FNR Characterization Package Workbook SP-018 Soil Sampling.will specify MDCs of less than 10% of the...

FNR CharacterizationPackage Workbook

SP-018Soil Sampling

Master Copy

Bartlett Services, Inc2007

Package Log No: FNR-SP-018 Survey Area: 12 Survey Units: 12-01, 12-02Survey Unit/Area Description: FNR Surface and Subsurface Soil.

SURVEY PACKAGE COVER SHEETSurvey Type: Characterization Survey, Final Status Survey

Survey Objectives:This package addresses soil in the vicinity of the FNR and beneath the FNR buildingfootprint. This includes soil beneath the FNR reactor foundation, the basement and adjacentto the Storage Ports west of the FNR. The objectives of this package are to:1. Confirm that soil activity concentrations are below soil Screening-Level DCGLs in the

vicinity of the field tile drain beneath the Beam Port Floor adjacent to the PoolFoundation, adjacent to the FNR Foundation and at any other locations potentiallyimpacted by leakage of contaminated water from the FNR.

2. Confirm that soil activity concentrations due to neutron activation in the vicinity ofStorage Port No. 1 are below soil screening-level DCGLs.

3. Alternatively, if soil is found to contain concentrations of licensed radioactive materialsabove the screening level DCGLs, identify the extent of the contamination to guideremediation.

Package Contents:" Document Change Control Form" Survey Unit Walkdown Notes" Survey Design Worksheet* Survey & Sampling Instructions" Sample Chain Of Custody Forms" References

Attachments1. Photographs2. Survey Design and Support Maps3. Blank Survey Forms4. Completed Forms5. Survey Timeline6. JHA & Pre-Job hazard briefing attendance

sheets7. UM Counting Lab Reports8. Vendor Lab Lab Analysis Reports9. Summary Data Reports10. Reference Material11. QC Checklist12. Superseded Information

Survey Package Implementation:Rock P. NeveauRadiological Engineer Printed Name Signature Date

Bruce J. MannHealth Physics Supervisor Printed Signature DateName SignatureDateImplementation Comments: The collection of soil samples may be accomplished by a combination ofhand sampling and push tool (Geoprobe-type) techniques. This may be performed in more than onesampling campaign. This will be determined by accessibility to the sub-floor areas in the FNR and Projectschedule and support resource constraints.

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Package Log No: FNR-SP-018 I Survey Area: 12 1Survey Unit/Area Description: FNR Surface and Subsurface Soil.

Survey Units: 12-01, 12-02

SP-0 18_Pkg MainFormsRev2 Page 2 of 12 11/12/2007

Package Log No: FNR-SP-018 T Survey Area: 12 1 Survey Units: 12-01, 12-02Survey Unit/Area Description: FNR Surface and Subsurface Soil.

Survey Package Document Control Change Form

Package Log No: FNR-SP-018 Survey Area: 12 Survey Units: 12-01, 12-02

Survey Unit/Area Description: Surface and subsurface soil.

Change # Description Initiator/Date RE

4 +

SP-0 18_PkgMain_FormsRev2 Page 3 of 12 11/12/2007

[ Package Log No: FNR-SP-018 Survey Area: 12 Survey Units: 12-01, 12-02Survey Unit/Area Description: FNR Surface and Subsurface Soil.

Survey Unit Walkdown RecordPackage Log No: FNR-SP-018 I Survey Area: 12 Survey Units: 12-01, 12-02Survey Unit/Area Description: Surface and subsurface soil.Walkdown Notes:

1. July 18-07, C. Becker and B. Mann; discussion, walkdown and review of soil samplinghistory and objectives for the Decommissioning Phase soil sampling:

a. The soil in the vicinity of the sub-foundation tile drain was sampled in the 2003Characterization survey and the results showed minimal activity.

b. Similarly, soil external to and adjacent to the FNR was investigated in the 2003Characterization survey and no detectable licensed radioactive materials weremeasured.

c. Soil locations that are potentially impacted beneath the FNR include:i. Adjacent to/beneath the line in the Basement that runs from the Cold

Sump to the field tile drainii. Adjacent to and beneath the Cold Sump, because of potential cracks in the

sump. The sump should be drained and inspected to identify leak paths.Soil sampling will be influenced by the results.

iii. Adjacent to the Hot Sump in the Basement. Similar to the Cold Sump, thesump should be drained and inspected to identify leak paths. Soil samplingwill be influenced by the results.

iv. Beneath the former Hot Ion-exchange process pit. The Pit should bedrained and inspected to identify leak paths. The drains from this pit arelikely to be significantly corroded.

v. Beneath the Pool Foundation. It was recommended that two cores bedrilled down through the Foundation near the joint between the FNR andthe PML - to provide access for push-tool soil samples to be collected inthe soil beneath the Pool.

vi. Provisions should be made to sample the soil beneath the N. side of thePool Foundation.

d. Additional sampling locations may be identified following video inspection offloor drain piping located beneath the Beam Port Floor - West Side.

End of Walkdown Notes

SP-0 1 8_PkgMain_FormsRev2 Page 4 of 12 11/12/2007

Package Log No: FNR-SP-018 1 Survey Area: 12 1 Survey Units: 12-01, 12-02Survey Unit/Area Description: FNR Surface and Subsurface Soil.

Survey Design WorksheetDescription:Locations of interest for sampling under this package include N. side FNR foundation tile drain,Storage Ports, Pool Foundation, beneath Basement sumps and drains and beneath the Beam PortFloor west side. Additional descriptions are provided in the General Instructions.

Survey Unit History:The 2003 FNR Historical Site Assessment (HSA did not identify any soil areas as impacted,however the HSA identified a four inch foundation tile drain as impacted [UM 2003]. The drainruns below grade around the FNR foundation, exterior to the building and around the PoolFoundation in the unexcavated sub-floor soil on the west side of the Beam Port Floor, interior tothe building. The approximate elevation of this drain is 824 ft. Per original design, this drain,discharged to the Cold Sump in the FNR Basement. The reason the HSA identified the drain asimpacted is that approximately 7500 gallons of Pool Water back-flowed into the tile drain in1993. Subsequently, the tile drain was isolated from the Cold Sump.

Soil beneath and adjacent to the FNR was investigated in the 2003 FNR Characterization[CH2MHill 2004]. Two locations exterior to the FNR were sampled and samples were collectedfrom two locations beneath the building. All locations were sampled using a push drivenGeoprobe closed barrel core sampling apparatus. The sampler was driven to a depth of 7.6 m (inall except one location, beneath the Beam Port Floor where refusal occurred at 6.1 m) The soilsampling tubes were divided into sub-samples (aliquots) of soil in depth increments. The sampleswere analyzed by Gamma Spectroscopy and for H-3 and C-14. For the most part the results werenegative (concentrations < MDC). for all the sample aliquots. However, in several samplelocations detectable activity concentrations were reported, mostly in sub-surface soil. Theseresults are summarized in Table 1 below.

Surveys of the Storage Ports performed in 2006 and 2007 identified zones of elevated activity atthe maximum depth into Ports 1, 2 and 3. These elevated measurements persisted after theseports were decontaminated. A Pu-Be neutron source was stored in Port 1. This suggests that theport walls and possibly the soil in the vicinity are activated.

Table 1 Summary of 2003 Characterization Survey Soil Sample ResultsSample Nuclides Detected Concentration Depth Increment Notes

Location (pCi/g)Foundation tile C-14 45 7.0 - 7.6 m Tile drain is aboutdrain E. of FNR Pu-242 0.1 (+ 0.1) 7.0 - 7.6 m 5 m below grade at

this loc.Adj. to Storage Co-60 1.2 7.0 - 7.6 m Storage Ports arePorts from 3 to 4 m

below grade.Beneath Basement None Near center of Sfloor half below ceiling

hatch.Beneath BP floor H-3 14.5 0 - 0.3 m About 3 ft. from

Pool Foundation.NE

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Package Log No: FNR-SP-018 I Survey Area: 12 I Survey Units: 12-01, 12-02Survey Unit/Area Description: FNR Surface and Subsurface Soil.

Design Assumptions:

1. Potential pathways for soil contamination include seepage from the Pool through joints,cracks and voids in the Pool foundation, between the foundation and adjacent walls in theFNR and PML, cracks and voids in sumps and floor drains in the FNR and back-flow ofPool water into the FNR foundation tile drain.

2. Locations with potentially impacted soil identified for evaluation under this surveypackage are:

a. Adjacent to the FNR tile drain on the east side of the FNRb.. Adjacent to Storage Ports 1-3Note: It is assumed that the Storage Ports will be removed. Samples of soilsurrounding Ports 1, 2 and 3 will be sampled during the soil excavation.c. Beneath and adjacent to the Pool Foundationd. Beneath and adjacent to Hot and Cold Sumps, Ion Exchange Pits and Basement

Drainse. Beneath floor drains on the west side of the Beam Port Floor.

3. Single radionuclide Screening-level DCGLs for surface soil published by the NRC willbe used to establish analytical detection limits (MDCs) for evaluation of soil sampleresults. Soil samples will be analyzed for radionuclides of concern and analysis requestswill specify MDCs of less than 10% of the DCGL values. Table 2 below lists thescreening level DCGLs and the MDCs to be requested.

4. Soil sampled from 0-15 cm from the surface outside the FNR will be evaluated againstNRC screening-level DCGLs in Table 2 to determine if remediation is required.

5. Soil from depths greater than 15 cm from the surface at locations exterior to the FNR andfrom locations beneath the FNR will be evaluated against interim criteria for sub-surfacesoil. (to be developed).

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Package Log No: FNR-SP-018 T Survey Area: 12 F Survey Units: 12-01, 12-02Survey Unit/Area Description: FNR Surface and Subsurface Soil.

Design Assumptions, Cont'd.:

Table 2, Single Radionuclide DCGLs and Analytical Procedure MDCsNuclide Half-Life Surface Soil 10% of MDC to be

(yr) DCGL (1) Surface Soil Requested(pCi/g) DCGL (pCi/g) (pCi/g) (

Potential Radionuclide Contaminants (3)

Carbon-14 (C-14) 5.73E+03 12 1.2 1

Cesium-137 (Cs-137) 30.2 11 1.1 0.1

Cobalt-60 (Co-60) 5.3 3.8 0.38 0.1

Europium-152 (Eu-152) 13.5 8.7 0.87 0.5

Europium-154 (Eu-154) 8.5 8 0.8 0.5

Iron-55 (Fe-55) 2.7 10,000 1000 10

Iodine-129 1.57E+07 0.5 0.05 0.05

Nickel-59 (Ni-59) 7.5E+04 5,500 550 10

Nickel-63 (Ni-63) 100 2,100 210 10

Silver-108m (Ag-108m) 127 3.5 0.3 0.1

Silver-llOm (Ag-llOm) 0.68 4:9 0.5 0.1

Strontium-90 (Sr-90) 30 1.7 0.17 0.1

Tritium (H-3) 12.3 110 11 10

Other Radionuclides of Potential Interest (4)

Uranium-235 (U-235) 7.04E+08 8.0 0.8 0.5U-235 + Daughters 3.2 0.3Uranium-238 WU-238) 4.47E+08 14 1.4 1U-238 + Daughters 7.2 0.7Plutonium-241 14.4 72 7.2 5Plutonium-242 3.76E+05 29.1 2.9 3

Notes:1. Screening-default values published by NRC. See NUREG-1757, Vol. 2 (Table H.1 for building

surface contamination and Table H.2 for surface soil) or NUREG/CR-5512, Vol. 3 (Table 5.19for building surface contamination and Table 6.91 for surface soil).

2. The requested minimum detectable concentrations are a'priori target values selected to ensurethat requesled MDCs are less than 10% of the most restrictive DCGL, i. e., the DCGL for surfacesoil.

3. Radionuclides listed here are either listed in the January 2006 Decommissioning Plan (Table 2-4),or were reported in multiple samples in the 2003 Characterization Survey Report. Radionuclideswith half-lives < one y are excluded (except for Ag- 110, which has been measured in samples asrecently as 2006).

4. These radionuclides have been reported in at least one sample collected as part of the 2003 FNRCharacterization survey - mostly at very low concentrations.

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Package Log No: FNR-SP-018 1 Survey Area: 12 1 Survey Units: 12-01, 12-02Survey Unit/Area Description: FNR Surface and Subsurface Soil.

Survey and Sampling Instruction Form

A. General Instructions:

Soil samples will be collected at the following locations:1. Tile foundation drain - E side of FNR2. Storage Ports 1-3 W of the FNR3. Adjacent to former tile drain line to Cold Sump4. Beneath the Hot and Cold Sumps5. Beneath the former Ion exchange pits6. Beneath Basement floor drains7. Beneath the Pool Foundation8. Adjacent to floor drains under the Beam Port Floor - west side

It is assumed that the tile foundation drain sample collected on the east side of the FNR (Bullet #1above) will be collected using a Geoprobe unit. All other samples are assumed to be collectedusing hand tools and will have an initial collection depth of 15 cm. If additional sampling depthsare required, samples will be collected in increments of 30 cm.

Soil sampling at the tile drain location east of the FNR will be performed using push-tooltechnology (Geoprobe or equivalent). The requested sample core-length is 3 meters. Note that thetotal core depth required (from the surface at grade) is approximately 7.6 meters. Soil samplescollected at the Storage Ports and designated locations beneath the FNR Beam Port and Basementfloors will be collected using either split spoon or core barrel sampling devices with cores of oneand ½ or two inch diameter. The requested initial core length (depth of sample) is 15 cm.Additional samples may be collected at depths depending on the activity and conditions foundwithin the Sampling Zones. Reference elevations (in ft. above sea level) and soilsampling zonethicknesses in the principal areas of interest are provided in Table 3 below.

Table 3, Sampling Locations and Reference ElevationsLocation Elevation Description

Top Surface of Soil Sampling ZoneE side FNR Tile Drain 839 ft - 1 in. 824. to 812 ft. (3m) Drain tile El. is 824 ft.

W side FNR Storage 848 ft. - 2 in. 834 to 825 ft. (2 m) Storage Port El's. arePorts 827 ft 9 in. to 833 ft 4

_½in.

Pool Foundation 819 ft. - 1 2 in. 819 ft 1 ½ in to 813 ft. Soil beneath Pool(2 m) Found.

Hot and Cold Sumps 819 ft. 6 in. 812 ft. to 819 ft 6 in. Sump bottoms are 6(2 m) in. concrete.

Beam Port Floor W 833 ft. 827 ft to 833 ft. (2 m) Floor slab is min. 12side - unexcavated in thick


Package Log No: FNR-SP-018 I Survey Area: 12 1 Survey Units: 12-01, 12-02Survey Unit/Area Description: FNR Surface and Subsurface Soil.

B. Access and Support Requirements1. Access for sampling equipment at locations outside the FNR will be provided by the

University.2. A geotechnical sample depth-profile log is requested to be developed for Geoprobe cores at

outdoor locations.3. Samples will be collected adjacent to Ports 1, 2 and 3 during soil excavation for removal of

the Storage Ports.4. Access for collection of soil samples beneath the FNR Beam Port and Basement floors will

be provided by either coring through the floors, or in some cases by direct access resultingfrom removal of floor concrete:

a. Where no access directly above sample locations is available, a six-inch core will bedrilled through the concrete, directly above the sample location.

b. To gain access to sample the soil beneath the south end of the Pool where the formerPool abutted the PML, two vertical six-inch cores will be drilled through the Poolfoundation.

5. Portable lighting may be required to provide sufficient illumination for sampling activitiesbeneath the FNR.

C. Precautions and Limitations1. Access areas and surfaces to soil sampling locations beneath the FNR must be maintained

dry. Precautions must be taken when coring through concrete to prevent cooling water tobreak through and contact the soil below.

2. Safety precautions are identified in the JHA (Attachment 6).

D. Specific Instructions:

1. Tile foundation drain - E side of FNR (assuming use of Geoprobe unit for this sample)a. Determine the location for the sample bore - to align within one foot of the tile drain

just north of the drain that formerly connected the tile drain to the Cold Sump.b. Drive sampling tubes to 6.8 meter depth. Collect the soil in 30 cm. increments from

5 meters to 6.8 meters and prepare sample containers for each.

2. Storage Ports 1-3 W of the FNRa. Expose the soil horizon at approximately six inches above Port No. 2 (the port at the

highest elevation of Ports 1 -3)..b. Collect samples of 15 cm depth at the juncture of the ports and the west mounting

wall, immediately south of port 1, immediately north of port 1, immediately north ofport 3. If additional sample depths are required, collect the soil from each tube inincrements of 30 cm into individual samples.


Package Log No: FNR-SP-018 I Survey Area: 12 I Survey Units: 12-01, 12-02Survey Unit/Area Description: FNR Surface and Subsurface Soil.

3. Adjacent to former tile drain line to Cold Sump.a. Provide access to this line by drilling a six inch core through the basement floor

with center at one and ½ ft. from the east wall and one and ½ ft. from the north wallinside the basement stair landing (see drawings M-7 and M-17).

b. Drive a sampling tube to approximately 15 cm depth. If additional sample depths arerequired, collect the soil from the tube in increments of 30 cm into individualsamples.

4. Beneath the Hot and Cold Sumpsa. Access may be provided by removal of the sumps - if the sumps are not removed,

drill a six-inch core through the bottom of each sump concrete to gain access.b. Drive a sampling tube to approximately 15 cm depth in the soil beneath each sump.

If additional sample depths are required, collect the soil from the tubes in incrementsof 30 cm into individual samples.

5. Beneath the former Ion exchange pitsa. Access may be provided by removal of the pits - if the pits are not removed, drill a

six-inch core through the bottom of each pit to gain access.b. Drive a sampling tube to approximately 15 cm depth in the soil beneath each pit. If

additional sample depths are required, collect the soil from the tubes in incrementsof 30 cm into individual samples.

6. Beneath Basement floor drainsa. Select locations adjacent to the floor drain pits (approximately 1 ft square) for the

Basement Floor drains (up to three locations).b. Access may be gained by removing the pits and surrounding concrete or by drilling

a six-inch core.c. Drive a sampling tube to approximately 15 cm depth in the soil beneath each drain.

If additional sampling depths are required, collect the soil from the tubes inincrements of 30 cm into individual samples.

7. Beneath the Pool Foundationa. Drill two six-inch cores through the pool foundation. These are to be located at the

south end of the Pool footprint. Each core is to be located at approximately thelocation of the east and west junctures of the former pool bottom with the formerpool inner walls.

b. Drive a sampling tube to approximately 15 cm depth in the soil beneath each corelocation. If additional sampling depths are required, collect the soil from the tubes inincrements of 30 cm into individual samples.

c. Collect samples at two locations just north of the Pool foundation at approximately10 o'clock and 2 o'clock viewed from above looking north. Access may be gainedfrom concrete removal to remove drains running E-W located just north of the PoolFoundation.

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Package Log No: FNR-SP-018 ] Survey Area: 12 1 Survey Units: 12-01, 12-02Survey Unit/Area Description: FNR Surface and Subsurface Soil.

d. Drive a sampling tube to approximately 15 cm depth in the soil beneath each corelocation. If additional sampling depths are required, collect the soil from the tubes inincrements of 30 cm into individual samples.

8. Adjacent to floor drains under the Beam Port Floor - west sidea. Note: exact locations to be determined from inspections of embedded drain piping

and after removal of concrete and embedded and buried drain piping. It is estimatedthat between three and six locations will be sampled.

b. At each designated location drive a sampling tube to 15 cm depth. If additionalsampling depths are required, collect the soil from each tube in increments of 30 cminto individual samples.

Characterization Package References

1. U of Mich Referencesa. University of Michigan, FNR Decommissioning Plan, Rev 1, 2006.b. University of Michigan, Ford Nuclear Reactor, Historical Site Assessment, January

2003.c. CH2MHill, Characterization of the Ford Reactor Facility, June .2004.

2. Technical Referencesa. Ford Nuclear Reactor Decommissioning Project Memorandum, Requested Minimum

Detectable Concentration from Vendor laboratories, FNR-RP-013, 14-Nov-06b. Oak Ridge Institute for Science and Education, Survey Procedures Manual,

Independent Environmental Assessment and Verification Program, Section 8.9Surface Soil Sampling for Chemical Analysis Rev 3, August 7, 2006.

c. Oak Ridge Institute for Science and Education, Survey Procedures Manual,Independent Environmental Assessment and Verification Program, Section 8.10Subsurface Soil Sampling for Chemical Analysis Rev 3, August 7, 2006.

3. Regulatory Documentsa. US Nuclear Regulatory Commission, NMSS Decommissioning Standard Review

Plan, NUREG 1727, Sept. 2000b. US Nuclear Regulatory Commission Consolidated NMSS Decommissioning

Guidance, Volume 2, Characterization, Survey and Determination of RadiologicalCriteria, NUREG-1757, Final September 2003.

SP-0 1 8PkgMain_FormsRev2 Page I I of 12 11/12/2007

Package Log No: FNR-SP-018 Survey Area: 12 1 Survey Units: 12-01, 12-02Survey Unit/Area Description: FNR Surface and Subsurface Soil.

4. Drawings:

Drawing No. DescriptionDwg No. A-i, Smyth, Basement PlanHinchman & Grylls, 1/24/55Dwg No. A-2, Smyth, Reactor Building, Basement Plan and Schedules (Door andHinchman & Grylls, 1/24/55 Finish)Dwg No. A-3, Smyth, Reactor Building, First and Second FloorHinchman & Grylls, 1/24/55Dwg No. A-6, Smyth, Reactor Building SectionsHinchman & Grylls, 1/24/55Dwg No. S-1, Smyth, Reactor Building, Basement, Foundation and First Floor PlansHinchman & Grylls, 1/24/55Dwg No. S-7, Smyth, Reactor Building Sections and DetailsHinchman & Grylls, 1/24/55Dwg No. M-7, Smyth, Reactor Building Process Piping, Basement Floor (showsHinchman & Grylls, 1/24/55 Sump elevations)Dwg No. M-17, Smyth, Reactor Building Heat Exchanger RoomHinchman & Grylls, 1/24/55 _

SP-0 1 8PkgMain_FormsRev2 Page 12 of 12 11/12/2007

CH2MHILL1%

Characterizationof the

Ford Nuclear Reactor Facility

FinalRevision 0

Prepared forUniversity of Michigan

Reactor Facility Decommissioning Project

June 2004

riedHealth Phy cist

Date

CH2MHILL

3190 George Washington Way

Richland, WA 99352

CH2MHILL

Contents

1.0 Introduction ................... 1-12.0 Site Description ........................................................................................................................ 2-13.0 Contaminants of Concern ....................................................................................................... 3-14.0 Survey Approach ...................................................................................................................... 4-1

4.1 General ............................................................ I .............................................................. 4-14.2 Instrumentation ............................................................................................................. 4-14.3 Survey Activities ........................................................................................................... 4-2

4.3.1 Preliminary Survey ......................................................................................... 4-24.3.2 Characterization Survey ................................................................................. 4-4

4.4 Sample Analysis .......................................................................................................... 4-154.5 Quality Control ........................................................................................................... 4-15

5.0 Survey Results ........................................................................................................................... 5-15.1 Preliminary Survey ....................................................................................................... 5-1

5.1.1 Backgrounds ..................................................................................................... 5-15.1.2 Scanning ............................................................................................................ 5-25.1.3 Surface Activity M easurements ..................................................................... 5-2

5.2 Characterization Surveys ............................................................................................. 5-65.2.1 Scanning ............................................................................................................ 5-65.2.2 Surface Activity M easurements ..................................................................... 5-65.2.3 Sample Results ................................................................................................. 5-95.2.4 In Situ Gamm a Spectra 5................................................................................. 5-24

6.0 Discussion of Results .............................................................................................................. 6-1

Figures

Figure 2-1 General Configuration of the FNR and PM L ............................................................ 2-2Figure 2-2 Floor Plan of the Ford Nuclear Reactor - Pool/Control Area, 3rd Floor .............. 2-3Figure 2-3 Floor Plan of the Ford Nuclear Reactor - 2nd Floor ............................................ 2-4Figure 2-4 Floor Plan of the Ford Nuclear Reactor - Beamport Area, 1st Floor ...................... 2-5Figure 2-5 Floor Plan of the Ford Nuclear Reactor - Liquid Systems, Basement Level ........ 2-6Figure 2-6 Floor Plan of the Ford Nuclear Reactor - Cooling Tower, Roof Level ................. 2-7Figure 4-1 Ford Nuclear Reactor Site. Plan Indicating Sampling Locations ............................ 4-7Figure 4-2 Ford Nuclear Reactor Basement Indicating Sampling Locations .......................... 4-8Figure 4-3 Ford Nuclear Reactor 1st Floor Indicating Sampling Locations ............................. 4-9Figure 4-4 Ford Nuclear Reactor 3rd Floor Indicating Sampling Locations ........................... 4-10Figure 4-5 Ford Nuclear Reactor 4th Floor Indicating Sampling Locations ........................... 4-11Figure 5-1 3rd Floor Locations of Beta Surface Activity Exceeding Guideline Levels ............ 5-4Figure 5-2 1st Floor Locations of Beta Surface Activity Exceeding Guideline Levels ............ 5-5

Charactenzation ivFord Nuclear Reactor Facility

CH2MHILL

Tables

Table 3-1 Potential FNR Contaminants of Concern .................................................................. 3-1Table 3-2 Acceptable License Termination Screening Values of Common Radionuclides

for Structure Surfaces ................................................................................................... 3-3Table 3-3 Acceptable License Termination Screening Values of Common Radionuclides

for Surface Soil .......................................................................................................... 3-4Table 4-1 Instruments Used for Characterization Surveys ...................... 4-2Table 4-2 Sam pling Locations ................................................................................................... 4-12Table 5-1 Instrument Background Levels (Shutdown Mode) ................................................. 5-1Table 5-2 Instrument Background Levels (Operating Mode) .................................................. 5-1Table 5-3 Summary of Surface Beta Activity Measurements .................... 5-2Table 5-4 Surfaces with Beta Activity Exceeding Interim Guidelines .................................... 5-3Table 5-5 Summary of Surface Activity Measurement Results ............................................... 5-7Table 5-5a Tritium Concentrations in Smears ............................................................................. 5-8Table 5-6 Radionuclide Concentrations in Background Soil Samples ................................. 5-10Table 5-7 Radionuclide Concentrations in Soil Samples From Drain Tile Field Area ....... 5-11Table 5-8 Radionuclide Concentrations in Soil Samples From Source Storage

P ort A rea 5........................................................................................................... : ......... 5-12Table 5-9 Radionuclide Concentrations in Soil Samples From Beneath FNR Basement

Floor A rea ..................................................................................................................... 5-13Table 5-10 Radionuclide Concentrations in Soil Samples From Beneath Beamport Floor

Area.......................................................... ........................ ... 5-15Table 5-11 Radionuclide Concentrations in Background Concrete Samples ........................ 5-18Table 5-12 Radionuclide Concentrations in Concrete Samples ............................................... 5-19Table 5-13 Radionuclide Concentrations in Samples From Sanitary Sewer Locations ........ 5-21Table 5-14 Radionuclide Concentrations in Samples From Contaminated Drains .............. 5-23Table 5-15 Radionuclide Concentrations in Samples From Sump Locations ........................ 5-26Table 5-16 Chemical Concentrations in Samples From Sump Locations ............................... 5-27Table 5-17 Radionuclide Concentrations in Miscellaneous Samples of Anomalous

M aterials ................................................................................ ................ 5-28Table 5-18 Radionuclide Concentrations in Rinsate and Water Samples ........... .................. 5-29Table 5-19 Radionuclide Concentrations in Ground Water Sample ...................................... 5-31

Appendices

A Instrument Calibration and Performance Test Information ...................................... A-1B List of Procedures Used for Characterization ................................................................ B-1C Field Survey Data Preliminary Survey ......................................................................... C-1D Characterization Plan ........................................................................................................ D-1E Work Package for Sample Collection and Survey Measurements .................................. E-1F Field Survey Data Characterization Survey ............................. F-1G In Situ Gamma Spectra ...................................................................................................... G-1H Chemical Laboratory Data ................................................................................................ H-1I Radiological Analytical Data .............................................................................................. I-1

CharacterizationFord Nuclear Reactor Facility

CH2MHILL

Executive Summary

The University of Michigan (UM) has ceased operation of the 2-megawatt (MW) FordNuclear Reactor (FNR) at its North Campus, and plans to follow with decontamination and-decommissioning (D & D) of the facility and termination of the Nuclear RegulatoryCommission (NRC) license. The UM contracted with CH2M HILL to assist in characterizingthe facility in preparation for D & D. The purposes of the characterization were thefollowing:

* To identify principal radiological contaminants

" To identify those reactor and facility systems and surfaces that are likely torequire remediation

* To determine whether the environment surrounding the FNR has been impacted

* To identify radiological hazardous materials to be addressed during D&D

Information obtained from the characterization effort will be used in establishingdecommissioning guideline levels for structures and soil; plan environmental, safety, andhealth (ES & H) actions; plan and schedule D & D activities; and estimate the nature andquantity of project waste.

Because the reactor was still fueled and operational at the time of the surveys, many systemsand locations could not be safely accessed for survey or sample. Continuing characterizationof these locations will be conducted following permanent shutdown and defueling and afterimpacted components and systems are removed.

The characterization entailed performing a site investigation process, preparing plans,performing radiological surveys, and collecting samples for analysis.

The site investigation involved a site walk-down and historical site assessment (HSA) byCH2M HILL, from which information such as the facility source term and operationalhistory for the facility were gained. Based on the information obtained from the siteinvestigation, CH2M HILL developed plans detailing the characterization survey, such asCharacterization Plan; Quality Assurance Project Plan; Environmental, Safety, axgd HealthPlan; Radiation Protection Plan; and Sample Collection and Survey Measurement WorkPackage. Plans were developed following the data quality objectives (DQO) process asdescribed in NUREG-1575 (Multi-Agency Radiation Survey and Site Investigation Manual[MARSSIM]). The NRC default screening criteria were chosen as a conservative basis forcomparison of characterization results; a beta activity level of 13,800 disintegrations perminute (dpm)/100 square centimeters (cm2)was selected as an interim guideline, based on a50 percent/50 percent mixture of Co-60 and Cs-137.

After planning was complete, a survey team from Safety and Ecology Corporation (SEC) -teaming partner with CH2M HILL - visited the site and performed radiologicalmeasurements and sampling. A preliminary survey in November 2002 and a follow-oncharacterization survey in April 2003 were conducted. The measurements and samples

Characterization ES-1Ford Nuclear Reactor Facility

CH2MHILL

collected for the radiological characterization survey consisted of surface gamma and betascans; direct alpha measurements; direct beta measurements; smear samples for removablealpha and beta contamination; smear samples for removable tritium contamination;exposure rate measurements; and soil, concrete, sludge, water, and miscellaneousanomalous samples for laboratory analysis. Analyses for potential hazardous materialconstituents also were performed on sludge from sumps.

Survey plans were developed and measurements performed for surface, structures, andenvirons backgrounds. Direct beta background values for naturally occurring radioactivematerial (NORM) in brick, tile, cinder block, and concrete were determined and applied tothe direct beta measurements collected at the FNR facility surfaces and structures to equatethe reported beta activity to net results per 100 cm 2. Also, survey measurements andsamples collected from the environs were analyzed to determine background values forNORM and the contribution from activity from weapons testing fallout in soil, concrete, andwater of the environs. These values are stated in the report, but, conservatively, were notapplied to the results.

The findings of the characterization were that the FNR facility and site, for the most part, arenot radiologically contaminated. However, the following areas and locations at the FNRfacility and site will require decontamination before the site is suitable for release from theNRC license currently in effect:

1. Floor drains on the Basement, 1st Floor, and 3rd Floor

2. Small areas of floor near the reactor pool on the 3rd Floor, the bioshield on the 1stFloor, and waste handling systems on the Basement level

3. The bioshield wall on the west and north sides, where pool water appears to beleaking through the concrete

4. Ventilation systems for the neutron activation equipment, beamports, and sourcestorage ports

5. To be determined - additional systems and locations that could not be addressedwhile the facility was still in operation.

Other locations had associated measurements that were potentially influenced by "ambientdirect radiation levels or had background levels that were too high to allow meaningfulcharacterization. These surfaces will be reevaluated after permanent shutdown and removalof components with high radiation levels.

The dominant radionudides present are Co-60 and Cs-137 with smaller concentrations ofmultiple activation and fission product radionuclides. There is no uniform radionuclidemix, based on the limited sampling and analyses performed. At license termination time,Co-60 and Cs-137 are expected to be the primary contaminants remaining from licensedactivities.

Additional measurements and samples of various media will be obtained during continuingcharacterization to further define the nature, levels, and extent of radiologicalcontamination. The following locations will be addressed in this follow-on characterization:

Characterization ES-2Ford Nuclear Reactor Facility

CH2MHILL

* 3rd Floor- Reactor pool and contents- South wall of reactor room- Floor in vicinity of reactor pool- Drains- Pneumatic lines in the reactor pool and throughout the facility- Exhaust ventilation for neutron activation hood- Janitor's closet

1st Floor- Bioshield- Drains- Source ports and surrounding soil- Floor near bioshield- Soil beneath floor near bioshield and sump- Beamport and local exhaust ventilation

Basement Level- Drains- Sumps- All structure surfaces- Primary coolant systems- Soil beneath reactor and around sumps


ES-3

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1.0 Introduction

The Ford Nuclear Reactor (FNR) facility at the University of Michigan (UM) has operatedsince 1957 under Atomic Energy Commission/Nuclear Regulatory Commission(AEC/NRC) License No. R-28 in support of a wide variety of education and researchprograms. In anticipation of ceasing reactor operation, the UM contracted with CH2M HILLto characterize the facility. The purpose of the characterization is to define the nature,magnitude, and extent of radioactive and radioactively hazardous contamination in thefacility, for use in further decommissioning planning.

The characterization began with a historic site assessment (HSA) by CH2M HILL, followedin November 2002 by a preliminary survey of readily accessible areas of the facility bySafety and Ecology Corporation (SEC), teaming partner with CH2M HILL for the FNRproject. The following were objectives of the preliminary survey, based on the HSA report:

" To identify potential radionuclide contaminants" To confirm the impacted/non-impacted radiological status of structure surfaces* To identify areas in need of further evaluation; to evaluate ambient background levels in

operating and shutdown modes" To provide additional information for planning additional characterization activities

Based on the results of the HSA report and preliminary survey, additional characterizationwas conducted by CH2M HILL and SEC in April 2003. The primary focus of thischaracterization was to determine the extent of contamination and activation of certainstructural surfaces and document the radiological status of subsurface soil, sewer system,and ground water in the vicinity of the FNR. This report describes these preliminary andcharacterization survey efforts and reports their results.

Characterization I-1Ford Nuclear Reactor Facility

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CH2MHILL

and equipment inaccessible with the floor monitor were scanned using a Model43-89 dual alpha/beta scintillation detector; coverage was 50 to 100 percent.Scans were performed by maintaining the detector as close as practicable to thesurface and advancing the detector at a rate of less than I detector-width/sec.Audible signals were monitored and locations of discernible elevated count rateswere noted for further investigation.

4.3.2.5 Measurements of total surface activity were performed at locationsrepresentative of the general surface; a minimum of one measurement wasperformed per m 2 of surface area. Measurements also were obtained by scans atlocations identified previously for further investigation. Both alpha and betaactivity levels were determined until sufficient data were recorded todemonstrate that alpha contamination was not of concern.

4.3.2.6 Smears for removable alpha and beta activity were performed at locations ofdirect measurements (Section 4.3.2.5) by wiping a surface area of approximately100 cm 2 with a dry cloth filter, using moderate pressure. Smears for removableH-3 activity also were obtained at selected locations considered to have apotential for such contamination; these smears were placed immediately intopre-filled liquid scintillation vials to prevent loss of contaminant as a result ofevaporation.

4.3.2.7 Locations were selected for sampling to determine the nature and extent ofcontaminants on various facility surfaces and systems to identify possibleimpacts on the environment of FNR. Figures 4-1 through 4-5 and Table 4-2indicate these locations. Because the reactor was fueled and operational at thetime of this survey, intrusive sampling was not conducted at some locationsproposed in the Characterization Plan (see Appendix D). At other proposedsampling locations, sufficient sample quantities were not available.

• 4.3.2.8 Boreholes were drilled and soil samples of 500 to 1,000 grams were obtained atvarying depths using a driven closed-barrel sampler at the following locations:

Drain Tile-Field Outside-FNR (East)4.3 to 4.9 m depth5.8 to 6.4 m depth7.0 to 7.6 m depth

Adjacent to Source Storage Ports (West)3.4 to 4.0 m depth5.5 to 6.1 m depth7.0 to 7.6 m depth

Characterization 4-5Ford Nuclear Reactor Facility

CH2MHILL

Beneath Basement Floor0 to 0.3 m beneath floor0.3 to 1.5 m beneath floor1.5 to 3.0 m beneath floor3.0 to 4.6 m beneath floor4.6 to 6.1 m beneath floor6.1 to 7.6 m beneath floor

Beneath Beamport Floor (1st Floor)0 to 0.3 m beneath floor1.5 to 3.0 m beneath floor3.0 to 4.6 m beneath floor4.6 to 6.1 m beneath floor


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FIGURE 4-2Ford Nuclear Reactor Basement Indicating Sampling Locations


4-8

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FIGURE 4-3Ford Nuclear Reactor 1st Floor Indicating Sampling Locations


4-9

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FIGURE 4-4Ford Nuclear Reactor 3rd Floor Indicating Sampling Locations

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4-10

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FIGURE 4-5Ford Nuclear Reactor 4th Floor Indicating Sampling Locations


4-11

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TABLE 4-2 (2 PAGES)Sampling Locations

Sample Description Sample Radiochemical Chemical CommentsLocationa Type Analysis Analysis

1 East side FNR near drain tile Soil Tritium, GEA, GA, GB, N/Afield 10 CFR Part 61

2 West side FNR near source Soil Tritium GEA, GA, GB, N/Astorage ports 10 CFR Part 61

3 Beneath FNR (Basement Soil Tritium GEA, GA, GB, N/Anear reactor pool and holding 10 CFR Part 61tank pit)

4 Beneath FNR (1st Floor Soil Tritium GEA, GA, GB, N/Aunexcavated area) 10 CFR Part 61

5 Background soil Soil 10 CFR Part 61 N/A

6A Basement (area of ion- Concrete 10 CFR Part 61 N/Aexchange columns)

6B Basement near filters Concrete 10 CFR Part 61 N/A

7 Basement hot sump Concrete 10 CFR Part 61 N/A Not obtained

8 1st Floor (area with Concrete 10 CFR Part 61 N/Ahighest level of fixedcontamination)

9 1st Floor "hot spot" Concrete GEA, GA, GB N/Abetween Beamports J and I

10 3rd Floor ceiling Concrete GEA, GA, GB N/A(directly above verticalbeam tube)

11 Reactor pool "bathtub ring" Concrete Tritium, GEA, GA, GB N/A Not obtained

12 Reactor pool activated Concrete GEA, GA, GB N/A Not obtainedconcrete

13 Heavy water addition Concrete Tritium N/Astation-reactor pooloperating floor

14 Background concrete Concrete 10 CFR Part 61 N/A

15A Basement contaminated drain Sludge GEA, GA, GB N/A

15B 1 st Floor contaminated drain Sludge GEA, GA, GB N/A

15C 3rd Floor contaminated drain Sludge GEA, GA, GB N/A

16 Sanitary sewer (before exiting Sludge 10 CFR Part 61 N/AFNR)

17 Sanitary sewer (where FNR Sludge Tritium, GEA, GA, GB N/Aline joins trunk line) _

18 Sanitary sewer (middle of trunk Sludge Tritium, GEA, GA, GB N/Aline)

'19 Sanitary sewer (end of trunk Sludge Tritium, GEA, GA, GB N/Aline)

20 Sanitary sewer (background - Sludge 10 CFR Part 61 N/Aupstream of FNR)

21 'Composite - hot and cold Sludge Tritium, GEA, GA, GB Metals, Hg,sumps PCBs, Ph

22 1 st Floor - sump Sludge GEA, GA, GB N/A


4-12

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TABLE 4-2 (2 PAGES)Sampling Locations

Sample Description Sample Radiochemical Chemical CommentsLocationa Type Analysis Analysis

23 Composite - ion exchange Resin Tritium, GEA, GA, GB IPC metals, Not Obtainedresin reactor cooling system mercury

24 Hold-up tank Sludge Tritium, GEA, GA, GB N/A Not Obtained

25 Heat exchanger - primary side Sludge 10 CFR Part 61 N/A Not Obtained

26a Beam port exhaust system Metal GEA, GA, GB N/A Not Obtainedcoupon

26b Reactor exhaust system Metal GEA, GA, GB N/A Not Obtainedcoupon

27 1 Floor - source storage Metal GEA, GA, GB N/A Not Obtainedports coupon

28 Crane - reactor pool overhead Oil/ GEA, GA, GB IPC metals, Not Obtainedcrane grease PCB

29 Reactor cooling system Water 10 CFR Part 61 N/A Not Obtained

30 Irradiated components Metal GEA, GA, GB N/A Not Obtainedcoupon

31A Scraping from bioshield wall Misc. 10 CFR Part 61 N/A

31B Scraping from bioshield wall Misc. 10 CFR Part 61 N/A

31C Scraping from crane rail Misc. 10 CFR Part 61 N/A

32 Monitoring well Water GEA, GA, GB N/Aa Refer to Figures 4-1 to 4-5.

FNR - Ford Nuclear Reactor.N/A - not applicable.

4.3.2.9 Background soil samples were obtained from the surface (0 to 15 cm) and

subsurface (0.15 to 0.45 m). Soil was obtained from three non-impacted locations

approximately 200 to 500 m east of the FNR and computed. ?

4.3.2.10 Samples of concrete were obtained from the following surfaces where direct

monitoring and/or operating history suggest potential contamination by spills oractivation.

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Basement near resin column roomBasement near liquid transfer systemBeamport floor trench between ports I and JBeamport floor trench at north bioshield wallReactor level floor near heavy water systemCeiling of 3rd Floor above vertical beam tube

Samples of approximately 50 to 200 grams were obtained by clipping theconcrete from the upper 0.6 cm of surface, using an electric drill/impact hammer.

4.3.2.11 A background concrete sample was obtained from the non-impacted tunnel tothe Cooley Building.


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4.3.2.12 Sludge was obtained from the sanitary sewer system servicing the FNR at thefollowing locations:

" Drain line at exit from PML• Manhole outside PML where drain joins main trunk line" Manhole midway between campus and city treatment facility* Manhole near city treatment facility* Manhole upstream of PML drain entry (baseline)

4.3.2.13 Samples were obtained from floor drains on the Reactor, Beamport, andBasement levels and from the Basement hot/cold sump and Beamport FloorSump.

4.3.2.14 Scrapings were collected from two locations on the bioshield wall and from therailing of the Reactor Room Crane.

4.3.2.15 Field data were recorded on data forms and/or facility drawings. Appendix Fcontains the field data for the Characterization Survey.

4.3.2.16 In situ gamma spectra were collected at the following locations on the Beamportlevel where direct measurements indicated potential radionuclide contamination:

* Source Port #1* Floor Between Ports I and J* Floor Between Ports G and F

Appendix G contains the in situ gamma spectra.

4.3.2.17 A ground water monitoring well was placed to the south of the PML. Soilsamples of 500 to 1,000 grams were obtained at varying depths. A monitoringwell was established and a ground water sample was collected. The followinglocations indicate the depths of the samples collected:

Monitoring Well South of PML0 to 1.5 m depth (soil)4.3 to 5.8 m depth (soil)5.8 to 7.3 m depth (soil)7.3 to 8.2 m depth (soil)10.4 to 11.9 m depth (soil)13.4 to 14.9 m depth (soil)

13.1 to 14.0 m depth (water)

Note: The soil samples collected were not analyzed. These samples werecollected to support further analysis if the ground water sample analysiswarranted such an investigation.


CiHI21HILL

5.2.3 Sample Results5.2.3.1 Soil

Background

Table 5-6 presents the radionuclide concentrations in soil from the background locations.Only C-14, members of the naturally occurring Ra-226 and Th-232 series, and Pu-242 wereidentified at detectable levels. The C-14, Ra-226, and Th-232 concentrations were consistentwith typical soils. The Pu-2421evel was very low (less than 0.2 picocurie/ gram [pCi/g]) andthe source of this nuclide is not known.

Drain Tile Field

Table 5-7 presents the radionuclide concentrations in samples from the drain tile field. Theconcentration of C-14 was 45.0 pCi/g at the 7.0 to 7.6 m depth and the Pu-242 concentrationat that depth also was detectable, but very low. All other radionuclide concentrations inthese samples were either consistent with the background soil levels or less than thedetectable concentrations.

Source Storage Port Area

Concentrations, presented in Table 5-8, are consistent with background levels or are lessthan the method detection sensitivity. One exception is the Co-60 concentration of 1.17pCi/g at the 7.0 to 7.6 m depth. While less than the NRC guideline level, the presence of any!detectable Co-60 inf this sample was not expected and further evaluation of this area iswarranted.

Beneath Basement Floor

Table 5-9 presents radionuclide concentrations in these soil samples. No detectableradionuclides, other than those present in typical background soil, were identified. Pu-242was detectable at the 7.0 to 7.6 m depth, but was very low.

Beneath Beamport Floor

With the exception of slightly elevated concentrations of H-3 (up to 14.5 pCi/g at the0 to 0.3 m depth), there were no detectable radionuclides other than those present inbackground soil. Table 5-10 lists results for these samples.

Note: The plan called for sampling to a depth of 7.6 m; however, refusal occurred at the 6.1m depth.


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TABLE 5-6Radionuclide Concentrations in Background Soil Samples

Concentration (pCi/g) bRadionuclide

Surface Depth Subsurface Depth

Ag-11im <0.09 <0.11

Am-241 <0.08 <0.06

C-14 3.59 +1- 1.98 3.20 +1- 1.77

Cm-242 <0.08 <0.01

Cm-2431244 <0.09 <0.10

Co-57 <0.07 <0.07

Co-60 <0.10 <0.13

Cr-51 <1.14 <1.34

Cs-137 <0.10 <0.14

Eu-152 <0.60 <0.58

Eu-154 <0.31 <0.44

H-3 <3.99 <3.94

1-129 <0.42 <1.13

Mn-54 <0.09 <0.11

Ni-63 <2.18 <2.44

Pu-238 <0.09 <0.03

Pu-239/240 <0.06 <0.03

Pu-241 <3.99 <1.52

Pu-242 0.19 +/-0.11 0.2+/-0.11

Ra-226 a 0.72 +/- 0.20 0.71 +/- 0.23

Sb-124 <0.11 <0.12

Sb-125 <0.26 <0.29

Sn-113 <0.11 <0.14

Total Sr <0.55 <0.49

Tc-99 <0.22 <0.22

Th-232 a 0.5 +/- 0.29 <0.58

U-235 <0.05 <0.56

U-238 <2.25 <2.04

Zn-65 <0.24 <0.32

Gross alpha _ - c

Gross beta rs I _-

a In equilibrium with progeny.

b Total propagated uncertainty at 95 percent confidence level.c Indicates the analysis was not requested.


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TABLE 5-7Radionuclide Concentrations in Soil Samples From Drain Tile Field Area

Concentration (pCi/g) b

Radionuclide4.3 to 4.9 m Depth 5.8 to 6.4 m Depth 7.0 to 7.6 m Depth

Ag-11Om <0.07 <0.09 <0.07

Am-241 -- C -- C <0.03

C-14 C C 45.0 +/- 2.25

Cm-242 -- C -- C <0.05

Cm-243/244 __ C __ C <0.06

Co-57 <0.05 <0.06 <0.05

Co-60 <0.09 <0.12 <0.08

Cr-51 <0.94 <1.02 <0.96

Cs-137 <0.08 <0.09 <0.07

Eu-1 52 <0.50 <0.65 <0.55

Eu-1 54 <0.28 <0.26 <0.22

H-3 <4.20 <4.07 <3.97

1-129 <0.87 <0.87 <0.76

Mn-54 <0.08 <0.09 <0.08

Ni-63 -- C -- C <2.04

Pu-238 __ C -_ C <0.03

Pu-239/240 -- C -- C <0.02

Pu-241 .- c -_ C <1.60

Pu-242 -- -- 0.11 +/- 0.09

Ra-226 a 0.35 +/- 0.13 0.71 +/- 0.41 0.52 +/- 0.11

Sb-124 <0.10 <0.09 <0.09

Sb-125 <0.23 <0.22 <0.20

Sn-113 <0.09 <0.16 <0.09

T o ta l S r -- C ._ C C_ c

Tc-99 -- c c C

Th-232 a <0.40 0.61 +/- 0.28 0.43 +1- 0.16

U-235 <0.39 <0.50 <0.38

U-238 <1.49 <1.58 1.84 +/- 0.87

Zn-65 <0.21 <0.21 <0.17

Gross alpha <2.56 <4.72 -- C

Gross beta <7.26 <7.32 -_ c


b Total propagated uncertainty'at 95 percent confidence level.

6 Indicates the analysis was not requested.


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TABLE 5-8Radionuclide Concentrations in Soil Samples From Source Storage Port Area


Radionuclide3.11 to 4.0 m Depth 5.5 to 6.1 m Depth 7.0 to 7.6 m Depth

Ag-110m <0.07 <0.07 <0.09

Am-241 C -_ c <0.73

C-14 C _C 1.98 +/- 1.10

Cm-242 -- - <0.05

Cm-243/244 -- -- <0.06

Co-57 <0.05 <0.06 <0.07

Co-60 <0.10 <0.10 1.17 +/- 0.15

Cr-51 <1.06 <0.99 <1.22

Cs-137 <0.08 <0.07 <0.10

Eu-152 <0.64 <0.51 <1.35

Eu-1 54 <0.25 <0.31 <0.56

H-3 <3.94 <3.88 <3.56

1-129 <0.85 <0.85 <0.23

Mn-54 <0.09 <0.09 <0.12

Ni-63 - _C <2.24

Pu-238 C __ C <0.01

Pu-239/240 -- C -- C <0.02

Pu-241 C C <1.21

'Pu-242 C -- C <0.12

Ra-226 0.53 +/- 0.15 0.67 +/- 0.15 0.67 +/- 0.18

Sb-124 <0.10 <0.09 <0.12

Sb-125 <0.19 <0.19 <0.27

Sn-113 <0.10 <0.09 <0.12

Total Sr -- C -- C <0.46

Tc-99 -- C -- C <0.21

Th-232 a <0.41 0.42 +/- 0.20 <0.57

U-235 <0.47 <0.46 <0.51

U-238 1.71 +1- 0.87 <1.57 <1.71

Zn-65 <0.20 <0.21 <0.28

Gross alpha <5.14 <7.74 -- C

Gross beta <7.14 <6.80 __ C




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TABLE 5-9 (2 PAGES)Radionuclide Concentrations in Soil Samples From Beneath FNR Basement Floor Area


Radionuclide0 to 0.3 m Depth 0.3 to 1.5 m Depth 1.5 to 3.0 m Depth

Ag-110m <0.11 <0.07 <0.08

Am-241 _ C __ C

C-14 C c C

Cm -242 -- - _ c-

Cm-243/244 __ C C

Co-57 <0.07 <0.06 <0.05

Co-60 <0.14 <0.12 <0.07

Cr-51 <1.26 <0.82 <0.89

Cs-137 <0.14 <0.08 <0.08

Eu-152 <0.98 <0.63 '<0.64

Eu-154 <0.41 <0.24 <0.24

H-3 <4.21 <4.12 <4.10

1-129 <0.81 <0.82 <0.80

Mn-54 <0.13 <0.07 <0.09

Ni-63 _ C __ C _

Pu-238 C C C

Pu-239/240 -- -- --

Pu-241- C c

Pu-242 C C C

Ra-226 a 0.67 +/- 0.21 0.43 +/- 0.14 0.53 +/- 0.14

Sb-124 <0.15 <0.10 <0.09

Sb-125 <0.32 <0.19 <0.21

Sn-113 <0.15 <0.10 <0.10

Total Sr -- c-- _ -- c

Tc-99 -- c-- _c

Th-232 a <0.57 <0.37 0.40 +/- 0.17

U-235 <0.60 <0.44 <0.43

U-238 <1.90 <1.51 <1.49

Zn-65 <0.34 <0.17 <0.18

Gross alpha <11.0 <7.19 <5.93

Gross beta <7.19 <7.33 <7.37a In equilibrium with progeny.

b Total propagated uncertainty at 95 percent confidence level.

c Indicates the analysis was not requested.

FNR - Ford Nuclear Reactor.


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TABLE 5-9 (CONTINUED) (2 PAGES)Radionuclide Concentrations in Soil Samples From Beneath FNR Basement Floor Area


Radionuclide3.0 to 4.6 m depth 4.6 to 6.1 m depth 6.1 to 7.6 m depth

Ag-110m <0.08 <0.71 <0.08

Am-241 -- c-- . <0.62

C-14 __ _c 1.89 +/-1.04

Cm-242 c <0.05

Cm-243/244 _ c __ C <0.05

Co-57 <0.06 <0.53 <0.05

Co-60 <0.12 <0.10 <0.09

Cr-51 <1.08 <1.0 <0.96

Cs-137 <0.09 <0.08 <0.08

Eu-1 52 <0.75 <0.58 <0.52.

Eu-1 54 <0.29 <0.24 <0.22

H-3 <3.92 <3.89 <3.97

1-129 <0.94 <0.85 <0.78

Mn-54 <0.1 <0.09 <0.08

Ni-63 _ _c <1.82

Pu-238 _. _c <0.01

Pu-239/240 -- _C <0.02

Pu-241 C C <1.36

Pu-242 c _ 0.11 +/- 0.09

Ra-226 a 0.49 +/- 0.16 0.52 +/- 0.16 0.53 +/- 0.14

Sb-124 <0.12 <0.08 <0.09

Sb-125 <0.28 <0.19 <0.21

Sn-113 <0.12 <0.10 <0.09

Total Sr __ C c <0.43

Tc-99 _ C C <0.23

Th-232 a <0.47 <0.38 0.63 +/- 0.19

U-235 <0.52 <0.44 <0.44

U-238 <1.68 <1.39 <1.37

Zn-65 <0.2 <0.18 <0.16

Gross alpha <8.91 <7.23 -- C

Gross beta <7.59 <6.81 __ ca In.equilibrium with progeny.


FNR - Ford Nuclear Reactor,,


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TABLE 5-10 (2 PAGES)Radionuclide Concentrations in Soil Samples From Beneath Beamport Floor Area

Concentration (pCilg) b

Radionuclide0 to 0.3 m Depth 1.5 to 3.0 m Depth 3.0 to 4.6 m Depth

Ag-110m <0.16 <0.08 <0.08

Am-241 _ C -_ C __ C

C-14 C C C

C m -242 -- - _ .c

C m -2 4 3 /2 4 4 .. - _ .c

Co-57 <0.08 <0.06 <0.05

Co-60 <0.21 <0.10 <0.10

Cr-51 <1.68 <1.18 <0.97

Cs-137 <0.16 <0.08 <0.08

Eu-152 <1.19 <0.67 <0.51

Eu-154 <0.44 <0.30 <0.24

H-3 14.5 +/- 4.23 11.9 +/- 2.99 4.34 +/- 2.51

1-129 <1.08 <0.96 <0.86

Mn-54 <0.01 <0.09 <0.08

Ni-63 C C C

Pu-238 C C C

C C

P u -2 3 9 /2 4 0 -G ._ c_

P u-24 1 - _ - _ --

Pu-242 C C C

Ra-226 a 0.55 +/- 0.21 0.65 +/- 0.14 0.48 +/- 0.15

Sb-124 <0.01 <0.08 <0.09

Sb-1i25 <0.02 <0.22 <0.21

Sn-113 <0.01 <0.11 <0.09

Total Sr -- c-- --

T c -9 9 -- C _ _ .c

Th-232 a 0.73 +/- 0.45 0.56 +/- 0.24 0.30 +/- 0.16

U-235 <0.78 <0.49 <0.45

U-238 <2.35 <1.62 <1.47

Zn-65 <0.03 <0.23 <0.16

Gross alpha 3.96 +/- 0.54 <4.90 5.57 +/- 4.54

Gross beta <7.76 <7.06 10.9 +/- 7.05In equilibrium with progeny.



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CH2MHILL

TABLE 5-10 (CONTINUED) (2 PAGES)Radionuclide Concentrations in Soil Samples From Beneath Beamport Floor Area.


Radionuclide4.6 to 6.1 m Depth

Ag-110m <0.16

Am-241 <0.11

C-14 3.54

Cm-242 <0.1

Cm-243/244 <0.14

Co-57 <0.05

Co-60 <0.10

Cr-51 <0.97

Cs-137 <0.08

Eu-1 52 <0.57

Eu-1 54 <0.24

H-3 <3.83

1-129 <0.29

Mn-54 <0.08

Ni-63 <2.43

Pu-238 <0.03

Pu-239/240 <0.02

Pu-241 <1.82

Pu-242 0.22 +/-.12

Ra-226 a 0.52 +/-0.12

Sb-124 <0.08

Sb-125 <0.19

Sn-113 <0.09

Total Sr <0.53

Tc-99 <0.22

Th-232 a <0.43

U-235 <0.42

U-238 <1.43

Zn-65 <0.20

Gross alpha -- c

Gross beta __ cIn equilibrium with progeny.

b Total propagated uncertainty at 95 percent confidence level.

c Indicates analysis not performed.


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FNR Characterization Package Workbook SP-018 Soil Sampling.will specify MDCs of less than 10% of the...

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