ML12095A387

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Fnr Characterization Package Workbook SP-018 Soil Sampling
ML12095A387
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Site: University of Michigan
Issue date: 02/14/2012
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Occupational Safety & Environmental Health University of Michigan
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NRC/FSME
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FNR Characterization Package Workbook SP-018 Soil Sampling Master Copy Bartlett Services, Inc 2007

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

Description:

FNR Surface and Subsurface Soil.

SURVEY PACKAGE COVER SHEET Survey Type: Characterization Survey, Final Status Survey Survey Objectives:

This package addresses soil in the vicinity of the FNR and beneath the FNR building footprint. This includes soil beneath the FNR reactor foundation, the basement and adjacent to 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 Pool Foundation, adjacent to the FNR Foundation and at any other locations potentially impacted by leakage of contaminated water from the FNR.
2. Confirm that soil activity concentrations due to neutron activation in the vicinity of Storage Port No. 1 are below soil screening-level DCGLs.
3. Alternatively, if soil is found to contain concentrations of licensed radioactive materials above the screening level DCGLs, identify the extent of the contamination to guide remediation.

Package Contents: Attachments

" Document Change Control Form 1. Photographs

" Survey Unit Walkdown Notes 2. Survey Design and Support Maps

" Survey Design Worksheet 3. Blank Survey Forms

  • Survey & Sampling Instructions 4. Completed Forms

" Sample Chain Of Custody Forms 5. Survey Timeline

" References 6. JHA & Pre-Job hazard briefing attendance sheets

7. UM Counting Lab Reports
8. Vendor Lab Lab Analysis Reports
9. Summary Data Reports
10. Reference Material
11. QC Checklist
12. Superseded Information Survey Package Implementation:

Rock P. Neveau Radiological Engineer Printed Name Signature Date Bruce J. Mann Health Physics Supervisor Printed Signature Date Name SignatureDate Implementation Comments: The collection of soil samples may be accomplished by a combination of hand sampling and push tool (Geoprobe-type) techniques. This may be performed in more than one sampling campaign. This will be determined by accessibility to the sub-floor areas in the FNR and Project schedule and support resource constraints.

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Package Log No: FNR-SP-018 I Survey Area: 12 1 Survey Units: 12-01, 12-02 Survey Unit/Area

Description:

FNR Surface and Subsurface Soil.

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, 12-02 Survey 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 +

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[Survey PackageUnit/Area

Description:

FNR Surface Log No: FNR-SP-018 andArea:

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

Description:

Surface and subsurface soil.

Walkdown Notes:

1. July 18-07, C. Becker and B. Mann; discussion, walkdown and review of soil sampling history and objectives for the Decommissioning Phase soil sampling:
a. The soil in the vicinity of the sub-foundation tile drain was sampled in the 2003 Characterization survey and the results showed minimal activity.
b. Similarly, soil external to and adjacent to the FNR was investigated in the 2003 Characterization survey and no detectable licensed radioactive materials were measured.
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 drain ii. 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, the sump should be drained and inspected to identify leak paths. Soil sampling will be influenced by the results.

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

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

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

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

End of Walkdown Notes SP-0 18_PkgMain_FormsRev2 Page 4 of 12 11/12/2007

Package Log No: FNR-SP-018 1 Survey Area: 12 1 Survey Units: 12-01, 12-02 Survey Unit/Area

Description:

FNR Surface and Subsurface Soil.

Survey Design Worksheet

Description:

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 Port Floor 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 drain runs below grade around the FNR foundation, exterior to the building and around the Pool Foundation in the unexcavated sub-floor soil on the west side of the Beam Port Floor, interior to the 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 as impacted is that approximately 7500 gallons of Pool Water back-flowed into the tile drain in 1993. 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 collected from two locations beneath the building. All locations were sampled using a push driven Geoprobe closed barrel core sampling apparatus. The sampler was driven to a depth of 7.6 m (in all except one location, beneath the Beam Port Floor where refusal occurred at 6.1 m) The soil sampling tubes were divided into sub-samples (aliquots) of soil in depth increments. The samples were analyzed by Gamma Spectroscopy and for H-3 and C-14. For the most part the results were negative (concentrations < MDC). for all the sample aliquots. However, in several sample locations detectable activity concentrations were reported, mostly in sub-surface soil. These results are summarized in Table 1 below.

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

Table 1 Summary of 2003 Characterization Survey Soil Sample Results Sample Nuclides Detected Concentration Depth Increment Notes Location (pCi/g)

Foundation tile C-14 45 7.0 - 7.6 m Tile drain is about drain 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 are Ports from 3 to 4 m below grade.

Beneath Basement None Near center of S floor half below ceiling hatch.

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

NE SP-018 PkgMainFormsRev2 Page 5 of 12 11/12/2007

Package Log No: FNR-SP-018 I Survey Area: 12 I Survey Units: 12-01, 12-02 Survey 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 the FNR and PML, cracks and voids in sumps and floor drains in the FNR and back-flow of Pool water into the FNR foundation tile drain.
2. Locations with potentially impacted soil identified for evaluation under this survey package are:
a. Adjacent to the FNR tile drain on the east side of the FNR b.. Adjacent to Storage Ports 1-3 Note: It is assumed that the Storage Ports will be removed. Samples of soil surrounding Ports 1, 2 and 3 will be sampled during the soil excavation.
c. Beneath and adjacent to the Pool Foundation
d. Beneath and adjacent to Hot and Cold Sumps, Ion Exchange Pits and Basement Drains
e. 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 will be used to establish analytical detection limits (MDCs) for evaluation of soil sample results. Soil samples will be analyzed for radionuclides of concern and analysis requests will specify MDCs of less than 10% of the DCGL values. Table 2 below lists the screening level DCGLs and the MDCs to be requested.
4. Soil sampled from 0-15 cm from the surface outside the FNR will be evaluated against NRC 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 and from locations beneath the FNR will be evaluated against interim criteria for sub-surface soil. (to be developed).

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Package Log No: FNR-SP-018 T Survey Area: 12 F Survey Units: 12-01, 12-02 Survey Unit/Area

Description:

FNR Surface and Subsurface Soil.

Design Assumptions, Cont'd.:

Table 2, Single Radionuclide DCGLs and Analytical Procedure MDCs Nuclide 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 0.5 U-235 + Daughters 3.2 0.3 Uranium-238 WU-238) 4.47E+08 14 1.4 1 U-238 + Daughters 7.2 0.7 Plutonium-241 14.4 72 7.2 5 Plutonium-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 5.19 for building surface contamination and Table 6.91 for surface soil).
2. The requested minimum detectable concentrations are a'priori target values selected to ensure that requesled MDCs are less than 10% of the most restrictive DCGL, i. e., the DCGL for surface soil.
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. Radionuclides with half-lives < one y are excluded (except for Ag- 110, which has been measured in samples as recently as 2006).

4. These radionuclides have been reported in at least one sample collected as part of the 2003 FNR Characterization 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, 12-02 Survey 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 FNR
2. Storage Ports 1-3 W of the FNR
3. Adjacent to former tile drain line to Cold Sump
4. Beneath the Hot and Cold Sumps
5. Beneath the former Ion exchange pits
6. Beneath Basement floor drains
7. Beneath the Pool Foundation
8. 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 #1 above) will be collected using a Geoprobe unit. All other samples are assumed to be collected using hand tools and will have an initial collection depth of 15 cm. If additional sampling depths are 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-tool technology (Geoprobe or equivalent). The requested sample core-length is 3 meters. Note that the total core depth required (from the surface at grade) is approximately 7.6 meters. Soil samples collected at the Storage Ports and designated locations beneath the FNR Beam Port and Basement floors will be collected using either split spoon or core barrel sampling devices with cores of one and 1/2 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 found within the Sampling Zones. Reference elevations (in ft. above sea level) and soilsampling zone thicknesses in the principal areas of interest are provided in Table 3 below.

Table 3, Sampling Locations and Reference Elevations Location Elevation Description Top Surface of Soil Sampling Zone E 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. are Ports 827 ft 9 in. to 833 ft 4

_1/2in.

Pool Foundation 819 ft. - 1 2 in. 819 ft 1 1/2 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. 12 side - unexcavated in thick SP-0 18_PkgMain_FormsRev2 Page 8 of 12 11/12/2007

Package Log No: FNR-SP-018 I Survey Area: 12 1 Survey Units: 12-01, 12-02 Survey Unit/Area

Description:

FNR Surface and Subsurface Soil.

B. Access and Support Requirements

1. 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 resulting from removal of floor concrete:
a. Where no access directly above sample locations is available, a six-inch core will be drilled 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 former Pool abutted the PML, two vertical six-inch cores will be drilled through the Pool foundation.
5. Portable lighting may be required to provide sufficient illumination for sampling activities beneath the FNR.

C. Precautions and Limitations

1. 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 to break 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 FNR
a. 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 of port 3. If additional sample depths are required, collect the soil from each tube in increments of 30 cm into individual samples.

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Package Log No: FNR-SP-018 I Survey Area: 12 I Survey Units: 12-01, 12-02 Survey 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 1/2 ft. from the east wall and one and 1/2 ft. from the north wall inside 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 are required, collect the soil from the tube in increments of 30 cm into individual samples.
4. Beneath the Hot and Cold Sumps
a. 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 increments of 30 cm into individual samples.

5. Beneath the former Ion exchange pits
a. 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 increments of 30 cm into individual samples.
6. Beneath Basement floor drains
a. 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 in increments of 30 cm into individual samples.

7. Beneath the Pool Foundation
a. 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 the location of the east and west junctures of the former pool bottom with the former pool inner walls.
b. Drive a sampling tube to approximately 15 cm depth in the soil beneath each core location. If additional sampling depths are required, collect the soil from the tubes in increments of 30 cm into individual samples.
c. Collect samples at two locations just north of the Pool foundation at approximately 10 o'clock and 2 o'clock viewed from above looking north. Access may be gained from concrete removal to remove drains running E-W located just north of the Pool Foundation.

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Package Log No: FNR-SP-018 ] Survey Area: 12 1 Survey Units: 12-01, 12-02 Survey Unit/Area

Description:

FNR Surface and Subsurface Soil.

d. Drive a sampling tube to approximately 15 cm depth in the soil beneath each core location. If additional sampling depths are required, collect the soil from the tubes in increments of 30 cm into individual samples.
8. Adjacent to floor drains under the Beam Port Floor - west side
a. 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 estimated that between three and six locations will be sampled.
b. At each designated location drive a sampling tube to 15 cm depth. If additional sampling depths are required, collect the soil from each tube in increments of 30 cm into individual samples.

Characterization Package References

1. U of Mich References
a. University of Michigan, FNR DecommissioningPlan, Rev 1, 2006.
b. University of Michigan, Ford Nuclear Reactor, HistoricalSite Assessment, January 2003.
c. CH2MHill, Characterizationof the FordReactor Facility,June .2004.
2. Technical References
a. Ford Nuclear Reactor Decommissioning Project Memorandum, Requested Minimum Detectable Concentrationfrom Vendor laboratories,FNR-RP-013, 14-Nov-06
b. Oak Ridge Institute for Science and Education, Survey Procedures Manual, Independent Environmental Assessment and Verification Program, Section 8.9 Surface Soil Samplingfor ChemicalAnalysis Rev 3, August 7, 2006.
c. Oak Ridge Institute for Science and Education, Survey Procedures Manual, Independent Environmental Assessment and Verification Program, Section 8.10 Subsurface Soil Samplingfor Chemical Analysis Rev 3, August 7, 2006.
3. Regulatory Documents
a. US Nuclear Regulatory Commission, NMSS DecommissioningStandardReview Plan, NUREG 1727, Sept. 2000
b. US Nuclear Regulatory Commission ConsolidatedNMSS Decommissioning Guidance, Volume 2, Characterization,Survey and Determinationof Radiological Criteria,NUREG-1757, Final September 2003.

SP-0 18PkgMain_FormsRev2 Page I I of 12 11/12/2007

Package Log No: FNR-SP-018 Survey Area: 12 1 Survey Units: 12-01, 12-02 Survey Unit/Area

Description:

FNR Surface and Subsurface Soil.

4. Drawings:

Drawing No. Description Dwg No. A-i, Smyth, Basement Plan Hinchman & Grylls, 1/24/55 Dwg No. A-2, Smyth, Reactor Building, Basement Plan and Schedules (Door and Hinchman & Grylls, 1/24/55 Finish)

Dwg No. A-3, Smyth, Reactor Building, First and Second Floor Hinchman & Grylls, 1/24/55 Dwg No. A-6, Smyth, Reactor Building Sections Hinchman & Grylls, 1/24/55 Dwg No. S-1, Smyth, Reactor Building, Basement, Foundation and First Floor Plans Hinchman & Grylls, 1/24/55 Dwg No. S-7, Smyth, Reactor Building Sections and Details Hinchman & Grylls, 1/24/55 Dwg No. M-7, Smyth, Reactor Building Process Piping, Basement Floor (shows Hinchman & Grylls, 1/24/55 Sump elevations)

Dwg No. M-17, Smyth, Reactor Building Heat Exchanger Room Hinchman & Grylls, 1/24/55 _

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CH2MHILL 1%

Characterization of the Ford Nuclear Reactor Facility Final Revision 0 Prepared for University 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 ................... 1-1 2.0 Site Description ........................................................................................................................ 2-1 3.0 Contaminants of Concern ....................................................................................................... 3-1 4.0 Survey Approach ...................................................................................................................... 4-1 4.1 General ............................................................ I.............................................................. 4-1 4.2 Instrumentation ............................................................................................................. 4-1 4.3 Survey Activities ........................................................................................................... 4-2 4.3.1 Preliminary Survey ......................................................................................... 4-2 4.3.2 Characterization Survey ................................................................................. 4-4 4.4 Sample Analysis .......................................................................................................... 4-15 4.5 Quality Control ........................................................................................................... 4-15 5.0 Survey Results ........................................................................................................................... 5-1 5.1 Preliminary Survey ....................................................................................................... 5-1 5.1.1 Backgrounds ..................................................................................................... 5-1 5.1.2 Scanning ............................................................................................................ 5-2 5.1.3 Surface Activity M easurements ..................................................................... 5-2 5.2 Characterization Surveys ............................................................................................. 5-6 5.2.1 Scanning ............................................................................................................ 5-6 5.2.2 Surface Activity M easurements ..................................................................... 5-6 5.2.3 Sample Results ................................................................................................. 5-9 5.2.4 In Situ Gamm a Spectra 5-24 5...........................

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

CH2MHILL Tables Table 3-1 Potential FNR Contaminants of Concern .................................................................. 3-1 Table 3-2 Acceptable License Termination Screening Values of Common Radionuclides for Structure Surfaces ................................................................................................... 3-3 Table 3-3 Acceptable License Termination Screening Values of Common Radionuclides for Surface Soil .......................................................................................................... 3-4 Table 4-1 Instruments Used for Characterization Surveys ...................... 4-2 Table 4-2 Sampling Locations ................................................................................................... 4-12 Table 5-1 Instrument Background Levels (Shutdown Mode) ................................................. 5-1 Table 5-2 Instrument Background Levels (Operating Mode) .................................................. 5-1 Table 5-3 Summary of Surface Beta Activity Measurements .................... 5-2 Table 5-4 Surfaces with Beta Activity Exceeding Interim Guidelines .................................... 5-3 Table 5-5 Summary of Surface Activity Measurement Results ............................................... 5-7 Table 5-5a Tritium Concentrations in Smears ............................................................................. 5-8 Table 5-6 Radionuclide Concentrations in Background Soil Samples ................................. 5-10 Table 5-7 Radionuclide Concentrations in Soil Samples From Drain Tile Field Area ....... 5-11 Table 5-8 Radionuclide Concentrations in Soil Samples From Source Storage P ort Area  :......... 5-12 5.........................

Table 5-9 Radionuclide Concentrations in Soil Samples From Beneath FNR Basement Floor Area ..................................................................................................................... 5-13 Table 5-10 Radionuclide Concentrations in Soil Samples From Beneath Beamport Floor Area.......................................................... ........................ ...5-15 Table 5-11 Radionuclide Concentrations in Background Concrete Samples ........................ 5-18 Table 5-12 Radionuclide Concentrations in Concrete Samples ............................................... 5-19 Table 5-13 Radionuclide Concentrations in Samples From Sanitary Sewer Locations ........ 5-21 Table 5-14 Radionuclide Concentrations in Samples From Contaminated Drains .............. 5-23 Table 5-15 Radionuclide Concentrations in Samples From Sump Locations ........................ 5-26 Table 5-16 Chemical Concentrations in Samples From Sump Locations ............................... 5-27 Table 5-17 Radionuclide Concentrations in Miscellaneous Samples of Anomalous M aterials ................................................................................ ................ 5-28 Table 5-18 Radionuclide Concentrations in Rinsate and Water Samples ........... .................. 5-29 Table 5-19 Radionuclide Concentrations in Ground Water Sample ...................................... 5-31 Appendices A Instrument Calibration and Performance Test Information ...................................... A-1 B List of Procedures Used for Characterization ................................................................ B-1 C Field Survey Data Preliminary Survey ......................................................................... C-1 D Characterization Plan ........................................................................................................ D-1 E Work Package for Sample Collection and Survey Measurements .................................. E-1 F Field Survey Data Characterization Survey ............................. F-1 G In Situ Gamma Spectra ...................................................................................................... G-1 H Chemical Laboratory Data ................................................................................................ H-1 I Radiological Analytical Data .............................................................................................. I-1 Characterization Ford Nuclear Reactor Facility

CH2MHILL Executive Summary The University of Michigan (UM) has ceased operation of the 2-megawatt (MW) Ford Nuclear Reactor (FNR) at its North Campus, and plans to follow with decontamination and

-decommissioning (D & D) of the facility and termination of the Nuclear Regulatory Commission (NRC) license. The UM contracted with CH2M HILL to assist in characterizing the facility in preparation for D & D. The purposes of the characterization were the following:

  • To identify principal radiological contaminants

" To identify those reactor and facility systems and surfaces that are likely to require 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 establishing decommissioning guideline levels for structures and soil; plan environmental, safety, and health (ES & H) actions; plan and schedule D & D activities; and estimate the nature and quantity of project waste.

Because the reactor was still fueled and operational at the time of the surveys, many systems and locations could not be safely accessed for survey or sample. Continuing characterization of these locations will be conducted following permanent shutdown and defueling and after impacted 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) by CH2M HILL, from which information such as the facility source term and operational history for the facility were gained. Based on the information obtained from the site investigation, CH2M HILL developed plans detailing the characterization survey, such as Characterization Plan; Quality Assurance Project Plan; Environmental, Safety, axgd Health Plan; Radiation Protection Plan; and Sample Collection and Survey Measurement Work Package. Plans were developed following the data quality objectives (DQO) process as described in NUREG-1575 (Multi-Agency Radiation Survey and Site Investigation Manual

[MARSSIM]). The NRC default screening criteria were chosen as a conservative basis for comparison of characterization results; a beta activity level of 13,800 disintegrations per minute (dpm)/100 square centimeters (cm 2)was selected as an interim guideline, based on a 50 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 radiological measurements and sampling. A preliminary survey in November 2002 and a follow-on characterization survey in April 2003 were conducted. The measurements and samples Characterization ES-1 Ford Nuclear Reactor Facility

CH2MHILL collected for the radiological characterization survey consisted of surface gamma and beta scans; direct alpha measurements; direct beta measurements; smear samples for removable alpha and beta contamination; smear samples for removable tritium contamination; exposure rate measurements; and soil, concrete, sludge, water, and miscellaneous anomalous samples for laboratory analysis. Analyses for potential hazardous material constituents also were performed on sludge from sumps.

Survey plans were developed and measurements performed for surface, structures, and environs backgrounds. Direct beta background values for naturally occurring radioactive material (NORM) in brick, tile, cinder block, and concrete were determined and applied to the direct beta measurements collected at the FNR facility surfaces and structures to equate the reported beta activity to net results per 100 cm 2. Also, survey measurements and samples collected from the environs were analyzed to determine background values for NORM and the contribution from activity from weapons testing fallout in soil, concrete, and water of the environs. These values are stated in the report, but, conservatively, were not applied to the results.

The findings of the characterization were that the FNR facility and site, for the most part, are not radiologically contaminated. However, the following areas and locations at the FNR facility and site will require decontamination before the site is suitable for release from the NRC 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 1st Floor, and waste handling systems on the Basement level
3. The bioshield wall on the west and north sides, where pool water appears to be leaking through the concrete
4. Ventilation systems for the neutron activation equipment, beamports, and source storage ports
5. To be determined - additional systems and locations that could not be addressed while the facility was still in operation.

Other locations had associated measurements that were potentially influenced by "ambient direct radiation levels or had background levels that were too high to allow meaningful characterization. These surfaces will be reevaluated after permanent shutdown and removal of components with high radiation levels.

The dominant radionudides present are Co-60 and Cs-137 with smaller concentrations of multiple activation and fission product radionuclides. There is no uniform radionuclide mix, 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 licensed activities.

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

Characterization ES-2 Ford 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 Characterization ES-3 Ford Nuclear Reactor Facility

CH2MHILL 1.0 Introduction The Ford Nuclear Reactor (FNR) facility at the University of Michigan (UM) has operated since 1957 under Atomic Energy Commission/Nuclear Regulatory Commission (AEC/NRC) License No. R-28 in support of a wide variety of education and research programs. In anticipation of ceasing reactor operation, the UM contracted with CH2M HILL to characterize the facility. The purpose of the characterization is to define the nature, magnitude, and extent of radioactive and radioactively hazardous contamination in the facility, for use in further decommissioning planning.

The characterization began with a historic site assessment (HSA) by CH2M HILL, followed in November 2002 by a preliminary survey of readily accessible areas of the facility by Safety and Ecology Corporation (SEC), teaming partner with CH2M HILL for the FNR project. 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 characterization was conducted by CH2M HILL and SEC in April 2003. The primary focus of this characterization was to determine the extent of contamination and activation of certain structural 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 and characterization survey efforts and reports their results.

Characterization I-1 Ford Nuclear Reactor Facility

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CH2MHILL and equipment inaccessible with the floor monitor were scanned using a Model 43-89 dual alpha/beta scintillation detector; coverage was 50 to 100 percent.

Scans were performed by maintaining the detector as close as practicable to the surface and advancing the detector at a rate of less than I detector-width/sec.

Audible signals were monitored and locations of discernible elevated count rates were noted for further investigation.

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

4.3.2.6 Smears for removable alpha and beta activity were performed at locations of direct measurements (Section 4.3.2.5) by wiping a surface area of approximately 100 cm 2 with a dry cloth filter, using moderate pressure. Smears for removable H-3 activity also were obtained at selected locations considered to have a potential for such contamination; these smears were placed immediately into pre-filled liquid scintillation vials to prevent loss of contaminant as a result of evaporation.

4.3.2.7 Locations were selected for sampling to determine the nature and extent of contaminants on various facility surfaces and systems to identify possible impacts on the environment of FNR. Figures 4-1 through 4-5 and Table 4-2 indicate these locations. Because the reactor was fueled and operational at the time of this survey, intrusive sampling was not conducted at some locations proposed in the Characterization Plan (see Appendix D). At other proposed sampling 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 at varying depths using a driven closed-barrel sampler at the following locations:

Drain Tile-Field Outside-FNR (East) 4.3 to 4.9 m depth 5.8 to 6.4 m depth 7.0 to 7.6 m depth Adjacent to Source Storage Ports (West) 3.4 to 4.0 m depth 5.5 to 6.1 m depth 7.0 to 7.6 m depth Characterization 4-5 Ford Nuclear Reactor Facility

CH2MHILL Beneath Basement Floor 0 to 0.3 m beneath floor 0.3 to 1.5 m beneath floor 1.5 to 3.0 m beneath floor 3.0 to 4.6 m beneath floor 4.6 to 6.1 m beneath floor 6.1 to 7.6 m beneath floor Beneath Beamport Floor (1st Floor) 0 to 0.3 m beneath floor 1.5 to 3.0 m beneath floor 3.0 to 4.6 m beneath floor 4.6 to 6.1 m beneath floor Characterization 4-6 Ford Nuclear Reactor Facility

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CH2MHILL FIGURE 4-2 Ford Nuclear Reactor Basement Indicating Sampling Locations Characterization 4-8 Ford Nuclear Reactor Facility

CH2MHILL FIGURE 4-3 Ford Nuclear Reactor 1st Floor Indicating Sampling Locations Characterization 4-9 Ford Nuclear Reactor Facility

CH2MHILL FIGURE 4-4 Ford Nuclear Reactor 3rd Floor Indicating Sampling Locations II Stair #3 0

3110 1F Control Room 3108 Office 3109 False Floor -I-i Stair #2 own 1-v- Dow I I I I I I I Li Corridor 3101 Stair #1 Lab 'A' Lab 'B' Lab 'C' 3102 3"103 3104 A

Characterization 4-10 Ford Nuclear Reactor Facility

CH2MHILL FIGURE 4-5 Ford Nuclear Reactor 4th Floor Indicating Sampling Locations Characterization 4-11 Ford Nuclear Reactor Facility

CH2MHILL TABLE 4-2 (2 PAGES)

Sampling Locations Sample Description Sample Radiochemical Chemical Comments Locationa Type Analysis Analysis 1 East side FNR near drain tile Soil Tritium, GEA, GA, GB, N/A field 10 CFR Part 61 2 West side FNR near source Soil Tritium GEA, GA, GB, N/A storage ports 10 CFR Part 61 3 Beneath FNR (Basement Soil Tritium GEA, GA, GB, N/A near reactor pool and holding 10 CFR Part 61 tank pit) 4 Beneath FNR (1st Floor Soil Tritium GEA, GA, GB, N/A unexcavated 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/A exchange 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/A highest level of fixed contamination) 9 1st Floor "hot spot" Concrete GEA, GA, GB N/A between Beamports J and I 10 3rd Floor ceiling Concrete GEA, GA, GB N/A (directly above vertical beam 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 obtained concrete 13 Heavy water addition Concrete Tritium N/A station-reactor pool operating 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/A FNR) 17 Sanitary sewer (where FNR Sludge Tritium, GEA, GA, GB N/A line joins trunk line) _

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

'19 Sanitary sewer (end of trunk Sludge Tritium, GEA, GA, GB N/A line) 20 Sanitary sewer (background - Sludge 10 CFR Part 61 N/A upstream 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 Characterization 4-12 Ford Nuclear Reactor Facility

CH2MHILL TABLE 4-2 (2 PAGES)

Sampling Locations Sample Description Sample Radiochemical Chemical Comments Locationa Type Analysis Analysis 23 Composite - ion exchange Resin Tritium, GEA, GA, GB IPC metals, Not Obtained resin 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 Obtained coupon 26b Reactor exhaust system Metal GEA, GA, GB N/A Not Obtained coupon 27 1 Floor - source storage Metal GEA, GA, GB N/A Not Obtained ports coupon 28 Crane - reactor pool overhead Oil/ GEA, GA, GB IPC metals, Not Obtained crane 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 Obtained coupon 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/A a 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 or activation.

0 Basement near resin column room S Basement near liquid transfer system 0 Beamport floor trench between ports I and J S Beamport floor trench at north bioshield wall 0 Reactor level floor near heavy water system Ceiling of 3rd Floor above vertical beam tube Samples of approximately 50 to 200 grams were obtained by clipping the concrete 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 to the Cooley Building.

Characterization 4-13 Ford Nuclear Reactor Facility

CH2MHILL 4.3.2.12 Sludge was obtained from the sanitary sewer system servicing the FNR at the following 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, and Basement levels and from the Basement hot/cold sump and Beamport Floor Sump.

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

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

4.3.2.16 In situ gamma spectra were collected at the following locations on the Beamport level 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. Soil samples of 500 to 1,000 grams were obtained at varying depths. A monitoring well was established and a ground water sample was collected. The following locations indicate the depths of the samples collected:

Monitoring Well South of PML 0 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 were collected to support further analysis if the ground water sample analysis warranted such an investigation.

Characterization 4-14 Ford Nuclear Reactor Facility

CiHI21HILL 5.2.3 Sample Results 5.2.3.1 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 were identified at detectable levels. The C-14, Ra-226, and Th-232 concentrations were consistent with typical soils. The Pu-2421evel was very low (less than 0.2 picocurie/ gram [pCi/g]) and the source of this nuclide is not known.

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

Source Storage Port Area Concentrations, presented in Table 5-8, are consistent with background levels or are less than the method detection sensitivity. One exception is the Co-60 concentration of 1.17 pCi/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 is warranted.

Beneath Basement Floor Table 5-9 presents radionuclide concentrations in these soil samples. No detectable radionuclides, other than those present in typical background soil, were identified. Pu-242 was 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 the 0 to 0.3 m depth), there were no detectable radionuclides other than those present in background 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 6.1 m depth.

Characterization 5-9 Ford Nuclear Reactor Facility

CH2MHILL TABLE 5-6 Radionuclide Concentrations in Background Soil Samples Concentration (pCi/g) b Radionuclide 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 rs Ibeta _-

a In equilibrium with progeny.

b Total propagated uncertainty at 95 percent confidence level.

c Indicates the analysis was not requested.

Characterization 5-10 Ford Nuclear Reactor Facility

CH2MHILL TABLE 5-7 Radionuclide Concentrations in Soil Samples From Drain Tile Field Area Concentration (pCi/g) b Radionuclide 4.3 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 ota 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 a In equilibrium with progeny.

b Total propagated uncertainty'at 95 percent confidence level.

6 Indicates the analysis was not requested.

Characterization 5-11 Ford Nuclear Reactor Facility

CH2MHILL TABLE 5-8 Radionuclide Concentrations in Soil Samples From Source Storage Port Area Concentration (pCi/g) b Radionuclide 3.11 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

<5.14 <7.74 -- C Gross alpha Gross beta <7.14 <6.80 __C a In equilibrium with progeny.

b Total propagated uncertainty at 95 percent confidence level.

c Indicates the analysis was not requested.

Characterization 5-12 Ford Nuclear Reactor Facility

CH2MHILL TABLE 5-9 (2 PAGES)

Radionuclide Concentrations in Soil Samples From Beneath FNR Basement Floor Area Concentration (pCi/g) b Radionuclide 0 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 <7.37 a In equilibrium with progeny.

b Total propagated uncertainty at 95 percent confidence level.

c Indicates the analysis was not requested.

FNR - Ford Nuclear Reactor.

Characterization 5-13 Ford Nuclear Reactor Facility

CH2MHILL TABLE 5-9 (CONTINUED) (2 PAGES)

Radionuclide Concentrations in Soil Samples From Beneath FNR Basement Floor Area Concentration (pCi/g) b Radionuclide 3.0 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 __c a In.equilibrium with progeny.

b Total propagated uncertainty at 95 percent confidence level.

c Indicates the analysis was not requested.

FNR - Ford Nuclear Reactor,,

Characterization 5-14 Ford Nuclear Reactor Facility

CH2MHILL TABLE 5-10 (2 PAGES)

Radionuclide Concentrations in Soil Samples From Beneath Beamport Floor Area Concentration (pCilg) b Radionuclide 0 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 C C Ni-63 C C C Pu-238 C Pu -2 39 /2 4 0 -G C

._C c_

P u-24 1 - _ - _ --

C C C Pu-242 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

-- c-- --

Total Sr Tc - 99 -- 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 +/- 7.05 In equilibrium with progeny.

b Total propagated uncertainty at 95 percent confidence level.

c Indicates the analysis was not requested.

Characterization 5-15 Ford Nuclear Reactor Facility

CH2MHILL TABLE 5-10 (CONTINUED) (2 PAGES)

Radionuclide Concentrations in Soil Samples From Beneath Beamport Floor Area.

b Concentration (pCi/g)

Radionuclide 4.6 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 __c In equilibrium with progeny.

b Total propagated uncertainty at 95 percent confidence level.

c Indicates analysis not performed.

Characterization 5-16 Ford Nuclear Reactor Facility

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