conductivity of 1 unconfined aquifers with completely or partially penetrating wells. US Water [.] Conservation Laboratory. Phoenix AZ. Ferris, J.G., D.B. Knowles, R.H. Brown, and R.W. Stallman.1962. Theory of Aquifer Tests. USGS Water-Supply Paper 1536-E. ( Hazen, A.1892. Some physical properties of sands and gravels. Mass. State Board of Health. Annual Report. l Hvorslev, M.J.1951. Time Lag and Soil Permeability in Ground-Water Observations. Bulletin 36. US Army Corps of Engineers ,m / i /RTI Attachment B - Page 7 of 7
4 nV Table B-1. Summary of Slug-Test Analyses Reported in Comprehensive Site Assessment Slug Test 1 3/5/96 Slug Test 5 3/11/96 - Summary of K (ft/ day) Wells CAF 58-11B Grouped Together Hvorslev - Bouwer-Rice Test i Test 2 Test i Test 2 Slug in Slug Out Slug in Slug Out Slug in Slug Out Slug in Slug Out Mean 1.88 1,66 2.01 2.18 1.19 1.07 1.32 1.45 Geomean 1.61 1.38 1.73 1.74 1.00 0.86 1.12 1.13 Minimum 0.91 0.66 0.91 0.82 0.58 0.41 0.58 0.52 Maximum 4.10 4.10 '4.10 5.47 2.59 2.59 2.59 3.45 ^ AII Slug Tests Grouped Together K(ft/ day) Hvorslev Bouwer-Rice Mean 1.93 1.26 . O Geomean 1.61 1.02 Minimum 0.66 0.41 Maximum ' 5.47 3.45 Data r= 0.0833 Radius of Well Casing (ft)- = L= 10 = Length of screened interval (ft) R= 0.375 Radius of Borehole (ft) = H= ~ 20- = Estimated distance from water table to bottom of screen (ft) D= 40 Estimated saturated aquifer thickness (ft) = Lag Time (Time to 37% ofinitialhead change - minutes) Test 1 Test 2 Well Slug in l Slug Out Slug in l Slug Out CAF-5B 1.6 2.5 1.7 1.9 CAF-6B 1.8 2.1 1.8 - - 2.0 CAF-7B. 1.8 1.8 1.3 1.3 CAF-8B ' O.4 0.4 0.4 0.3 CAF-98 1.0 1.0 0.8 - 0.8 CAF-108 0.6 0.8 0.5 0.5 CAF-11B 0.9 1.1 1.1 1.1 0 Page 1 of 2
Tabie' B-1. Summary of Slug-Test Analy;ss R3 ported in Comprehensive Site Assessment (continued) ~ H l F l ti O~ vors ev ormu a on ~ ~ ~ ~ ~ K = (r^2)ln(UR)/2LTo K= calculated. Hydraulic Conductivity (ft/ day) = r= 0.0833 = ' Radius of Well Casing (ft) L=- 10 = Length of screenedinterval(ft) R= 0.375 Radius of Borehole (ft) = To = measured = Lag Time (Time to 37% of initial head change - minutes) 1440 (ft/ min) to (ft/ day) = K (ft/ day) - Calculated with Hvorslev Test 1 Test 2 Well Slug in Slug Out Slug in Slug Out CAF-5B 1.03 0.66 0.96 0.86-CAF-6B 0.91 0.78 0.91 0.82 ' CAF-78 0.91-0.91 1.26 1.26 CAF-8B. '4.10 4.10 4.10 5.47 CAF-98 1.64 1.64 2.05-2.05 CAF-10B 2.73' 2.05 3.28 3.28 CAF-11B 1.82 1A9 1.49 1.49 Lauwer and Rice Formulation K = r^2 In(Re/R)/2LTo r=' O.0833 Radius of WellCasing (ft) = L= 10 Length of screened interval (ft) = R= 0.375 Radius of Borehole (ft) = -Re= 2.983057 Effective pumping radius (ft) = To = measured Time to 37% of initial head change (min) = where: Re = R{exp[(1.1/in(H/R)) + (A+B(In[(D-H)/R]))/(UR))^-1} H= Distance from water table to bottom of screen (ft) = 20 A= dimensionless coefficient = 2.5 B ~= dimensionless coefficient = 0.75 D= saturated aquifer thickness (ft) = 40 K (ft/ day) ' Calculated with Bouwer-Rice Test i Test 2 Well Slug in Slug Out Slug in Slug Out CAF-5B 0.65 0.41 0.61 0.55 CAF-6B 0.58 0.49 0.58 0.52 CAF-78 0.58 0.58 0.80 0.80 CAF-8B 2.59 2.59 2.59 3.45 CAF-9B 1.04 1.04 1.30 1.30 CAF-10B 1.73 1.30 2.07 2.07 CAF-11B 1.15 0.94 0.94 0.94 [v) Page 2 of 2 j',,..
-s-...-. ~ - - ~ ~. - -. - - - - - Table B-2. Summary of Slug-Test Analysis Reported in Corrective Action Plan ,,y Hvorslev Analysis Result Bouwer-Rice Analysis Result (ft/ day) (ft/ day) CAF-16C. 5.70 4.50 CAF-17C 6.60 4.40 LF-3A 6.70 3.90 LF-3B 1.04 1.51 LF-3C 3.30 3.48 OCW-2C 2.30 1.90 OCW-4B 1.40 0.82 OCW 5D Test 1 .1.10 0.96 OCW-5D Test 2 - 1.00 0.91 Maximum - 6.70 4.50 ~ Geometric Mean - 1.05 0.93 AH Wells Geometric Mean 2.4 2.0 a 0 Page 1 of 1 _._}}