ML12065A334

Plum Brook Reactor Facility Final Status Survey Report Attachment 16, Revision 0

ML12065A334
Person / Time
Site:	Plum Brook
Issue date:	02/23/2012
From:	Mann B US National Aeronautics & Space Admin (NASA)
To:	NRC/FSME
References
Download: ML12065A334 (159)

Text

Plum Brook Reactor Facility Final Status Survey Report Attachment 16 Revision 0 Open Land Areas within Restricted Area and Outside Buffer Area

FINAL STATUS SURVEY REPORT ROUTING AND APPROVAL SHEET Document

Title:

Final Status Survey Report, Attachment 16 Open Land Areas within Restricted Area and Outside Buffer Areas Revision Number: 0 ROUTING DATE Prepared By B. Mann 2/23/12 Prepared By NIA Independent Technical Reviewer R. Case 2/23/12 Other Reviewer, QA Manager J. Thomas 2/23/12 Other Reviewer NIA FSS/Characterization Manager W. Stoner 2/23/ 12 NASA Project Radiation Safety Officer W. Stoner 2/23/12 11

NASA PBRF DECOMMISSIONING PROJECT CHANGE/CANCELLATION RECORD DOCUMENT TITLE: Final DOCUMENT NO: NA REVISION NO: 0 Status Survey Report, Attachment 16, Open Land Areas within Restricted Area and Outside Buffer Area Revision 0: Initial issue of Report Form AD-01/3 iii Rev 1

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 LIST OF EFFECTIVE PAGES DOCUMENT NO: NA REVISION NO: 0 Page No. Revision Level Page No. Revision Level Page No. Revision Level Cover Page 0 Routing & Approval Sheet 0 Change/Cancellation Record 0 LOEP 0 TOC 0 List of Tables & List 0

of Figures List of Acronyms &

0 Symbols, 3 pages Text, 34 pages 0 Appendix A, 0

26 pages Appendix B, 0

62 pages Appendix C, 0

28 pages Form AD-01/5 Rev 2 iv

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 TABLE OF CONTENTS 1.0 Introduction .................................................................................................................... 1 2.0 PBRF Site Description and History .............................................................................. 2 2.1 PBRF Site Description.................................................................................................. 2 2.2 History of PBRF Construction and Operation .............................................................. 3 2.3 Site Geology and Soil Description ............................................................................... 5 2.4 Final Configuration and Scope of FSS ......................................................................... 6 3.0 Operations with Radioactive Materials........................................................................ 6 3.1 Startup and Operations ................................................................................................. 7 3.2 Disposition of Materials in the Post-Shutdown Period ................................................ 8 3.4 Site Characterization..................................................................................................... 8 3.5 Decommissioning ....................................................................................................... 11 4.0 Survey Design and Implementation ........................................................................... 16 4.1 FSS Plan Requirements .............................................................................................. 16 4.2 Area Classification and Survey Unit Breakdown ....................................................... 18 4.3 Number of Samples .................................................................................................... 20 4.4 Instrumentation and Measurement Sensitivity ........................................................... 23 5.0 Survey Results .............................................................................................................. 25 5.1 Scan Surveys............................................................................................................... 25 5.2 Surface Soil Sample Results ....................................................................................... 27 5.3 Subsurface Soil ........................................................................................................... 30 5.4 QC Sample Results ..................................................................................................... 30 5.5 ALARA Evaluation .................................................................................................... 30 5.6 Comparison with EPA Trigger Levels ....................................................................... 31 5.7 Conclusions ................................................................................................................ 32 6.0 References ..................................................................................................................... 33 7.0 Appendices .................................................................................................................... 34 Appendix A - Exhibits Appendix B - Survey Unit Maps and Tables Showing Measurement Locations Appendix C - Soil Sample Results v

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 LIST OF TABLES Table 1, Spill Events Covered in Unusual Incident Reports (1960-1973) ..................................... 7 Table 2, Summary of 2004 Soil Characterization Survey .............................................................. 9 Table 3, Spill Area Summary........................................................................................................ 10 Table 4, Principal Radionuclides and Activity Fractions for Site Soils ....................................... 16 Table 5, FSS Plan Single Radionuclide DCGL Values for Soil ................................................... 17 Table 6, Surrogate DCGLs for OLA Soil FSS Scan Survey ........................................................ 17 Table 7, Class-Based Survey Scan Coverage and Action Level Requirements ........................... 18 Table 8, Open Land Area Survey Units for FSS .......................................................................... 18 Table 9, Survey Design Summary ................................................................................................ 21 Table 10, Sensitivity Analysis for FSS Design ............................................................................. 22 Table 11, Typical Detection Sensitivities of Field Instruments used for OLA Soil Scans ........... 24 Table 12, Scan Survey Results...................................................................................................... 25 Table 13, Systematic Sample Results for the OLA ...................................................................... 28 Table 14, Summary of Individual OLA Sample Results .............................................................. 29 Table 15, NRC Soil Screening Level ALARA Comparison ........................................................ 31 Table 16, Comparison of Soil Sample Results with EPA Trigger Levels .................................... 32 LIST OF FIGURES Figure 1, PBRF Site Map Showing the Facility Layout and Open Land Area Survey Units ......... 4 Figure 2, PBRF Site Map Showing Areas Where Soil Was Remediated ..................................... 15 vi

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 LIST OF ACRONYMS & SYMBOLS alpha; denotes alpha radiation, also type I error probability in hypothesis testing AEC Atomic Energy Commission ALARA As Low As Reasonably Achievable ATS Assembly Test Storage, Building 1121 beta; denotes beta radiation, also type II error probability in hypothesis testing bi background counts in observation interval BR Background count rate BPL Byproduct License CFR Code of Federal Regulations cm centimeters cm2 square Centimeters cpm counts per Minute CPT Cold Pipe Tunnel CRB Cold Retention Basins, Building 1154 delta, DCGLW - LBGR d Scan surveyor sensitivity index DCGL Derived Concentration Guideline Level DCGLEMC DCGL for small areas of elevated activity, used with the Elevated Measurement Comparison test (EMC)

DCGLW DCGL for average concentrations over a survey unit, used with statistical tests.

(the W suffix denotes Wilcoxon) dpm disintegrations per minute Ei Detector, or instrument efficiency Es Surface efficiency Et Total efficiency EMC Elevated Measurement Comparison EMT Elevated Measurement Test EPA US Environmental Protection Agency ERB Emergency Retention Basin FH Fan House, Building 1132 FSS Final Status Survey FSSP Final Status Survey Plan FSSR Final Status Survey Report gamma, denotes gamma radiation g gram HL Hot Laboratory, Building 1112 HRA Hot Retention Area, Building 1155 HSOO Health-Safety Operations Office i observation counting interval during scan surveys in. inch LMI Ludlum Measurements, Inc.

LBGR Lower Bound of the Gray Region m2 square meters vii

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 LIST OF ACRONYMS & SYMBOLS, Continued MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDA Minimum Detectable Activity (also identified as MDC, Minimum Detectable Concentration)

MDCscan Minimum Detectable Concentration for scanning surveys MDCstatic Minimum Detectable Concentration for static surface activity measurements MDCR Minimum Detectable Count Rate MOU Memorandum of Understanding mrem millirem MW Megawatt MWH Montgomery Watson Harza, Inc.

NACA National Advisory Committee for Aeronautics NASA National Aeronautics and Space Administration N Number of FSS measurements or samples established in a survey design N/A Not Applicable NaI Sodium Iodide NRC US Nuclear Regulatory Commission OLA Open Land Areas PBOW Plum Brook Ordinance Works PBRF Plum Brook Reactor Facility PNL Pacific Northwest Laboratory PPH Primary Pump House, Building 1134 Standard normal distribution function p surveyor efficiency for scan surveys pCi/g picocuries per gram

% percent QC Quality Control RAL Remedial Action Level RESRAD RESidual RADioactive - a pathway analysis computer code developed by Argonne National Laboratory for assessment of radiation doses. It is used to derive cleanup guideline values for soils contaminated with radioactive materials ROLB Reactor Office and Laboratory Building, Building 1141 s seconds generic symbol for standard deviation of a population SAIC Science Applications International Corporation SEB Service Equipment Building, Building 1131 SNL Sandia National Laboratory SR Survey Request tb background count time ts sample count time TBD Technical Basis Document

µ Mean activity concentration VOC Volatile Organic Compound VSP Visual Sample Plan WEMS Water Effluent Metering Station, Building 1192 (also identified as Water Effluent Monitoring System) viii

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 LIST OF ACRONYMS & SYMBOLS, Continued WEP Work Execution Package WHB Waste Handling Building, Building 1133 Z1- Proportion of standard normal distribution values less than 1-Z1- Proportion of standard normal distribution values less than 1-Mathematical symbol for infinity ix

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 1.0 Introduction This report presents the results of the final status radiological survey (FSS) of Open Land Areas (OLA) at the Plum Brook Reactor Facility (PBRF). The Open Land Areas comprise the 27 acre land area inside the PBRF restricted area fence and adjacent buffer areas. It is Attachment 16 of the PBRF Final Status Survey Report (FSSR) 1. This attachment describes the land areas, their history as regards PBRF operations and their condition for the final status survey (FSS). It describes the methods used in the FSS and presents the results.

It is noted that this report address the FSS of the open land areas in their condition after extensive remediation of the PBRF site soil by excavation. The excavated areas have been backfilled and restored to near-original PBRF surface contours. The FSS covers the present open area land surface that is soil-covered. It does not include any paved areas on open land at the PBRF.

As stated in the PBRF Final Status Survey Plan (FSSP) [NASA 2007], the goal of the decommissioning project is to release the facility for unrestricted use in compliance with the requirements of US NRC 10CFR20 Subpart E. The principal requirement is that the dose to future site occupants will be less than 25 mrem/y. Subpart E also requires that residual contamination be reduced to levels as low as reasonably achievable (ALARA). Single radionuclide Derived Concentration Guideline Levels (DCGLs) have been established for PBRF site soils in the FSSP. The principal radionuclides of PBRF origin in open land area soil residual contamination are Cs-137, Co-60 and Sr-90. Their respective DCGLs are: 14.7, 3.8 and 5.4 pCi/g.

The survey measurement results and supporting information presented herein demonstrate that residual contamination levels in each OLA survey unit are well below the applicable DCGLs.

Additionally, it is shown that residual contamination has been reduced to levels that are consistent with the ALARA requirement. Therefore, the Open Land Areas described in this FSS Report Attachment meet the criteria for unrestricted release.

Section 2.0 of the report provides a description of the Open Land Areas. This includes their location, relation to major PBRF buildings and facilities, final configuration for the FSS and scope of the FSS.

A brief history of PBRF operations is presented in Section 3.0. A chronology of significant milestones is followed by history of operations with radioactive materials. Post shutdown and decommissioning activities are summarized. Results of radiological characterization surveys of Open Land Areas in support of decommissioning are presented.

Section 4.0 presents the FSS design for the Open Land Areas. This section includes applicable FSS Plan requirements, breakdown into survey units and assignment of MARSSIM classifications. The survey design approach, instrumentation and measurement sensitivities are described.

1 The PBRF Final Status Survey Report comprises the report main body and several attachments. The attachments present survey results for individual buildings and open land areas. The entire final report will provide the basis for requesting termination of NRC Licenses TR-3 and R-93 in accordance with 10CFR50.82 (b) (6).

1

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 Survey results are presented in Section 5.0. This section includes a summary of the FSS scan survey results and samples collected in the OLA survey units, comparison to the applicable DCGLs and an evaluation of residual contamination levels relative to the ALARA criterion.

Supporting information is contained in Appendices. Appendix A contains figures and photos to supplement the text. Survey design maps and tables of coordinates for FSS sample locations for each survey unit are provided in Appendix B. Analysis results for the OLA soil samples are provided in Appendix C.

2.0 PBRF Site Description and History A description of the PBRF site is provided and the history of facility operations summarized to provide background for identification and description of the land areas which comprise the scope of this FSS report.

2.1 PBRF Site Description The PBRF site is located near the northern edge of the 6400 acre Plum Brook Station. The site, as described in the NRC license that controls decommissioning activities, comprises 27 acres which contain the Reactor Building and support buildings and facilities.2 The controlled-access site is bounded on the south by Pentolite Rd., on the west by Line 2 Rd. and on the north and east by a boundary fence. The southwest corner of the site, the intersection of Line 2 and Pentolite Roads is used as a reference location.3 The coordinates are 41o 23 03.73 North Latitude and 82o 41 05.80 West Longitude.4 Figure 1, a map of the PBRF site, shows the principal PBRF buildings and identifies the OLA survey units. Note that the Figure 1 map includes an overlay of 100 by 100 ft. grids (scaled to the map dimensions). The horizontal grid lines are labeled AZ to BS, South to North and the vertical grid lines are labeled, 90 to 103, West to East.

The site is generally level and graded to promote surface water drainage to the Water Effluent Metering Station (WEMS) located at the south east corner of the site [USACE 2004]. The site reference grade level at the Reactor Building is 631 ft. above mean sea level [NACA 1956].5 2

See Technical Specifications for the License No. TR-3 (Amendment 13) and License No. R-93 (Amendment 9) [NASA 2007a].

3 Prior to decommissioning, the Reactor Vessel center was typically used as a local reference location for the PBRF.

4 Note that the coordinate grid system used for construction of the PBRF was a local coordinate system established by the Army Corps of Engineers in the 1940s for construction of the Plum Brook Ordinance Works. This local grid system has been balanced (tied in) to the Ohio regional state plane coordinate system by NASA to align Glenn Research Center and Plum Brook Station geographic references with modern high-accuracy geo-reference systems. This provides the ability to reference locations specified on historical drawings to global latitude and longitude [Hagelin 2010].

5 The finished floor elevation of the Reactor Building first floor is designated as the 0 ft. elevation for major PBRF buildings. This is one ft. above grade level at the Reactor Building location.

2

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 The PBRF 27 acre site contained several multi-story buildings and numerous support structures. Below-grade structures and utilities extended throughout the site. These include underground pipe and utility tunnels, storm drains, catch basins, sanitary sewers, water and gas supply lines, cathodic protection wells and ground water monitoring wells. Prior to decommissioning, about 25% of the site was occupied by buildings, water processing structures and sludge basins, paved roadways, parking areas, sidewalks and equipment pads.

The remainder of the site surface was open land soil areas.

Areas adjacent to the PBRF on the north (north of North Rd.) contained utilities and support facilities for PBRF operations. These included the Assembly Test Storage (ATS) Building, the former Reactor Office Building, an electric substation and a deionized water storage tank.

All these facilities and the surrounding land area were cleared of licensed radioactive materials and released from the PBRF NRC licenses prior to decommissioning of the PBRF. 6 2.2 History of PBRF Construction and Operation Plum Brook Station was formerly a World War II era explosives manufacturing facility and prior to that was occupied by family farms and orchards [Bowles 2006]. Construction of the Plum Brook Ordinance Works (PBOW) in 1941-42, involved razing of existing farms, residences and small commercial buildings and construction of explosives manufacturing facilities. After World War II, the PBOW lay dormant for 10 years. In 1955, the Department of the Army transferred 500 acres in the northern portion of the former Ordinance Works to the National Advisory Committee on Aeronautics (NACA), the NASA predecessor agency, for construction of the Plum Brook test reactor facility.

6 License Number TR-3, Amendment No. 6, approved by NRC letter dated Dec. 17, 1976.

3

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 Figure 1, PBRF Site Map Showing the Facility Layout and Open Land Area Survey Units 4

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 Planning and design for the PBRF construction was initiated in 1955. Major PBRF milestones are listed below: 7 1956 - September, groundbreaking for PBRF.

1956 - Reactor Building construction initiated.

1959 - 1960 Major building construction completed.

1961 - June, 60 MW Test Reactor critical.

1973- January 5th, Reactor shutdown.

1973 - June 30, PBRF facilities placed in standby condition.

1985 - Initial radiological characterization, Teledyne Isotopes Inc.

1989 - Follow-up radiological characterization, GTS-Duratek.

2002 - Decommissioning Plan approved. Equipment removal and initial building decontamination.

2005 - 2010 - Decommissioning of Buildings and Excavation of Soil and Materials.

2011 - FSS of Open Land Areas.

It is noted that the major buildings were completed in the construction period, 1956 - 1960, but modifications to the site that affected PBRF land areas occurred throughout the operations period. These included construction of the Waste Handling Building (WHB), 1962-64, construction of the ATS Building utility and personnel passage tunnel to the Reactor Building 1964-65, WEMS modifications (several times during 1961 - 1973) and modification of storm drains, 1968.

2.3 Site Geology and Soil Description The Plum Brook Station and the PBRF site are underlain by shale and sandstone formations at varying depths (approximately 2 to 25 ft.) across the station with surface outcrops at some locations. The depth to bedrock is about 25 ft. in the vicinity of the Reactor Building [NASA 2007a]. Surface deposits constitute a mixture of soils derived from fine sand, silt, clay and unconsolidated glacial till [NASA 1959]. Soils in the vicinity of the PBRF are composed of loam, loamy fine sand and fine sandy loam [USACE 2004].

However, the PBRF site soils are highly disturbed and not considered characteristic of native-undisturbed soils in the site vicinity. A series of major disturbances have occurred dating back 7

Information sources for the site history include construction drawings and photos, PBRF operating cycle reports, PBRF annual reports, memoranda and other historical files maintained by PBRF Document Control.

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Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 to the 1940s. Construction of the PBOW involved extensive excavation to construct the ordinance production lines and waste water retention basins. As a result of PBOW operations from 1942 - 1945, the PBRF site was extensively contaminated with chemicals used in the manufacture of Pentolite.8 A site cleanup campaign was mounted prior to PBRF construction [Bowles 2006]. During this cleanup, unknown quantities of soil were reportedly removed from the site and fill material was likely brought in from off-site [USACE 2004].

And, as described in the previous section, construction of the PBRF involved extensive excavation and backfilling throughout the 27 acre site.

2.4 Final Configuration and Scope of FSS The Open Land Areas covered in this Attachment of the PBRF FSS Report include all the land area survey units shown in Figure 1, exclusive of the Pentolite Ditch and six Emergency Retention Basin (ERB) survey units. The FSS scope includes all areas that are not occupied by the remaining buildings, roadways and other paved areas. The FSS of the OLA covers backfilled areas that were formerly occupied by demolished structures (at the time of this writing the only buildings remaining are the Reactor Building, Hot Laboratory and Primary Pump House). The demolished buildings and other structures include the Reactor Office and Laboratory Building (ROLB), Service Equipment Building (SEB), Fan House (FH), Waste Handling Building (WHB), Hot Retention Area (HRA), the Cold Retention Basins (CRB) and the Water Effluent Monitoring Station (WEMS). The FSS also includes land areas formerly occupied by other structures and utilities that were demolished and backfilled. These include the Cooling Tower Basin, Precipitator Sludge Settling Basins the ERB (an earthen structure),

storm drains and catch basins, electrical distribution equipment pads and where underground utilities were removed and the areas backfilled.

To illustrate conditions and the configuration of the OLA at the time of the FSS, photos of representative areas of the site and the survey units within are shown in Exhibits 2 through 24 in Appendix A. The photos show the condition of the areas on the date that the survey unit inspections were performed, usually within a week or two of the FSS.

3.0 Operations with Radioactive Materials The US Atomic Energy Commission (AEC) authorized operations and use of radioactive materials at the PBRF under several licenses.9 License No.TR-3 (Docket 50-30) authorized the 60 MW test reactor. The 100 KW mock-up reactor was licensed under License No.R-93. A broad byproduct license (BPL) No. 34-06706-03, authorized possession and use of radioactive materials (byproduct material) produced by the Plum Brook 60MW and Mockup reactors and other radioactive materials.

Residual contamination in PBRF soil ultimately originated from PBRF operations, tests and experiments [PBRF 2009].

8 Pentolite is a military grade high explosive.

9 Authority for the PBRF reactor and radioactive materials licenses was assumed by the US Nuclear Regulatory Commission in 1975.

6

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 3.1 Startup and Operations During the period from startup and testing of the 60 MW Test Reactor in 1963, until facility shutdown in 1973, large quantities of radioactive materials were routinely stored, handled and processed at the PBRF. Transfer of radioactive contamination to the soil occurred through occasional spills onto outdoor pads and aprons and onto the surrounding soil. Leaks from underground process piping, storm drains and the effluent control system contributed to soil contamination. Table 1 summarizes typical spill events that were recorded in the PBRF Health-Safety Operations Office (HSOO) Cycle Reports.

Table 1, Spill Events Covered in Unusual Incident Reports (1960-1973)

Report Date Description Cycle No.

The Quadrant and Canal coolers, located outside the Fan House, froze, ruptured and spilled about one to two thousand gallons of contaminated water (8x10-5 µCi/cc gross 9 12/15/63 beta-gamma) onto the roadway. Due to the extreme cold, this water froze almost immediately and remained so until 12/21/63, when it was chipped up and removed to thaw over a hot drain.

Quadrant and Canal Cooler # 1 leaked approximately 30 gallons of contaminated water (6x10-5 µCi/cc gross beta-gamma) onto the ground adjacent to the Fan House.

10 12/21/63 No significant contamination was spread beyond the area of the spill due to the immediate freezing of this water.

A general radiation survey was performed on the North-South Effluent ditch on the East Side of Line Road 3. Readings from 2,500 to 6,000 cpm beta-gamma were detected with a portable GM survey meter. The activity is due to sediment from the 18 5/1/64 contaminated water released via this ditch during planned liquid waste disposal operations. Note: during the period from startup to 1968, the effluent ditch was an open ditch lined with an asphalt compound. Cracks and failures in the liner likely led to seepage of contaminated water into the surrounding soil.

A radioactive waste shipping container located on the storage pad south of the WHB, was found to be leaking contaminated water onto the pad. The changing weather 57 12/6/66 conditions (freezing and thawing), and possibly a chemical reaction inside the container, caused the cask to leak. The radioactive leakage was washed into the effluent ditch by heavy rainfall.

During the first shift at 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br />, it was observed that the ERB dike had breached at the northwest corner allowing the water in the basin to flow out into the 83 12/3/68 surrounding area. This resulted from the high water level in the basin and the heavy rainfall in the preceding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The WEMS gates had been closed prior to this break.

Other spill events not recorded in the HSOO Cycle reports occurred during facility operations and spills and cross contamination during decommissioning resulted in additional contamination of PBRF land area soil.

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Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 3.2 Disposition of Materials in the Post-Shutdown Period Notification was received on January 5, 1973 that due to budget constraints, NASA was terminating all nuclear related research operations at PBRF. The Test Reactor, Mock-up Reactor, Hot Laboratory and all associated operations were shutdown and placed in standby condition and the reactor staff terminated by June 30, 1973.

During the period between 1973 and the start of decommissioning, activities at PBRF were controlled in accordance with the modified AEC and NRC licenses: TR-3, R-93 and BPL No.

34-06706-03. These licenses authorized possession only of the remaining radioactive materials on site, i.e., no facility operations were permitted. During this period, selected equipment, materials, and waste (both low-level radioactive and non-radioactive) were removed to other locations or discarded as the projected long-term considerations for the facility changed from possible restart to standby to decommissioning. In 1982, the NRC terminated BPL 34-06706-03 at NASAs request. A Decommissioning and Dismantling amendment to Licenses TR-3 and R-93 transferred any existing licensed radioactive materials to those licenses. For a brief history of the activities during this period see the NASA PBRF Decommissioning Plan, Section 1.2.1 Decommissioning Historical Overview [NASA 2007a].

3.4 Site Characterization Open Land Areas at the PBRF have been characterized extensively, beginning with the Teledyne-Isotopes survey of 1984-85 [Tele 1987] and the 1998 GTS-Duratek confirmatory survey [GTS 1998]. The Teledyne report identified three areas where surface soil was contaminated at levels above the release criteria:10 a small area near the Primary Pump House (PPH) Resin Pit (located on the south side of the building),

an area located south of the WHB outdoor concrete pad and near the effluent trench just north of the WEMS structure.

Subsurface soil above the release criteria was measured to a depth of 6 ft. in a localized portion of the area located south of the WHB outdoor concrete pad. The Teledyne report indicated that the entire ERB floor was contaminated above the release criteria in virtually all areas to a depth of up to 6 in. Only a limited number of soil samples were subjected to isotopic analysis. The maximum concentrations reported were:

Cs-137: 90 pCi/g in ERB surface soil and 187 pCi/g in surface soil near the concrete pad south of the WHB Sr-90: 24 pCi/g in ERB surface soil Co-60: 126 pCi/g in ERB surface soil and 0.2 pCi/g in surface soil near the concrete pad south of the WHB.

10 Soil characterization surveys included collection of samples and analysis for gross beta and alpha activity and direct radiation measured at one meter from the surface. The release criterion for soils used in the Teledyne characterization study was less than two times natural background exclusive of instrument background for gross alpha and gross beta measurements. The criterion for direct radiation measurements was less than 5µR/h above natural background.

8

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 The 1998 GTS-Duratek survey included measurements of gamma dose rate and collection of soil samples from the ERB and the facility grounds. The GTS-Duratek survey reported gamma spectroscopy analysis results from samples collected at 4 locations in the ERB and 10 locations on the facility grounds. The ERB sample results are summarized:

Cs-137 in surface soil (0 to 6 in.) ranged from 8.4 to 166 pCi/g Cs-137 in subsurface soil (6 to 12 in.) ranged from 3.4 to 11.5 pCi/g Co-60 in surface soil ranged from 1.8 to 28.9 pCi/g Co-60 in subsurface soil ranged from < MDA (0.21 pCi/g) to 2.7 pCi/g.

The results of the 10 samples collected from the facility grounds were:

Cs-137 in surface soil (0 to 6 in.) ranged from < MDA (0.1 pCi/g) to 200 pCi/g (in area south of WHB south concrete pad).

Cs-137 in subsurface soil (6 to 12 in.) ranged from < MDA to 0.28 pCi/g.

Co-60 in surface and subsurface soil was < MDA (0.1 pCi/g) in all samples.

Soil characterization surveys were performed by decommissioning contractors from 2004 through 2006. The results of these characterization surveys are summarized here to identify the open land soil areas that required remediation and to identify radionuclide profiles established for PBRF soil.

A report issued in 2005 presented results of a comprehensive characterization survey of the PBRF site grounds [MWH 2005]. The 27 acre area inside the security fence was divided into 12 survey units and one survey unit was established outside the fence, east of the WEMS. The survey units are described and results of surface soil (0 to 6 in.) sample analysis summarized in Table 2. Exhibit 1 of Appendix A shows the principal survey units established for the characterization survey on a map of the PBRF.

Table 2, Summary of 2004 Soil Characterization Survey No. of Cs-137 (pCi/g) Co-60 (pCi/g)

Survey Description Locations Unit ID Sampled Average Maximum Average Maximum 1 Far SW area inside fence. 48 0.23 0.44 0.08 0.16 2 Far SE area inside fence. 51 15.7 217.9 4.28 37.2 3 Central SW area inside fence. 47 0.08 153.2 0.08 0.13 Central SE area inside fence 4 40 0.28 1.06 0.07 0.09 including northern 2/3 of ERB.

5 Midwest area inside fence. 50 0.32 1.45 0.07 0.14 6 Mideast area inside fence. 44 0.58 8.19 0.01 0.32 7 Central NW area inside fence. 29 0.34 0.77 75.7 604.8 8 Central NE area inside fence. 45 4.60 162.3 1.22 4.91 9 Northern area inside fence. 42 0.29 0.71 0.04 0.06 Area above North Rd. N of 10 34 0.32 0.76 0.07 0.10 Reactor Building.

ERB Southern 1/3 of ERB 24 37.7 81.9 2.15 7.61 Outside Area directly E of WEMS 37 2.11 19.1 0.66 4.57 Fence outside fence.

9

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 It is seen from Table 2 that soil concentrations in excess of applicable FSS Plan single nuclide DCGLs were measured in Survey Units 2, 3, 7, 8, the ERB and the area outside the fence east of the WEMS. The DCGL values used for this evaluation were 14.7 and 3.8 pCi/g for Cs-137 and Co-60, respectively. The maximum Cs-137 concentration measured in subsurface samples was 22.5 pCi/g in Survey Unit No. 3. Results for subsurface soil samples from the other survey units were below the Cs-137 DCGL. The overall average Cs-137 concentration in subsurface soil samples was 0.25 pCi/g.

The maximum Co-60 concentration measured in subsurface samples was 0.70 pCi/g in the ERB. The 2005 characterization report indicated that the following areas contained soil with concentrations above the DCGL and would require remediation:

a. East and west adjacent to the WEMS (surface soil),

b. East of the WEMS outside the PBRF fence (surface soil),

c. South berm of the ERB (surface soil),

d. South of the WHB pad (surface soil),

e. West of Storm Sewer Catch Basin WH-1, located just south of the storage pad south of the WHB (surface and subsurface soil),

f. South of the PPH (surface),

g. Southeast of the Precipitator Sludge Basins next to catch basin 9A (surface soil) and the

h. ERB floor (surface soil).

Characterization surveys were performed subsequently to further delineate the areas of contaminated soil identified above and to determine contamination levels and extent of contaminated soil throughout the facility. These characterization surveys ultimately guided soil remediation for the entire PBRF site and surrounding areas. The individual areas that were remediated by excavation are described in the following section. They included: seven discrete areas identified as spill areas; soil surrounding storm drains, sanitary sewers and impacted underground utilities and impacted soil under and adjacent to structure foundations. Perhaps most significant are the spill areas, as they contained most of the soil that was in excess of soil DCGLs. Table 3 provides a summary of the spill areas.

Table 3, Spill Area Summary Approximate Name Location Description Size (ft2) (1)

Contaminated concrete, asphalt and soil area.

Along E half of Cs-137 up to 1.67 pCi/g & Co-60 up to 4.48 Spill Area No. 1 25 PPH S wall pCi/g (in soil 0 to 6 in depth). Designated as a Co-60 area.(2)

N of Reactor Site of a 300 gallon liquid spill during transfer Spill Area No. 2 Building near 2000 of contaminated water in 2005. Was remediated Catch Basin 4 in 2005. Designated as a Co-60 area.(3)

Cs-137 up to 431 pCi/g & Co-60 up to 271 E side of Hot Lab Spill Area No. 3 1000 pCi/g (0 to 6 in depth).

at Rollup Door Designated as a Co-60 area.(3)

Smaller of two distinct sub-areas identified as Spill Area No. 4 S of WHB 22 Spill area No. 4. Above scan RAL (4), but no (small area) soil samples > 0.5 x DCGL.(3)

W of Line 3 Rd Larger of two distinct sub-areas identified as Spill Area No. 4 Spill area No. 4. Scan results > bkg., but below approximately 100 2400 (main area) scan RAL(4); no soil samples > 0.5 x DCGL. (3) ft. S of WHB 10

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 Table 3, Spill Area Summary Approximate Name Location Description Size (ft2) (1)

Spill Area No. 5 Above scan RAL (4), but no soil samples > 0.5 x S of South CRB 600 DCGL.(3)

Scan surveys in 2006 failed to detect levels E of SEB & S of above bkg., except in one very localized area (~

Spill Area No. 6 2500 Sludge Basins 2ft2) just south of catch basin CB-9A, which was > RAL.(4) (3)

E of WEMS Soil area contaminated from WEMS overflow-WEMS Spill flood events. Cs-137 up to 19.1 pCi/g & Co-60 outside Perimeter 2500 Area up to 1.28 pCi/g (0 to 6 in depth).(5)

Fence Table 3 Notes:

1. Approximate surface area of potentially impacted areas investigated. The actual areas of soil that are above the DCGLs are usually much smaller than the size of the area investigated.

2. Descriptive information and survey results from Survey Request SR-3.

3. Descriptive information and survey results from Survey Request SR-16 and personal communication, FSS supervisor.

4. RAL - abbreviation for remedial action level. The RALs used in characterization surveys, were typically set at a scan count rate equivalent to 50% of soil DCGL values.

5. Descriptive information and survey results from Survey Request SR-208.

As part of characterization activities to determine the extent of subsurface soil contamination, and to supplement the investigations of spill areas summarized in Table 3, subsurface soil adjacent to building foundations was investigated in 2008. Core bore samples were collected to depths of up to 4 meters (or refusal) using Geoprobe equipment. Core bore soil samples were collected at 41 locations. The bores were sectioned to capture soil from 0 to 6 in and one-meter sections below the 0 to 6 in. depth. The 0 to 6 in. samples and aliquots of each of the homogenized one-meter subsurface soil sections were analyzed by gamma spectroscopy.

All the subsurface samples were < MDA for Cs-137 and Co-60, except at location FH/WHB9, at the NE corner of the Fan House. The four meter depth sample showed Cs-137 concentration of 0.14 +/- 0.07 pCi/g (2 ).11 3.5 Decommissioning During decommissioning of the PBRF, soil areas were extensively remediated by excavation.

Excavation activities conducted inside the 27 acre restricted area and areas immediately outside the restricted area are summarized:12 Figure 2, a map of the PBRF site, shows the soil areas that were remediated inside and immediately adjacent to the restricted area (excavated areas at the Pentolite Ditch and Plum Brook are not shown as these areas are outside the scope of the present report).

11 Characterization Survey Request SR-96, issued 1/7/08, closed 4/2/08.

12 These descriptions of soil remediation are excerpted from Attachment 18 of the PBRF FSS Report.

11

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 The principal excavated areas located inside the 27 acre restricted area and the adjacent WEMS spill area are described below. Most of the excavated soil (except from the initial excavation of the ERB) was screened by survey technicians in the field using 2x2 in. NaI detectors. Soil above the RAL (one-half the Cs-137 DCGL) and below the DCGL was staged for processing and FSS by the Mactec Conveyor-sorter System. Soil above the DCGL was staged for disposal as radioactive waste. The FSS of excavated soil is reported in Attachment 18 of the PBRF FSS Report. The FSS of the Pentolite Ditch is reported in Attachment 4 of the FSS Report.

Emergency Retention Basin During 2005, approximately 3,400 tons of soil were excavated from the ERB and shipped for disposal as radwaste by the decommissioning contractor.13 In late 2009, demolition of the ERB was completed. This consisted of removal of standing water, removal of cover and miscellaneous debris, removal of temporary concrete block walls (installed for temporary repairs during decommissioning) and excavation of potentially contaminated soils.14 This work was performed under PBRF Work Execution Package PBRF-WEP-09-025.15 This included excavation of approximately 6 in. of soil from the basin floor and excavation of the entire surrounding berm.

Cold Retention Basins The Cold Retention Basins were removed in 2009. After the CRB structures and concrete basins were demolished and removed, potentially contaminated gravel and soil was removed from the basin cavities and perimeters. This work was performed under WEP-09-006.16 Storm Drains and Catch Basins In 2010 and early 2011, potentially contaminated soil was excavated while removing approximately 7700 feet of contaminated storm sewer piping and the associated catch basins.

This work was performed under PBRF Work Execution Packages, PBRF-WEP-09-020 and PBRF-WEP-09-027.17 A detailed description of this work and the FSS of the excavated storm drains and catch basins is provided in Attachment 7 of the FSS Report.

13 Weights of soil shipped as radwaste from the ERB and Pentolite Ditch during 2005 are obtained from PBRF Decommissioning Project waste shipment records.

14 The FSS of the ERB is reported in Attachment 10 of the PBRF Final Status Survey Report.

15 Work Execution Package, PBRF-WEP-09-025, Emergency Retention Basin Demolition, Oct. 6, 2009.

16 Work Execution Package, PBRF-WEP-09-006, Cold Retention Basin Dismantlement, April 30, 2009. The FSS of the CRB excavated areas is reported in Attachment 7 of the PBRF Final Status Survey Report.

17 Work Execution Package, PBRF-WEP-09-020, Storm Drain System Dismantlement, January 26, 2010. Work Execution Package, PBRF-WEP-09-027, Removal of Storm Sewer South of Building 1131 Excavation, June 27, 2010.

12

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 HRA Underground Storage Tanks Excavation of potentially contaminated soil required to remove underground storage tanks adjacent to the HRA was performed in 2010. This work was performed under PBRF Work Execution Package, PBRF-WEP-09-010.18 WHB and Fan House Sub-foundations Excavation of the WHB Evaporator Pit and the Fan House Resin Pit was performed in 2010.

In addition to removal of the concrete pit structures, potentially contaminated soil adjacent to and beneath the pits was removed. This work was performed under PBRF Work Execution Packages, PBRF-WEP-09-010 18 and PBRF-WEP-09-020 17.

Spill Areas Remediation of the designated spill areas was performed under several Work Execution Packages. Spill Areas No. 1 and No. 3 and the WEMS Spill Area were excavated under WEP-09-009.19 Spill Area No. 2 was remediated in 2005. Any remnants of this spill area were excavated in 2009-10 as part of the storm drain system dismantlement under PBRF-WEP 20.17 Spill Area No. 4 was also excavated as part of the Storm Drain system dismantlement. A contaminated soil area located just south of the south CRB identified as Spill Area 5 was excavated as part of the CRB excavation under PBRF-WEP-09-006.15 The FSS of the spill areas after excavation is reported in Attachment 7 of the FSS Report.

Building Demolition Several buildings have been demolished as of late 2011 during PBRF decommissioning. The Fan House, Waste Handling Building and Hot Retention Area structure were demolished under PBRF-WEP-09-017.20 The Service Equipment Building and the Reactor Office and Laboratory Building were demolished under PBRF-WEP-10-005 and WEP-10-006, respectively.21 These demolitions included excavation of some adjacent soil to gain access to contaminated sub-surface structures. Also, overburden soil was excavated from the Cold Pipe Tunnel (CPT) as part of the SEB demolition and from the underground Calibration Facility as part of the ROLB demolition. The FSS of excavated areas adjacent to the buildings identified above is reported in Attachment 7 of the FSS Report.

18 Work Execution Package, PBRF-WEP-09-010, Underground Storage Tank and Contaminated Soil Removal, April 19, 2010. The Final Status Surveys of the excavated areas of the HRA and WHB are reported in Attachment 7 of the PBRF Final Status Survey Report.

19 Work Execution Package, PBRF-WEP-09-009, Spill Area Excavation, November 5, 2009. The FSS of the spill areas is reported in Attachment 7 of the PBRF Final Status Survey Report.

20 Work Execution Package, PBRF-WEP-09-017, Buildings 1132, 1133 and 1155 Demolition, April 14, 2010.

21 Work Execution Package, PBRF-WEP-10-005, Service Equipment Building Demolition, July 13, 2010. Work Execution Package, PBRF-WEP-10-006, Reactor Office and laboratory Building Demolition, September 15, 2010.

13

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 Miscellaneous Structures and Pads (including the WEMS)

Approximately 50 miscellaneous structures (foundations, basins, pits and trenches) and equipment pads were removed during PBRF decommissioning. These included equipment pads, sidewalks, building roll-up truck door aprons, pipe trenches, and large structures such as the WEMS. A detailed listing is provided in WEP-09-15, which covered removal of most of these items.22 Some of these structures were removed or demolished under WEP-09-20.17 Pads on grade were removed and concrete structures that extended below grade were removed to at least 3 ft. below grade. Many of these structures and pads were either confirmed or potentially impacted by radiological contamination and the adjacent and underlying soil was excavated for evaluation and FSS. The FSS of excavated areas associated with the Miscellaneous Structures and Pads is reported in Attachment 7 of the FSS Report.

Impacted Utilities Several underground utilities that traversed impacted soil areas were removed during 2009 and 2010. This included:

excavation and removal of approximately 1300 ft. of sanitary sewer piping, removal of underground process piping from the CRB Valve Pit to the Fan House (including the HRA pump-out line),

removal of resin/valve pit adjacent to (south of) the Primary Pump House (PPH) and associated drain lines and removal of approximately 630 ft of miscellaneous piping in the vicinity of, and between the Fan House and the PPH. This work was performed under PBRF-WEP 007.23 RCRA Soil Area Soil potentially contaminated with volatile organic compounds (VOCs) was excavated during removal of approximately 60 ft. of storm drains, two catch basins and an abandoned water monitoring well located immediately south of the former SEB. This action was performed in accordance with the NASA Plum Brook groundwater remediation plan [SAIC 2010]. The plan called for removal of the subject storm drain piping, catch basins, former monitoring well and associated overburden and impacted soil as potential sources of groundwater contamination. This work was controlled under PBRF-WEP-09-027.17 Approximately 2000 tons of soil were excavated and evaluated for radioactivity and VOCs. The soil was surveyed for radioactivity and found to be acceptable for free release under PBRF Radiation Protection Procedure, RP-008 (no detectable activity). Seven 55-gallon drums of VOC contaminated liquid/sludge were removed from the catch basins, sampled and evaluated. They were classified as hazardous waste and shipped offsite for disposal at a licensed disposal facility

[SAIC 2010]. The FSS of excavated areas associated with remediation of the RCRA Soil Area is reported in Attachment 7 of the FSS Report.

22 Work Execution Package, PBRF-WEP-09-015, Miscellaneous Foundation Removal, October 14, 2009.

23 Work Execution Package, PBRF-WEP-09-007, Impacted Utility Excavation, October 14, 2009. The FSS of areas exposed by excavation of Impacted Utilities is reported in Attachment 7 of the FSS Report.

14

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 Figure 2, PBRF Site Map Showing Areas Where Soil Was Remediated 15

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 Using characterization survey results, radionuclide profiles were developed for the PBRF open land areas. These were published in a technical basis document which established radionuclide mixtures and DCGLs for FSS of the site soils [PBRF 2009]. The site and impacted adjacent environmental areas were divided into groups with similar radionuclide profiles. Activity fractions of the principal radionuclides, Cs-137, Co-60 and Sr-90 were established for each group. The results are shown in Table 4.24 Table 4, Principal Radionuclides and Activity Fractions for Site Soils Activity Fractions Location Cs-137 Co-60 Sr-90 Default for PBRF site and Spill Areas 4, 5 & 0.912 0.007 0.081 6.

Spill Areas 1, 2 & 3 0.201 0.714 0.085 Environs Outside 0.878 0.037 0.085 Perimeter Fence Pentolite Ditch and 0.969 0.014 0.017 Environs 4.0 Survey Design and Implementation This section describes the method for determination of the number of samples for FSS of the Open Land Areas. Applicable requirements of the FSS Plan are summarized. These include the DCGLW25, scan survey coverage and action-investigation levels, classification of areas and breakdown of the survey units. The radiological instrumentation and their detection sensitivities are discussed.

4.1 FSS Plan Requirements The DCGLs for individual radionuclides in soil were calculated using RESRAD Version 6.21 for a resident farmer site occupancy scenario. The DCGL calculations are described in the FSSP, Attachment B. The DCGL values from the FSSP for the three significant PBRF radionuclides are given in Table 5. These DCGL values are also applied to subsurface soil.

24 Other radionuclides have been measured in PBRF characterization soil samples. In the FSS Plan, soil DCGLs were published for eight radionuclides (Co-60, Cs-137, Sr-90, Eu-152, Eu-154, Fe-55, Ni-69 and Ni-63. The dose to the Resident Farmer from radionuclides other than the principal three was calculated to be only 0.5 mrem/y. Hence, as this dose is well below the NRC 10% criterion, these radionuclides are considered insignificant.

25 The convention used in the MARSSIM is to identify the DCGL used as the benchmark for evaluating survey unit measurement results, as the DCGLW. The W subscript denotes Wilcoxon, regardless of the particular test used (Wilcoxon Rank Sum Test, or Sign Test).

16

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 Table 5, FSS Plan Single Radionuclide DCGL Values for Soil DCGL Radionuclide (pCi/g)

Co-60 3.8 Sr-90 5.4 Cs-137 14.7 For application to FSS of soil at PBRF, surrogate DCGLs are used to determine scan sensitivities, action levels and sample analysis MDA requirements. They are calculated from the single nuclide soil DCGLs using radionuclide mixtures established for the various open land areas shown in Table 4. These values are established in the technical basis document on radionuclide distributions and DCGLs for site soils [PBRF 2009]. The following equation from the FSS Plan, Section 3.2.1 is used to calculate surrogate DCGLs:

1 DCGLSUR (Equation 1) 1 R2 R3 Rn

.....

DCGL1 DCGL2 DCGL3 DCGLn Where: DCGLSUR = Surrogate radionuclide DCGL, DCGL1 = DCGL for the radionuclide to be used as the surrogate for the other radionuclides, DCGL2, 3n = DCGL for radionuclides to be represented by the surrogate and Rn = Ratio of concentration (or nuclide mixture fraction) of radionuclide n to surrogate radionuclide.

The surrogate DCGLs for soil FSS scans of the various outdoor open land areas are shown in Table 6. For most of the excavated soil FSS, where Cs-137 is the predominate radionuclide, the most limiting DCGLSUR value, 10.3 pCi/g, is used as the basis for scan survey investigation and action levels.

Table 6, Surrogate DCGLs for OLA Soil FSS Scan Survey Activity Fractions Surrogate DCGLSUR Location Cs-137 Co-60 Sr-90 Radionuclide (pCi/g)

Default for PBRF site and 0.912 0.007 0.081 Cs-137 11.55 Spill Areas 4, 5 & 6.

Spill Areas 1, 2 & 3 0.201 0.714 0.085 Co-60 3.28 Environs Outside 0.878 0.037 0.085 Cs-137 10.31 Perimeter Fence Survey designs incorporate requirements for scan coverage and investigation levels derived from the MARSSIM classification of survey units. The values listed in the FSS Plan applicable to soils are shown in Table 7.

17

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 Table 7, Class-Based Survey Scan Coverage and Action Level Requirements Static Measurement Scan Survey Scan Investigation Classification or Sample Result Coverage Levels (1)

Investigation Levels Class 1 100% >DCGLEMC >DCGLEMC Class 2 10 to 100%

>DCGLW or >MDCscan

>DCGLW if MDCscan is >DCGLW Class 3 Minimum of 10%

>DCGLW or >MDCscan 50% of the DCGLW if MDCscan is >DCGLW Table 7 Note:

1. The scan investigation levels shown above are as listed in the FSS Plan. However, the scan investigation level was set below the DCGLW for Class 1 soil survey units.

4.2 Area Classification and Survey Unit Breakdown In the FSS Plan, the Open Land Areas covered in this report were divided into 11 areas identified as Environmental Survey Areas for initial classification and final status survey planning. Ten of the areas were located inside the restricted area fence and one was located outside the fence. This information is shown in Table 2-2 of the FSS Plan [NASA 2007]. Six Environmental Survey Areas inside the restricted area fence were classified as Class 1/2, two as Class 1/2/3, one as Class 2/3 and one as Class 3. The environmental area located outside the restricted area fence was classified as Class 1/3. For the FSS, the Open Land Areas have been divided into 59 survey units (52 Class 1 and 7 Class 2). These are identified in Table 8.

The area inside the restricted area fence is divided into 50 Class 1 survey units and one Class 2 survey unit. The area outside the fence was divided into 8 survey units; two Class 1 and six Class 2. One of the Class 1 areas located outside the 27 acre restricted area was established to cover the WEMS Spill Area (OL-1-98) and the other (OL-1-55) was established within a buffer area initially designated as Class 2 when discrete radioactive particles were discovered during the initial FSS scan survey (see Table 12 Notes for details).

Table 8, Open Land Area Survey Units for FSS Survey Area Survey Class Description Unit (m2) Design OL-1-46 2 7450 51 Restricted Area North of the BM Grid Line OL-1-47 1 1898 51 Restricted Area Grids AZ-90, AZ-91, BA-90, BA-91 OL-1-48 1 1644 51 Restricted Area Grids BB-90, BB-91 OL-1-49 1 1911 51 Restricted Area Grids AZ-92, BA-92, BB-92 (South 90)

OL-1-50 1 1912 51 Restricted Area Grids AZ-93, BA-93, BB-93 (South 90)

OL-1-51 1 1420 51 Restricted Area Grids BC-90, BD-90 OL-1-52 1 1858 51 Restricted Area Grids BC-91, BD-91 OL-1-53 1 1951 51 Restricted Area Grids BB-92 (North 10), BC-92, BD-92 OL-1-54 1 1951 51 Restricted Area Grids BB-93 (North 10), BC-93, BD-93 OL-1-55 1 1858 51 Restricted Area Grids BO-93, BP-93 Restricted Area Grids AZ-100 inside fence, BA-100 OL-1-56 1 1135 51 inside fence, BA-100 and BA-101 spill area outside fence 18

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 Table 8, Open Land Area Survey Units for FSS Survey Area Survey Class Description Unit (m2) Design OL-1-57 1 1547 51 Restricted Area Grids BB-100, BC-100 OL-1-58 1 1551 51 Restricted Area Grids BD-100, BE-100 OL-1-59 1 1586 51 Restricted Area Grids BL-99, BL-100 OL-1-60 1 1709 51 Restricted Area Grids BK-99, BK-100 OL-1-61 1 1558 51 Restricted Area Grids BJ-99, BJ-100 OL-1-62 1 1707 51 Restricted Area Grids BH-99, BH-100 OL-1-63 1 1706 51 Restricted Area Grids BG-99, BG-100 OL-1-64 1 1706 51 Restricted Area Grids BF-99, BF-100 OL-1-65 1 1718 51 Restricted Area Grids BL-97, BL-98 OL-1-66 1 1841 51 Restricted Area Grids BK-97, BK-98 OL-1-67 1 1692 51 Restricted Area Grids BJ-97, BJ-98 OL-1-68 1 1755 51 Restricted Area Grids BH-97, BH-98 OL-1-69 1 1858 51 Restricted Area Grids BG-97, BG-98 OL-1-70 1 1858 51 Restricted Area Grids BF-97, BF-98 Restricted Area Grids BJ-93, 94, 95, & BK-94, 95 land OL-1-71 1 1398 51 between the HL, RB, PPH buildings and Line 3 Road Restricted Area Grids BG-93, 94, 95, & BH-93, 94, 95 OL-1-72 1 1729 51 land between the HL buildings and Line 3 Road OL-1-73 1 1913 51 Restricted Area Grids AZ-94, BA-94, BB-94 (South 90)

OL-1-74 1 1951 51 Restricted Area Grids BB-94 (North 10), BC-94, BD-94 Restricted Area Grids BA-95 through BG-95 land west of OL-1-75 1 1813 51 Line 3 Road OL-1-76 1 1697 51 Restricted Area Grids BE-90, BF-90, BG-90 (South 40)

OL-1-77 1 1858 51 Restricted Area Grids BE-91, BF-91 OL-1-78 1 1858 51 Restricted Area Grids BE-92, BF-92 OL-1-79 1 1858 51 Restricted Area Grids BE-93, BF-93 OL-1-80 1 1858 51 Restricted Area Grids BE-94, BF-94 Restricted Area Grids BG-92 east 25, BG-93, BG-94, OL-1-81 1 1963 51 BG-95 west of Line 3 Road Restricted Area Grids BG-90 north 60, BG-91, BG-92 OL-1-82 1 1961 51 west 75 OL-1-83 1 1817 51 Restricted Area Grids BH-90, BH-91, BH-92 Restricted Area Grids BJ-90, BJ-91, BJ-92 north of road, OL-1-84 1 2030 51 BK-90 to BK-92 south 50 Restricted Area Grids BK-90 north 50, BK-91 NW 50, OL-1-85 1 1530 51 BL-90, BL-91 west 50 Restricted Area Grids BK-91 ne 50, BL-91 east 50, BK-OL-1-86 1 1921 51 92, BL-92, BK-93 & BL-93 to RB east wall Restricted Area Grids BK-93, BL-93 BK-94, BL-94, BK-OL-1-87 1 1996 51 95, BL-95 between RB east Wall, PPH north wall, Line 3 Road, and North Road Restricted Area Grids BL-95 & 96 east of L3 Road, BK-OL-1-88 1 1851 51 95 & 96 East of L3 Road north 50 19

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 Table 8, Open Land Area Survey Units for FSS Survey Area Survey Class Description Unit (m2) Design Restricted Area Grids BK-95 & 96 East of L3 Road south OL-1-89 1 1935 51 50, BJ-95 & 96 east of L3 Road Restricted Area Grids BF-95, BG-95, BH-95 east of L3 OL-1-90 1 1322 51 Road OL-1-91 1 1858 51 Restricted Area Grids BG-96, BH-96 OL-1-92 1 1858 51 Restricted Area Grids BE-96, BF-96 Restricted Area Grids BC-95, BD-95, BE-95 east of L3 OL-1-93 1 1338 51 Road OL-1-94 1 1858 51 Restricted Area Grids BC-96, BD-96 Restricted Area Grids AZ-95, BA-95, BB-95, BB-96 east OL-1-95 1 1805 51 of L3 Road OL-1-96 1 1943 51 Restricted Area Grids AZ-96, AZ-97, BA-96, BA-97 OL-1-97 1 1942 51 Restricted Area Grids AZ-98, AZ-99, BA-98, BA-99 OL-1-98 1 999 51 Grids AZ-101 & BA-101 outside of the RA Fence OL-2-1 2 10896 54 Restricted Area Buffer Zone - Section #1 OL-2-2 2 9772 54 Restricted Area Buffer Zone - Section #2 OL-2-3 2 9268 54 Restricted Area Buffer Zone - Section #3 OL-2-4 2 9425 54 Restricted Area Buffer Zone - Section #4 OL-2-5 2 7394 54 Restricted Area Buffer Zone - Section #5 OL-2-6 2 7062 54 Restricted Area Buffer Zone - Section #6 4.3 Number of Samples The number of samples for each survey unit was determined using the MARSSIM statistical hypothesis testing framework as outlined in the FSS Plan. The Sign Test is selected because background concentrations of radionuclides of PBRF origin in soil are a small fraction of the applicable DCGLs. Decision error probabilities for the Sign Test are set at = 0.05 (Type I error) and = 0.10 (Type II error) in accordance with the FSSP.

The Visual Sample Plan (VSP) software was used to determine the number of FSS measurements in the OLA.26 When the Sign Test is selected, the VSP software uses MARSSIM Equation 5-2 to calculate the number of measurements. Equation 5-2 is shown below:

Z 1 Z 1 2

N 1.2 2 (Equation 2)

4 0.5

Where:

26 The FSS Plan (Section 5.2.4) states that a qualified software product, such as Visual Sample Plan© [PNL 2010], may be used in the survey design process.

20

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 1.2 = adjustment factor to add 20% to the calculated number of samples, per a MARSSIM requirement to provide a margin for measurement sufficiency, N = Number of measurements or samples,

= the type I error probability,

the type II error probability, Z1- = proportion of standard normal distribution < 1 - (1.6449 for

0.05),

Z1- = proportion of standard normal distribution < 1 - (1.2816 for = 0.1),

(/) = value of cumulative standard normal distribution over the interval -

, /,

= the relative shift, defined as the DCGL - the Lower Bound of the Gray Region (LBGR), and

= the standard deviation of residual contamination in the area to be surveyed (or a similar area).

The MARSSIM module of VSP requires user inputs for the following parameters: , ,

LBGR, the DCGLW and . The numbers of samples were calculated for the OLA survey units using the parameters established in 2 survey designs. Table 9 summarizes the survey designs and lists the values of key VSP input parameters.

Table 9, Survey Design Summary Design LBGR (1) Survey Units Class DCGL (2) (2) N No.

OL-1-46 through 51 1(3) 11.6 (4) 5.8 5.8 2.32 2.5 11 OL-1-98 OL-2-1 through OL- (4) 54 2 11.4 5.7 5.7 2.28 2.5 11 2-6 Table 9 Notes:

1. The data reported in this table is obtained from the Survey Design reports listed. They are maintained in the PBRF Document Control System.

2. Units are pCi/g.

3. Survey Unit OL-1-46 is classified as Class 2.

4. The DCGLs shown are for Cs-137. They are obtained from PBRF TBD-09-001 [PBRF 2009], with adjustment for insignificant radionuclides. The Co-60 DCGL for both designs is 3.7 pCi/g.

Selection of design input parameters followed guidance in the FSS Plan. The Plan states that the LBGR is initially set at 0.5 times the DCGLW, but may be adjusted to obtain a value for the relative shift (/) between 1 and 3. It is seen in Table 9 that a relative shift value of 2.5 was used in the final calculations for determining N.

The VSP software automatically performs an analysis to examine the sensitivity of N, the number of samples, to critical input parameter values. The following is an example obtained 21

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 for survey unit OL-1-47. The sensitivity of N was explored by varying the following parameters: standard deviation, lower bound of gray region (as % of DCGL), beta, probability of mistakenly concluding that the survey unit mean concentration, , is greater than the DCGL and alpha, probability of mistakenly concluding that the survey unit mean concentration, , is less than the DCGL. Table 10 summarizes this analysis. The region of interest is for = 0.05 (required to be fixed), = 0.10 (may be adjusted) and the LBGR at 50% to 70% of the DCGL. In this region, it is seen that N is sensitive to . Holding = 0.10 and doubling causes N to increase from 14 to 35 when the LBGR is 70% of the DCGL; 12 to 23 when the LBGR is 60% of the DCGL and 11 to 17 when the LBGR is 50% of the DCGL. However, the sensitivity of N to an incorrect conclusion that the survey unit will pass (regulators risk) is quite low; with the LBGR at 50% of the DCGL (as used in Design 51),

increasing from 0.05 to 0.10 and 0.15 and holding constant at 2.32 pCi/g, shows that the number of measurements is 11 or fewer in all cases. These results show that N = 11 represents a conservative design.27 Table 10, Sensitivity Analysis for FSS Design Number of Samples DCGL= 11.6 (1) = 0.05 (2) = 0.10 = 0.15

= 4.64 (1) (3) = 2.32 = 4.64 = 2.32 = 4.64 = 2.32 (5)

LBGR = 70% (1) (4) =0.05 44 18 35 14 29 12

=0.10 35 14 27 11 22 9

=0.15 29 12 22 9 18 7 LBGR = 60% =0.05 28 15 23 12 19 10

=0.10 23 12 17 9 14 8

=0.15 19 10 14 8 12 6 LBGR = 50% =0.05 21 14 17 11 14 9

=0.10 17 11 13 9 11 7

=0.15 14 9 11 7 9 6 Table 10 Notes:

1. Units of DCGL, and LBGR are pCi/g.

2. = alpha, probability of mistakenly concluding that µ < DCGL.

3. = Standard Deviation.

4. LBGR = Lower Bound of Gray Region (as % of DCGL).

5. = beta, probability of mistakenly concluding that > DCGL.

Visual Sample Plan was also used to determine the grid size, the random starting location coordinates (for Class 1 and 2 survey units) and to display the measurement locations on survey unit maps drawn to scale. Refer to Appendix B for location coordinate tables and scale VSP maps showing measurement locations for each OLA survey unit. Note that the maps show the survey units superimposed on the 100 by 100 foot grid system shown in Figure 1.

Grid coordinates are shown on each survey unit map to identify the reference location for establishing VSP sample location coordinates within the survey unit.

27 This conclusion is supported by the survey results. The standard deviation of Cs-137 concentrations reported for 680 systematic samples from the OLA survey units is only 0.29 pCi/g, much less than assumed in the survey designs. This indicates that in retrospect, the statistical power of the FSS samples is much greater than implied by the design assumptions.

22

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 The survey designs also specify scan survey coverage and action levels based on the MARSSIM classification listed in Table 7. If the scan sensitivity of the detectors used in Class 1 survey units is below the DCGLW, the number of measurements in each survey unit is determined solely by the Sign Test. If the scan sensitivity is not below the DCGLW, the number of measurements is increased as determined by the Elevated Measurement Comparison (EMC). As discussed in the next section, the scan sensitivities of instruments used in the FSS of the OLA are below the DCGLW, and no increase in the number of measurements above the value calculated using the Sign Test was required.

4.4 Instrumentation and Measurement Sensitivity Scan sensitivities for detectors used for walkover gamma scans of soil are determined using the method described in NUREG-1507 [USNRC 1998] and used in the PBRF FSS Plan

[NASA 2007]. Scan sensitivities for the Ludlum Model 44-10 NaI detectors used in FSS of soils at PBRF were developed in the Technical Basis Document, PBRF-TBD-09-002 [PBRF 2009a]. The method is summarized and the key equations presented. The scan MDC is calculated using the following equations adapted from NUREG-1507 for walkover gamma scanning with NaI detectors:

d ' bi 60 (Equation 3)

MDCRsurv p i MDCRsurv MDCscan (Equation 4)

Conv MS O where:

MDCsurv = the minimum detectable count rate in cpm that can be reliably detected by the surveyor, d = index of sensitivity, unitless (MARSSIM default value of 1.38 is assigned),

bi = background counts observed in the interval i, i = observation interval (s),

p = surveyor efficiency, unitless (MARSSIM default value of 0.5 for walkover scans is assigned),

MDCscan = the scan MDC, here in units of pCi/g, Conv = instrument response conversion factor, units of cpm per µR/h and MSo = instrument response in units of µR/h per pCi/g (determined empirically or with a shielding algorithm).

23

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 Site-specific parameter values for the MDCscan equation are obtained from PBRF-TBD 002 [PBRF 2009a]. The instrument response factor for Cs-137 is 0.138 µR/h per pCi/g as calculated using the MicroShield code. The most conservative instrument response conversion factor measured for detectors in the PBRF LMI 44-10 inventory is 232.39 cpm per µR/h for Cs-137. Using these values, minimum detectable count rates and MDCscan values for 44-10 detectors operated in the Cs-137 gamma energy window vs. background count rates were calculated. They are shown in Table 11.

Table 11, Typical Detection Sensitivities of Field Instruments used for OLA Soil Scans LMI 44-10 with Cs-137 Window (1)

Background (cpm) MDCRsurveyor (ncpm) MDCscan (pCi/g) (2) 50 101 3.13 100 142 4.43 150 174 5.42 200 201 6.26 250 225 7.0 Table 11 Notes:

1. Ludlum Model 44-10 NaI detector with Model 2350-1 data logging scaler-rate meter setup to count in Cs-137 energy window. Scan speed = 0.5 m/s, detector to soil surface = 10 cm.

2. The scan investigation level was typically set at 250 ncpm to ensure that 75% of the scan surrogate DCGL of 11.3 pCi/g (Cs-137) identified in Design 51, can be readily detected in areas with nominal background count rates.

The scan investigation level for Class 1 survey units listed in Table 7 is the DCGLEMC as specified in the FSS Plan, Section 8.1. However, the scan investigation level for the FSS of Open Land Area soil is actually set at a fraction of the DCGLW established in the survey design to ensure that areas in excess of the DCGL are identified and investigated. It is also noted that the FSS Plan states that technicians are to respond to indications of increased count rates even though scan count rates may not be above the investigation level specified in survey instructions. 28 Accordingly, the scan investigation level was set at 7.7 pCi/g, or 75%

of the 10.3 pCi/g DCGL for Cs-137 (typically 250 to 275 ncpm for the 44-10 NaI detectors used in the survey).

28 From FSS Plan Section 7.1.1: Technicians will respond to indications of elevated areas while surveying. Upon detecting an increase in visual or audible response, the technician will reduce the scan speed or pause and attempt to isolate the elevated area. If the elevated activity is verified to exceed the established investigation level, the area is bounded (e.g., marked and measured to obtain an estimated affected surface area). Representative static measurements are obtained as determined by the FSS/Characterization Engineer. The collected data is documented on a Radiological Survey Form.

24

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 5.0 Survey Results Results of the Open Land Areas FSS are presented in this section. This includes scan survey frequencies (% of area covered) for each survey unit and description of instances where the scan investigation level was exceeded. Results of the investigations are summarized. Results of systematic soil samples for each survey unit and the results of comparison tests of survey unit maximum concentration with the DCGL are presented. Calculated unity rule results (unity fractions) are reported. As discussed below, no statistical tests were required. It is shown that levels of residual contamination have been reduced to levels that are ALARA. The results are compared to, and found to be below EPA Trigger Level values. This section closes with a summary which concludes that applicable criteria for release of the OLA for unrestricted use are satisfied and all FSS Plan requirements are met.

5.1 Scan Surveys Scan survey results were reviewed to confirm that the scan coverage requirement (as % of survey unit area) was satisfied for all survey units. The results of QC replicate scan surveys were also reviewed to confirm that the minimum coverage requirement of 5% was satisfied.

Results of the scan surveys are compiled in Table 12. The table shows that scan coverage requirements were satisfied for all survey units. The table also shows that investigations were performed in five survey units. Samples were collected from localized areas which exhibited scan count rates above the investigation level. The highest Cs-137 concentration measured in these investigative samples was 6.39 pCi/g and the highest Co-60 concentration measured was 0.4 pCi/g (the only result with Co-60 > MDA). Since no sample results produced unity fractions greater than one, EMC and Elevated Measurement Tests (EMT) were not necessary.

See the Table 12 Notes for details.29 Table 12, Scan Survey Results Survey Scan Survey Investigation QC Replicate Scan Survey Unit Class Request Coverage (%) (1) Performed Coverage (%) (1) (2)

No.

OL-1-46 2 100 (3) 278/280 No 5.1 OL-1-47 1 100 278/280 No 6.9 OL-1-48 1 100 278/280 No 6.0 OL-1-49 1 100 278/280 No 5.8 OL-1-50 1 100 278/280 No 5.8 OL-1-51 1 100 278/280 No 6.0 OL-1-52 1 100 278/280 Yes (4) 6.0 OL-1-53 1 100 278/280 No 5.7 OL-1-54 1 100 278/280 Yes (5) 5.7 OL-1-55 1 100 278/280 No (6) 6.0 OL-1-56 1 100 278/280 No 8.5 OL-1-57 1 100 278/280 No 7.2 OL-1-58 1 100 278/280 No 6.0 OL-1-59 1 100 278/280 No 6.5 29 The average Cs-137 concentration reported in OLA Release Records for 13 investigative samples is 4.10 +/- 1.32 pCi/g (one standard deviation). The 95th %, upper confidence limit of the mean concentration is 4.82 pCi/g. The 95th % upper confidence limit of the measured Co-60 concentration in the samples is 1.32 pCi/g (only two samples were > MDA).

25

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 Table 12, Scan Survey Results Survey Scan Survey Investigation QC Replicate Scan Survey Unit Class Request Coverage (%) (1) Performed Coverage (%) (1) (2)

No.

OL-1-60 1 100 278/280 No 7.0 OL-1-61 1 100 278/280 No 7.2 OL-1-62 1 100 278/280 No 6.5 OL-1-63 1 100 278/280 No 6.5 OL-1-64 1 100 278/280 No 6.5 OL-1-65 1 100 278/280 No 6.5 OL-1-66 1 100 278/280 No 6.1 OL-1-67 1 100 278/280 No 5.8 OL-1-68 1 100 278/280 No 6.4 OL-1-69 1 100 278/280 Yes (7) 6.0 OL-1-70 1 100 278/280 No 6.0 OL-1-71 1 100 278/280 Yes (8) 7.4 OL-1-72 1 100 278/280 No 6.0 OL-1-73 1 100 278/280 No 5.8 OL-1-74 1 100 278/280 Yes (9) 5.7 OL-1-75 1 100 278/280 No 6.1 OL-1-76 1 100 278/280 No 6.2 OL-1-77 1 100 278/280 No 7.0 OL-1-78 1 100 278/280 No 6.0 OL-1-79 1 100 278/280 No 6.0 OL-1-80 1 100 278/280 No 6.0 OL-1-81 1 100 278/280 No 6.2 OL-1-82 1 100 278/280 No 5.7 OL-1-83 1 100 278/280 No 5.8 OL-1-84 1 100 278/280 No 6.0 OL-1-85 1 100 278/280 No 6.7 OL-1-86 1 100 278/280 No 5.8 OL-1-87 1 100 278/280 No 6.0 OL-1-88 1 100 278/280 No 5.4 OL-1-89 1 100 278/280 No 6.2 OL-1-90 1 100 278/280 No 7.4 OL-1-91 1 100 278/280 No 6.0 OL-1-92 1 100 278/280 No 6.0 OL-1-93 1 100 278/280 No 8.2 OL-1-94 1 100 278/280 No 6.0 OL-1-95 1 100 278/280 No 6.2 OL-1-96 1 100 278/280 No 5.7 OL-1-97 1 100 278/280 No 5.7 OL-1-98 1 100 278/280 No 7.4 OL-2-1 2 33.5 281 No 5.3 OL-2-2 2 30.4 281 No 6.3 OL-2-3 2 36.6 281 No 5.5 OL-2-4 2 35.7 281 No 5.5 OL-2-5 2 99.9 281 No 6.5 OL-2-6 2 41.4 281 No 6.4 26

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 Table 12 Notes:

1. Scan % coverage values for class 2 survey units and for QC replicate scan coverage are rounded to the nearest whole per cent. Values reported with the first decimal as 5, e. g., 5.5, are rounded downward.

2. The % scan coverage is given as the % of the area scanned in the initial survey.

3. A discrete particle was found in an adjacent survey unit (formerly part of OL-2-5, see Note 6),

so a 100% scan was performed in OL-1-46 to ensure that no such particles were present.

4. Two localized areas were identified in OL-1-52 with scan count rates of approximately 400 to 500 ncpm. Soil samples were collected from 5 locations. All Cs-137 results were < DCGL (the highest Cs-137 concentration was 5.48 pCi/g). All Co-60 results were < MDA.

5. Two small areas were identified in OL-1-54 with scan count rates of approximately 290 to 320 ncpm. Soil samples were collected from 6 locations. All Cs-137 results were < DCGL (the highest Cs-137 concentration was 4.62 pCi/g). All Co-60 results were < MDA.

6. This land area covered by survey unit, OL-1-55, was originally part of OL-2-5, established as a Class 2 survey unit. However, OL-1-55 was established as a Class 1 survey unit, after discovery of a discrete particle during the initial scan survey. During the resurvey, 100 % of the survey unit was scanned, and no counts above the scan investigation level were observed.

7. Two small areas (~1 ft2) were identified in OL-1-69 during the scan survey. In the first, a static measurement yielded 333 ncpm. A soil sample collected at this location (IM-1) and analyzed was reported as 5.28 pCi/g Cs-137 and 0.34 pCi/g Co-60. The unity fraction was determined to be 0.55. At the second location, IM-2, a static count rate of 307 ncpm was measured and 6.39 pCi/g was measured in a soil sample collected from this location. The Co-60 result was <

MDA.

8. An area of about one ft2, near the SE corner of the PPH, was investigated during the scan survey of OL-1-71. The maximum unity fraction for samples collected from this area was 0.55 (3.36 pCi/g Cs-137 and 1.0 pCi/g Co-60) .

9. Three small areas, each about one ft2, were investigated in Survey Unit OL-1-74. The highest unity fraction calculated from sample results from the 3 locations was 0.32 (3.76 pCi/g Cs-137 and < MDA Co-60).

5.2 Surface Soil Sample Results Results of the analysis of the systematic FSS soil samples collected from the OLA are shown in Table 13. Gamma spectroscopic analysis of the samples was performed in the PBRF on-site counting laboratory. The samples were collected from locations established on a triangular grid (with random start). Appendix B contains VSP maps and tables of sample location coordinates for each survey unit.

Table 13 provides a summary of the results for each survey unit. Individual sample results are provided in Table 1 of Appendix C. Table 13 lists the number of samples, maximum, average and standard deviation of the Cs-137 concentrations measured in each survey unit. The table provides results of comparisons of maximum and average values to the Cs-137 surrogate DCGL. The smaller of the DCGL values in the two OLA designs is used (11.4 pCi/g). The comparisons show that all the maximum and average OLA survey unit Cs-137 concentrations are below the DCGL, hence no statistical tests are required. The table also shows the maximum unity fraction obtained from the individual sample results in each survey unit. The overall maximum unity fraction is 0.21 obtained in Survey Unit OL-1-53, where the maximum measured Cs-137 concentration is 2.40 pCi/g.

27

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 A summary of the 680 individual sample results is provided in Table 14. The table shows that all Co-60 analysis results are < MDA. It also shows that 367 of 680 Cs-137 analysis results are < MDA. The overall average systematic sample Cs-137 concentration is 0.38 +/- 0.29 pCi/g (one standard deviation).

Table 13, Systematic Sample Results for the OLA Test Test Maximum Survey Maximum Result: Average Result: Std. Dev.

N Unity Unit ID (pCi/g) Max. < (pCi/g) Avg. < (pCi/g)

Fraction DCGLw DCGLw OL-1-46 11 2.46E-01 Yes 2.29E-01 Yes 0.021 2.40E-02 OL-1-47 11 2.93E-01 Yes 2.62E-01 Yes 0.025 2.99E-02 OL-1-48 12 3.53E-01 Yes 2.68E-01 Yes 0.030 5.91E-02 OL-1-49 12 4.35E-01 Yes 2.99E-01 Yes 0.038 6.84E-02 OL-1-50 12 3.18E-01 Yes 2.77E-01 Yes 0.027 5.87E-02 OL-1-51 12 2.73E-01 Yes 2.73E-01 Yes 0.024 N/A (1)

OL-1-52 12 1.05E+00 Yes 5.05E-01 Yes 0.091 3.07E-01 OL-1-53 15 2.40E+00 Yes 1.02E+00 Yes 0.207 6.70E-01 OL-1-54 12 1.07E+00 Yes 6.08E-01 Yes 0.092 3.09E-01 OL-1-55 12 2.44E-01 Yes 2.21E-01 Yes 0.021 2.25E-02 OL-1-56 11 3.71E-01 Yes 3.10E-01 Yes 0.032 7.74E-02 OL-1-57 12 3.31E-01 Yes 2.62E-01 Yes 0.029 4.38E-02 OL-1-58 12 3.32E-01 Yes 2.40E-01 Yes 0.029 6.15E-02 OL-1-59 11 3.41E-01 Yes 3.17E-01 Yes 0.029 2.19E-02 OL-1-60 11 3.57E-01 Yes 2.83E-01 Yes 0.031 5.32E-02 OL-1-61 11 3.32E-01 Yes 3.32E-01 Yes 0.029 N/A (1)

OL-1-62 11 4.58E-01 Yes 2.79E-01 Yes 0.039 1.10E-01 OL-1-63 11 2.69E-01 Yes 2.20E-01 No 0.023 5.76E-02 OL-1-64 11 3.26E-01 Yes 2.82E-01 Yes 0.028 5.83E-02 OL-1-65 11 3.30E-01 Yes 3.30E-01 Yes 0.028 N/A (1)

OL-1-66 11 3.51E-01 Yes 3.32E-01 Yes 0.030 2.07E-02 OL-1-67 11 3.80E-01 Yes 2.99E-01 Yes 0.033 6.07E-02 OL-1-68 11 3.35E-01 Yes 2.36E-01 Yes 0.029 7.22E-02 OL-1-69 11 3.69E-01 Yes 2.90E-01 Yes 0.032 7.22E-02 OL-1-70 11 2.74E-01 Yes 2.72E-01 Yes 0.024 1.53E-03 OL-1-71 12 2.62E-01 Yes 2.24E-01 Yes 0.023 6.24E-02 OL-1-72 11 5.18E-01 Yes 3.32E-01 Yes 0.045 9.11E-02 OL-1-73 13 1.78E+00 Yes 6.97E-01 Yes 0.153 5.67E-01 OL-1-74 12 2.44E+00 Yes 8.13E-01 Yes 0.210 6.14E-01 OL-1-75 13 5.73E-01 Yes 3.53E-01 Yes 0.049 1.20E-01 OL-1-76 11 3.32E-01 Yes 2.52E-01 Yes 0.029 6.96E-02 OL-1-77 12 0.00E+00 Yes N/A (1) N/A 0.000 N/A (1)

OL-1-78 12 3.80E-01 Yes 2.71E-01 Yes 0.033 7.09E-02 OL-1-79 12 3.71E-01 Yes 2.75E-01 Yes 0.032 6.19E-02 28

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 Table 13, Systematic Sample Results for the OLA Test Test Maximum Survey Maximum Result: Average Result: Std. Dev.

N Unity Unit ID (pCi/g) Max. < (pCi/g) Avg. < (pCi/g)

Fraction DCGLw DCGLw OL-1-80 12 4.74E-01 Yes 3.19E-01 Yes 0.041 8.71E-02 OL-1-81 11 4.01E-01 Yes 3.22E-01 Yes 0.035 5.38E-02 OL-1-82 11 3.12E-01 Yes 2.84E-01 Yes 0.027 3.27E-02 OL-1-83 11 2.24E-01 Yes 2.24E-01 Yes 0.019 N/A (1)

OL-1-84 11 2.72E-01 Yes 2.57E-01 Yes 0.023 2.12E-02 OL-1-85 11 4.35E-01 Yes 3.66E-01 Yes 0.038 6.04E-02 OL-1-86 11 4.36E-01 Yes 2.58E-01 Yes 0.038 1.69E-01 (1)

OL-1-87 11 3.26E-01 Yes 3.26E-01 Yes 0.028 N/A OL-1-88 11 6.63E-01 Yes 4.45E-01 Yes 0.057 1.93E-01 OL-1-89 11 7.42E-01 Yes 5.01E-01 Yes 0.064 1.99E-01 OL-1-90 12 4.83E-01 Yes 4.15E-01 Yes 0.042 6.17E-02 OL-1-91 12 4.79E-01 Yes 3.79E-01 Yes 0.041 7.02E-02 OL-1-92 12 1.00E+00 Yes 4.86E-01 Yes 0.086 2.35E-01 OL-1-93 11 4.28E-01 Yes 3.16E-01 Yes 0.037 1.15E-01 OL-1-94 12 4.37E-01 Yes 3.46E-01 Yes 0.038 6.84E-02 OL-1-95 11 4.22E-01 Yes 3.05E-01 Yes 0.036 7.79E-02 OL-1-96 11 6.32E-01 Yes 4.07E-01 Yes 0.054 1.46E-01 OL-1-97 12 3.74E-01 Yes 2.81E-01 Yes 0.032 6.14E-02 OL-1-98 11 6.86E-01 Yes 3.87E-01 Yes 0.059 2.17E-01 OL-2-1 11 4.04E-01 Yes 3.19E-01 Yes 0.035 8.63E-02 OL-2-2 11 2.97E-01 Yes 2.26E-01 Yes 0.026 4.80E-02 OL-2-3 13 1.95E+00 Yes 7.33E-01 Yes 0.168 8.15E-01 OL-2-4 11 3.47E-01 Yes 2.72E-01 Yes 0.030 4.36E-02 OL-2-5 12 5.09E-01 Yes 3.60E-01 Yes 0.044 9.79E-02 OL-2-6 11 5.60E-01 Yes 3.81E-01 Yes 0.048 1.40E-01 Table 13 Note:

1. The acronym N/A is used to denote where the parameter cannot be calculated, for example when all sample results are < MDA or only one positive result is reported.

Table 14, Summary of Individual OLA Sample Results Cs-137 Cs-137 2 Co-60 Co-60 2 Cs-137 MDA Co-60 MDA Statistic (pCi/g)

(1) (1) (1) (2) (2)

Number 313 313 0 0 (1) 367 680 Maximum 2.44E+00 3.43E-01 < MDA < MDA 2.43E-01 9.91E-01 Average 3.84E-01 1.32E-01 N/A N/A 1.13E-01 1.17E-01 Std. Dev. 2.90E-01 4.27E-02 N/A N/A 3.39E-02 3.85E-02 Table 14 Notes:

1. Number of samples with measured concentrations > MDA.

2. Number of samples with measured concentration < MDA and the MDA value was reported.

29

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 5.3 Subsurface Soil Subsurface soil sampling was not included in the FSS of Open Land Areas covered by this Report. Areas that were identified with subsurface contamination above RAL values were remediated prior to FSS of the Open Land Areas. The extensive areas of subsurface soil exposed by remediation were subjected to FSS and found to meet the FSS Plan release criteria. These areas were subsequently backfilled with excavated soil that was processed for FSS, surveyed and demonstrated to be below the release criteria, or with clean backfill trucked in from off-site.30 Also, it is noted that the subsurface soil was included in each of the major characterization surveys described in Section 3.4.

5.4 QC Sample Results Sixty replicate QC soil samples were collected and analyzed by gamma spectroscopy at the PBRF on-site counting laboratory. This constitutes 8.8% of the 680 systematic samples collected and analyzed for the OLA FSS. The QC sample results and comparison with the associated original sample results are provided in Appendix C, Table 2. The QC and original sample results were compared in accordance with the method in the FSS Plan, Section 12.7.2

[NASA 2007]. In this method the sample resolution is calculated as the quotient of the original sample result and the original sample one-sigma uncertainty. Then the ratios of QC to original sample results are compared to acceptance values specified for each range of resolution given in FSS Plan Table 12.2.

It is seen in Table 2 of Appendix C that all but 3 of 60 the sample pairs passed the acceptance criterion. Each sample pair failing to meet the acceptance criterion was individually investigated in accordance with FSS Plan requirements and implementing procedures, resolved and determined to be acceptable.31 5.5 ALARA Evaluation It is shown that residual contamination in the OLA has been reduced to levels that are ALARA, using a method acceptable to the NRC. The NRC guidance on determining that residual contamination levels are ALARA includes the following:

In light of the conservatism in the building surface and surface soil generic screening levels developed by the NRC, NRC staff presumes, absent information to the contrary, 30 The FSS of excavated areas is reported in Attachment 7 of the PBRF FSS Report and the FSS of excavated and backfill materials, is reported in Attachment 18 of the Report. Subsurface sampling of the ERB footprint and the results, all below the applicable DCGLs, are reported in Attachment 10 of the Report.

31 When the acceptance criterion is not met, an investigation is performed to determine the cause and corrective actions.

The investigation may include repetition of the replicate QC measurement or other actions determined by the FSS/Characterization Supervisor. If upon repetition, the acceptance criterion is still not satisfied, the result may be accepted if the original and QC replicate measurement are both are below the DCGL W for the survey unit, the FSS/Characterization Supervisor reviews the investigation and concurs that the measurements are acceptable and the results of the investigation are documented in the Survey Request Summary and Close-out (Procedure CS-01, Survey Methodology to Support PBRF License Termination).

30

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 that licensees who remediate building surfaces or soil to the generic screening levels do not need to provide analyses to demonstrate that these screening levels are ALARA. In addition, if residual radioactivity cannot be detected, it may be presumed that it had been reduced to levels that are ALARA. Therefore the licensee may not need to conduct an explicit analysis to meet the ALARA requirement.32 Soil activity concentrations measured in the OLA FSS are compared to NRC surface soil screening level values in Table 15. As shown in the table, all soil activity concentrations are well below their respective screening level values. From these comparisons, it is concluded that the ALARA criterion is satisfied.

Table 15, NRC Soil Screening Level ALARA Comparison NRC Screening Maximum Measured Radionuclide Level (pCi/g) Concentration (pCi/g)

Co-60 3.8 < MDA(1)

Cs-137 11 2.40 (2)

Sr-90 1.7 0.21 (3)

Table 15 Notes:

1. The average Co-60 MDA for 680 systematic samples is 0.12 +/- 0.04 pCi/g. The upper 95th % confidence limit of the mean concentration of two investigative samples is 1.32 pCi/g.

2. The maximum concentration measured in 680 systematic samples. The upper 95th

% confidence limit of the mean concentration of 13 investigative samples is 4.82 pCi/g.

3. The maximum Sr-90 concentration is inferred from the systematic sample results based on the maximum measured Cs-137 concentration of 2.40 pCi/g and a Sr-90:Cs-137 activity ratio of 0.089 (from Table 6, Default Areas).

5.6 Comparison with EPA Trigger Levels The PBRF license termination process includes a review of residual contamination levels in groundwater and soil, as applicable, in accordance with the October 2002 Memorandum of Understanding (MOU) between the US NRC and the US Environmental Protection Agency (EPA) [USEPA 2002]. Concentrations of individual radionuclides, identified as trigger levels for further review and consultation between the agencies, are published in the MOU.

Maximum activity concentrations of radionuclides of concern measured in the FSS of the OLA are compared to EPA trigger levels. This comparison is shown in Table 16. The table shows that the measured soil activity concentrations are well below EPA trigger levels. It is noted that groundwater is not within the scope of this FSS Report.

32 This guidance was initially published in Draft Regulatory Guide DG-4006, but has been reissued in NUREG-1757 Volume 2, Appendix N [USNRC 2006].

31

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 Table 16, Comparison of Soil Sample Results with EPA Trigger Levels EPA Trigger Maximum Measured Radionuclide Level (pCi/g) Concentration (pCi/g)

Co-60 4 < MDA(1)

Cs-137 (4) 6 2.40 (2)

Sr-90 (4) 23 0.21 (3)

Table 16 Notes:

1. See Table 15, Note 1.

2. See Table 15, Note 2.

3. See Table 15, Note 3.

4. Specified in the MOU as including daughter activity [USEPA 2002].

5.7 Conclusions The results presented above demonstrate that the Open Land Areas satisfy all FSS Plan commitments and meet the release criteria in 10CFR20 Subpart E. The principal conclusions are:

Scan surveys were performed in 100 % of the accessible surface area of all 52 Open Land Area Class 1 survey units and in 30% or more of the surface area in the 7 Class 2 survey units.

In performance of scan surveys of the Open Land Area survey units, scan count rates above the investigation level were observed in five survey units. Analysis results of investigative samples collected from these survey units were all below the applicable DCGL.

All analysis results of 680 systematic soil samples from locations selected per survey design are less than the applicable DCGLW values.

All survey unit mean soil activity concentrations are below the applicable DCGLW values, hence no statistical tests were required.

Measured values of residual soil contamination in the Open Land Areas are shown to be less than NRC screening level values - demonstrating that the ALARA criterion is satisfied.

Measured values of residual soil contamination in the Open Land Areas are shown to be less than the EPA Trigger level values.

Changes from what was proposed in the FSS Plan were made. The Open Land Area was divided into 59 survey units for the FSS, whereas the FSS Plan had identified 11 Environmental Survey Areas. When establishing the 59 survey units, all were classified equal to or higher (meaning from Class 2 to Class 1, etc) than in the FSS Plan, as described in Section 4.2.

There were some changes from initial assumptions in the FSS Plan regarding the extent of residual activity in the Open Land Areas. It was determined that areas of soil contamination were more extensive than assumed in the FSS Plan. This led to upward 32

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 classification of areas as explained in the preceding bullet item. No reclassification of survey units was required as a result of FSS measurements and investigations.

6.0 References Bowles 2006 Mark D. Bowles, Science in Flux, NASAs Nuclear Program at Plum Brook station 1955 - 2005, The NASA History Series, June 2006.

GTS 1998 GTS-Duratek, Inc., NASA/Lewis Plum Brook Facility 1998 Confirmation Survey, Volume 1 - Survey Packages and Survey Results, November 1998.

Hagelin 2010 Karl W. Hagelin, Bremba K. Jones and Associates, NASA Plum Brook Reactor Facility Coordinates, Personal Communication, December 20, 2010.

MWH 2005 Montgomery Watson Harza, Inc. Soil Characterization Report, Plum Brook Reactor Facility, February 14, 2005.

NACA 1956 National Advisory Committee on Aeronautics, NACA Nuclear Reactor Plot Plan and Soil Boring Data, Drawing No. PF00101, Plot Plan and Soil Boring Data, Dec.

4, 1956.

NASA 1959 NASA, Final Hazards Summary Part II, Appendix D, Memorandum on the Geology and Hydrology of a Proposed Reactor site Near Sandusky, Ohio, 1959.

NASA 2007 NASA Safety and Mission Assurance Directorate, Final Status Survey Plan for the Plum Brook Reactor Facility, Revision 1, February 2007.

NASA 2007a NASA Safety and Mission Assurance Directorate, Decommissioning Plan for the Plum Brook Reactor Facility, Revision 6, July 2007.

PBRF 2009 Plum Brook Reactor Facility Technical Basis Document, Radionuclide Distributions and Adjusted DCGLs for Site Soils, PBRF-TBD-09-001, June 2009.

PBRF 2009a Plum Brook Reactor Facility Technical Basis Document, 44-10 NaI Detector MDCscan Values for Various Survey Conditions, PBRF-TBD-09-002, June 2009.

PNL 2010 Battelle Pacific Northwest Laboratories (PNL), Visual sample Plan, Version 5.9, 2010.

SAIC 2010 Science Applications International Corporation, 2010 Summary of Revised Closure Activities and August 2010 Monitoring Well Sampling for the Reactor Area, NASA Plum Brook Station, Sandusky, Ohio, October 19, 2010.

Tele 1987 Teledyne Isotopes, An Evaluation of the Plum Brook Reactor Facility and Documentation of Existing Conditions, Prepared for NASA Lewis Research Center, December 1987.

33

Plum Brook Reactor Facility FSSR Attachment 16, Rev. 0 USACE 2004 US Army Corps of Engineers Louisville District, Hydrological Report Plum Brook Reactor Facility Sandusky, Ohio, November 17, 2004.

USEPA 2002 Memorandum of Understanding, US Environmental Protection Agency and US Nuclear Regulatory Commission, Consultation and Finality on Decommissioning and Decontamination of Contaminated Sites, October 9, 2002.

USNRC 1998 US Nuclear Regulatory Commission, Minimum Detectable Concentrations with Typical survey Instruments for Various Contaminants and Field Conditions, NUREG 1507, June 1998.

USNRC 2000 US Nuclear Regulatory Commission, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM), NUREG-1575, Rev.1, August 2000.

USNRC 2006 US Nuclear Regulatory Commission, Consolidated Decommissioning Guidance, Characterization, Survey and Determination of Radiological Criteria, NUREG 1757, Vol. 2, Rev.1, September 2006.

7.0 Appendices Appendix A - Exhibits Appendix B - Survey Unit Maps and Tables Showing Measurement Locations Appendix C - Soil Sample Results 34

Plum Brook Reactor Facility Final Status Survey Report Attachment 16 Open Land Areas within Restricted Area And Outside Buffer Area Revision 0 Appendix A Exhibits

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix A, Rev. 0, Page 2 of 26 List of Exhibits Exhibit 1, PBRF Site Map Showing Characterization Survey Units ..................................................... 3 Exhibit 2, Southwest Area of the PBRF Site Looking West (8/2/11) .................................................... 4 Exhibit 3, Southwest Area of PBRF Site Looking North from Pentolite Road (8/29/11) .................... 5 Exhibit 4, Looking North From the South Fence West of Line 3 Road (9/13/11) ................................. 6 Exhibit 5, Southeast Portion of the Site Looking East from North of Pentolite Road (10/17/11) ......... 7 Exhibit 6, Looking East over Former WEMS Area (9/1/11) ................................................................. 8 Exhibit 7, Area outside Fence at SE Corner of the Site Looking Northeast (11/2/11) .......................... 9 Exhibit 8, View from Outside E. Boundary Fence Looking North from the South End (10/4/11) ..... 10 Exhibit 9, View of East-central Portion of the Site Looking East (9/21/11)........................................ 11 Exhibit 10, View of East-central Area of the Site Looking North (11/1/11) ....................................... 12 Exhibit 11, View of West-central Portion of the Site Looking South (9/29/11) .................................. 13 Exhibit 12, West-central Portion of the Site Looking South, Line 2 Road is on the Right (9/29/11) . 14 Exhibit 13, View toward the East from just North of Security Building (10/13/11) ........................... 15 Exhibit 14, View of Survey Unit OL-1-72 from East with Hot Laboratory in Background (9/1/11) .. 16 Exhibit 15, View from East of the Hot Lab Looking East ................................................................... 17 Exhibit 16, View Looking West toward Hot Laboratory and PPH (11/8/11) ...................................... 18 Exhibit 17, View Looking West toward Primary Pump House from Line 3 Road (9/1/11) ................ 19 Exhibit 18, View Looking NE toward Reactor Building (10/13/11) ................................................... 20 Exhibit 19, View Looking East - Reactor Building on Right (10/13/11) ............................................ 21 Exhibit 20, View Looking West toward Reactor Building and ATS Building (11/8/11) .................... 22 Exhibit 21, View Looking North inside Northern Extension of Boundary Fence (9/1/11) ................. 23 Exhibit 22, View of Northern Buffer Area North of Northern Fence Line (4/14/11).......................... 24 Exhibit 23, View South of ATS Building looking East, Showing Survey Unit OL-2-5 (4/14/11)...... 25 Exhibit 24, View East of E. Fence Line Looking South, Showing Survey Unit OL-2-1 (6/1/11) ...... 26

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix A, Rev. 0, Page 3 of 26 Exhibit 1, PBRF Site Map Showing Characterization Survey Units Exhibit 1 Note: Figure is from the 2005 MWH Characterization report [MWH 2005].

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix A, Rev. 0, Page 4 of 26 Exhibit 2, Southwest Area of the PBRF Site Looking West (8/2/11)

(All or parts of Survey Units OL-1-47 through OL-1-54 are shown.)

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix A, Rev. 0, Page 5 of 26 Exhibit 3, Southwest Area of PBRF Site Looking North from Pentolite Road (8/29/11)

(All or parts of Survey Units OL-1-50, 1-54, 1-79, 1-73, 1-74 and 1-80 are shown)

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix A, Rev. 0, Page 6 of 26 Exhibit 4, Looking North From the South Fence West of Line 3 Road (9/13/11)

(Survey Unit OL-1-75 is in the foreground and portions of OL-1-73, 1-74 and 1-80 are visible.)

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix A, Rev. 0, Page 7 of 26 Exhibit 5, Southeast Portion of the Site Looking East from North of Pentolite Road (10/17/11)

(Survey Units OL-1-96 and OL-1-97 are visible as well as portions of OL-1-27 through OL-1-29.)

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix A, Rev. 0, Page 8 of 26 Exhibit 6, Looking East over Former WEMS Area (9/1/11)

(Survey Unit OL-1-56 with eastern portion of OL-1-97 in foreground)

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix A, Rev. 0, Page 9 of 26 Exhibit 7, Area outside Fence at SE Corner of the Site Looking Northeast (11/2/11)

(Survey Unit OL-1-98 is in the foreground with southern portion of OL-2-1 visible in background)

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix A, Rev. 0, Page 10 of 26 Exhibit 8, View from Outside E. Boundary Fence Looking North from the South End (10/4/11)

(Survey Unit OL-2-1 extends north along the fence.)

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix A, Rev. 0, Page 11 of 26 Exhibit 9, View of East-central Portion of the Site Looking East (9/21/11)

(The area north of the former ERB; portions of Survey Units OL-1-63, 1-64, 1-69 and 1-70 are visible.)

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix A, Rev. 0, Page 12 of 26 Exhibit 10, View of East-central Area of the Site Looking North (11/1/11)

(All or portions of Survey Units OL-1-90, 1-92, 1-69, 1-69 and 1-70 are visible.)

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix A, Rev. 0, Page 13 of 26 Exhibit 11, View of West-central Portion of the Site Looking South (9/29/11)

(All or portions of Survey Units Ol-1-78, 1-79, 1-80, 1-53, 1-54, and 1-74 are visible.)

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix A, Rev. 0, Page 14 of 26 Exhibit 12, West-central Portion of the Site Looking South, Line 2 Road is on the Right (9/29/11)

(All or portions of Survey Units OL-1-82, 1-76, 1-77, 1-51, and 1-52 are visible)

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix A, Rev. 0, Page 15 of 26 Exhibit 13, View toward the East from just North of Security Building (10/13/11)

(This view shows primarily Survey Unit OL-1-83, with a portion of OL-1-82 on the right.)

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix A, Rev. 0, Page 16 of 26 Exhibit 14, View of Survey Unit OL-1-72 from East with Hot Laboratory in Background (9/1/11)

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix A, Rev. 0, Page 17 of 26 Exhibit 15, View from East of the Hot Lab Looking East (Survey Unit OL-1-91 is in the foreground with OL-1-68 and 1-69 in the background.)

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix A, Rev. 0, Page 18 of 26 Exhibit 16, View Looking West toward Hot Laboratory and PPH (11/8/11)

(All or portions of Survey Units OL-1-61, 1-62, 1-67, 1-68, 1-89, 1-90 and 1-91 are visible.)

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix A, Rev. 0, Page 19 of 26 Exhibit 17, View Looking West toward Primary Pump House from Line 3 Road (9/1/11)

(Survey Units OL-1-71 and 1-72 are visible)

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix A, Rev. 0, Page 20 of 26 Exhibit 18, View Looking NE toward Reactor Building (10/13/11)

(Survey Unit OL-1-84 and portions of OL-1-85 and 1-86 are visible.)

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix A, Rev. 0, Page 21 of 26 Exhibit 19, View Looking East - Reactor Building on Right (10/13/11)

(Survey Unit OL-1-85 is in the foreground, OL-1-86 in the center and a portion of OL-1-87 is visible in the background.)

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix A, Rev. 0, Page 22 of 26 Exhibit 20, View Looking West toward Reactor Building and ATS Building (11/8/11)

(All or portions of Survey Units OL-1-65, 1-66, 1-88 and 1-89 are visible.)

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix A, Rev. 0, Page 23 of 26 Exhibit 21, View Looking North inside Northern Extension of Boundary Fence (9/1/11)

(This view shows mostly Survey Unit OL-1-46 with a portion of OL-2-3 visible to the right of Line 3 Road)

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix A, Rev. 0, Page 24 of 26 Exhibit 22, View of Northern Buffer Area North of Northern Fence Line (4/14/11)

(This view shows primarily Survey Unit OL-2-4.)

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix A, Rev. 0, Page 25 of 26 Exhibit 23, View South of ATS Building looking East, Showing Survey Unit OL-2-5 (4/14/11)

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix A, Rev. 0, Page 26 of 26 Exhibit 24, View East of E. Fence Line Looking South, Showing Survey Unit OL-2-1 (6/1/11)

Plum Brook Reactor Facility Final Status Survey Report Attachment 16 Open Land Areas within the Restricted Area and Outside Buffer Areas Revision 0 Appendix B Survey Unit Maps and Tables Showing Measurement Locations

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 2 of 62 Index of Open Land Area Survey Unit Maps and Tables of Coordinates Page Number Survey Unit Description Number of Pages OL-1-46 Restricted Area North of the BM Grid Line 4 1 OL-1-47 Restricted Area Grids AZ-90, AZ-91, BA-90, BA-91 5 1 OL-1-48 Restricted Area Grids BB-90, BB-91 6 1 OL-1-49 Restricted Area Grids AZ-92, BA-92, BB-92 (South 90) 7 1 OL-1-50 Restricted Area Grids AZ-93, BA-93, BB-93 (South 90) 8 1 OL-1-51 Restricted Area Grids BC-90, BD-90 9 1 OL-1-52 Restricted Area Grids BC-91, BD-91 10 1 OL-1-53 Restricted Area Grids BB-92 (North 10), BC-92, BD-92 11 1 OL-1-54 Restricted Area Grids BB-93 (North 10), BC-93, BD-93 12 1 OL-1-55 Restricted Area Grids BO-93, BP-93 13 1 Restricted Area Grids AZ-100 inside fence, BA-100 inside fence, BA-OL-1-56 14 1 100 and BA-101 spill area outside fence OL-1-57 Restricted Area Grids BB-100, BC-100 15 1 OL-1-58 Restricted Area Grids BD-100, BE-100 16 1 OL-1-59 Restricted Area Grids BL-99, BL-100 17 1 OL-1-60 Restricted Area Grids BK-99, BK-100 18 1 OL-1-61 Restricted Area Grids BJ-99, BJ-100 19 1 OL-1-62 Restricted Area Grids BH-99, BH-100 20 1 OL-1-63 Restricted Area Grids BG-99, BG-100 21 1 OL-1-64 Restricted Area Grids BF-99, BF-100 22 1 OL-1-65 Restricted Area Grids BL-97, BL-98 23 1 OL-1-66 Restricted Area Grids BK-97, BK-98 24 1 OL-1-67 Restricted Area Grids BJ-97, BJ-98 25 1 OL-1-68 Restricted Area Grids BH-97, BH-98 26 1 OL-1-69 Restricted Area Grids BG-97, BG-98 27 1 OL-1-70 Restricted Area Grids BF-97, BF-98 28 1 Restricted Area Grids BJ-93, 94, 95, & BK-94, 95 land between the HL, OL-1-71 28 1 RB, PPH buildings and Line 3 Road Restricted Area Grids BG-93, 94, 95, & BH-93, 94, 95 land between the OL-1-72 30 1 HL buildings and Line 3 Road OL-1-73 Restricted Area Grids AZ-94, BA-94, BB-94 (South 90) 31 1 OL-1-74 Restricted Area Grids BB-94 (North 10), BC-94, BD-94 32 1 OL-1-75 Restricted Area Grids BA-95 through BG-95 land west of Line 3 Road 33 1 OL-1-76 Restricted Area Grids BE-90, BF-90, BG-90 (South 40) 34 1 OL-1-77 Restricted Area Grids BE-91, BF-91 35 1 OL-1-78 Restricted Area Grids BE-92, BF-92 36 1 OL-1-79 Restricted Area Grids BE-93, BF-93 37 1 OL-1-80 Restricted Area Grids BE-94, BF-94 38 1 Restricted Area Grids BG-92 east 25, BG-93, BG-94, BG-95 west of OL-1-81 39 1 Line 3 Road OL-1-82 Restricted Area Grids BG-90 north 60, BG-91, BG-92 west 75 40 1 OL-1-83 Restricted Area Grids BH-90, BH-91, BH-92 41 1 Restricted Area Grids BJ-90, BJ-91, BJ-92 north of road, BK-90 to BK-OL-1-84 42 1 92 south 50

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 3 of 62 Index of Open Land Area Survey Unit Maps and Tables of Coordinates Page Number Survey Unit Description Number of Pages Restricted Area Grids BK-90 north 50, BK-91 NW 50, BL-90, BL-91 OL-1-85 43 1 west 50 Restricted Area Grids BK-91 ne 50, BL-91 east 50, BK-92, BL-92, BK-OL-1-86 44 1 93 & BL-93 to RB east wall Restricted Area Grids BK-93, BL-93 BK-94, BL-94, BK-95, BL-95 OL-1-87 45 1 between RB east Wall, PPH north wall, Line 3 Road, and North Road Restricted Area Grids BL-95 & 96 east of L3 Road, BK-95 & 96 East of OL-1-88 46 1 L3 Road north 50 Restricted Area Grids BK-95 & 96 East of L3 Road south 50, BJ-95 &

OL-1-89 47 1 96 east of L3 Road OL-1-90 Restricted Area Grids BF-95, BG-95, BH-95 east of L3 Road 48 1 OL-1-91 Restricted Area Grids BG-96, BH-96 49 1 OL-1-92 Restricted Area Grids BE-96, BF-96 50 1 OL-1-93 Restricted Area Grids BC-95, BD-95, BE-95 east of L3 Road 51 1 OL-1-94 Restricted Area Grids BC-96, BD-96 52 1 OL-1-95 Restricted Area Grids AZ-95, BA-95, BB-95, BB-96 east of L3 Road 53 1 OL-1-96 Restricted Area Grids AZ-96, AZ-97, BA-96, BA-97 54 1 OL-1-97 Restricted Area Grids AZ-98, AZ-99, BA-98, BA-99 55 1 OL-1-98 Grids AZ-101 & BA-101 outside of the RA Fence 56 1 OL-2-1 Restricted Area Buffer Zone - Section #1 57 1 OL-2-2 Restricted Area Buffer Zone - Section #2 58 1 OL-2-3 Restricted Area Buffer Zone - Section #3 59 1 OL-2-4 Restricted Area Buffer Zone - Section #4 60 1 OL-2-5 Restricted Area Buffer Zone - Section #5 61 1 OL-2-6 Restricted Area Buffer Zone - Section #6 62 1 Appendix B Notes:

1. The survey units listed in the index and shown on each map are described by their location relative to the grid system shown in Figure 1 of the main text. Each survey unit is identified by the grids it either fully or partially occupies. Grids are identified by the SW corner grid coordinates. For example Survey Unit OL-1-47 partially occupies grids AZ-90, AZ-91 and fully occupies grids BA-90 and BA-91.

2. Grid pins are identified on each survey unit VSP map by their coordinates in the grid.

They are the reference location (0,0) for the local x,y coordinates of each sample location in the survey unit.

3. The VSP maps show the survey unit open land soil area in color. Yellow denotes Class1 and blue, Class 2. The maps include other features within and adjacent to the survey unit area, but which are not part of the soil area undergoing FSS. These include roadways and other paved areas (usually colored gray) and building footprints (usually colored dark gray).

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 4 of 62 Survey Unit OL-1-46 Restricted Area North of the BM Grid Line SP-10 SP-11 SP-9 SP-7 SP-8 SP-6 SP-4 SP-5 SP-2 SP-3 Grid Pin BM-94 SP-1 OL 1-46 Restricted Area North of the BM Grid Line Measurement Locations X Coord Y Coord Label Type 36.3 -13.0 SP-1 Systematic

-9.6 66.4 SP-2 Systematic 82.2 66.4 SP-3 Systematic 36.3 145.9 SP-4 Systematic 128.0 145.9 SP-5 Systematic 82.2 225.3 SP-6 Systematic 36.3 304.8 SP-7 Systematic 128.0 304.8 SP-8 Systematic 82.2 384.2 SP-9 Systematic 36.3 463.7 SP-10 Systematic 128.0 463.7 SP-11 Systematic All sample points are measured from Grid Pin BM-94.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 5 of 62 Survey Unit OL-1-47 Restricted Area Grids AZ-90, AZ-91, BA-90, BA-91 SP-8 SP-9 SP-10 SP-11 SP-5 SP-6 SP-7 Grid Pin BA-91 SP-1 SP-2 SP-3 SP-4 OL 1-47 Area: Restricted Area Grids AZ-90, AZ-91, BA-90, BA-91 Measurement Locations X Coord Y Coord Label Type

-54.3 1.1 SP-1 Systematic

-8.0 1.1 SP-2 Systematic 38.3 1.1 SP-3 Systematic 84.6 1.1 SP-4 Systematic

-31.2 41.3 SP-5 Systematic 15.2 41.3 SP-6 Systematic 61.5 41.3 SP-7 Systematic

-54.3 81.4 SP-8 Systematic

-8.0 81.4 SP-9 Systematic 38.3 81.4 SP-10 Systematic 84.6 81.4 SP-11 Systematic All sample points are measured from Grid Pin BA-91.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 6 of 62 Survey Unit OL-1-48 Restricted Area Grids BB-90, BB-91 SP-9 SP-10 SP-11 SP-12 SP-5 SP-6 SP-7 SP-8 SP-1 SP-2 SP-3 SP-4 Grid Pin BB-91 OL 1-48 Area: Restricted Area Grids BB-90, BB-91 Measurement Locations X Coord Y Coord Label Type

-46.3 12.8 SP-1 Systematic 0.6 12.8 SP-2 Systematic 47.6 12.8 SP-3 Systematic 94.6 12.8 SP-4 Systematic

-69.8 53.5 SP-5 Systematic

-22.9 53.5 SP-6 Systematic 24.1 53.5 SP-7 Systematic 71.1 53.5 SP-8 Systematic

-46.3 94.2 SP-9 Systematic 0.6 94.2 SP-10 Systematic 47.6 94.2 SP-11 Systematic 94.6 94.2 SP-12 Systematic All sample points are measured from Grid Pin BB-91.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 7 of 62 Survey Unit OL-1-49 Restricted Area Grids AZ-92, BA-92, BB-92 (South 90)

SP-11 SP-12 SP-8 SP-9 SP-10 SP-6 SP-7 SP-3 SP-4 SP-5 Grid Pin BA-92 SP-1 SP-2 OL 1-49 Area: Restricted Area Grids AZ-92, BA-92, BB-92 (South 90)

Measurement Locations X Coord Y Coord Label Type 24.6 -7.0 SP-1 Systematic 71.7 -7.0 SP-2 Systematic 1.1 33.7 SP-3 Systematic 48.1 33.7 SP-4 Systematic 95.2 33.7 SP-5 Systematic 24.6 74.5 SP-6 Systematic 71.7 74.5 SP-7 Systematic 1.1 115.3 SP-8 Systematic 48.1 115.3 SP-9 Systematic 95.2 115.3 SP-10 Systematic 24.6 156.1 SP-11 Systematic 71.7 156.1 SP-12 Systematic All sample points are measured from Grid Pin BA-92.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 8 of 62 Survey Unit OL-1-50 Restricted Area Grids AZ-93, BA-93, BB-93 (South 90)

SP-11 SP-12 SP-8 SP-9 SP-10 SP-6 SP-7 SP-3 SP-4 SP-5 SP-1 SP-2 Grid Pin BA-93 OL 1-50 Area: Restricted Area Grids AZ-93, BA-93, BB-93 (South 90)

Measurement Locations X Coord Y Coord Label Type 28.8 10.8 SP-1 Systematic 75.9 10.8 SP-2 Systematic 5.3 51.6 SP-3 Systematic 52.4 51.6 SP-4 Systematic 99.5 51.6 SP-5 Systematic 28.8 92.4 SP-6 Systematic 75.9 92.4 SP-7 Systematic 5.3 133.2 SP-8 Systematic 52.4 133.2 SP-9 Systematic 99.5 133.2 SP-10 Systematic 28.8 174.0 SP-11 Systematic 75.9 174.0 SP-12 Systematic All sample points are measured from Grid Pin BA-93.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 9 of 62 Survey Unit OL-1-51 Restricted Area Grids BC-90, BD-90 SP-11 SP-12 SP-9 SP-10 SP-7 SP-8 SP-5 SP-6 SP-3 SP-4 SP-1 SP-2 Grid Pin BC-91 OL 1-51 Area: Restricted Area Grids BC-90, BD-90 Measurement Locations X Coord Y Coord Label Type

-70.8 6.2 SP-1 Systematic

-27.1 6.2 SP-2 Systematic

-48.9 44.0 SP-3 Systematic

-5.2 44.0 SP-4 Systematic

-70.8 81.9 SP-5 Systematic

-27.1 81.9 SP-6 Systematic

-48.9 119.7 SP-7 Systematic

-5.2 119.7 SP-8 Systematic

-70.8 157.6 SP-9 Systematic

-27.1 157.6 SP-10 Systematic

-48.9 195.4 SP-11 Systematic

-5.2 195.4 SP-12 Systematic All sample points are measured from Grid Pin BC-91.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 10 of 62 Survey Unit OL-1-52 Restricted Area Grids BC-91, BD-91 SP-11 SP-12 SP-8 SP-9 SP-10 SP-6 SP-7 SP-3 SP-4 SP-5 SP-1 SP-2 Grid Pin BC-91 OL 1-52 Area: Restricted Area Grids BC-91, BD-91 Measurement Locations X Coord Y Coord Label Type 27.9 9.4 SP-1 Systematic 74.3 9.4 SP-2 Systematic 4.7 49.6 SP-3 Systematic 51.1 49.6 SP-4 Systematic 97.5 49.6 SP-5 Systematic 27.9 89.8 SP-6 Systematic 74.3 89.8 SP-7 Systematic 4.7 130.0 SP-8 Systematic 51.1 130.0 SP-9 Systematic 97.5 130.0 SP-10 Systematic 27.9 170.2 SP-11 Systematic 74.3 170.2 SP-12 Systematic All sample points are measured from Grid Pin BC-91.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 11 of 62 Survey Unit OL-1-53 Restricted Area Grids BB-92 (North 10), BC-92, BD-92 SP-13 SP-14 SP-15 SP-11 SP-12 SP-8 SP-9 SP-10 SP-6 SP-7 SP-3 SP-4 SP-5 SP-1 SP-2 Grid Pin BC-92 OL 1-53 Area: Restricted Area Grids BB-92 (North 10), BC-92, BD-92 Measurement Locations X Coord Y Coord Label Type 28 -8 SP-1 Systematic 76 -8 SP-2 Systematic 4 33 SP-3 Systematic 52 33 SP-4 Systematic 99 33 SP-5 Systematic 28 75 SP-6 Systematic 76 75 SP-7 Systematic 4 116 SP-8 Systematic 52 116 SP-9 Systematic 99 116 SP-10 Systematic 28 157 SP-11 Systematic 76 157 SP-12 Systematic 4 198 SP-13 Systematic 52 198 SP-14 Systematic 99 198 SP-15 Systematic All sample points are measured from Grid Pin BC-92.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 12 of 62 Survey Unit OL-1-54 Restricted Area Grids BB-93 (North 10), BC-93, BD-93 SP-11 SP-12 SP-9 SP-10 SP-7 SP-8 SP-5 SP-6 SP-3 SP-4 SP-1 SP-2 Grid Pin BC-93 OL 1-54 Area: Restricted Area Grids BB-93 (North 10), BC-93, BD-93 Measurement Locations X Coord Y Coord Label Type 31 -8 SP-1 Systematic 79 -8 SP-2 Systematic 8 34 SP-3 Systematic 55 34 SP-4 Systematic 31 75 SP-5 Systematic 79 75 SP-6 Systematic 8 116 SP-7 Systematic 55 116 SP-8 Systematic 31 157 SP-9 Systematic 79 157 SP-10 Systematic 8 198 SP-11 Systematic 55 198 SP-12 Systematic All sample points are measured from Grid Pin BC-93.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 13 of 62 Survey Unit OL-1-55 Restricted Area Grids BO-93, BP-93 SP-11 SP-12 SP-8 SP-9 SP-10 SP-6 SP-7 SP-3 SP-4 SP-5 SP-1 SP-2 Grid Pin BO-93 OL 1-55 Area: Restricted Area Grids BO-93, BP-93 Measurement Locations X Coord Y Coord Label Type 25 5 SP-1 Systematic 74 5 SP-2 Systematic 1 46 SP-3 Systematic 49 46 SP-4 Systematic 98 46 SP-5 Systematic 25 88 SP-6 Systematic 74 88 SP-7 Systematic 1 130 SP-8 Systematic 49 130 SP-9 Systematic 98 130 SP-10 Systematic 25 172 SP-11 Systematic 74 172 SP-12 Systematic All sample points are measured from Grid Pin BO-93.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 14 of 62 Survey Unit OL-1-56 Restricted Area Grids AZ-100 inside fence, BA-100 inside fence, BA-100 and BA-101 spill area outside fence SP-8 SP-9 SP-10 SP-11 SP-5 SP-6 SP-7 SP-3 SP-4 SP-1 SP-2 Grid Pin BA-100 OL 1-56 Area: Restricted Area Grids AZ-100 inside fence, BA-100 inside fence, BA-100 and BA-101 spill area outside fence Measurement Locations X Coord Y Coord Label Type 20 -13 SP-1 Systematic 56 -13 SP-2 Systematic 74 18 SP-3 Systematic 110 18 SP-4 Systematic 20 49 SP-5 Systematic 56 49 SP-6 Systematic 92 49 SP-7 Systematic 2 80 SP-8 Systematic 38 80 SP-9 Systematic 74 80 SP-10 Systematic 110 80 SP-11 Systematic All sample points are measured from Grid Pin BA-100.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 15 of 62 Survey Unit OL-1-57 Restricted Area Grids BB-100, BC-100 SP-11 SP-12 SP-9 SP-10 SP-7 SP-8 SP-5 SP-6 SP-3 SP-4 Grid Pin BB-100 SP-1 SP-2 OL 1-57 Area: Restricted Area Grids BB-100, BC-100 Measurement Locations X Coord Y Coord Label Type 30 1 SP-1 Systematic 76 1 SP-2 Systematic 7 41 SP-3 Systematic 53 41 SP-4 Systematic 30 80 SP-5 Systematic 76 80 SP-6 Systematic 7 120 SP-7 Systematic 53 120 SP-8 Systematic 30 159 SP-9 Systematic 76 159 SP-10 Systematic 7 199 SP-11 Systematic 53 199 SP-12 Systematic All sample points are measured from Grid Pin BB-100.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 16 of 62 Survey Unit OL-1-58 Restricted Area Grids BD-100, BE-100 SP-11 SP-12 SP-9 SP-10 SP-7 SP-8 SP-5 SP-6 SP-3 SP-4 Grid Pin BD-100 SP-1 SP-2 OL 1-58 Area: Restricted Area Grids BD-100, BE-100 Measurement Locations X Coord Y Coord Label Type 8 8 SP-1 Systematic 51 8 SP-2 Systematic 30 45 SP-3 Systematic 73 45 SP-4 Systematic 8 83 SP-5 Systematic 51 83 SP-6 Systematic 30 120 SP-7 Systematic 73 120 SP-8 Systematic 8 158 SP-9 Systematic 51 158 SP-10 Systematic 30 196 SP-11 Systematic 73 196 SP-12 Systematic All sample points are measured from Grid Pin BD-100.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 17 of 62 Survey Unit OL-1-59 Restricted Area Grids BL-99, BL-100 SP-8 SP-9 SP-10 SP-11 SP-5 SP-6 SP-7 SP-1 SP-2 SP-3 SP-4 Grid Pin BL-99 OL 1-59 Area: Restricted Area Grids BL-99, BL-100 Measurement Locations X Coord Y Coord Label Type 15 4 SP-1 Systematic 65 4 SP-2 Systematic 115 4 SP-3 Systematic 165 4 SP-4 Systematic 40 47 SP-5 Systematic 90 47 SP-6 Systematic 140 47 SP-7 Systematic 15 91 SP-8 Systematic 65 91 SP-9 Systematic 115 91 SP-10 Systematic 165 91 SP-11 Systematic All sample points are measured from Grid Pin BL-99.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 18 of 62 Survey Unit OL-1-60 Restricted Area Grids BK-99, BK-100 SP-8 SP-9 SP-10 SP-11 SP-5 SP-6 SP-7 SP-1 SP-2 SP-3 SP-4 Grid Pin BK-99 OL 1-60 Area: Restricted Area Grids BK-99, BK-100 Measurement Locations X Coord Y Coord Label Type 20 8 SP-1 Systematic 62 8 SP-2 Systematic 105 8 SP-3 Systematic 147 8 SP-4 Systematic 84 45 SP-5 Systematic 126 45 SP-6 Systematic 168 45 SP-7 Systematic 20 82 SP-8 Systematic 62 82 SP-9 Systematic 105 82 SP-10 Systematic 147 82 SP-11 Systematic All sample points are measured from Grid Pin BK-99.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 19 of 62 Survey Unit OL-1-61 Restricted Area Grids BJ-99, BJ-100 SP-9 SP-10 SP-11 SP-5 SP-6 SP-7 SP-8 SP-1 SP-2 SP-3 SP-4 Grid Pin BJ-99 OL 1-61 Area: Restricted Area Grids BJ-99, BJ-100 Measurement Locations X Coord Y Coord Label Type 42 3 SP-1 Systematic 84 3 SP-2 Systematic 126 3 SP-3 Systematic 167 3 SP-4 Systematic 21 39 SP-5 Systematic 63 39 SP-6 Systematic 105 39 SP-7 Systematic 146 39 SP-8 Systematic 84 76 SP-9 Systematic 126 76 SP-10 Systematic 167 76 SP-11 Systematic All sample points are measured from Grid Pin BJ-99.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 20 of 62 Survey Unit OL-1-62 Restricted Area Grids BH-99, BH-100 SP-8 SP-9 SP-10 SP-11 SP-5 SP-6 SP-7 SP-1 SP-2 SP-3 SP-4 Grid Pin BH-99 OL 1-62 Area: Restricted Area Grids BH-99, BH-100 Measurement Locations X Coord Y Coord Label Type 23 0 SP-1 Systematic 74 0 SP-2 Systematic 124 0 SP-3 Systematic 174 0 SP-4 Systematic 48 44 SP-5 Systematic 99 44 SP-6 Systematic 149 44 SP-7 Systematic 23 88 SP-8 Systematic 74 88 SP-9 Systematic 124 88 SP-10 Systematic 174 88 SP-11 Systematic All sample points are measured from Grid Pin BH-99.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 21 of 62 Survey Unit OL-1-63 Restricted Area Grids BG-99, BG-100 SP-8 SP-9 SP-10 SP-11 SP-5 SP-6 SP-7 SP-1 SP-2 SP-3 SP-4 Grid Pin BG-99 OL 1-63 Area: Restricted Area Grids BG-99, BG-100 Measurement Locations X Coord Y Coord Label Type 12 4 SP-1 Systematic 63 4 SP-2 Systematic 113 4 SP-3 Systematic 163 4 SP-4 Systematic 37 48 SP-5 Systematic 88 48 SP-6 Systematic 138 48 SP-7 Systematic 12 92 SP-8 Systematic 63 92 SP-9 Systematic 113 92 SP-10 Systematic 163 92 SP-11 Systematic All sample points are measured from Grid Pin BG-99.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 22 of 62 Survey Unit OL-1-64 Restricted Area Grids BF-99, BF-100 SP-8 SP-9 SP-10 SP-11 SP-5 SP-6 SP-7 SP-1 SP-2 SP-3 SP-4 Grid Pin BF-99 OL 1-64 Area: Restricted Area Grids BF-99, BF-100 Measurement Locations X Coord Y Coord Label Type 25 6 SP-1 Systematic 75 6 SP-2 Systematic 126 6 SP-3 Systematic 176 6 SP-4 Systematic 50 49 SP-5 Systematic 100 49 SP-6 Systematic 151 49 SP-7 Systematic 25 93 SP-8 Systematic 75 93 SP-9 Systematic 126 93 SP-10 Systematic 176 93 SP-11 Systematic All sample points are measured from Grid Pin BF-99.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 23 of 62 Survey Unit OL-1-65 Restricted Area Grids BL-97, BL-98 SP-9 SP-10 SP-11 SP-5 SP-6 SP-7 SP-8 SP-1 SP-2 SP-3 SP-4 Grid Pin BL-97 OL 1-65 Area: Restricted Area Grids BL-97, BL-98 Measurement Locations X Coord Y Coord Label Type 20 6 SP-1 Systematic 71 6 SP-2 Systematic 121 6 SP-3 Systematic 172 6 SP-4 Systematic 46 50 SP-5 Systematic 96 50 SP-6 Systematic 147 50 SP-7 Systematic 197 50 SP-8 Systematic 20 94 SP-9 Systematic 71 94 SP-10 Systematic 121 94 SP-11 Systematic All sample points are measured from Grid Pin BL-97.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 24 of 62 Survey Unit OL-1-66 Restricted Area Grids BK-97, BK-98 SP-8 SP-9 SP-10 SP-11 SP-5 SP-6 SP-7 SP-1 SP-2 SP-3 SP-4 Grid Pin BK-97 OL 1-66 Area: Restricted Area Grids BK-97, BK-98 Measurement Locations X Coord Y Coord Label Type 23 4 SP-1 Systematic 75 4 SP-2 Systematic 128 4 SP-3 Systematic 180 4 SP-4 Systematic 49 50 SP-5 Systematic 102 50 SP-6 Systematic 154 50 SP-7 Systematic 23 95 SP-8 Systematic 75 95 SP-9 Systematic 128 95 SP-10 Systematic 180 95 SP-11 Systematic All sample points are measured from Grid Pin BK-97.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 25 of 62 Survey Unit OL-1-67 Restricted Area Grids BJ-97, BJ-98 SP-8 SP-9 SP-10 SP-11 SP-5 SP-6 SP-7 SP-1 SP-2 SP-3 SP-4 Grid Pin BJ-97 OL 1-67 Area: Restricted Area Grids BJ-97, BJ-98 Measurement Locations X Coord Y Coord Label Type 27 0 SP-1 Systematic 83 0 SP-2 Systematic 139 0 SP-3 Systematic 194 0 SP-4 Systematic 55 49 SP-5 Systematic 111 49 SP-6 Systematic 167 49 SP-7 Systematic 27 97 SP-8 Systematic 83 97 SP-9 Systematic 139 97 SP-10 Systematic 194 97 SP-11 Systematic All sample points are measured from Grid Pin BJ-97.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 26 of 62 Survey Unit OL-1-68 Restricted Area Grids BH-97, BH-98 SP-8 SP-9 SP-10 SP-11 SP-5 SP-6 SP-7 SP-1 SP-2 SP-3 SP-4 Grid Pin BH-97 OL 1-68 Area: Restricted Area Grids BH-97, BH-98 Measurement Locations X Coord Y Coord Label Type 21 6 SP-1 Systematic 74 6 SP-2 Systematic 127 6 SP-3 Systematic 179 6 SP-4 Systematic 48 52 SP-5 Systematic 100 52 SP-6 Systematic 153 52 SP-7 Systematic 21 97 SP-8 Systematic 74 97 SP-9 Systematic 127 97 SP-10 Systematic 179 97 SP-11 Systematic All sample points are measured from Grid Pin BH-97.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 27 of 62 Survey Unit OL-1-69 Restricted Area Grids BG-97, BG-98 SP-8 SP-9 SP-10 SP-11 SP-5 SP-6 SP-7 SP-1 SP-2 SP-3 SP-4 Grid Pin BG-97 OL 1-69 Area: Restricted Area Grids BG-97, BG-98 Measurement Locations X Coord Y Coord Label Type 23 2 SP-1 Systematic 79 2 SP-2 Systematic 134 2 SP-3 Systematic 189 2 SP-4 Systematic 51 50 SP-5 Systematic 106 50 SP-6 Systematic 162 50 SP-7 Systematic 23 98 SP-8 Systematic 79 98 SP-9 Systematic 134 98 SP-10 Systematic 189 98 SP-11 Systematic All sample points are measured from Grid Pin BG-97.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 28 of 62 Survey Unit OL-1-70 Restricted Area Grids BF-97, BF-98 SP-8 SP-9 SP-10 SP-11 SP-5 SP-6 SP-7 SP-1 SP-2 SP-3 SP-4 Grid Pin BF-97 OL 1-70 Area: Restricted Area Grids BF-97, BF-98 Measurement Locations X Coord Y Coord Label Type 24 4 SP-1 Systematic 77 4 SP-2 Systematic 129 4 SP-3 Systematic 182 4 SP-4 Systematic 51 50 SP-5 Systematic 103 50 SP-6 Systematic 156 50 SP-7 Systematic 24 95 SP-8 Systematic 77 95 SP-9 Systematic 129 95 SP-10 Systematic 182 95 SP-11 Systematic All sample points are measured from Grid Pin BF-97.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 29 of 62 Survey Unit OL-1-71 Restricted Area Grids BJ-93, 94, 95, & BK-94, 95 land between the HL, RB, PPH buildings and Line 3 Road SP-10 SP-11 SP-8 SP-9 SP-5 SP-6 SP-7 SP-1 SP-2 SP-3 SP-4 Grid Pin BJ-95 OL 1-71 Area: Restricted Area Grids BJ-93, 94, 95, & BK-94, 95 land between the HL, RB, PPH buildings and Line 3 Road Measurement Locations X Coord Y Coord Label Type

-117 1 SP-1 Systematic

-72 1 SP-2 Systematic

-26 1 SP-3 Systematic 20 1 SP-4 Systematic

-94 41 SP-5 Systematic

-49 41 SP-6 Systematic

-3 41 SP-7 Systematic

-26 80 SP-8 Systematic 20 80 SP-9 Systematic

-49 120 SP-10 Systematic

-3 120 SP-11 Systematic All sample points are measured from Grid Pin BJ-95.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 30 of 62 Survey Unit OL-1-72 Restricted Area Grids BG-93, 94, 95, & BH-93, 94, 95 land between the HL buildings and Line 3 Road SP-8 SP-9 SP-10 SP-11 SP-5 SP-6 SP-7 SP-1 SP-2 SP-3 SP-4 Grid Pin BH-95 OL 1-72 Area: Restricted Area Grids BG-93, 94, 95, & BH-93, 94, 95 land between the HL buildings and Line 3 Road Measurement Locations X Coord Y Coord Label Type

-134 5 SP-1 Systematic

-90 5 SP-2 Systematic

-46 5 SP-3 Systematic

-2 5 SP-4 Systematic

-112 44 SP-5 Systematic

-68 44 SP-6 Systematic

-24 44 SP-7 Systematic

-134 82 SP-8 Systematic

-90 82 SP-9 Systematic

-46 82 SP-10 Systematic

-2 82 SP-11 Systematic All sample points are measured from Grid Pin BH-95.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 31 of 62 Survey Unit OL-1-73 Restricted Area Grids AZ-94, BA-94, BB-94 (South 90)

SP-11 SP-12 SP-8 SP-9 SP-10 SP-6 SP-7 SP-3 SP-4 SP-5 SP-1 SP-2 Grid Pin BA-94 OL 1-73 Area: Restricted Area Grids AZ-94, BA-94, BB-94 (South 90)

Measurement Locations X Coord Y Coord Label Type 24 5 SP-1 Systematic 72 5 SP-2 Systematic 0 47 SP-3 Systematic 48 47 SP-4 Systematic 97 47 SP-5 Systematic 24 89 SP-6 Systematic 72 89 SP-7 Systematic 0 130 SP-8 Systematic 48 130 SP-9 Systematic 97 130 SP-10 Systematic 24 172 SP-11 Systematic 72 172 SP-12 Systematic All sample points are measured from Grid Pin BA-94.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 32 of 62 Survey Unit OL-1-74 Restricted Area Grids BB-94 (North 10), BC-94, BD-94 SP-11 SP-12 SP-8 SP-9 SP-10 SP-6 SP-7 SP-3 SP-4 SP-5 SP-1 SP-2 Grid Pin BC-94 OL 1-74 Area: Restricted Area Grids BB-94 (North 10), BC-94, BD-94 Measurement Locations X Coord Y Coord Label Type 28 19 SP-1 Systematic 76 19 SP-2 Systematic 5 60 SP-3 Systematic 52 60 SP-4 Systematic 100 60 SP-5 Systematic 28 101 SP-6 Systematic 76 101 SP-7 Systematic 5 143 SP-8 Systematic 52 143 SP-9 Systematic 100 143 SP-10 Systematic 28 184 SP-11 Systematic 76 184 SP-12 Systematic All sample points are measured from Grid Pin BC-94.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 33 of 62 Survey Unit OL-1-75 Restricted Area Grids BA-95 through BG-95 land west of Line 3 Road SP-13 SP-12 SP-11 SP-10 SP-9 SP-8 SP-7 SP-6 SP-5 SP-4 SP-3 SP-2 SP-1 Grid Pin BA-95 OL 1-75 Area: Restricted Area Grids BA-95 through BG-95 land west of Line 3 Road Measurement Locations X Coord Y Coord Label Type 1 6 SP-1 Systematic 29 55 SP-2 Systematic 1 104 SP-3 Systematic 29 153 SP-4 Systematic 1 201 SP-5 Systematic 29 250 SP-6 Systematic 1 299 SP-7 Systematic 29 348 SP-8 Systematic 1 397 SP-9 Systematic 29 446 SP-10 Systematic 1 495 SP-11 Systematic 29 544 SP-12 Systematic 1 593 SP-13 Systematic All sample points are measured from Grid Pin BA-95

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 34 of 62 Survey Unit OL-1-76 Restricted Area Grids BE-90, BF-90, BG-90 (South 40)

SP-10 SP-11 SP-9 SP-7 SP-8 SP-6 SP-4 SP-5 SP-3 Grid Pin BE-91 SP-1 SP-2 OL 1-76 Area: Restricted Area Grids BE-90, BF-90, BG-90 (South 40)

Measurement Locations X Coord Y Coord Label Type

-63 4 SP-1 Systematic

-20 4 SP-2 Systematic

-41 42 SP-3 Systematic

-63 80 SP-4 Systematic

-20 80 SP-5 Systematic

-41 118 SP-6 Systematic

-63 155 SP-7 Systematic

-20 155 SP-8 Systematic

-41 193 SP-9 Systematic

-63 231 SP-10 Systematic

-20 231 SP-11 Systematic All sample points are measured from Grid Pin BE-91.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 35 of 62 Survey Unit OL-1-77 Restricted Area Grids BE-91, BF-91 SP-11 SP-12 SP-8 SP-9 SP-10 SP-6 SP-7 SP-3 SP-4 SP-5 SP-1 SP-2 Grid Pin BE-91 OL 1-77 Area: Restricted Area Grids BE-91, BF-91 Measurement Locations X Coord Y Coord Label Type 30 34 SP-1 Systematic 76 34 SP-2 Systematic 7 74 SP-3 Systematic 53 74 SP-4 Systematic 99 74 SP-5 Systematic 30 114 SP-6 Systematic 76 114 SP-7 Systematic 7 153 SP-8 Systematic 53 153 SP-9 Systematic 99 153 SP-10 Systematic 30 193 SP-11 Systematic 76 193 SP-12 Systematic All sample points are measured from Grid Pin BE-91.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 36 of 62 Survey Unit OL-1-78 Restricted Area Grids BE-92, BF-92 SP-11 SP-12 SP-8 SP-9 SP-10 SP-6 SP-7 SP-3 SP-4 SP-5 SP-1 SP-2 Grid Pin BE-92 OL 1-78 Area: Restricted Area Grids BE-92, BF-92 Measurement Locations X Coord Y Coord Label Type 29 39 SP-1 Systematic 75 39 SP-2 Systematic 6 79 SP-3 Systematic 52 79 SP-4 Systematic 98 79 SP-5 Systematic 29 119 SP-6 Systematic 75 119 SP-7 Systematic 6 160 SP-8 Systematic 52 160 SP-9 Systematic 98 160 SP-10 Systematic 29 200 SP-11 Systematic 75 200 SP-12 Systematic All sample points are measured from Grid Pin BE-92.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 37 of 62 Survey Unit OL-1-79 Restricted Area Grids BE-93, BF-93 SP-11 SP-12 SP-8 SP-9 SP-10 SP-6 SP-7 SP-3 SP-4 SP-5 SP-1 SP-2 Grid Pin BE-93 OL 1-79 Area: Restricted Area Grids BE-93, BF-93 Measurement Locations X Coord Y Coord Label Type 24 31 SP-1 Systematic 72 31 SP-2 Systematic 0 72 SP-3 Systematic 48 72 SP-4 Systematic 95 72 SP-5 Systematic 24 113 SP-6 Systematic 72 113 SP-7 Systematic 0 154 SP-8 Systematic 48 154 SP-9 Systematic 95 154 SP-10 Systematic 24 195 SP-11 Systematic 72 195 SP-12 Systematic All sample points are measured from Grid Pin BE-93.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 38 of 62 Survey Unit OL-1-80 Restricted Area Grids BE-94, BF-94 SP-11 SP-12 SP-8 SP-9 SP-10 SP-6 SP-7 SP-3 SP-4 SP-5 SP-1 SP-2 Grid Pin BE-94 OL 1-80 Area: Restricted Area Grids BE-94, BF-94 Measurement Locations X Coord Y Coord Label Type 28 38 SP-1 Systematic 74 38 SP-2 Systematic 5 78 SP-3 Systematic 51 78 SP-4 Systematic 97 78 SP-5 Systematic 28 119 SP-6 Systematic 74 119 SP-7 Systematic 5 159 SP-8 Systematic 51 159 SP-9 Systematic 97 159 SP-10 Systematic 28 199 SP-11 Systematic 74 199 SP-12 Systematic All sample points are measured from Grid Pin BE-94.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 39 of 62 Survey Unit OL-1-81 Restricted Area Grids BG-92 east 25, BG-93, BG-94, BG-95 west of Line 3 Road SP-7 SP-8 SP-9 SP-10 SP-11 SP-1 SP-2 SP-3 SP-4 SP-5 SP-6 Grid Pin BG-93 OL 1-81 Area: Restricted Area Grids BG-92 east 25, BG-93, BG-94, BG-95 west of Line 3 Road Measurement Locations X Coord Y Coord Label Type

-19 25 SP-1 Systematic 28 25 SP-2 Systematic 75 25 SP-3 Systematic 122 25 SP-4 Systematic 169 25 SP-5 Systematic 217 25 SP-6 Systematic 5 65 SP-7 Systematic 52 65 SP-8 Systematic 99 65 SP-9 Systematic 146 65 SP-10 Systematic 193 65 SP-11 Systematic All sample points are measured from Grid Pin BG-93.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 40 of 62 Survey Unit OL-1-82 Restricted Area Grids BG-90 north 60, BG-91, BG-92 west 75 SP-9 SP-10 SP-11 SP-4 SP-5 SP-6 SP-7 SP-8 SP-1 SP-2 SP-3 Grid Pin BG-91 OL 1-82 Area: Restricted Area Grids BG-90 north 60, BG-91, BG-92 west 75 Measurement Locations X Coord Y Coord Label Type 29 3 SP-1 Systematic 84 3 SP-2 Systematic 140 3 SP-3 Systematic

-55 51 SP-4 Systematic 1 51 SP-5 Systematic 57 51 SP-6 Systematic 112 51 SP-7 Systematic 168 51 SP-8 Systematic

-27 99 SP-9 Systematic 29 99 SP-10 Systematic 84 99 SP-11 Systematic All sample points are measured from Grid Pin BG-91.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 41 of 62 Survey Unit OL-1-83 Restricted Area Grids BH-90, BH-91, BH-92 SP-11 SP-6 SP-7 SP-8 SP-9 SP-10 SP-5 SP-1 SP-2 SP-3 SP-4 Grid Pin BH-91 OL 1-83 Area: Restricted Area Grids BH-90, BH-91, BH-92 Measurement Locations X Coord Y Coord Label Type

-12 10 SP-1 Systematic 33 10 SP-2 Systematic 79 10 SP-3 Systematic 124 10 SP-4 Systematic 101 49 SP-5 Systematic

-57 88 SP-6 Systematic

-12 88 SP-7 Systematic 33 88 SP-8 Systematic 79 88 SP-9 Systematic 124 88 SP-10 Systematic

-80 127 SP-11 Systematic All sample points are measured from Grid Pin BH-91.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 42 of 62 Survey Unit OL-1-84 Restricted Area Grids BJ-90, BJ-91, BJ-92 north of road, BK-90 to BK-92 south 50 SP-9 SP-10 SP-11 SP-6 SP-7 SP-8 SP-4 SP-5 SP-1 SP-2 SP-3 Grid Pin BJ-91 OL 1-84 Area: Restricted Area Grids BJ-90, BJ-91, BJ-92 north of road, BK-90 to BK-92 south 50 Measurement Locations X Coord Y Coord Label Type

-42 16 SP-1 Systematic 6 16 SP-2 Systematic 54 16 SP-3 Systematic

-18 57 SP-4 Systematic 30 57 SP-5 Systematic

-42 99 SP-6 Systematic 6 99 SP-7 Systematic 54 99 SP-8 Systematic

-18 140 SP-9 Systematic 30 140 SP-10 Systematic 78 140 SP-11 Systematic All sample points are measured from Grid Pin BJ-91.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 43 of 62 Survey Unit OL-1-85 Restricted Area Grids BK-90 north 50, BK-91 NW 50, BL-90, BL-91 west 50 SP-8 SP-9 SP-10 SP-11 SP-5 SP-6 SP-7 SP-1 SP-2 SP-3 SP-4 Grid Pin BL-91 OL 1-85 Area: Restricted Area Grids BK-90 north 50, BK-91 NW 50, BL-90, BL-91 west 50 Measurement Locations X Coord Y Coord Label Type

-85 -41 SP-1 Systematic

-44 -41 SP-2 Systematic

-2 -41 SP-3 Systematic 39 -41 SP-4 Systematic

-65 -5 SP-5 Systematic

-23 -5 SP-6 Systematic 19 -5 SP-7 Systematic

-85 31 SP-8 Systematic

-44 31 SP-9 Systematic

-2 31 SP-10 Systematic 39 31 SP-11 Systematic All sample points are measured from Grid Pin BL-91.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 44 of 62 Survey Unit OL-1-86 Restricted Area Grids BK-91 ne 50, BL-91 east 50, BK-92, BL-92, BK-93 & BL-93 to RB east wall SP-7 SP-8 SP-9 SP-10 SP-11 SP-2 SP-3 SP-4 SP-5 SP-6 SP-1 Grid Pin BL-92 OL 1-86 Area: Restricted Area Grids BK-91 ne 50, BL-91 east 50, BK-92, BL-92, BK-93 & BL-93 to RB east wall Measurement Locations X Coord Y Coord Label Type

-17 -36 SP-1 Systematic

-40 4 SP-2 Systematic 6 4 SP-3 Systematic 53 4 SP-4 Systematic 99 4 SP-5 Systematic 146 4 SP-6 Systematic

-17 45 SP-7 Systematic 29 45 SP-8 Systematic 76 45 SP-9 Systematic 123 45 SP-10 Systematic 169 45 SP-11 Systematic All sample points are measured from Grid Pin BL-92.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 45 of 62 Survey Unit OL-1-87 Restricted Area Grids BK-93, BL-93 BK-94, BL-94, BK-95, BL-95 between RB east Wall, PPH north wall, Line 3 Road, and North Road SP-8 SP-9 SP-10 SP-11 SP-5 SP-6 SP-7 Grid Pin BL-94 SP-1 SP-2 SP-3 SP-4 OL 1-87 Area: Restricted Area Grids BK-93, BL-93 BK-94, BL-94, BK-95, BL-95 between RB east Wall, PPH north wall, Line 3 Road, and North Road Measurement Locations X Coord Y Coord Label Type

-13 -52 SP-1 Systematic 34 -52 SP-2 Systematic 82 -52 SP-3 Systematic 129 -52 SP-4 Systematic 11 -10 SP-5 Systematic 58 -10 SP-6 Systematic 106 -10 SP-7 Systematic

-13 31 SP-8 Systematic 34 31 SP-9 Systematic 82 31 SP-10 Systematic 129 31 SP-11 Systematic All sample points are measured from Grid Pin BL-94.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 46 of 62 Survey Unit OL-1-88 Restricted Area Grids BL-95 & 96 east of L3 Road, BK-95 & 96 East of L3 Road north 50 SP-10 SP-11 SP-7 SP-8 SP-9 SP-4 SP-5 SP-6 Grid Pin BL-96 SP-1 SP-2 SP-3 OL 1-88 Area: Restricted Area Grids BL-95 & 96 east of L3 Road, BK-95 & 96 East of L3 Road north 50 Measurement Locations X Coord Y Coord Label Type

-4 -43 SP-1 Systematic 41 -43 SP-2 Systematic 87 -43 SP-3 Systematic

-27 -3 SP-4 Systematic 19 -3 SP-5 Systematic 64 -3 SP-6 Systematic

-4 37 SP-7 Systematic 41 37 SP-8 Systematic 87 37 SP-9 Systematic 19 76 SP-10 Systematic 64 76 SP-11 Systematic All sample points are measured from Grid Pin BL-96.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 47 of 62 Survey Unit OL-1-89 Restricted Area Grids BK-95 & 96 East of L3 Road south 50, BJ-95 & 96 east of L3 Road SP-8 SP-9 SP-10 SP-11 SP-5 SP-6 SP-7 SP-1 SP-2 SP-3 SP-4 Grid Pin BJ-96 OL 1-89 Area: Restricted Area Grids BK-95 & 96 East of L3 Road south 50, BJ-95 &

96 east of L3 Road Measurement Locations X Coord Y Coord Label Type

-43 49 SP-1 Systematic 4 49 SP-2 Systematic 51 49 SP-3 Systematic 98 49 SP-4 Systematic

-19 89 SP-5 Systematic 28 89 SP-6 Systematic 74 89 SP-7 Systematic

-43 130 SP-8 Systematic 4 130 SP-9 Systematic 51 130 SP-10 Systematic 98 130 SP-11 Systematic All sample points are measured from Grid Pin BJ-96.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 48 of 62 Survey Unit OL-1-90 Restricted Area Grids BF-95, BG-95, BH-95 east of L3 Road SP-12 SP-10 SP-11 SP-9 SP-7 SP-8 SP-6 SP-4 SP-5 SP-3 SP-1 SP-2 Grid Pin BF-96 OL 1-90 Area: Restricted Area Grids BF-95, BG-95, BH-95 east of L3 Road Measurement Locations X Coord Y Coord Label Type

-48 5 SP-1 Systematic

-3 5 SP-2 Systematic

-25 44 SP-3 Systematic

-48 83 SP-4 Systematic

-3 83 SP-5 Systematic

-25 122 SP-6 Systematic

-48 161 SP-7 Systematic

-3 161 SP-8 Systematic

-25 200 SP-9 Systematic

-48 239 SP-10 Systematic

-3 239 SP-11 Systematic

-25 278 SP-12 Systematic All sample points are measured from Grid Pin BF-96.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 49 of 62 Survey Unit OL-1-91 Restricted Area Grids BG-96, BH-96 SP-11 SP-12 SP-8 SP-9 SP-10 SP-6 SP-7 SP-3 SP-4 SP-5 SP-1 SP-2 Grid Pin BG-96 OL 1-91 Area: Restricted Area Grids BG-96, BH-96 Measurement Locations X Coord Y Coord Label Type 29 29 SP-1 Systematic 75 29 SP-2 Systematic 5 69 SP-3 Systematic 52 69 SP-4 Systematic 98 69 SP-5 Systematic 29 110 SP-6 Systematic 75 110 SP-7 Systematic 5 150 SP-8 Systematic 52 150 SP-9 Systematic 98 150 SP-10 Systematic 29 190 SP-11 Systematic 75 190 SP-12 Systematic All sample points are measured from Grid Pin BG-96.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 50 of 62 Survey Unit OL-1-92 Restricted Area Grids BE-96, BF-96 SP-11 SP-12 SP-8 SP-9 SP-10 SP-6 SP-7 SP-3 SP-4 SP-5 Grid Pin BE-96 SP-1 SP-2 OL 1-92 Area: Restricted Area Grids BE-96, BF-96 Measurement Locations X Coord Y Coord Label Type 26 14 SP-1 Systematic 74 14 SP-2 Systematic 1 56 SP-3 Systematic 50 56 SP-4 Systematic 99 56 SP-5 Systematic 26 99 SP-6 Systematic 74 99 SP-7 Systematic 1 141 SP-8 Systematic 50 141 SP-9 Systematic 99 141 SP-10 Systematic 26 183 SP-11 Systematic 74 183 SP-12 Systematic All sample points are measured from Grid Pin BE-96.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 51 of 62 Survey Unit OL-1-93 Restricted Area Grids BC-95, BD-95, BE-95 east of L3 Road SP-11 SP-10 SP-9 SP-8 SP-7 SP-5 SP-6 SP-4 SP-2 SP-3 Grid Pin BC-96 SP-1 OL 1-93 Area: Restricted Area Grids BC-95, BD-95, BE-95 east of L3 Road Measurement Locations X Coord Y Coord Label Type

-28 3 SP-1 Systematic

-48 37 SP-2 Systematic

-9 37 SP-3 Systematic

-28 70 SP-4 Systematic

-48 104 SP-5 Systematic

-9 104 SP-6 Systematic

-28 138 SP-7 Systematic

-9 171 SP-8 Systematic

-28 205 SP-9 Systematic

-9 239 SP-10 Systematic

-28 272 SP-11 Systematic All sample points are measured from Grid Pin BC-96.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 52 of 62 Survey Unit OL-1-94 Restricted Area Grids BC-96, BD-96 SP-11 SP-12 SP-8 SP-9 SP-10 SP-6 SP-7 SP-3 SP-4 SP-5 SP-1 SP-2 Grid Pin BC-96 OL 1-94 Area: Restricted Area Grids BC-96, BD-96 Measurement Locations X Coord Y Coord Label Type 27 29 SP-1 Systematic 73 29 SP-2 Systematic 4 69 SP-3 Systematic 50 69 SP-4 Systematic 95 69 SP-5 Systematic 27 108 SP-6 Systematic 73 108 SP-7 Systematic 4 148 SP-8 Systematic 50 148 SP-9 Systematic 95 148 SP-10 Systematic 27 188 SP-11 Systematic 73 188 SP-12 Systematic All sample points are measured from Grid Pin BC-96.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 53 of 62 Survey Unit OL-1-95 Restricted Area Grids AZ-95, BA-95, BB-95, BB-96 east of L3 Road SP-9 SP-10 SP-11 SP-6 SP-7 SP-8 SP-3 SP-4 SP-5 Grid Pin BB-96 SP-2 SP-1 OL 1-95 Area: Restricted Area Grids AZ-95, BA-95, BB-95, BB-96 east of L3 Road Measurement Locations X Coord Y Coord Label Type

-30 -107 SP-1 Systematic

-30 -29 SP-2 Systematic

-7 10 SP-3 Systematic 38 10 SP-4 Systematic 83 10 SP-5 Systematic

-30 49 SP-6 Systematic 16 49 SP-7 Systematic 61 49 SP-8 Systematic

-7 88 SP-9 Systematic 38 88 SP-10 Systematic 83 88 SP-11 Systematic All sample points are measured from Grid Pin BB-96.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 54 of 62 Survey Unit OL-1-96 Restricted Area Grids AZ-96, AZ-97, BA-96, BA-97 SP-8 SP-9 SP-10 SP-11 SP-5 SP-6 SP-7 SP-1 SP-2 SP-3 SP-4 Grid Pin BA-96 OL 1-96 Area: Restricted Area Grids AZ-96, AZ-97, BA-96, BA-97 Measurement Locations X Coord Y Coord Label Type 27 -9 SP-1 Systematic 84 -9 SP-2 Systematic 140 -9 SP-3 Systematic 197 -9 SP-4 Systematic 55 40 SP-5 Systematic 112 40 SP-6 Systematic 169 40 SP-7 Systematic 27 89 SP-8 Systematic 84 89 SP-9 Systematic 140 89 SP-10 Systematic 197 89 SP-11 Systematic All sample points are measured from Grid Pin BA-96.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 55 of 62 Survey Unit OL-1-97 Restricted Area Grids AZ-98, AZ-99, BA-98, BA-99 SP-9 SP-10 SP-11 SP-12 SP-5 SP-6 SP-7 SP-8 Grid Pin BA-98 SP-1 SP-2 SP-3 SP-4 OL 1-97 Area: Restricted Area Grids AZ-98, AZ-99, BA-98, BA-99 Measurement Locations X Coord Y Coord Label Type 6 -4 SP-1 Systematic 61 -4 SP-2 Systematic 117 -4 SP-3 Systematic 172 -4 SP-4 Systematic 34 44 SP-5 Systematic 89 44 SP-6 Systematic 144 44 SP-7 Systematic 200 44 SP-8 Systematic 6 92 SP-9 Systematic 61 92 SP-10 Systematic 117 92 SP-11 Systematic 172 92 SP-12 Systematic All sample points are measured from Grid Pin BA-98.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 56 of 62 Survey Unit OL-1-98 Grids AZ-101 & BA-101 outside of the RA Fence SP-9 SP-10 SP-11 SP-7 SP-8 SP-4 SP-5 SP-6 Grid Pin BA-101 SP-1 SP-2 SP-3 OL 1-98 Area: Grids AZ-101 & BA-101 outside of the RA Fence Measurement Locations X Coord Y Coord Label Type

-12.6 -12.5 SP-1 Systematic 21.0 -12.5 SP-2 Systematic 54.6 -12.5 SP-3 Systematic 4.2 16.6 SP-4 Systematic 37.8 16.6 SP-5 Systematic 71.4 16.6 SP-6 Systematic 21.0 45.7 SP-7 Systematic 54.6 45.7 SP-8 Systematic 4.2 74.8 SP-9 Systematic 37.8 74.8 SP-10 Systematic 71.4 74.8 SP-11 Systematic All sample points are measured from Grid Pin BA-101.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 57 of 62 Survey Unit OL-2-1 Restricted Area Buffer Zone - Section #1 SP-11 SP-10 SP-9 SP-8 SP-7 OL 2-1 Area: Restricted Area Buffer Zone - Section #1 SP-6 Measurement Locations X Coord Y Coord Label Type 120 29 SP-1 Systematic 64 126 SP-2 Systematic 175 126 SP-3 Systematic SP-5 9 222 SP-4 Systematic 64 318 SP-5 Systematic 9 414 SP-6 Systematic 64 510 SP-7 Systematic SP-4 9 606 SP-8 Systematic 64 702 SP-9 Systematic 9 798 SP-10 Systematic 64 894 SP-11 Systematic All sample points are measured from Grid Pin BA-101. SP-2 SP-3 Grid Pin BA-101 SP-1

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 58 of 62 Survey Unit OL-2-2 Restricted Area Buffer Zone - Section #2 SP-8 SP-9 SP-10 SP-11 SP-4 SP-5 SP-6 SP-7 Grid Pin BM-98 SP-3 SP-1 SP-2 OL 2-2 Area: Restricted Area Buffer Zone - Section #2 Measurement Locations X Coord Y Coord Label Type 290 -135 SP-1 Systematic 396 -135 SP-2 Systematic 343 -44 SP-3 Systematic 80 47 SP-4 Systematic 185 47 SP-5 Systematic 290 47 SP-6 Systematic 396 47 SP-7 Systematic 28 138 SP-8 Systematic 133 138 SP-9 Systematic 238 138 SP-10 Systematic 343 138 SP-11 Systematic All sample points are measured from Grid Pin BM-98.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 59 of 62 Survey Unit OL-2-3 Restricted Area Buffer Zone - Section #3 SM-11 SM-12 SM-13 SM-9 SM-10 SM-6 SM-7 SM-8 SM-4 SM-5 SM-1 SM-2 SM-3 Grid Pin BM-96 OL 2-3 Area: Restricted Area Buffer Zone - Section #3 Measurement Locations X Coord Y Coord Label Type

-21.3 17.2 SP-1 Systematic 87.8 17.2 SP-2 Systematic 197.0 17.2 SP-3 Systematic 33.3 111.7 SP-4 Systematic 142.4 111.7 SP-5 Systematic

-21.3 206.2 SP-6 Systematic 87.8 206.2 SP-7 Systematic 197.0 206.2 SP-8 Systematic 33.3 300.8 SP-9 Systematic 142.4 300.8 SP-10 Systematic

-21.3 395.3 SP-11 Systematic 87.8 395.3 SP-12 Systematic 197.0 395.3 SP-13 Systematic All sample points are measured from Grid Pin BM-96.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 60 of 62 Survey Unit OL-2-4 Restricted Area Buffer Zone - Section #4 SP-6 SP-7 SP-8 SP-9 SP-10 SP-11 SP-1 SP-2 SP-3 SP-4 SP-5 Grid Pin BQ-92 OL 2-4 Area: Restricted Area Buffer Zone - Section #4 Measurement Locations X Coord Y Coord Label Type 52.5 58.4 SP-1 Systematic 155.6 58.4 SP-2 Systematic 362.0 58.4 SP-3 Systematic 465.2 58.4 SP-4 Systematic 568.4 58.4 SP-5 Systematic 0.9 147.8 SP-6 Systematic 104.1 147.8 SP-7 Systematic 207.2 147.8 SP-8 Systematic 310.4 147.8 SP-9 Systematic 413.6 147.8 SP-10 Systematic 516.8 147.8 SP-11 Systematic All sample points are measured from Grid Pin BQ-92.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 61 of 62 Survey Unit OL-2-5 Restricted Area Buffer Zone - Section #5 SP-12 Measure SP-11 & 12 from this point SP-11 Measure SP-8, 9 & 10 from these points SP-8 SP-9 SP-10 SP-5 SP-6 SP-7 Measure SP-6, & 7 from these points SP-3 SP-4 Measure SP-3, & 4 from this point OL 2-5 SP-2 Area: Restricted Area Buffer Zone - Section #5 Measurement Locations X Coord Y Coord Label Type Measure SP-1, 2, & -10 -58 SP-1 Systematic 5 from this point -10 150 SP-2 Systematic 49 Edge of fence SP-3 Systematic 169 Edge of fence SP-4 Systematic

-10 358 SP-5 Systematic

-5 28 SP-6 Systematic 11 54 SP-7 Systematic

-10 26 SP-8 Systematic 8 25 SP-9 Systematic SP-1 15 -19 SP-10 Systematic 9 -34 SP-11 Systematic 70 71 SP-12 Systematic Sample points are measured from the points shown on the map.

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix B Rev. 0, Page 62 of 62 Survey Unit OL-2-6 Restricted Area Buffer Zone - Section #6 OL 2-6 SP-11 Area: Restricted Area Buffer Zone - Section #6 Measurement Locations X Coord Y Coord Label Type 83 -55 SP-1 Systematic 211 -55 SP-2 Systematic 339 -55 SP-3 Systematic 467 -55 SP-4 Systematic 595 -55 SP-5 Systematic 723 -55 SP-6 Systematic SP-10 851 -55 SP-7 Systematic 19 56 SP-8 Systematic 19 277 SP-9 Systematic 19 499 SP-10 Systematic 19 720 SP-11 Systematic All sample points are measured from Grid Pin BA-90.

SP-9 SP-8 Grid Pin BA-90 SP-1 SP-2 SP-3 SP-4 SP-5 SP-6 SP-7

Plum Brook Reactor Facility Final Status Survey Report Attachment 16 Open Land Areas within Restricted Area And Outside Buffer Area Revision 0 Appendix C Soil Sample Results

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 2 of 28 Table of Contents Table 1, Open Land Area FSS Sample Results ...................................................................................... 3 Table 2, QC Soil Sample Comparison for Open Land Areas FSS ....................................................... 26

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 3 of 28 Table 1, Open Land Area FSS Sample Results Cs-137 Co-60 Cs-137 Co-60 Weight Unity Sample # Location MDA MDA (g) pCi/g 2 pCi/g 2 Fraction pCi/g pCi/g SR-280-13 OL-1-46, SP-1 423.5 < MDA < MDA < MDA < MDA 0.000 1.13E-01 1.03E-01 SR-280-15 OL-1-46, SP-2 416.4 < MDA < MDA < MDA < MDA 0.000 6.56E-02 1.04E-01 SR-280-16 OL-1-46, SP-3 430.8 < MDA < MDA < MDA < MDA 0.000 8.00E-02 1.01E-01 SR-280-17 OL-1-46, SP-4 433.8 < MDA < MDA < MDA < MDA 0.000 6.30E-02 1.00E-01 SR-280-18 OL-1-46, SP-5 349.6 2.46E-01 1.14E-01 < MDA < MDA 0.021 1.24E-01 SR-280-19 OL-1-46, SP-6 365.9 < MDA < MDA < MDA < MDA 0.000 1.06E-01 1.19E-01 SR-280-20 OL-1-46, SP-7 411.7 < MDA < MDA < MDA < MDA 0.000 6.89E-02 1.10E-01 SR-280-21 OL-1-46, SP-8 384.3 2.12E-01 9.15E-02 < MDA < MDA 0.018 1.13E-01 SR-280-22 OL-1-46, SP-9 351.6 < MDA < MDA < MDA < MDA 0.000 1.24E-01 1.28E-01 SR-280-23 OL-1-46, SP-10 331.7 < MDA < MDA < MDA < MDA 0.000 8.24E-02 1.31E-01 SR-280-24 OL-1-46, SP-11 351.2 < MDA < MDA < MDA < MDA 0.000 9.43E-02 1.28E-01 SR-280-1 OL-1-47, SP-1 344.7 < MDA < MDA < MDA < MDA 0.000 9.65E-02 1.27E-01 SR-280-2 OL-1-47, SP-2 354.9 < MDA < MDA < MDA < MDA 0.000 1.08E-01 1.30E-01 SR-280-4 OL-1-47, SP-3 348.9 < MDA < MDA < MDA < MDA 0.000 8.95E-02 1.26E-01 SR-280-5 OL-1-47, SP-4 359.5 < MDA < MDA < MDA < MDA 0.000 1.66E-01 1.83E-01 SR-280-6 OL-1-47, SP-5 438.4 < MDA < MDA < MDA < MDA 0.000 1.14E-01 1.04E-01 SR-280-7 OL-1-47, SP-6 445.3 < MDA < MDA < MDA < MDA 0.000 1.05E-01 9.84E-02 SR-280-8 OL-1-47, SP-7 431.0 2.82E-01 1.19E-01 < MDA < MDA 0.024 1.07E-01 SR-280-9 OL-1-47, SP-8 393.3 2.33E-01 1.10E-01 < MDA < MDA 0.020 1.16E-01 SR-280-10 OL-1-47, SP-9 441.7 < MDA < MDA < MDA < MDA 0.000 1.25E-01 9.92E-02 SR-280-11 OL-1-47, SP-10 436.2 2.93E-01 1.16E-01 < MDA < MDA 0.025 1.06E-01 SR-280-12 OL-1-47, SP-11 432.5 2.40E-01 9.37E-02 < MDA < MDA 0.021 1.05E-01 SR-280-25 OL-1-48, SP-1 318.4 <MDA <MDA <MDA <MDA 0.000 8.58E-02 1.37E-01 SR-280-26 OL-1-48, SP-2 414.2 <MDA <MDA <MDA <MDA 0.000 1.06E-01 1.18E-01 SR-280-27 OL-1-48, SP-3 429.3 2.38E-01 8.58E-02 <MDA <MDA 0.021 5.26E-02 SR-280-28 OL-1-48, SP-4 435.3 2.56E-01 9.47E-02 <MDA <MDA 0.022 1.00E-01 SR-280-30 OL-1-48, SP-5 359.1 2.51E-01 1.12E-01 <MDA <MDA 0.022 1.21E-01 SR-280-31 OL-1-48, SP-6 420.3 2.63E-01 1.15E-01 <MDA <MDA 0.023 1.09E-01 SR-280-32 OL-1-48, SP-7 441.2 1.74E-01 7.87E-02 <MDA <MDA 0.015 1.02E-01 SR-280-33 OL-1-48, SP-8 441.3 3.53E-01 1.11E-01 <MDA <MDA 0.030 9.87E-02

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 4 of 28 Table 1, Open Land Area FSS Sample Results Cs-137 Co-60 Cs-137 Co-60 Weight Unity Sample # Location MDA MDA (g) pCi/g 2 pCi/g 2 Fraction pCi/g pCi/g SR-280-34 OL-1-48, SP-9 426.8 <MDA <MDA <MDA <MDA 0.000 1.09E-01 1.08E-01 SR-280-35 OL-1-48, SP-10 395.2 <MDA <MDA <MDA <MDA 0.000 1.12E-01 1.14E-01 SR-280-36 OL-1-48, SP-11 450.4 2.56E-01 9.75E-02 <MDA <MDA 0.022 1.02E-01 SR-280-37 OL-1-48, SP-12 412.8 3.51E-01 1.39E-01 <MDA <MDA 0.030 1.09E-01 SR-280-38 OL-1-49, SP-1 342.3 <MDA <MDA <MDA <MDA 0.000 9.52E-02 1.27E-01 SR-280-39 OL-1-49, SP-2 341.4 2.90E-01 1.19E-01 <MDA <MDA 0.025 1.34E-01 SR-280-40 OL-1-49, SP-3 412.8 <MDA <MDA <MDA <MDA 0.000 6.87E-02 1.09E-01 SR-280-41 OL-1-49, SP-4 423.8 <MDA <MDA <MDA <MDA 0.000 6.45E-02 1.03E-01 SR-280-42 OL-1-49, SP-5 451.8 <MDA <MDA <MDA <MDA 0.000 1.04E-01 1.02E-01 SR-280-43 OL-1-49, SP-6 430.0 2.22E-01 1.02E-01 <MDA <MDA 0.019 1.05E-01 SR-280-44 OL-1-49, SP-7 437.3 2.20E-01 8.76E-02 <MDA <MDA 0.019 9.96E-02 SR-280-45 OL-1-49, SP-8 442.4 3.05E-01 1.19E-01 <MDA <MDA 0.026 1.04E-01 SR-280-46 OL-1-49, SP-9 408.1 3.04E-01 1.17E-01 <MDA <MDA 0.026 1.11E-01 SR-280-47 OL-1-49, SP-10 393.5 3.36E-01 1.62E-01 <MDA <MDA 0.029 1.11E-01 SR-280-49 OL-1-49, SP-11 409.0 4.35E-01 1.29E-01 <MDA <MDA 0.038 1.07E-01 SR-280-50 OL-1-49, SP-12 391.3 2.76E-01 1.18E-01 <MDA <MDA 0.024 1.17E-01 SR-280-51 OL-1-50, SP-1 346.9 <MDA <MDA <MDA <MDA 0.000 9.94E-02 1.26E-01 SR-280-53 OL-1-50, SP-2 426.1 <MDA <MDA <MDA <MDA 0.000 9.98E-02 1.06E-01 SR-280-54 OL-1-50, SP-3 414.2 <MDA <MDA <MDA <MDA 0.000 1.03E-01 1.05E-01 SR-280-55 OL-1-50, SP-4 370.6 <MDA <MDA <MDA <MDA 0.000 8.20E-02 1.24E-01 SR-280-56 OL-1-50, SP-5 439.3 <MDA <MDA <MDA <MDA 0.000 7.20E-02 1.03E-01 SR-280-57 OL-1-50, SP-6 454.6 3.18E-01 1.04E-01 <MDA <MDA 0.027 9.58E-02 SR-280-58 OL-1-50, SP-7 420.6 2.35E-01 9.65E-02 <MDA <MDA 0.020 1.09E-01 SR-280-59 OL-1-50, SP-8 448.2 <MDA <MDA <MDA <MDA 0.000 7.69E-02 1.01E-01 SR-280-60 OL-1-50, SP-9 413.3 <MDA <MDA <MDA <MDA 0.000 1.27E-01 1.05E-01 SR-280-61 OL-1-50, SP-10 427.3 <MDA <MDA <MDA <MDA 0.000 1.80E-01 1.07E-01 SR-280-62 OL-1-50, SP-11 423.8 <MDA <MDA <MDA <MDA 0.000 1.33E-01 1.39E-01 SR-280-63 OL-1-50, SP-12 433.6 <MDA <MDA <MDA <MDA 0.000 1.12E-01 1.00E-01 SR-280-64 OL-1-51, SP-1 408.5 <MDA <MDA <MDA <MDA 0.000 6.69E-02 1.07E-01 SR-280-65 OL-1-51, SP-2 384.6 <MDA <MDA <MDA <MDA 0.000 7.90E-02 1.19E-01

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 5 of 28 Table 1, Open Land Area FSS Sample Results Cs-137 Co-60 Cs-137 Co-60 Weight Unity Sample # Location MDA MDA (g) pCi/g 2 pCi/g 2 Fraction pCi/g pCi/g SR-280-66 OL-1-51, SP-3 419.4 <MDA <MDA <MDA <MDA 0.000 1.26E-01 1.08E-01 SR-280-67 OL-1-51, SP-4 351.6 <MDA <MDA <MDA <MDA 0.000 9.45E-02 1.24E-01 SR-280-68 OL-1-51, SP-5 403.3 <MDA <MDA <MDA <MDA 0.000 9.83E-02 1.14E-01 SR-280-70 OL-1-51, SP-6 364.4 <MDA <MDA <MDA <MDA 0.000 7.50E-02 1.20E-01 SR-280-71 OL-1-51, SP-7 423.8 <MDA <MDA <MDA <MDA 0.000 8.88E-02 1.08E-01 SR-280-72 OL-1-51, SP-8 411.5 2.73E-01 1.11E-01 <MDA <MDA 0.024 1.10E-01 SR-280-73 OL-1-51, SP-9 434.8 <MDA <MDA <MDA <MDA 0.000 7.79E-02 1.00E-01 SR-280-74 OL-1-51, SP-10 357.5 <MDA <MDA <MDA <MDA 0.000 8.50E-02 1.28E-01 SR-280-75 OL-1-51, SP-11 409.5 <MDA <MDA <MDA <MDA 0.000 8.09E-02 1.10E-01 SR-280-76 OL-1-51, SP-12 427.5 <MDA <MDA <MDA <MDA 0.000 6.39E-02 1.02E-01 SR-280-77 OL-1-52, SP-1 409.5 <MDA <MDA <MDA <MDA 0.000 8.85E-02 1.06E-01 SR-280-78 OL-1-52, SP-2 419.3 2.56E-01 1.06E-01 <MDA <MDA 0.022 1.04E-01 SR-280-79 OL-1-52, SP-3 442.4 <MDA <MDA <MDA <MDA 0.000 9.68E-02 9.84E-02 SR-280-81 OL-1-52, SP-4 397.3 <MDA <MDA <MDA <MDA 0.000 7.49E-02 1.10E-01 SR-280-82 OL-1-52, SP-5 426.9 1.87E-01 8.80E-02 <MDA <MDA 0.016 1.06E-01 SR-280-83 OL-1-52, SP-6 408.9 6.99E-01 1.65E-01 <MDA <MDA 0.060 1.06E-01 SR-280-84 OL-1-52, SP-7 432.4 <MDA <MDA <MDA <MDA 0.000 8.13E-02 1.04E-01 SR-280-85 OL-1-52, SP-8 410.2 4.39E-01 1.47E-01 <MDA <MDA 0.038 1.06E-01 SR-280-86 OL-1-52, SP-9 389.3 <MDA <MDA <MDA <MDA 0.000 1.17E-01 1.16E-01 SR-280-87 OL-1-52, SP-10 395.7 6.20E-01 1.69E-01 <MDA <MDA 0.053 1.10E-01 SR-280-88 OL-1-52, SP-11 419.8 2.82E-01 1.14E-01 <MDA <MDA 0.024 1.08E-01 SR-280-89 OL-1-52, SP-12 411.1 1.05E+00 2.24E-01 <MDA <MDA 0.091 1.06E-01 SR-280-152 OL-1-53, SP-1 412.9 5.00E-01 1.62E-01 <MDA <MDA 0.043 1.09E-01 SR-280-153 OL-1-53, SP-2 439.2 5.27E-01 1.42E-01 <MDA <MDA 0.045 9.90E-02 SR-280-154 OL-1-53, SP-3 431.9 <MDA <MDA <MDA <MDA 0.000 9.92E-02 1.01E-01 SR-280-155 OL-1-53, SP-4 413.2 3.72E-01 1.20E-01 <MDA <MDA 0.032 1.09E-01 SR-280-156 OL-1-53, SP-5 441.7 7.25E-01 1.71E-01 <MDA <MDA 0.063 9.85E-02 SR-280-157 OL-1-53, SP-6 394.5 1.33E+00 2.45E-01 <MDA <MDA 0.115 1.14E-01 SR-280-158 OL-1-53, SP-7 384.7 1.02E+00 2.09E-01 <MDA <MDA 0.088 1.13E-01 SR-280-159 OL-1-53, SP-8 422.7 1.62E+00 2.66E-01 <MDA <MDA 0.140 1.07E-01

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 6 of 28 Table 1, Open Land Area FSS Sample Results Cs-137 Co-60 Cs-137 Co-60 Weight Unity Sample # Location MDA MDA (g) pCi/g 2 pCi/g 2 Fraction pCi/g pCi/g SR-280-160 OL-1-53, SP-9 408.6 5.54E-01 1.52E-01 <MDA <MDA 0.048 1.06E-01 SR-280-161 OL-1-53, SP-10 393.9 <MDA <MDA <MDA <MDA 0.000 9.40E-02 1.15E-01 SR-280-163 OL-1-53, SP-11 424.0 1.73E+00 2.82E-01 <MDA <MDA 0.149 1.06E-01 SR-280-164 OL-1-53, SP-12 400.6 2.40E+00 3.43E-01 <MDA <MDA 0.207 1.09E-01 SR-280-165 OL-1-53, SP-13 430.9 3.96E-01 1.27E-01 <MDA <MDA 0.034 1.05E-01 SR-280-166 OL-1-53, SP-14 373.3 <MDA <MDA <MDA <MDA 0.000 9.92E-02 1.21E-01 SR-280-167 OL-1-53, SP-15 430.8 <MDA <MDA <MDA <MDA 0.000 1.22E-01 1.01E-01 SR-280-168 OL-1-54, SP-1 410.8 3.91E-01 1.34E-01 <MDA <MDA 0.034 1.06E-01 SR-280-169 OL-1-54, SP-2 450.9 <MDA <MDA <MDA <MDA 0.000 9.86E-02 1.00E-01 SR-280-170 OL-1-54, SP-3 434.3 5.21E-01 1.37E-01 <MDA <MDA 0.045 1.09E-01 SR-280-171 OL-1-54, SP-4 425.6 4.84E-01 1.45E-01 <MDA <MDA 0.042 1.06E-01 SR-280-172 OL-1-54, SP-5 415.0 8.49E-01 1.82E-01 <MDA <MDA 0.073 1.05E-01 SR-280-173 OL-1-54, SP-6 430.0 6.02E-01 1.61E-01 <MDA <MDA 0.052 1.05E-01 SR-280-174 OL-1-54, SP-7 459.6 8.70E-01 2.05E-01 <MDA <MDA 0.075 9.46E-02 SR-280-176 OL-1-54, SP-8 417.3 3.60E-01 1.27E-01 <MDA <MDA 0.031 1.04E-01 SR-280-177 OL-1-54, SP-9 399.7 1.06E+00 2.29E-01 <MDA <MDA 0.091 1.13E-01 SR-280-178 OL-1-54, SP-10 427.1 1.07E+00 2.13E-01 <MDA <MDA 0.092 1.02E-01 SR-280-179 OL-1-54, SP-11 396.4 1.75E-01 8.30E-02 <MDA <MDA 0.015 1.21E-01 SR-280-180 OL-1-54, SP-12 420.4 3.07E-01 1.16E-01 <MDA <MDA 0.026 1.03E-01 SR-280-181 OL-1-55, SP-1 354.0 <MDA <MDA <MDA <MDA 0.000 6.98E-02 6.15E-02 SR-280-182 OL-1-55, SP-2 365.3 2.21E-01 9.75E-02 <MDA <MDA 0.019 1.24E-01 SR-280-183 OL-1-55, SP-3 362.0 2.44E-01 1.03E-01 <MDA <MDA 0.021 1.25E-01 SR-280-184 OL-1-55, SP-4 407.8 <MDA <MDA <MDA <MDA 0.000 3.35E-02 5.34E-02 SR-280-185 OL-1-55, SP-5 321.5 <MDA <MDA <MDA <MDA 0.000 8.82E-02 1.40E-01 SR-280-186 OL-1-55, SP-6 361.0 2.44E-01 1.17E-01 <MDA <MDA 0.021 1.25E-01 SR-280-188 OL-1-55, SP-7 316.2 <MDA <MDA <MDA <MDA 0.000 1.17E-01 1.43E-01 SR-280-189 OL-1-55, SP-8 316.3 <MDA <MDA <MDA <MDA 0.000 1.24E-01 1.43E-01 SR-280-190 OL-1-55, SP-9 338.0 <MDA <MDA <MDA <MDA 0.000 9.23E-02 1.29E-01 SR-280-191 OL-1-55, SP-10 387.4 1.99E-01 8.96E-02 <MDA <MDA 0.017 1.17E-01 SR-280-192 OL-1-55, SP-11 353.4 1.99E-01 9.23E-02 <MDA <MDA 0.017 1.23E-01

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 7 of 28 Table 1, Open Land Area FSS Sample Results Cs-137 Co-60 Cs-137 Co-60 Weight Unity Sample # Location MDA MDA (g) pCi/g 2 pCi/g 2 Fraction pCi/g pCi/g SR-280-193 OL-1-55, SP-12 339.8 <MDA <MDA <MDA <MDA 0.000 8.35E-02 1.33E-01 SR-280-140 OL-1-56, SP-1 352.8 <MDA <MDA <MDA <MDA 0.000 1.31E-01 1.28E-01 SR-280-141 OL-1-56, SP-2 387.8 1.88E-01 8.72E-02 <MDA <MDA 0.016 1.16E-01 SR-280-142 OL-1-56, SP-3 324.9 <MDA <MDA <MDA <MDA 0.000 8.73E-02 1.39E-01 SR-280-143 OL-1-56, SP-4 338.4 <MDA <MDA <MDA <MDA 0.000 1.37E-01 1.33E-01 SR-280-144 OL-1-56, SP-5 412.7 3.69E-01 1.38E-01 <MDA <MDA 0.032 1.09E-01 SR-280-146 OL-1-56, SP-6 438.0 <MDA <MDA <MDA <MDA 0.000 9.35E-02 9.93E-02 SR-280-147 OL-1-56, SP-7 363.0 <MDA <MDA <MDA <MDA 0.000 1.05E-01 1.24E-01 SR-280-148 OL-1-56, SP-8 402.1 2.80E-01 1.34E-01 <MDA <MDA 0.024 1.08E-01 SR-280-149 OL-1-56, SP-9 394.3 3.41E-01 1.17E-01 <MDA <MDA 0.029 1.14E-01 SR-280-150 OL-1-56, SP-10 408.8 <MDA <MDA <MDA <MDA 0.000 6.68E-02 1.06E-01 SR-280-151 OL-1-56, SP-11 410.7 3.71E-01 1.31E-01 <MDA <MDA 0.032 1.10E-01 SR-280-114 OL-1-57, SP-1 382.5 <MDA <MDA <MDA <MDA 0.000 1.54E-01 1.14E-01 SR-280-115 OL-1-57, SP-2 376.4 3.07E-01 1.14E-01 <MDA <MDA 0.026 1.20E-01 SR-280-116 OL-1-57, SP-3 412.0 <MDA <MDA <MDA <MDA 0.000 8.37E-02 1.06E-01 SR-280-117 OL-1-57, SP-4 426.1 3.31E-01 1.37E-01 <MDA <MDA 0.029 1.06E-01 SR-280-118 OL-1-57, SP-5 427.0 2.23E-01 8.21E-02 <MDA <MDA 0.019 5.10E-02 SR-280-120 OL-1-57, SP-6 370.7 2.70E-01 1.05E-01 <MDA <MDA 0.023 1.17E-01 SR-280-121 OL-1-57, SP-7 388.0 <MDA <MDA <MDA <MDA 0.000 7.31E-02 1.16E-01 SR-280-122 OL-1-57, SP-8 394.1 2.27E-01 1.05E-01 <MDA <MDA 0.020 1.15E-01 SR-280-123 OL-1-57, SP-9 372.5 2.19E-01 9.44E-02 <MDA <MDA 0.019 1.17E-01 SR-280-124 OL-1-57, SP-10 393.6 <MDA <MDA <MDA <MDA 0.000 8.93E-02 1.15E-01 SR-280-125 OL-1-57, SP-11 425.3 2.55E-01 1.06E-01 <MDA <MDA 0.022 1.09E-01 SR-280-126 OL-1-57, SP-12 369.5 <MDA <MDA <MDA <MDA 0.000 7.67E-02 1.22E-01 SR-280-127 OL-1-58, SP-1 389.8 <MDA <MDA <MDA <MDA 0.000 9.99E-02 1.12E-01 SR-280-128 OL-1-58, SP-2 416.3 2.68E-01 1.01E-01 <MDA <MDA 0.023 1.08E-01 SR-280-129 OL-1-58, SP-3 437.6 <MDA <MDA <MDA <MDA 0.000 9.13E-02 9.94E-02 SR-280-130 OL-1-58, SP-4 390.3 1.68E-01 8.19E-02 <MDA <MDA 0.014 1.16E-01 SR-280-131 OL-1-58, SP-5 385.0 2.41E-01 9.75E-02 <MDA <MDA 0.021 1.13E-01 SR-280-132 OL-1-58, SP-6 397.7 <MDA <MDA <MDA <MDA 0.000 1.25E-01 1.13E-01

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 8 of 28 Table 1, Open Land Area FSS Sample Results Cs-137 Co-60 Cs-137 Co-60 Weight Unity Sample # Location MDA MDA (g) pCi/g 2 pCi/g 2 Fraction pCi/g pCi/g SR-280-133 OL-1-58, SP-7 421.2 <MDA <MDA <MDA <MDA 0.000 1.08E-01 1.03E-01 SR-280-134 OL-1-58, SP-8 350.5 <MDA <MDA <MDA <MDA 0.000 8.09E-02 1.29E-01 SR-280-135 OL-1-58, SP-9 435.2 1.75E-01 8.46E-02 <MDA <MDA 0.015 1.00E-01 SR-280-136 OL-1-58, SP-10 414.4 2.55E-01 1.17E-01 <MDA <MDA 0.022 1.09E-01 SR-280-137 OL-1-58, SP-11 412.0 <MDA <MDA <MDA <MDA 0.000 1.10E-01 1.06E-01 SR-280-138 OL-1-58, SP-12 403.3 3.32E-01 1.48E-01 <MDA <MDA 0.029 1.12E-01 SR-280-579 OL-1-59, SP-1 396.1 3.12E-01 1.40E-01 < MDA < MDA 0.027 1.16E-01 SR-280-581 OL-1-59, SP-2 384.0 3.41E-01 1.37E-01 < MDA < MDA 0.029 1.20E-01 SR-280-582 OL-1-59, SP-3 421.7 < MDA < MDA < MDA < MDA 0.000 1.84E-01 1.07E-01 SR-280-583 OL-1-59, SP-4 370.2 < MDA < MDA < MDA < MDA 0.000 1.65E-01 1.24E-01 SR-280-584 OL-1-59, SP-5 397.9 < MDA < MDA < MDA < MDA 0.000 9.60E-02 1.14E-01 SR-280-585 OL-1-59, SP-6 388.7 < MDA < MDA < MDA < MDA 0.000 1.69E-01 1.18E-01 SR-280-586 OL-1-59, SP-7 368.3 < MDA < MDA < MDA < MDA 0.000 1.45E-01 1.23E-01 SR-280-587 OL-1-59, SP-8 356.2 < MDA < MDA < MDA < MDA 0.000 1.10E-01 1.29E-01 SR-280-588 OL-1-59, SP-9 355.5 < MDA < MDA < MDA < MDA 0.000 1.42E-01 6.36E-02 SR-280-589 OL-1-59, SP-10 368.5 < MDA < MDA < MDA < MDA 0.000 1.45E-01 1.25E-01 SR-280-590 OL-1-59, SP-11 357.0 2.98E-01 1.40E-01 < MDA < MDA 0.026 1.27E-01 SR-280-615 OL-1-60, SP-1 348.5 < MDA < MDA < MDA < MDA 0.000 1.19E-01 1.30E-01 SR-280-616 OL-1-60, SP-2 336.7 < MDA < MDA < MDA < MDA 0.000 1.44E-01 1.34E-01 SR-280-617 OL-1-60, SP-3 361.9 < MDA < MDA < MDA < MDA 0.000 1.47E-01 1.25E-01 SR-280-618 OL-1-60, SP-4 380.4 < MDA < MDA < MDA < MDA 0.000 1.70E-01 1.19E-01 SR-280-620 OL-1-60, SP-5 322.4 < MDA < MDA < MDA < MDA 0.000 1.49E-01 1.40E-01 SR-280-621 OL-1-60, SP-6 331.1 < MDA < MDA < MDA < MDA 0.000 1.60E-01 1.37E-01 SR-280-622 OL-1-60, SP-7 365.7 2.74E-01 1.09E-01 < MDA < MDA 0.024 1.24E-01 SR-280-623 OL-1-60, SP-8 388.0 3.57E-01 1.47E-01 < MDA < MDA 0.031 1.17E-01 SR-280-624 OL-1-60, SP-9 396.2 2.72E-01 1.32E-01 < MDA < MDA 0.023 1.14E-01 SR-280-625 OL-1-60, SP-10 404.8 2.30E-01 1.07E-01 < MDA < MDA 0.020 1.12E-01 SR-280-626 OL-1-60, SP-11 412.2 < MDA < MDA < MDA < MDA 0.000 1.42E-01 1.10E-01 SR-280-627 OL1-61, SP-1 369.7 < MDA < MDA < MDA < MDA 0.000 1.35E-01 1.22E-01 SR-280-628 OL1-61, SP-2 384.9 < MDA < MDA < MDA < MDA 0.000 1.25E-01 1.37E-01

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 9 of 28 Table 1, Open Land Area FSS Sample Results Cs-137 Co-60 Cs-137 Co-60 Weight Unity Sample # Location MDA MDA (g) pCi/g 2 pCi/g 2 Fraction pCi/g pCi/g SR-280-629 OL1-61, SP-3 414.8 < MDA < MDA < MDA < MDA 0.000 9.49E-02 1.55E-01 SR-280-630 OL1-61, SP-4 330.3 < MDA < MDA < MDA < MDA 0.000 2.03E-01 1.37E-01 SR-280-631 OL1-61, SP-5 399.5 < MDA < MDA < MDA < MDA 0.000 1.38E-01 1.15E-01 SR-280-632 OL1-61, SP-6 322.6 3.32E-01 1.58E-01 < MDA < MDA 0.029 1.42E-01 SR-280-633 OL1-61, SP-7 398.2 < MDA < MDA < MDA < MDA 0.000 9.28E-02 1.15E-01 SR-280-634 OL1-61, SP-8 354.8 < MDA < MDA < MDA < MDA 0.000 1.08E-01 1.29E-01 SR-280-636 OL1-61, SP-9 336.4 < MDA < MDA < MDA < MDA 0.000 2.41E-01 1.37E-01 SR-280-637 OL1-61, SP-10 326.3 < MDA < MDA < MDA < MDA 0.000 1.24E-01 1.41E-01 SR-280-638 OL1-61, SP-11 333.6 < MDA < MDA < MDA < MDA 0.000 1.56E-01 1.36E-01 SR-280-234 OL-1-62, SP-1 377.1 2.65E-01 1.17E-01 < MDA < MDA 0.023 1.20E-01 SR-280-235 OL-1-62, SP-2 348.0 4.58E-01 1.43E-01 < MDA < MDA 0.039 1.25E-01 SR-280-236 OL-1-62, SP-3 341.0 < MDA < MDA < MDA < MDA 0.000 1.15E-01 1.32E-01 SR-280-237 OL-1-62, SP-4 334.9 < MDA < MDA < MDA < MDA 0.000 1.21E-01 1.30E-01 SR-280-238 OL-1-62, SP-5 394.6 < MDA < MDA < MDA < MDA 0.000 9.53E-02 1.14E-01 SR-280-239 OL-1-62, SP-6 402.2 1.59E-01 6.73E-02 < MDA < MDA 0.014 4.21E-02 SR-280-240 OL-1-62, SP-7 394.8 2.38E-01 1.15E-01 < MDA < MDA 0.021 1.14E-01 SR-280-241 OL-1-62, SP-8 392.7 2.73E-01 7.82E-02 < MDA < MDA 0.024 3.69E-02 SR-280-243 OL-1-62, SP-9 401.0 < MDA < MDA < MDA < MDA 0.000 1.06E-01 1.13E-01 SR-280-244 OL-1-62, SP-10 396.4 < MDA < MDA < MDA < MDA 0.000 9.00E-02 1.10E-01 SR-280-245 OL-1-62, SP-11 341.0 < MDA < MDA < MDA < MDA 0.000 1.28E-01 1.28E-01 SR-280-258 OL-1-63, SP-1 410.7 < MDA < MDA < MDA < MDA 0.000 8.83E-02 1.06E-01 SR-280-259 OL-1-63, SP-2 376.5 2.45E-01 1.01E-01 < MDA < MDA 0.021 1.20E-01 SR-280-260 OL-1-63, SP-3 452.5 2.69E-01 1.05E-01 < MDA < MDA 0.023 9.63E-02 SR-280-261 OL-1-63, SP-4 372.4 < MDA < MDA < MDA < MDA 0.000 7.62E-02 1.21E-01 SR-280-262 OL-1-63, SP-5 408.6 2.27E-01 9.19E-02 < MDA < MDA 0.020 1.07E-01 SR-280-263 OL-1-63, SP-6 408.7 < MDA < MDA < MDA < MDA 0.000 1.38E-01 1.11E-01 SR-280-264 OL-1-63, SP-7 447.7 1.37E-01 4.29E-02 < MDA < MDA 0.012 3.83E-02 SR-280-265 OL-1-63, SP-8 356.2 < MDA < MDA < MDA < MDA 0.000 8.88E-02 1.27E-01 SR-280-266 OL-1-63, SP-9 378.2 < MDA < MDA < MDA < MDA 0.000 8.44E-02 1.15E-01 SR-280-267 OL-1-63, SP-10 421.3 < MDA < MDA < MDA < MDA 0.000 8.19E-02 1.07E-01

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 10 of 28 Table 1, Open Land Area FSS Sample Results Cs-137 Co-60 Cs-137 Co-60 Weight Unity Sample # Location MDA MDA (g) pCi/g 2 pCi/g 2 Fraction pCi/g pCi/g SR-280-268 OL-1-63, SP-11 425.2 < MDA < MDA < MDA < MDA 0.000 7.34E-02 1.02E-01 SR-280-246 OL-1-64, SP-1 440.0 < MDA < MDA < MDA < MDA 0.000 1.17E-01 9.89E-02 SR-280-247 OL-1-64, SP-2 379.2 3.16E-01 1.20E-01 < MDA < MDA 0.027 1.15E-01 SR-280-248 OL-1-64, SP-3 405.8 < MDA < MDA < MDA < MDA 0.000 1.26E-01 1.07E-01 SR-280-249 OL-1-64, SP-4 402.1 2.86E-01 1.04E-01 < MDA < MDA 0.025 1.37E-01 SR-280-250 OL-1-64, SP-5 378.4 1.81E-01 5.44E-02 < MDA < MDA 0.016 4.51E-02 SR-280-252 OL-1-64, SP-6 369.8 2.99E-01 1.27E-01 < MDA < MDA 0.026 1.22E-01 SR-280-253 OL-1-64, SP-7 380.2 3.26E-01 1.35E-01 < MDA < MDA 0.028 1.19E-01 SR-280-254 OL-1-64, SP-8 391.3 < MDA < MDA < MDA < MDA 0.000 8.46E-02 1.15E-01 SR-280-255 OL-1-64, SP-9 425.1 < MDA < MDA < MDA < MDA 0.000 7.44E-02 1.06E-01 SR-280-256 OL-1-64, SP-10 450.8 < MDA < MDA < MDA < MDA 0.000 1.30E-01 1.00E-01 SR-280-257 OL-1-64, SP-11 388.1 < MDA < MDA < MDA < MDA 0.000 8.88E-02 1.16E-01 SR-280-603 OL-1-65, SP-1 348.7 < MDA < MDA < MDA < MDA 0.000 9.89E-02 1.30E-01 SR-280-604 OL-1-65, SP-2 341.8 < MDA < MDA < MDA < MDA 0.000 1.15E-01 1.32E-01 SR-280-605 OL-1-65, SP-3 344.5 < MDA < MDA < MDA < MDA 0.000 1.14E-01 1.31E-01 SR-280-606 OL-1-65, SP-4 352.2 < MDA < MDA < MDA < MDA 0.000 8.06E-02 1.29E-01 SR-280-607 OL-1-65, SP-5 378.0 < MDA < MDA < MDA < MDA 0.000 1.34E-01 1.20E-01 SR-280-609 OL-1-65, SP-6 388.0 < MDA < MDA < MDA < MDA 0.000 1.12E-01 1.17E-01 SR-280-610 OL-1-65, SP-7 350.9 < MDA < MDA < MDA < MDA 0.000 1.27E-01 1.29E-01 SR-280-611 OL-1-65, SP-8 360.2 < MDA < MDA < MDA < MDA 0.000 1.27E-01 1.26E-01 SR-280-612 OL-1-65, SP-9 350.0 < MDA < MDA < MDA < MDA 0.000 1.52E-01 1.29E-01 SR-280-613 OL-1-65, SP-10 327.0 3.30E-01 1.26E-01 < MDA < MDA 0.028 1.38E-01 SR-280-614 OL-1-65, SP-11 321.9 < MDA < MDA < MDA < MDA 0.000 1.19E-01 1.41E-01 SR-280-639 OL-1-66, SP-1 348.8 3.51E-01 1.49E-01 < MDA < MDA 0.030 1.30E-01 SR-280-640 OL-1-66, SP-2 382.2 < MDA < MDA < MDA < MDA 0.000 1.21E-01 1.20E-01 SR-280-641 OL-1-66, SP-3 356.1 < MDA < MDA < MDA < MDA 0.000 1.17E-01 1.27E-01 SR-280-642 OL-1-66, SP-4 367.9 < MDA < MDA < MDA < MDA 0.000 1.15E-01 1.25E-01 SR-280-643 OL-1-66, SP-5 384.7 < MDA < MDA < MDA < MDA 0.000 1.08E-01 1.18E-01 SR-280-644 OL-1-66, SP-6 364.4 < MDA < MDA < MDA < MDA 0.000 1.16E-01 1.26E-01 SR-280-645 OL-1-66, SP-7 380.8 < MDA < MDA < MDA < MDA 0.000 1.33E-01 1.21E-01

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 11 of 28 Table 1, Open Land Area FSS Sample Results Cs-137 Co-60 Cs-137 Co-60 Weight Unity Sample # Location MDA MDA (g) pCi/g 2 pCi/g 2 Fraction pCi/g pCi/g SR-280-647 OL-1-66, SP-8 349.7 < MDA < MDA < MDA < MDA 0.000 1.48E-01 1.31E-01 SR-280-648 OL-1-66, SP-9 339.2 < MDA < MDA < MDA < MDA 0.000 1.80E-01 1.33E-01 SR-280-649 OL-1-66, SP-10 335.0 3.35E-01 1.63E-01 < MDA < MDA 0.029 1.37E-01 SR-280-650 OL-1-66, SP-11 354.6 3.10E-01 1.33E-01 < MDA < MDA 0.027 1.28E-01 SR-280-651 OL-1-67, SP-1 371.4 2.73E-01 1.30E-01 < MDA < MDA 0.024 1.24E-01 SR-280-652 OL-1-67, SP-2 368.3 < MDA < MDA < MDA < MDA 0.000 1.45E-01 1.23E-01 SR-280-653 OL-1-67, SP-3 342.9 < MDA < MDA < MDA < MDA 0.000 9.64E-02 1.34E-01 SR-280-654 OL-1-67, SP-4 357.3 2.34E-01 1.17E-01 < MDA < MDA 0.020 1.27E-01 SR-280-655 OL-1-67, SP-5 373.7 2.65E-01 1.09E-01 < MDA < MDA 0.023 1.23E-01 SR-280-656 OL-1-67, SP-6 377.5 3.45E-01 1.34E-01 < MDA < MDA 0.030 1.20E-01 SR-280-657 OL-1-67, SP-7 359.7 < MDA < MDA < MDA < MDA 0.000 1.97E-01 1.28E-01 SR-280-659 OL-1-67, SP-8 327.3 3.80E-01 1.50E-01 < MDA < MDA 0.033 1.40E-01 SR-280-660 OL-1-67, SP-9 401.9 < MDA < MDA < MDA < MDA 0.000 9.36E-02 1.13E-01 SR-280-661 OL-1-67, SP-10 343.4 < MDA < MDA < MDA < MDA 0.000 1.42E-01 1.34E-01 SR-280-662 OL-1-67, SP-11 339.2 < MDA < MDA < MDA < MDA 0.000 1.49E-01 1.33E-01 SR-280-270 OL-1-68, SP-1 386.9 1.53E-01 6.85E-02 < MDA < MDA 0.013 5.64E-02 SR-280-272 OL-1-68, SP-2 404.1 < MDA < MDA < MDA < MDA 0.000 6.77E-02 1.08E-01 SR-280-273 OL-1-68, SP-3 383.2 2.34E-01 1.06E-01 < MDA < MDA 0.020 1.14E-01 SR-280-274 OL-1-68, SP-4 383.8 < MDA < MDA < MDA < MDA 0.000 7.12E-02 1.14E-01 SR-280-275 OL-1-68, SP-5 391.4 < MDA < MDA < MDA < MDA 0.000 1.12E-01 1.12E-01 SR-280-276 OL-1-68, SP-6 426.9 < MDA < MDA < MDA < MDA 0.000 1.07E-01 1.02E-01 SR-280-277 OL-1-68, SP-7 370.3 < MDA < MDA < MDA < MDA 0.000 1.08E-01 1.18E-01 SR-280-278 OL-1-68, SP-8 422.5 1.84E-01 8.13E-02 < MDA < MDA 0.016 1.03E-01 SR-280-279 OL-1-68, SP-9 433.2 < MDA < MDA < MDA < MDA 0.000 7.67E-02 1.01E-01 SR-280-280 OL-1-68, SP-10 367.7 2.74E-01 1.19E-01 < MDA < MDA 0.024 1.19E-01 SR-280-281 OL-1-68, SP-11 352.5 3.35E-01 1.35E-01 < MDA < MDA 0.029 1.24E-01 SR-280-282 OL-1-69, SP-1 361.4 2.26E-01 9.74E-02 < MDA < MDA 0.019 1.21E-01 SR-280-283 OL-1-69, SP-2 350.6 2.34E-01 1.12E-01 < MDA < MDA 0.020 1.25E-01 SR-280-284 OL-1-69, SP-3 380.0 < MDA < MDA < MDA < MDA 0.000 1.13E-01 1.15E-01 SR-280-285 OL-1-69, SP-4 362.4 < MDA < MDA < MDA < MDA 0.000 8.99E-02 1.20E-01

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 12 of 28 Table 1, Open Land Area FSS Sample Results Cs-137 Co-60 Cs-137 Co-60 Weight Unity Sample # Location MDA MDA (g) pCi/g 2 pCi/g 2 Fraction pCi/g pCi/g SR-280-286 OL-1-69, SP-5 402.0 3.69E-01 1.27E-01 < MDA < MDA 0.032 1.09E-01 SR-280-287 OL-1-69, SP-6 373.3 3.67E-01 1.33E-01 < MDA < MDA 0.032 1.17E-01 SR-280-288 OL-1-69, SP-7 423.4 < MDA < MDA < MDA < MDA 0.000 8.57E-02 1.03E-01 SR-280-289 OL-1-69, SP-8 421.7 < MDA < MDA < MDA < MDA 0.000 9.72E-02 1.04E-01 SR-280-290 OL-1-69, SP-9 404.1 2.52E-01 1.14E-01 < MDA < MDA 0.022 1.08E-01 SR-280-291 OL-1-69, SP-10 404.2 < MDA < MDA < MDA < MDA 0.000 8.38E-02 1.08E-01 SR-280-292 OL-1-69, SP-11 418.8 < MDA < MDA < MDA < MDA 0.000 1.09E-01 1.04E-01 SR-280-358 OL-1-70, SP-1 318.0 < MDA < MDA < MDA < MDA 0.000 1.43E-01 1.38E-01 SR-280-359 OL-1-70, SP-2 327.0 < MDA < MDA < MDA < MDA 0.000 1.63E-01 1.41E-01 SR-280-360 OL-1-70, SP-3 372.5 < MDA < MDA < MDA < MDA 0.000 1.25E-01 1.18E-01 SR-280-362 OL-1-70, SP-4 397.9 < MDA < MDA < MDA < MDA 0.000 8.67E-02 1.10E-01 SR-280-363 OL-1-70, SP-5 364.1 2.72E-01 1.12E-01 < MDA < MDA 0.023 1.27E-01 SR-280-364 OL-1-70, SP-6 355.0 2.74E-01 1.18E-01 < MDA < MDA 0.024 1.23E-01 SR-280-365 OL-1-70, SP-7 377.5 < MDA < MDA < MDA < MDA 0.000 1.60E-01 1.22E-01 SR-280-366 OL-1-70, SP-8 347.7 2.71E-01 1.17E-01 < MDA < MDA 0.023 1.26E-01 SR-280-367 OL-1-70, SP-9 334.6 < MDA < MDA < MDA < MDA 0.000 1.30E-01 1.38E-01 SR-280-368 OL-1-70, SP-10 380.0 < MDA < MDA < MDA < MDA 0.000 7.20E-02 1.15E-01 SR-280-369 OL-1-70, SP-11 349.1 < MDA < MDA < MDA < MDA 0.000 1.28E-01 1.25E-01 SR-280-102 OL-1-71, SP-1 434.9 <MDA <MDA <MDA <MDA 0.000 6.28E-02 1.00E-01 SR-280-103 OL-1-71, SP-2 434.2 <MDA <MDA <MDA <MDA 0.000 6.53E-02 1.04E-01 SR-280-104 OL-1-71, SP-3 418.6 <MDA <MDA <MDA <MDA 0.000 7.62E-02 1.04E-01 SR-280-105 OL-1-71, SP-4 382.5 2.62E-01 1.04E-01 <MDA <MDA 0.023 1.18E-01 OL-1-71, SP-4 SR-280-105 recount 382.5 1.52E-01 5.26E-02 <MDA <MDA 0.013 4.69E-02 SR-280-107 OL-1-71, SP-5 430.0 <MDA <MDA <MDA <MDA 0.000 8.32E-02 1.05E-01 SR-280-108 OL-1-71, SP-6 366.0 <MDA <MDA <MDA <MDA 0.000 1.17E-01 1.19E-01 SR-280-109 OL-1-71, SP-7 384.7 2.58E-01 1.26E-01 <MDA <MDA 0.022 1.17E-01 SR-280-110 OL-1-71, SP-8 428.2 <MDA <MDA <MDA <MDA 0.000 7.29E-02 1.02E-01 SR-280-111 OL-1-71, SP-9 414.8 <MDA <MDA <MDA <MDA 0.000 8.92E-02 1.09E-01 SR-280-112 OL-1-71, SP-10 416.7 <MDA <MDA <MDA <MDA 0.000 6.56E-02 1.04E-01

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 13 of 28 Table 1, Open Land Area FSS Sample Results Cs-137 Co-60 Cs-137 Co-60 Weight Unity Sample # Location MDA MDA (g) pCi/g 2 pCi/g 2 Fraction pCi/g pCi/g SR-280-113 OL-1-71, SP-11 413.1 <MDA <MDA <MDA <MDA 0.000 1.20E-01 1.05E-01 SR-280-90 OL-1-72, SP-1 420.3 <MDA <MDA <MDA <MDA 0.000 9.51E-02 1.04E-01 SR-280-91 OL-1-72, SP-2 377.2 2.86E-01 1.39E-01 <MDA <MDA 0.025 1.66E-01 SR-280-92 OL-1-72, SP-3 389.2 2.32E-01 8.36E-02 <MDA <MDA 0.020 5.59E-02 SR-280-93 OL-1-72, SP-4 356.0 5.18E-01 1.62E-01 <MDA <MDA 0.045 1.27E-01 SR-280-95 OL-1-72, SP-5 371.6 3.06E-01 1.43E-01 <MDA <MDA 0.026 1.17E-01 SR-280-96 OL-1-72, SP-6 372.1 3.21E-01 1.17E-01 <MDA <MDA 0.028 1.29E-01 SR-280-97 OL-1-72, SP-7 371.2 3.64E-01 1.38E-01 <MDA <MDA 0.031 1.17E-01 SR-280-98 OL-1-72, SP-8 443.4 <MDA <MDA <MDA <MDA 0.000 6.40E-02 1.02E-01 SR-280-99 OL-1-72, SP-9 418.6 <MDA <MDA <MDA <MDA 0.000 6.53E-02 1.04E-01 SR-280-100 OL-1-72, SP-10 398.3 2.96E-01 1.19E-01 <MDA <MDA 0.026 1.09E-01 SR-280-101 OL-1-72, SP-11 365.4 <MDA <MDA <MDA <MDA 0.000 1.09E-01 1.19E-01 SR-280-221 OL-1-73, SP-1 364.9 <MDA <MDA <MDA <MDA 0.000 8.74E-02 1.19E-01 SR-280-222 OL-1-73, SP-2 372.0 <MDA <MDA <MDA <MDA 0.000 7.62E-02 1.21E-01 SR-280-223 OL-1-73, SP-3 408.5 3.26E-01 1.20E-01 <MDA <MDA 0.028 1.06E-01 SR-280-224 OL-1-73, SP-4 454.2 6.06E-01 1.61E-01 <MDA <MDA 0.052 9.93E-02 SR-280-225 OL-1-73, SP-5 438.9 2.87E-01 1.00E-01 <MDA <MDA 0.025 9.91E-02 SR-280-226 OL-1-73, SP-6 415.2 <MDA <MDA <MDA <MDA 0.000 1.07E-01 1.09E-01 SR-280-227 OL-1-73, SP-7 410.5 2.92E-01 1.11E-01 <MDA <MDA 0.025 1.06E-01 SR-280-228 OL-1-73, SP-8 380.7 2.81E-01 1.39E-01 <MDA <MDA 0.024 1.18E-01 SR-280-229 OL-1-73, SP-9 415.7 6.51E-01 1.70E-01 <MDA <MDA 0.056 1.05E-01 SR-280-230 OL-1-73, SP-10 413.9 <MDA <MDA <MDA <MDA 0.000 1.24E-01 1.09E-01 SR-280-231 OL-1-73, SP-11 374.7 1.78E+00 2.96E-01 <MDA <MDA 0.153 1.16E-01 OL-1-73, SP-11 SR-280-231 recount 374.7 1.35E+00 1.48E-01 <MDA <MDA 0.116 5.14E-02 SR-280-233 OL-1-73, SP-12 387.2 <MDA <MDA <MDA <MDA 0.000 7.06E-02 1.12E-01 SR-280-208 OL-1-74, SP-1 381.9 4.90E-01 1.73E-01 <MDA <MDA 0.042 1.14E-01 SR-280-209 OL-1-74, SP-2 381.4 3.69E-01 1.38E-01 <MDA <MDA 0.032 1.18E-01 SR-280-211 OL-1-74, SP-3 408.0 6.79E-01 1.65E-01 <MDA <MDA 0.059 1.11E-01 SR-280-212 OL-1-74, SP-4 420.2 9.62E-01 1.94E-01 <MDA <MDA 0.083 1.04E-01

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 14 of 28 Table 1, Open Land Area FSS Sample Results Cs-137 Co-60 Cs-137 Co-60 Weight Unity Sample # Location MDA MDA (g) pCi/g 2 pCi/g 2 Fraction pCi/g pCi/g SR-280-213 OL-1-74, SP-5 407.1 4.29E-01 1.49E-01 <MDA <MDA 0.037 1.11E-01 SR-280-214 OL-1-74, SP-6 464.5 8.81E-01 1.99E-01 <MDA <MDA 0.076 9.37E-02 SR-280-215 OL-1-74, SP-7 419.9 8.30E-01 1.94E-01 <MDA <MDA 0.072 1.08E-01 SR-280-216 OL-1-74, SP-8 420.1 2.44E+00 3.39E-01 <MDA <MDA 0.210 1.04E-01 SR-280-217 OL-1-74, SP-9 434.4 7.31E-01 1.75E-01 <MDA <MDA 0.063 1.04E-01 SR-280-218 OL-1-74, SP-10 367.0 <MDA <MDA <MDA <MDA 0.000 1.31E-01 1.19E-01 SR-280-219 OL-1-74, SP-11 431.8 3.23E-01 1.16E-01 <MDA <MDA 0.028 1.05E-01 SR-280-220 OL-1-74, SP-12 459.9 <MDA <MDA <MDA <MDA 0.000 7.78E-02 9.82E-02 SR-280-194 OL-1-75, SP-1 328.9 2.37E-01 1.04E-01 <MDA <MDA 0.020 1.32E-01 SR-280-195 OL-1-75, SP-2 419.0 <MDA <MDA <MDA <MDA 0.000 6.77E-02 1.08E-01 SR-280-196 OL-1-75, SP-3 415.4 2.87E-01 1.26E-01 <MDA <MDA 0.025 1.05E-01 SR-280-197 OL-1-75, SP-4 436.2 2.24E-01 9.69E-02 <MDA <MDA 0.019 1.04E-01 SR-280-198 OL-1-75, SP-5 406.3 3.76E-01 1.54E-01 <MDA <MDA 0.032 1.07E-01 SR-280-199 OL-1-75, SP-6 429.5 5.73E-01 1.54E-01 <MDA <MDA 0.049 1.12E-01 SR-280-200 OL-1-75, SP-7 426.2 <MDA <MDA <MDA <MDA 0.000 8.90E-02 1.02E-01 SR-280-201 OL-1-75, SP-8 436.4 <MDA <MDA <MDA <MDA 0.000 7.07E-02 1.03E-01 SR-280-202 OL-1-75, SP-9 425.4 <MDA <MDA <MDA <MDA 0.000 1.01E-01 1.02E-01 SR-280-203 OL-1-75, SP-10 447.6 <MDA <MDA <MDA <MDA 0.000 1.19E-01 1.01E-01 SR-280-204 OL-1-75, SP-11 404.6 4.03E-01 1.32E-01 <MDA <MDA 0.035 1.08E-01 SR-280-205 OL-1-75, SP-12 371.8 <MDA <MDA <MDA <MDA 0.000 7.63E-02 1.21E-01 SR-280-206 OL-1-75, SP-13 374.2 3.70E-01 1.30E-01 <MDA <MDA 0.032 1.16E-01 SR-280-294 OL-1-76, SP-1 402.8 3.32E-01 1.21E-01 < MDA < MDA 0.029 1.15E-01 SR-280-295 OL-1-76, SP-2 380.6 < MDA < MDA < MDA < MDA 0.000 8.91E-02 1.21E-01 SR-280-297 OL-1-76, SP-3 424.0 < MDA < MDA < MDA < MDA 0.000 7.17E-02 1.09E-01 SR-280-298 OL-1-76, SP-4 335.1 2.10E-01 9.74E-02 < MDA < MDA 0.018 1.30E-01 SR-280-299 OL-1-76, SP-5 392.0 < MDA < MDA < MDA < MDA 0.000 1.11E-01 1.17E-01 SR-280-300 OL-1-76, SP-6 413.2 < MDA < MDA < MDA < MDA 0.000 1.23E-01 1.06E-01 SR-280-301 OL-1-76, SP-7 354.5 < MDA < MDA < MDA < MDA 0.000 9.57E-02 1.30E-01 SR-280-302 OL-1-76, SP-8 381.2 < MDA < MDA < MDA < MDA 0.000 7.61E-02 1.15E-01 SR-280-303 OL-1-76, SP-9 400.2 < MDA < MDA < MDA < MDA 0.000 1.57E-01 1.15E-01

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 15 of 28 Table 1, Open Land Area FSS Sample Results Cs-137 Co-60 Cs-137 Co-60 Weight Unity Sample # Location MDA MDA (g) pCi/g 2 pCi/g 2 Fraction pCi/g pCi/g SR-280-304 OL-1-76, SP-10 390.3 < MDA < MDA < MDA < MDA 0.000 1.27E-01 1.12E-01 SR-280-305 OL-1-76, SP-11 388.0 2.13E-01 9.55E-02 < MDA < MDA 0.018 1.19E-01 SR-280-306 OL-1-77, SP-1 378.0 < MDA < MDA < MDA < MDA 0.000 1.08E-01 1.16E-01 SR-280-307 OL-1-77, SP-2 406.0 < MDA < MDA < MDA < MDA 0.000 8.15E-02 1.14E-01 SR-280-308 OL-1-77, SP-3 425.7 < MDA < MDA < MDA < MDA 0.000 7.17E-02 1.03E-01 SR-280-309 OL-1-77, SP-4 349.5 < MDA < MDA < MDA < MDA 0.000 1.08E-01 1.32E-01 SR-280-310 OL-1-77, SP-5 328.1 < MDA < MDA < MDA < MDA 0.000 1.25E-01 1.33E-01 SR-280-311 OL-1-77, SP-6 397.0 < MDA < MDA < MDA < MDA 0.000 1.32E-01 1.16E-01 SR-280-312 OL-1-77, SP-7 430.7 < MDA < MDA < MDA < MDA 0.000 9.17E-02 1.02E-01 SR-280-313 OL-1-77, SP-8 380.0 < MDA < MDA < MDA < MDA 0.000 1.23E-01 1.21E-01 SR-280-314 OL-1-77, SP-9 386.0 < MDA < MDA < MDA < MDA 0.000 8.27E-02 1.13E-01 SR-280-315 OL-1-77, SP-10 398.4 < MDA < MDA < MDA < MDA 0.000 7.63E-02 1.16E-01 SR-280-316 OL-1-77, SP-11 402.8 < MDA < MDA < MDA < MDA 0.000 1.15E-01 1.09E-01 SR-280-317 OL-1-77, SP-12 380.0 < MDA < MDA < MDA < MDA 0.000 8.00E-02 1.21E-01 SR-280-319 OL-1-78, SP-1 365.7 < MDA < MDA < MDA < MDA 0.000 1.38E-01 1.24E-01 SR-280-320 OL-1-78, SP-2 358.3 3.34E-01 1.37E-01 < MDA < MDA 0.029 1.29E-01 SR-280-321 OL-1-78, SP-3 354.9 < MDA < MDA < MDA < MDA 0.000 9.13E-02 1.28E-01 SR-280-322 OL-1-78, SP-4 371.8 < MDA < MDA < MDA < MDA 0.000 8.17E-02 1.24E-01 SR-280-323 OL-1-78, SP-5 401.7 2.23E-01 7.74E-02 < MDA < MDA 0.019 5.64E-02 SR-280-325 OL-1-78, SP-6 402.6 < MDA < MDA < MDA < MDA 0.000 9.05E-02 1.13E-01 SR-280-326 OL-1-78, SP-7 428.0 2.62E-01 1.19E-01 < MDA < MDA 0.023 1.08E-01 SR-280-327 OL-1-78, SP-8 439.0 < MDA < MDA < MDA < MDA 0.000 9.46E-02 1.03E-01 SR-280-328 OL-1-78, SP-9 429.0 3.80E-01 1.58E-01 < MDA < MDA 0.033 1.07E-01 SR-280-329 OL-1-78, SP-10 457.4 < MDA < MDA < MDA < MDA 0.000 9.51E-02 9.91E-01 SR-280-330 OL-1-78, SP-11 424.8 2.08E-01 9.91E-02 < MDA < MDA 0.018 1.07E-01 SR-280-331 OL-1-78, SP-12 426.0 2.17E-01 8.95E-02 < MDA < MDA 0.019 1.06E-01 SR-280-332 OL-1-79, SP-1 360.2 2.26E-01 1.11E-01 < MDA < MDA 0.019 1.26E-01 SR-280-333 OL-1-79, SP-2 424.6 < MDA < MDA < MDA < MDA 0.000 7.97E-02 1.07E-01 SR-280-334 OL-1-79, SP-3 380.2 2.33E-01 9.82E-02 < MDA < MDA 0.020 1.19E-01 SR-280-335 OL-1-79, SP-4 459.4 < MDA < MDA < MDA < MDA 0.000 1.05E-01 9.88E-02

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 16 of 28 Table 1, Open Land Area FSS Sample Results Cs-137 Co-60 Cs-137 Co-60 Weight Unity Sample # Location MDA MDA (g) pCi/g 2 pCi/g 2 Fraction pCi/g pCi/g SR-280-336 OL-1-79, SP-5 394.0 3.71E-01 1.23E-01 < MDA < MDA 0.032 1.15E-01 SR-280-337 OL-1-79, SP-6 392.6 2.68E-01 8.62E-02 < MDA < MDA 0.023 5.78E-02 SR-280-339 OL-1-79, SP-7 397.9 2.17E-01 1.01E-01 < MDA < MDA 0.019 1.14E-01 SR-280-340 OL-1-79, SP-8 362.1 3.53E-01 1.39E-01 < MDA < MDA 0.030 1.21E-01 SR-280-341 OL-1-79, SP-9 348.1 < MDA < MDA < MDA < MDA 0.000 1.08E-01 1.30E-01 SR-280-342 OL-1-79, SP-10 420.0 2.21E-01 8.95E-02 < MDA < MDA 0.019 1.04E-01 SR-280-343 OL-1-79, SP-11 379.1 < MDA < MDA < MDA < MDA 0.000 9.10E-02 1.20E-01 SR-280-344 OL-1-79, SP-12 402.6 3.07E-01 1.15E-01 < MDA < MDA 0.026 1.09E-01 SR-280-345 OL-1-80, SP-1 410.8 2.98E-01 1.06E-01 < MDA < MDA 0.026 1.07E-01 SR-280-346 OL-1-80, SP-2 389.5 2.31E-01 1.15E-01 < MDA < MDA 0.020 1.17E-01 SR-280-347 OL-1-80, SP-3 381.0 2.75E-01 1.23E-01 < MDA < MDA 0.024 1.15E-01 SR-280-348 OL-1-80, SP-4 402.6 4.32E-01 1.45E-01 < MDA < MDA 0.037 1.13E-01 SR-280-349 OL-1-80, SP-5 375.8 3.85E-01 1.26E-01 < MDA < MDA 0.033 1.17E-01 SR-280-350 OL-1-80, SP-6 367.4 4.07E-01 1.53E-01 < MDA < MDA 0.035 1.24E-01 SR-280-351 OL-1-80, SP-7 412.3 4.74E-01 1.43E-01 < MDA < MDA 0.041 1.06E-01 SR-280-352 OL-1-80, SP-8 384.7 2.14E-01 1.02E-01 < MDA < MDA 0.018 1.18E-01 SR-280-353 OL-1-80, SP-9 446.8 2.19E-01 8.64E-02 < MDA < MDA 0.019 5.16E-02 SR-280-354 OL-1-80, SP-10 397.0 3.33E-01 9.49E-02 < MDA < MDA 0.029 5.81E-02 SR-280-355 OL-1-80, SP-11 393.0 2.66E-01 1.15E-01 < MDA < MDA 0.023 1.17E-01 SR-280-356 OL-1-80, SP-12 371.4 2.98E-01 1.14E-01 < MDA < MDA 0.026 6.21E-02 SR-280-370 OL-1-81, SP-1 365.1 < MDA < MDA < MDA < MDA 0.000 7.49E-02 1.20E-01 SR-280-371 OL-1-81, SP-2 323.8 2.68E-01 1.17E-01 < MDA < MDA 0.023 1.42E-01 SR-280-372 OL-1-81, SP-3 333.0 < MDA < MDA < MDA < MDA 0.000 8.21E-02 1.31E-01 SR-280-373 OL-1-81, SP-4 383.4 < MDA < MDA < MDA < MDA 0.000 1.00E-01 1.20E-01 SR-280-374 OL-1-81, SP-5 371.0 3.48E-01 1.33E-01 < MDA < MDA 0.030 1.18E-01 SR-280-375 OL-1-81, SP-6 339.2 3.83E-01 1.86E-01 < MDA < MDA 0.033 1.36E-01 SR-280-376 OL-1-81, SP-7 359.2 2.79E-01 1.09E-01 < MDA < MDA 0.024 1.22E-01 SR-280-377 OL-1-81, SP-8 394.5 3.16E-01 1.25E-01 < MDA < MDA 0.027 1.17E-01 SR-280-379 OL-1-81, SP-9 359.8 4.01E-01 1.37E-01 < MDA < MDA 0.035 1.28E-01 SR-280-380 OL-1-81, SP-10 372.0 2.53E-01 1.10E-01 < MDA < MDA 0.022 1.18E-01

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 17 of 28 Table 1, Open Land Area FSS Sample Results Cs-137 Co-60 Cs-137 Co-60 Weight Unity Sample # Location MDA MDA (g) pCi/g 2 pCi/g 2 Fraction pCi/g pCi/g SR-280-381 OL-1-81, SP-11 355.2 3.27E-01 1.46E-01 < MDA < MDA 0.028 1.30E-01 SR-280-382 OL-1-82, SP-1 369.5 2.91E-01 1.10E-01 < MDA < MDA 0.025 1.18E-01 SR-280-383 OL-1-82, SP-2 448.2 < MDA < MDA < MDA < MDA 0.000 7.19E-02 1.03E-01 SR-280-384 OL-1-82, SP-3 342.6 3.12E-01 1.42E-01 < MDA < MDA 0.027 1.28E-01 SR-280-385 OL-1-82, SP-4 367.7 < MDA < MDA < MDA < MDA 0.000 9.44E-02 1.25E-01 SR-280-386 OL-1-82, SP-5 383.6 2.23E-01 9.39E-02 < MDA < MDA 0.019 1.14E-01 SR-280-387 OL-1-82, SP-6 345.6 2.77E-01 1.27E-01 < MDA < MDA 0.024 1.27E-01 SR-280-389 OL-1-82, SP-7 403.4 < MDA < MDA < MDA < MDA 0.000 9.16E-02 1.14E-01 SR-280-390 OL-1-82, SP-8 376.8 2.92E-01 1.22E-01 < MDA < MDA 0.025 1.16E-01 SR-280-391 OL-1-82, SP-9 346.2 3.10E-01 1.22E-01 < MDA < MDA 0.027 1.33E-01 SR-280-392 OL-1-82, SP-10 396.5 < MDA < MDA < MDA < MDA 0.000 6.90E-02 1.10E-01 SR-280-393 OL-1-82, SP-11 443.0 < MDA < MDA < MDA < MDA 0.000 6.86E-02 1.04E-01 SR-280-394 OL-1-83, SP-1 368.8 2.24E-01 1.01E-01 < MDA < MDA 0.019 1.25E-01 SR-280-395 OL-1-83, SP-2 412.0 < MDA < MDA < MDA < MDA 0.000 1.10E-01 1.10E-01 SR-280-397 OL-1-83, SP-3 404.5 < MDA < MDA < MDA < MDA 0.000 7.02E-02 1.12E-01 SR-280-398 OL-1-83, SP-4 362.8 < MDA < MDA < MDA < MDA 0.000 8.38E-02 1.27E-01 SR-280-399 OL-1-83, SP-5 421.8 < MDA < MDA < MDA < MDA 0.000 1.16E-01 1.08E-01 SR-280-400 OL-1-83, SP-6 363.4 < MDA < MDA < MDA < MDA 0.000 1.37E-01 1.27E-01 SR-280-401 OL-1-83, SP-7 378.6 < MDA < MDA < MDA < MDA 0.000 1.46E-01 1.20E-01 SR-280-402 OL-1-83, SP-8 356.7 < MDA < MDA < MDA < MDA 0.000 1.39E-01 1.27E-01 SR-280-403 OL-1-83, SP-9 388.9 < MDA < MDA < MDA < MDA 0.000 9.69E-02 1.19E-01 SR-280-404 OL-1-83, SP-10 343.2 < MDA < MDA < MDA < MDA 0.000 1.71E-01 1.32E-01 SR-280-405 OL-1-83, SP-11 320.6 < MDA < MDA < MDA < MDA 0.000 1.70E-01 1.44E-01 SR-280-430 OL-1-84, SP-1 363.6 < MDA < MDA < MDA < MDA 0.000 1.28E-01 1.26E-01 SR-280-432 OL-1-84, SP-2 359.4 < MDA < MDA < MDA < MDA 0.000 9.66E-02 1.28E-01 SR-280-433 OL-1-84, SP-3 345.8 2.42E-01 1.10E-01 < MDA < MDA 0.021 1.26E-01 SR-280-434 OL-1-84, SP-4 370.7 < MDA < MDA < MDA < MDA 0.000 8.20E-02 1.24E-01 SR-280-435 OL-1-84, SP-5 362.9 2.72E-01 1.24E-01 < MDA < MDA 0.023 1.20E-01 SR-280-436 OL-1-84, SP-6 353.2 < MDA < MDA < MDA < MDA 0.000 8.60E-02 1.30E-01 SR-280-437 OL-1-84, SP-7 352.7 < MDA < MDA < MDA < MDA 0.000 1.63E-01 1.24E-01

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 18 of 28 Table 1, Open Land Area FSS Sample Results Cs-137 Co-60 Cs-137 Co-60 Weight Unity Sample # Location MDA MDA (g) pCi/g 2 pCi/g 2 Fraction pCi/g pCi/g SR-280-438 OL-1-84, SP-8 397.2 < MDA < MDA < MDA < MDA 0.000 8.20E-02 1.10E-01 SR-280-439 OL-1-84, SP-9 327.9 < MDA < MDA < MDA < MDA 0.000 1.39E-01 1.40E-01 SR-280-440 OL-1-84, SP-10 361.3 < MDA < MDA < MDA < MDA 0.000 8.24E-02 1.21E-01 SR-280-441 OL-1-84, SP-11 366.1 < MDA < MDA < MDA < MDA 0.000 1.41E-01 1.26E-01 SR-280-418 OL-85, SP-1 318.3 3.99E-01 1.41E-01 < MDA < MDA 0.034 1.43E-01 SR-280-419 OL-85, SP-2 340.2 3.15E-01 1.56E-01 < MDA < MDA 0.027 1.33E-01 SR-280-420 OL-85, SP-3 341.1 < MDA < MDA < MDA < MDA 0.000 1.72E-01 1.33E-01 SR-280-421 OL-85, SP-4 355.5 < MDA < MDA < MDA < MDA 0.000 1.70E-01 1.28E-01 SR-280-422 OL-85, SP-5 313.1 4.35E-01 1.67E-01 < MDA < MDA 0.038 1.45E-01 SR-280-423 OL-85, SP-6 374.8 < MDA < MDA < MDA < MDA 0.000 1.37E-01 1.21E-01 SR-280-424 OL-85, SP-7 390.4 3.16E-01 1.32E-01 < MDA < MDA 0.027 1.16E-01 SR-280-425 OL-85, SP-8 362.0 < MDA < MDA < MDA < MDA 0.000 1.18E-01 1.25E-01 SR-280-427 OL-85, SP-9 357.2 < MDA < MDA < MDA < MDA 0.000 8.43E-02 1.27E-01 SR-280-428 OL-85, SP-10 383.3 < MDA < MDA < MDA < MDA 0.000 1.22E-01 1.20E-01 SR-280-429 OL-85, SP-11 388.1 < MDA < MDA < MDA < MDA 0.000 1.07E-01 1.17E-01 SR-280-442 OL-1-86, SP-1 381.5 4.36E-01 1.87E-01 < MDA < MDA 0.038 1.21E-01 SR-280-443 OL-1-86, SP-2 421.1 1.00E-01 1.42E-02 < MDA < MDA 0.009 1.61E-02 SR-280-445 OL-1-86, SP-3 373.7 < MDA < MDA < MDA < MDA 0.000 7.83E-02 1.21E-01 SR-280-446 OL-1-86, SP-4 404.6 < MDA < MDA < MDA < MDA 0.000 1.48E-01 1.12E-01 SR-280-447 OL-1-86, SP-5 430.4 < MDA < MDA < MDA < MDA 0.000 9.52E-02 1.07E-01 SR-280-448 OL-1-86, SP-6 390.1 < MDA < MDA < MDA < MDA 0.000 1.05E-01 1.18E-01 SR-280-449 OL-1-86, SP-7 387.0 < MDA < MDA < MDA < MDA 0.000 9.55E-02 1.19E-01 SR-280-450 OL-1-86, SP-8 378.6 < MDA < MDA < MDA < MDA 0.000 1.74E-01 1.20E-01 SR-280-451 OL-1-86, SP-9 379.8 < MDA < MDA < MDA < MDA 0.000 1.11E-01 1.22E-01 SR-280-452 OL-1-86, SP-10 384.3 < MDA < MDA < MDA < MDA 0.000 9.48E-02 1.18E-01 SR-280-453 OL-1-86, SP-11 382.1 2.38E-01 1.02E-01 < MDA < MDA 0.021 1.21E-01 SR-280-406 OL-1-87, SP-1 336.4 < MDA < MDA < MDA < MDA 0.000 1.10E-01 1.37E-01 SR-280-408 OL-1-87, SP-2 356.3 < MDA < MDA < MDA < MDA 0.000 1.11E-01 1.27E-01 SR-280-409 OL-1-87, SP-3 340.8 < MDA < MDA < MDA < MDA 0.000 1.64E-01 1.35E-01 SR-280-410 OL-1-87, SP-4 369.3 3.26E-01 1.35E-01 < MDA < MDA 0.028 1.23E-01

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 19 of 28 Table 1, Open Land Area FSS Sample Results Cs-137 Co-60 Cs-137 Co-60 Weight Unity Sample # Location MDA MDA (g) pCi/g 2 pCi/g 2 Fraction pCi/g pCi/g SR-280-411 OL-1-87, SP-5 331.8 < MDA < MDA < MDA < MDA 0.000 1.55E-01 1.39E-01 SR-280-412 OL-1-87, SP-6 374.4 < MDA < MDA < MDA < MDA 0.000 1.55E-01 1.21E-01 SR-280-413 OL-1-87, SP-7 348.1 < MDA < MDA < MDA < MDA 0.000 1.67E-01 1.33E-01 SR-280-414 OL-1-87, SP-8 360.2 < MDA < MDA < MDA < MDA 0.000 1.90E-01 1.26E-01 SR-280-415 OL-1-87, SP-9 383.3 < MDA < MDA < MDA < MDA 0.000 1.87E-01 1.46E-01 SR-280-416 OL-1-87, SP-10 357.2 < MDA < MDA < MDA < MDA 0.000 1.30E-01 1.27E-01 SR-280-417 OL-1-87, SP-11 321.2 < MDA < MDA < MDA < MDA 0.000 1.31E-01 1.44E-01 SR-280-591 OL-1-88, SP-1 389.9 < MDA < MDA < MDA < MDA 0.000 7.79E-02 1.18E-01 SR-280-592 OL-1-88, SP-2 389.9 3.75E-01 1.49E-01 < MDA < MDA 0.032 1.16E-01 SR-280-593 OL-1-88, SP-3 376.9 6.63E-01 1.98E-01 < MDA < MDA 0.057 1.22E-01 SR-280-594 OL-1-88, SP-4 355.8 < MDA < MDA < MDA < MDA 0.000 1.41E-01 1.27E-01 SR-280-595 OL-1-88, SP-5 375.6 < MDA < MDA < MDA < MDA 0.000 1.20E-01 1.22E-01 SR-280-596 OL-1-88, SP-6 349.6 < MDA < MDA < MDA < MDA 0.000 1.32E-01 1.29E-01 SR-280-597 OL-1-88, SP-7 348.0 < MDA < MDA < MDA < MDA 0.000 1.40E-01 1.32E-01 SR-280-599 OL-1-88, SP-8 360.9 < MDA < MDA < MDA < MDA 0.000 1.74E-01 1.27E-01 SR-280-600 OL-1-88, SP-9 345.4 < MDA < MDA < MDA < MDA 0.000 1.75E-01 1.33E-01 SR-280-601 OL-1-88, SP-10 360.2 < MDA < MDA < MDA < MDA 0.000 1.29E-01 1.26E-01 SR-280-602 OL-1-88, SP-11 373.1 2.97E-01 1.40E-01 < MDA < MDA 0.026 1.23E-01 SR-280-554 OL-1-89, SP-1 413.8 < MDA < MDA < MDA < MDA 0.000 1.32E-01 1.11E-01 SR-280-555 OL-1-89, SP-2 422.2 < MDA < MDA < MDA < MDA 0.000 7.31E-02 1.07E-01 SR-280-556 OL-1-89, SP-3 385.6 < MDA < MDA < MDA < MDA 0.000 1.54E-01 1.19E-01 SR-280-557 OL-1-89, SP-4 389.4 3.38E-01 1.42E-01 < MDA < MDA 0.029 1.16E-01 SR-280-558 OL-1-89, SP-5 402.4 < MDA < MDA < MDA < MDA 0.000 1.20E-01 1.14E-01 SR-280-559 OL-1-89, SP-6 378.0 5.89E-01 1.62E-01 < MDA < MDA 0.051 1.21E-01 SR-280-560 OL-1-89, SP-7 373.5 7.42E-01 1.80E-01 < MDA < MDA 0.064 1.21E-01 SR-280-562 OL-1-89, SP-8 383.2 2.01E-01 9.06E-02 < MDA < MDA 0.017 1.18E-01 SR-280-563 OL-1-89, SP-9 364.0 < MDA < MDA < MDA < MDA 0.000 2.27E-01 1.26E-01 SR-280-564 OL-1-89, SP-10 384.4 5.13E-01 1.60E-01 < MDA < MDA 0.044 1.17E-01 SR-280-565 OL-1-89, SP-11 389.5 6.22E-01 1.88E-01 < MDA < MDA 0.054 1.18E-01 SR-280-566 OL-1-90, SP-1 430.4 < MDA < MDA < MDA < MDA 0.000 1.35E-01 1.07E-01

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 20 of 28 Table 1, Open Land Area FSS Sample Results Cs-137 Co-60 Cs-137 Co-60 Weight Unity Sample # Location MDA MDA (g) pCi/g 2 pCi/g 2 Fraction pCi/g pCi/g SR-280-568 OL-1-90, SP-2 376.2 4.05E-01 1.87E-01 < MDA < MDA 0.035 1.22E-01 SR-280-569 OL-1-90, SP-3 360.7 4.83E-01 1.92E-01 < MDA < MDA 0.042 1.25E-01 SR-280-570 OL-1-90, SP-4 352.1 3.88E-01 1.00E-01 < MDA < MDA 0.033 3.86E-02 SR-280-571 OL-1-90, SP-5 362.7 4.55E-01 1.74E-01 < MDA < MDA 0.039 1.27E-01 SR-280-572 OL-1-90, SP-6 370.9 3.94E-01 1.79E-01 < MDA < MDA 0.034 1.22E-01 SR-280-573 OL-1-90, SP-7 364.2 < MDA < MDA < MDA < MDA 0.000 1.63E-01 1.26E-01 SR-280-574 OL-1-90, SP-8 389.7 4.74E-01 1.56E-01 < MDA < MDA 0.041 1.35E-01 SR-280-575 OL-1-90, SP-9 412.2 3.06E-01 1.27E-01 < MDA < MDA 0.026 1.11E-01 SR-280-576 OL-1-90, SP-10 415.4 < MDA < MDA < MDA < MDA 0.000 1.09E-01 1.09E-01 SR-280-577 OL-1-90, SP-11 404.5 < MDA < MDA < MDA < MDA 0.000 1.47E-01 1.14E-01 SR-280-578 OL-1-90, SP-12 404.8 < MDA < MDA < MDA < MDA 0.000 1.07E-01 1.12E-01 SR-280-491 OL-1-91, SP-1 411.6 3.51E-01 1.53E-01 < MDA < MDA 0.030 1.12E-01 SR-280-493 OL-1-91, SP-2 369.9 4.79E-01 2.19E-01 < MDA < MDA 0.041 1.24E-01 SR-280-494 OL-1-91, SP-3 375.2 < MDA < MDA < MDA < MDA 0.000 1.83E-01 1.28E-01 SR-280-495 OL-1-91, SP-4 388.7 4.20E-01 1.87E-01 < MDA < MDA 0.036 1.18E-01 SR-280-496 OL-1-91, SP-5 397.0 < MDA < MDA < MDA < MDA 0.000 1.40E-01 1.14E-01 SR-280-497 OL-1-91, SP-6 401.7 < MDA < MDA < MDA < MDA 0.000 1.37E-01 1.14E-01 SR-280-498 OL-1-91, SP-7 407.4 3.02E-01 1.18E-01 < MDA < MDA 0.026 1.11E-01 SR-280-499 OL-1-91, SP-8 388.8 < MDA < MDA < MDA < MDA 0.000 7.81E-02 1.18E-01 SR-280-500 OL-1-91, SP-9 383.6 < MDA < MDA < MDA < MDA 0.000 1.18E-01 1.18E-01 SR-280-501 OL-1-91, SP-10 396.6 < MDA < MDA < MDA < MDA 0.000 1.63E-01 1.16E-01 SR-280-502 OL-1-91, SP-11 380.6 3.43E-01 1.30E-01 < MDA < MDA 0.030 1.19E-01 SR-280-503 OL-1-91, SP-12 412.8 < MDA < MDA < MDA < MDA 0.000 1.32E-01 1.11E-01 SR-280-504 OL-1-92, SP-1 355.7 3.09E-01 1.36E-01 < MDA < MDA 0.027 1.29E-01 SR-280-505 OL-1-92, SP-2 388.0 4.20E-01 1.60E-01 < MDA < MDA 0.036 1.16E-01 SR-280-506 OL-1-92, SP-3 411.9 4.24E-01 2.00E-01 < MDA < MDA 0.037 1.11E-01 SR-280-507 OL-1-92, SP-4 399.0 3.70E-01 1.36E-01 < MDA < MDA 0.032 1.13E-01 SR-280-508 OL-1-92, SP-5 365.1 < MDA < MDA < MDA < MDA 0.000 1.51E-01 1.26E-01 SR-280-509 OL-1-92, SP-6 341.6 1.00E+00 2.21E-01 < MDA < MDA 0.086 1.32E-01 SR-280-510 OL-1-92, SP-7 381.1 < MDA < MDA < MDA < MDA 0.000 1.17E-01 1.20E-01

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 21 of 28 Table 1, Open Land Area FSS Sample Results Cs-137 Co-60 Cs-137 Co-60 Weight Unity Sample # Location MDA MDA (g) pCi/g 2 pCi/g 2 Fraction pCi/g pCi/g SR-280-511 OL-1-92, SP-8 346.6 3.23E-01 1.61E-01 < MDA < MDA 0.028 1.30E-01 SR-280-512 OL-1-92, SP-9 375.8 7.62E-01 1.97E-01 < MDA < MDA 0.066 1.22E-01 SR-280-514 OL-1-92, SP-10 389.6 < MDA < MDA < MDA < MDA 0.000 1.46E-01 1.18E-01 SR-280-515 OL-1-92, SP-11 390.1 3.80E-01 1.68E-01 < MDA < MDA 0.033 1.16E-01 SR-280-516 OL-1-92, SP-12 337.8 3.87E-01 1.54E-01 < MDA < MDA 0.033 1.36E-01 SR-280-529 OL-1-93, SP-1 381.3 < MDA < MDA < MDA < MDA 0.000 1.70E-01 1.20E-01 SR-280-531 OL-1-93, SP-2 400.8 < MDA < MDA < MDA < MDA 0.000 1.31E-01 1.15E-01 SR-280-532 OL-1-93, SP-3 354.0 1.96E-01 9.30E-02 < MDA < MDA 0.017 1.28E-01 SR-280-533 OL-1-93, SP-4 385.0 < MDA < MDA < MDA < MDA 0.000 1.24E-01 1.19E-01 SR-280-534 OL-1-93, SP-5 374.9 < MDA < MDA < MDA < MDA 0.000 1.51E-01 1.21E-01 SR-280-535 OL-1-93, SP-6 342.7 3.99E-01 1.70E-01 < MDA < MDA 0.034 1.34E-01 SR-280-536 OL-1-93, SP-7 372.1 < MDA < MDA < MDA < MDA 0.000 1.52E-01 1.23E-01 SR-280-537 OL-1-93, SP-8 375.2 < MDA < MDA < MDA < MDA 0.000 1.21E-01 1.20E-01 SR-280-538 OL-1-93, SP-9 387.9 < MDA < MDA < MDA < MDA 0.000 1.09E-01 1.18E-01 SR-280-539 OL-1-93, SP-10 372.3 4.28E-01 1.80E-01 < MDA < MDA 0.037 1.21E-01 SR-280-540 OL-1-93, SP-11 416.2 2.39E-01 1.08E-01 < MDA < MDA 0.021 1.10E-01 SR-280-541 OL-1-94, SP-1 360.4 < MDA < MDA < MDA < MDA 0.000 1.26E-01 1.27E-01 SR-280-543 OL-1-94, SP-2 404.8 < MDA < MDA < MDA < MDA 0.000 1.15E-01 1.13E-01 SR-280-544 OL-1-94, SP-3 349.0 2.95E-01 1.19E-01 < MDA < MDA 0.025 1.32E-01 SR-280-545 OL-1-94, SP-4 362.3 2.75E-01 1.36E-01 < MDA < MDA 0.024 1.27E-01 SR-280-546 OL-1-94, SP-5 361.7 3.55E-01 1.74E-01 < MDA < MDA 0.031 1.25E-01 SR-280-547 OL-1-94, SP-6 383.3 3.96E-01 1.53E-01 < MDA < MDA 0.034 1.20E-01 SR-280-548 OL-1-94, SP-7 348.1 4.29E-01 2.01E-01 < MDA < MDA 0.037 1.30E-01 SR-280-549 OL-1-94, SP-8 375.3 < MDA < MDA < MDA < MDA 0.000 8.09E-02 1.22E-01 SR-280-550 OL-1-94, SP-9 408.7 2.64E-01 1.29E-01 < MDA < MDA 0.023 1.11E-01 SR-280-551 OL-1-94, SP-10 351.0 < MDA < MDA < MDA < MDA 0.000 1.39E-01 1.31E-01 SR-280-552 OL-1-94, SP-11 363.2 3.20E-01 1.27E-01 < MDA < MDA 0.028 1.24E-01 SR-280-553 OL-1-94, SP-12 374.8 4.37E-01 1.62E-01 < MDA < MDA 0.038 1.23E-01 SR-280-454 OL-1-95, SP-1 332.0 2.81E-01 1.27E-01 < MDA < MDA 0.024 1.39E-01 SR-280-456 OL-1-95, SP-2 357.9 2.60E-01 1.18E-01 < MDA < MDA 0.022 1.29E-01

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 22 of 28 Table 1, Open Land Area FSS Sample Results Cs-137 Co-60 Cs-137 Co-60 Weight Unity Sample # Location MDA MDA (g) pCi/g 2 pCi/g 2 Fraction pCi/g pCi/g SR-280-457 OL-1-95, SP-3 314.7 3.06E-01 1.24E-01 < MDA < MDA 0.026 1.44E-01 SR-280-458 OL-1-95, SP-4 410.5 4.09E-01 1.41E-01 < MDA < MDA 0.035 1.12E-01 SR-280-459 OL-1-95, SP-5 373.5 2.58E-01 1.04E-01 < MDA < MDA 0.022 1.22E-01 SR-280-460 OL-1-95, SP-6 416.2 < MDA < MDA < MDA < MDA 0.000 7.30E-02 1.11E-01 SR-280-461 OL-1-95, SP-7 402.7 < MDA < MDA < MDA < MDA 0.000 9.92E-02 1.13E-01 SR-280-462 OL-1-95, SP-8 349.6 1.91E-01 7.47E-02 < MDA < MDA 0.016 3.50E-02 SR-280-463 OL-1-95, SP-9 408.5 4.22E-01 1.58E-01 < MDA < MDA 0.036 1.13E-01 SR-280-464 OL-1-95, SP-10 392.7 < MDA < MDA < MDA < MDA 0.000 1.27E-01 1.16E-01 SR-280-465 OL-1-95, SP-11 372.0 3.16E-01 1.59E-01 < MDA < MDA 0.027 1.22E-01 SR-280-479 OL-1-96, SP-1 331.9 2.98E-01 1.22E-01 < MDA < MDA 0.026 1.39E-01 SR-280-480 OL-1-96, SP-2 325.6 < MDA < MDA < MDA < MDA 0.000 1.16E-01 1.42E-01 SR-280-481 OL-1-96, SP-3 361.8 < MDA < MDA < MDA < MDA 0.000 1.02E-01 1.28E-01 SR-280-482 OL-1-96, SP-4 351.5 2.79E-01 1.31E-01 < MDA < MDA 0.024 1.39E-01 SR-280-483 OL-1-96, SP-5 360.4 5.28E-01 1.75E-01 < MDA < MDA 0.046 1.26E-01 SR-280-484 OL-1-96, SP-6 373.8 < MDA < MDA < MDA < MDA 0.000 1.17E-01 6.17E-02 SR-280-486 OL-1-96, SP-7 378.6 6.32E-01 2.12E-01 < MDA < MDA 0.054 1.22E-01 SR-280-487 OL-1-96, SP-8 354.4 4.13E-01 1.65E-01 < MDA < MDA 0.036 1.28E-01 SR-280-488 OL-1-96, SP-9 379.8 2.94E-01 1.31E-01 < MDA < MDA 0.025 1.20E-01 SR-280-489 OL-1-96, SP-10 402.6 < MDA < MDA < MDA < MDA 0.000 1.97E-01 1.47E-01 SR-280-490 OL-1-96, SP-11 381.1 < MDA < MDA < MDA < MDA 0.000 1.22E-01 1.19E-01 SR-280-466 OL-1-97, SP-1 341.4 < MDA < MDA < MDA < MDA 0.000 1.08E-01 1.35E-01 SR-280-467 OL-1-97, SP-2 338.3 < MDA < MDA < MDA < MDA 0.000 1.88E-01 1.34E-01 SR-280-468 OL-1-97, SP-3 362.1 3.74E-01 1.45E-01 < MDA < MDA 0.032 1.27E-01 SR-280-469 OL-1-97, SP-4 349.1 2.21E-01 9.96E-02 < MDA < MDA 0.019 1.30E-01 SR-280-470 OL-1-97, SP-5 338.8 3.56E-01 1.55E-01 < MDA < MDA 0.031 1.36E-01 SR-280-471 OL-1-97, SP-6 417.0 2.42E-01 8.10E-02 < MDA < MDA 0.021 5.45E-02 SR-280-473 OL-1-97, SP-7 405.0 2.01E-01 8.10E-02 < MDA < MDA 0.017 5.70E-02 SR-280-474 OL-1-97, SP-8 408.6 2.90E-01 1.17E-01 < MDA < MDA 0.025 1.11E-01 SR-280-475 OL-1-97, SP-9 395.6 < MDA < MDA < MDA < MDA 0.000 1.35E-01 1.17E-01 SR-280-476 OL-1-97, SP-10 396.6 2.66E-01 1.21E-01 < MDA < MDA 0.023 1.16E-01

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 23 of 28 Table 1, Open Land Area FSS Sample Results Cs-137 Co-60 Cs-137 Co-60 Weight Unity Sample # Location MDA MDA (g) pCi/g 2 pCi/g 2 Fraction pCi/g pCi/g SR-280-477 OL-1-97, SP-11 366.1 < MDA < MDA < MDA < MDA 0.000 9.43E-02 1.24E-01 SR-280-478 OL-1-97, SP-12 395.8 2.97E-01 1.28E-01 < MDA < MDA 0.026 1.17E-01 SR-280-517 OL-1-98, SP-1 354.0 < MDA < MDA < MDA < MDA 0.000 8.58E-02 1.30E-01 SR-280-518 OL-1-98, SP-2 373.8 < MDA < MDA < MDA < MDA 0.000 9.04E-02 1.21E-01 SR-280-520 OL-1-98, SP-3 338.6 6.86E-01 2.10E-01 < MDA < MDA 0.059 1.33E-01 SR-280-521 OL-1-98, SP-4 357.0 < MDA < MDA < MDA < MDA 0.000 1.03E-01 1.29E-01 SR-280-522 OL-1-98, SP-5 351.8 2.30E-01 1.01E-01 < MDA < MDA 0.020 1.28E-01 SR-280-523 OL-1-98, SP-6 373.4 < MDA < MDA < MDA < MDA 0.000 8.13E-02 1.23E-01 SR-280-524 OL-1-98, SP-7 359.2 2.25E-01 9.91E-02 < MDA < MDA 0.019 1.26E-01 SR-280-525 OL-1-98, SP-8 312.1 < MDA < MDA < MDA < MDA 0.000 1.49E-01 1.47E-01 SR-280-526 OL-1-98, SP-9 378.4 < MDA < MDA < MDA < MDA 0.000 2.43E-01 1.19E-01 SR-280-527 OL-1-98, SP-10 352.1 4.07E-01 1.58E-01 < MDA < MDA 0.035 1.30E-01 SR-280-528 OL-1-98, SP-11 339.5 < MDA < MDA < MDA < MDA 0.000 1.53E-01 1.33E-01 SR-281-84 OL-2-1, SP-1 363.8 < MDA < MDA < MDA < MDA 0.000 1.70E-01 1.26E-01 SR-281-85 OL-2-1, SP-2 342.5 3.33E-01 1.07E-01 < MDA < MDA 0.029 6.60E-02 SR-281-87 OL-2-1, SP-3 331.8 4.04E-01 1.61E-01 < MDA < MDA 0.035 1.38E-01 SR-281-88 OL-2-1, SP-4 350.3 < MDA < MDA < MDA < MDA 0.000 1.38E-01 1.29E-01 SR-281-89 OL-2-1, SP-5 365.4 3.86E-01 1.79E-01 < MDA < MDA 0.033 1.26E-01 SR-281-90 OL-2-1, SP-6 359.3 < MDA < MDA < MDA < MDA 0.000 9.22E-02 1.26E-01 SR-281-91 OL-2-1, SP-7 367.6 < MDA < MDA < MDA < MDA 0.000 1.78E-01 1.25E-01 SR-281-92 OL-2-1, SP-8 337.2 < MDA < MDA < MDA < MDA 0.000 2.05E-01 1.36E-01 SR-281-93 OL-2-1, SP-9 344.1 < MDA < MDA < MDA < MDA 0.000 1.41E-01 1.31E-01 SR-281-94 OL-2-1, SP-10 347.4 1.90E-01 9.53E-02 < MDA < MDA 0.016 1.32E-01 SR-281-95 OL-2-1, SP-11 361.2 2.84E-01 1.34E-01 < MDA < MDA 0.024 6.25E-02 SR-281-58 OL-2-2, SP-1 388.8 2.10E-01 9.05E-02 < MDA < MDA 0.018 1.12E-01 SR-281-60 OL-2-2, SP-2 374.3 < MDA < MDA < MDA < MDA 0.000 7.95E-02 1.16E-01 SR-281-61 OL-2-2, SP-3 364.5 2.54E-01 1.14E-01 < MDA < MDA 0.022 1.20E-01 SR-281-62 OL-2-2, SP-4 345.2 < MDA < MDA < MDA < MDA 0.000 1.42E-01 1.26E-01 SR-281-63 OL-2-2, SP-5 342.6 2.25E-01 1.01E-01 < MDA < MDA 0.019 1.32E-01 SR-281-64 OL-2-2, SP-6 382.2 < MDA < MDA < MDA < MDA 0.000 1.12E-01 1.14E-01

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 24 of 28 Table 1, Open Land Area FSS Sample Results Cs-137 Co-60 Cs-137 Co-60 Weight Unity Sample # Location MDA MDA (g) pCi/g 2 pCi/g 2 Fraction pCi/g pCi/g SR-281-65 OL-2-2, SP-7 392.0 2.16E-01 9.30E-02 < MDA < MDA 0.019 1.15E-01 SR-281-66 OL-2-2, SP-8 352.2 2.97E-01 1.23E-01 < MDA < MDA 0.026 1.24E-01 SR-281-67 OL-2-2, SP-9 367.6 < MDA < MDA < MDA < MDA 0.000 8.18E-02 1.23E-01 SR-281-68 OL-2-2, SP-10 384.7 1.53E-01 7.03E-02 < MDA < MDA 0.013 5.97E-02 SR-281-69 OL-2-2, SP-11 347.6 < MDA < MDA < MDA < MDA 0.000 1.23E-01 1.25E-01 SR-281-20 OL-2-3, SP-1 362.3 < MDA < MDA < MDA < MDA 0.000 9.00E-02 1.21E-01 SR-281-21 OL-2-3, SP-2 369.2 < MDA < MDA < MDA < MDA 0.000 1.47E-01 1.23E-01 SR-281-23 OL-2-3, SP-3 325.3 3.32E-01 1.27E-01 < MDA < MDA 0.029 1.40E-01 SR-281-24 OL-2-3, SP-4 366.7 < MDA < MDA < MDA < MDA 0.000 8.71E-02 1.19E-01 SR-281-25 OL-2-3, SP-5 355.3 4.23E-01 1.58E-01 < MDA < MDA 0.036 1.30E-01 SR-281-26 OL-2-3, SP-6 367.1 < MDA < MDA < MDA < MDA 0.000 7.73E-02 1.24E-01 SR-281-27 OL-2-3, SP-7 311.4 1.95E+00 3.35E-01 < MDA < MDA 0.168 1.41E-01 SR-281-28 OL-2-3, SP-8 401.6 2.28E-01 9.14E-02 < MDA < MDA 0.020 5.75E-02 SR-281-29 OL-2-3, SP-9 342.5 < MDA < MDA < MDA < MDA 0.000 8.29E-02 1.33E-01 SR-281-30 OL-2-3, SP-10 339.4 < MDA < MDA < MDA < MDA 0.000 8.06E-02 1.29E-01 SR-281-31 OL-2-3, SP-11 387.0 < MDA < MDA < MDA < MDA 0.000 1.20E-01 1.17E-01 SR-281-32 OL-2-3, SP-12 373.0 < MDA < MDA < MDA < MDA 0.000 1.20E-01 1.17E-01 SR-281-33 OL-2-3, SP-13 346.4 < MDA < MDA < MDA < MDA 0.000 1.07E-01 1.31E-01 SR-281-1 OL-2-4, SP-1 325.5 2.98E-01 9.27E-02 < MDA < MDA 0.026 7.03E-02 SR-281-2 OL-2-4, SP-2 321.6 2.59E-01 1.02E-01 < MDA < MDA 0.022 7.12E-02 SR-281-4 OL-2-4, SP-3 353.7 2.09E-01 8.22E-02 < MDA < MDA 0.018 6.15E-02 SR-281-5 OL-2-4, SP-4 332.5 2.61E-01 1.00E-01 < MDA < MDA 0.023 6.89E-02 SR-281-6 OL-2-4, SP-5 332.8 2.57E-01 9.06E-02 < MDA < MDA 0.022 6.88E-02 SR-281-7 OL-2-4, SP-6 327.8 3.35E-01 9.71E-02 < MDA < MDA 0.029 6.63E-02 SR-281-8 OL-2-4, SP-7 343.3 2.44E-01 8.45E-02 < MDA < MDA 0.021 6.67E-02 SR-281-9 OL-2-4, SP-8 331.4 3.47E-01 1.06E-01 < MDA < MDA 0.030 6.56E-02 SR-281-10 OL-2-4, SP-9 325.9 < MDA < MDA < MDA < MDA 0.000 7.75E-02 7.03E-02 SR-281-11 OL-2-4, SP-10 319.6 2.32E-01 9.40E-02 < MDA < MDA 0.020 6.80E-02 SR-281-12 OL-2-4, SP-11 385.8 2.74E-01 1.06E-01 < MDA < MDA 0.024 5.94E-02 SR-281-70 OL-2-5, SP-1 375.6 3.86E-01 1.34E-01 < MDA < MDA 0.033 1.16E-01

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 25 of 28 Table 1, Open Land Area FSS Sample Results Cs-137 Co-60 Cs-137 Co-60 Weight Unity Sample # Location MDA MDA (g) pCi/g 2 pCi/g 2 Fraction pCi/g pCi/g SR-281-71 OL-2-5, SP-2 417.8 < MDA < MDA < MDA < MDA 0.000 1.06E-01 1.10E-01 SR-281-73 OL-2-5, SP-3 380.3 5.09E-01 1.58E-01 < MDA < MDA 0.044 1.15E-01 SR-281-74 OL-2-5, SP-4 431.4 < MDA < MDA < MDA < MDA 0.000 7.04E-02 1.06E-01 SR-281-75 OL-2-5, SP-5 414.7 < MDA < MDA < MDA < MDA 0.000 9.49E-02 1.09E-01 SR-281-76 OL-2-5, SP-6 386.0 < MDA < MDA < MDA < MDA 0.000 7.08E-02 1.13E-01 SR-281-77 OL-2-5, SP-7 375.3 3.25E-01 1.46E-01 < MDA < MDA 0.028 1.22E-01 SR-281-78 OL-2-5, SP-8 362.7 < MDA < MDA < MDA < MDA 0.000 7.82E-02 1.25E-01 SR-281-79 OL-2-5, SP-9 365.7 2.43E-01 1.01E-01 < MDA < MDA 0.021 1.19E-01 SR-281-80 OL-2-5, SP-10 344.9 < MDA < MDA < MDA < MDA 0.000 1.35E-01 1.33E-01 SR-281-81 OL-2-5, SP-11 334.6 < MDA < MDA < MDA < MDA 0.000 2.30E-01 1.35E-01 SR-281-82 OL-2-5, SP-12 384.7 3.37E-01 1.16E-01 < MDA < MDA 0.029 1.13E-01 SR-281-46 OL-2-6, SP-1 313.1 3.03E-01 1.27E-01 < MDA < MDA 0.026 1.47E-01 SR-281-48 OL-2-6, SP-2 320.9 5.60E-01 1.97E-01 < MDA < MDA 0.048 1.43E-01 SR-281-49 OL-2-6, SP-3 363.0 < MDA < MDA < MDA < MDA 0.000 1.39E-01 1.26E-01 SR-281-50 OL-2-6, SP-4 349.8 5.03E-01 1.69E-01 < MDA < MDA 0.043 1.31E-01 SR-281-51 OL-2-6, SP-5 347.2 < MDA < MDA < MDA < MDA 0.000 1.61E-01 1.51E-01 SR-281-52 OL-2-6, SP-6 332.6 2.70E-01 1.25E-01 < MDA < MDA 0.023 1.31E-01 SR-281-53 OL-2-6, SP-7 314.5 < MDA < MDA < MDA < MDA 0.000 1.20E-01 1.46E-01 SR-281-54 OL-2-6, SP-8 345.4 < MDA < MDA < MDA < MDA 0.000 9.24E-02 1.26E-01 SR-281-55 OL-2-6, SP-9 356.2 < MDA < MDA < MDA < MDA 0.000 1.13E-01 1.29E-01 SR-281-56 OL-2-6, SP-10 383.0 2.67E-01 1.17E-01 < MDA < MDA 0.023 1.14E-01 SR-281-57 OL-2-6, SP-11 352.7 < MDA < MDA < MDA < MDA 0.000 8.61E-02 1.30E-01

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 26 of 28 Table 2, QC Soil Sample Comparison for Open Land Areas FSS Original 2 Original Replicate Resolution Sample # Location Sigma Ratio (3) Pass (4) (5)

Result (1) Result (1) (2)

Uncertainty SR-280-14 OL-1-46, SP-1 QC < MDA < MDA < MDA N/A N/A Yes SR-280-3 OL-1-47, SP-2 QC < MDA < MDA < MDA N/A N/A Yes SR-280-29 OL-1-48, SP-4 QC 2.56E-01 2.97E-01 9.47E-02 5 1.2 Yes SR-280-48 OL-1-49, SP-10 QC 3.36E-01 2.50E-01 1.62E-01 4 0.7 Yes SR-280-52 OL-1-50, SP-1 QC <MDA <MDA <MDA N/A N/A Yes SR-280-69 OL-1-51, SP-5 QC <MDA <MDA <MDA N/A N/A Yes SR-280-80 OL-1-52, SP-3 QC <MDA <MDA <MDA N/A N/A Yes SR-280-162 OL-1-53, SP-10 QC <MDA <MDA <MDA N/A N/A Yes SR-280-175 OL-1-54, SP-7 QC 8.70E-01 9.31E-01 2.05E-01 8 1.1 Yes SR-280-187 OL-1-55, SP-6 QC 2.44E-01 1.84E-01 1.17E-01 4 0.8 Yes SR-280-145 OL-1-56, SP-5 QC 3.69E-01 3.23E-01 1.38E-01 5 0.9 Yes SR-280-119 OL-1-57, SP-5 QC 2.23E-01 3.19E-01 8.21E-02 5 1.4 Yes SR-280-139 OL-1-58, SP-12 QC 3.32E-01 2.11E-01 1.48E-01 4 0.6 Yes SR-280-580 OL-1-59, SP-1 QC 3.12E-01 1.61E-01 1.40E-01 4 0.5 Yes SR-280-619 OL-1-60, SP-4 QC 2.73E-01 1.70E-01 1.37E-01 4 0.6 Yes SR-280-598 OL-1-88, SP-7 QC < MDA < MDA < MDA N/A N/A Yes SR-280-635 OL1-61, SP-8 QC < MDA < MDA < MDA N/A N/A Yes SR-280-242 OL-1-62, SP-8 QC 2.73E-01 2.78E-01 7.82E-02 7 1.0 Yes SR-280-269 OL-1-63, SP-11 QC < MDA < MDA < MDA N/A N/A Yes SR-280-251 OL-1-64, SP-5 QC 1.81E-01 2.25E-01 5.44E-02 7 1.2 Yes SR-280-608 OL-1-65, SP-5 QC < MDA < MDA < MDA N/A N/A Yes SR-280-646 OL-1-66, SP-7 QC < MDA < MDA < MDA N/A N/A Yes SR-280-658 OL-1-67, SP-7 QC < MDA < MDA < MDA N/A N/A Yes SR-280-271 OL-1-68, SP-1 QC 1.53E-01 2.01E-01 6.85E-02 4 1.3 Yes SR-280-293 OL-1-69, SP-11 QC < MDA < MDA < MDA N/A N/A Yes SR-280-361 OL-1-70, SP-3 QC < MDA < MDA < MDA N/A N/A Yes SR-280-106 OL-1-71, SP-4 QC 2.62E-01 9.00E-02 1.04E-01 5 0.3 No

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 27 of 28 Table 2, QC Soil Sample Comparison for Open Land Areas FSS Original 2 Original Replicate Resolution Sample # Location Sigma Ratio (3) Pass (4) (5)

Result (1) Result (1) (2)

Uncertainty OL-1-71, SP-4 QC SR-280-106 1.52E-01 1.78E-01 5.26E-02 6 1.2 Yes recount SR-280-94 OL-1-72, SP-4 QC 5.18E-01 3.39E-01 1.62E-01 6 0.7 Yes SR-280-232 OL-1-73, SP-11 QC 1.78E+00 2.73E-01 2.96E-01 12 0.2 No OL-1-73, SP-11 QC SR-280-232 1.35E+00 2.19E-01 1.48E-01 18 0.2 No recount SR-280-210 OL-1-74, SP-2 QC 3.69E-01 3.66E-01 1.38E-01 5 1.0 Yes SR-280-207 OL-1-75, SP-13 QC 3.70E-01 2.52E-01 1.30E-01 6 0.7 Yes SR-280-296 OL-1-76, SP-2 QC < MDA < MDA < MDA N/A N/A Yes SR-280-318 OL-1-77, SP-12 QC 8.00E-02 1.29E-01 5.63E-02 3 1.6 Yes SR-280-324 OL-1-78, SP-5 QC 2.23E-01 3.20E-01 7.74E-02 6 1.4 Yes SR-280-338 OL-1-79, SP-6 QC 2.68E-01 1.98E-01 8.62E-02 6 0.7 Yes SR-280-357 OL-1-80, SP-12 QC 2.98E-01 3.90E-01 1.14E-01 5 1.3 Yes SR-280-378 OL-1-81, SP-8 QC 3.16E-01 1.20E-01 1.25E-01 5 0.4 No SR-280-388 OL-1-82, SP-6 QC 2.77E-01 2.62E-01 1.27E-01 4 0.9 Yes SR-280-396 OL-1-83, SP-2 QC < MDA < MDA < MDA N/A N/A Yes SR-280-431 OL-1-84, SP-1 QC < MDA < MDA < MDA N/A N/A Yes SR-280-426 OL-85, SP-8 QC < MDA < MDA < MDA N/A N/A Yes SR-280-444 OL-1-86, SP-2 QC 1.00E-01 1.65E-01 1.42E-02 14 1.7 No SR-280-407 OL-1-87, SP-1 QC < MDA < MDA < MDA N/A N/A Yes SR-280-561 OL-1-89, SP-7 QC 7.42E-01 7.39E-01 1.80E-01 8 1.0 Yes SR-280-567 OL-1-90, SP-1 QC 2.83E-01 1.35E-01 1.41E-01 4 0.5 Yes SR-280-492 OL-1-91, SP-1 QC 3.51E-01 5.10E-01 1.53E-01 5 1.5 Yes SR-280-513 OL-1-92, SP-9 QC 7.62E-01 7.47E-01 1.97E-01 8 1.0 Yes SR-280-530 OL-1-93, SP-1 QC < MDA < MDA < MDA N/A N/A Yes SR-280-542 OL-1-94, SP-1 QC 2.34E-01 1.26E-01 9.31E-02 5 0.5 Yes SR-280-455 OL-1-95, SP-1 QC 2.81E-01 2.17E-01 1.27E-01 4 0.8 Yes SR-280-485 OL-1-96, SP-6 QC 2.40E-01 1.17E-01 9.19E-02 5 0.5 Yes SR-280-472 OL-1-97, SP-6 QC 2.42E-01 1.51E-01 8.10E-02 6 0.6 Yes

Plum Brook Reactor Facility FSSR, Attachment 16 Appendix C, Rev. 0, Page 28 of 28 Table 2, QC Soil Sample Comparison for Open Land Areas FSS Original 2 Original Replicate Resolution Sample # Location Sigma Ratio (3) Pass (4) (5)

Result (1) Result (1) (2)

Uncertainty SR-280-519 OL-1-98, SP-2 QC < MDA < MDA < MDA N/A N/A Yes SR-281-36 OL-2-1, SP-2 QC < MDA < MDA < MDA N/A N/A Yes SR-281-86 OL-2-1, SP-2 QC 3.33E-01 1.62E-01 1.07E-01 6 0.5 Yes SR-281-59 OL-2-2, SP-1 QC 2.10E-01 1.60E-01 9.05E-02 5 0.8 Yes SR-281-22 OL-2-3, SP-2 QC < MDA < MDA < MDA N/A N/A Yes SR-281-3 OL-2-4, SP-2 QC 2.59E-01 1.82E-01 1.02E-01 5 0.7 Yes SR-281-72 OL-2-5, SP-2 QC < MDA < MDA < MDA N/A N/A Yes SR-281-47 OL-2-6, SP-1 QC 3.03E-01 3.22E-01 1.27E-01 5 1.1 Yes Table 2 Notes:

1. Sample comparison is made for Cs-137 Results. All Co-60 original and replicate samples are < MDA.

2. The sample resolution is calculated as the ratio of the original sample uncertainty and the sample measured activity concentration.

3. The ratio of QC to original sample results.

4. See the table below for ratio vs. resolution acceptance criteria

5. If both original and QC sample are < MDA, they are considered to be in agreement.

QC Sample Comparison Acceptance Criteria Resolution Ratio

<4 0.4 - 2.5 4-7 0.5 - 2.0 8 - 15 0.6 - 1.66 16 - 50 0.75 - 1.33 51 - 200 0.8 - 1.25

> 200 0.85 - 1.18 Acceptance Criteria Notes:

1. Acceptance Criteria are per FSS Plan Section, Section 12.7.2.

2. When comparing a positive result to a <MDA result, assume that the sample result is positive at the MDA and use the MDA value to determine the ratio.