ML102390408
| ML102390408 | |
| Person / Time | |
|---|---|
| Site: | Plum Brook File:National Aeronautics and Space Administration icon.png |
| Issue date: | 08/26/2010 |
| From: | Peecook K US National Aeronautics & Space Admin (NASA), John H. Glenn Research Ctr at Lewis Field |
| To: | Document Control Desk, NRC/FSME |
| References | |
| Download: ML102390408 (133) | |
Text
Space Administration John H. Glenn Research Center
,"Lewis Field Plum Brook Station 7'
Sandusky, OH, 44870
/
August 26, 4i11foi Reply to Attn of: QD U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
Subject:
Final Status Survey Report, Attachment 4, Pentolite Ditch, for the Plum Brook Reactor Facility, Licenses Nos. TR-3, Docket No. 50-30 and R-93, Docket No, 50-185 Enclosed for your review is Attachment 4 to the Final Status Survey Report supporting eventual termination of the licenses for the Plum Brook Reactor Facility.
The complete Final Status Survey Report will consist of a series of Attachments, each addressing an individual survey area or group of survey areas or environmental areas as described in our NRC approved Final Status Survey Plan. The final submission will be the main body of the Final Status Survey Report which will consolidate and summarize the details presented in the Attachments.
This Attachment addresses the Final Status Survey of the Pentolite Ditch Area (Environmental Area A2300). It supports our conclusion that radiological remediation of the area has been completed and it meets the criteria for unrestricted release specified in 10 CFR 20.1402.
Should you have any questions or need additional information, please contact me a NASA Plum Brook Station, 6100 Columbus Avenue, Sandusky, Ohio 44870, or by telephone at (419) 621-3277.
Sincerely, Keith M. Peecook NASA Decommissioning Program Manager
2 Enclosure Plum Brook Reactor Facility Final Status Survey Report, Attachment 4, Pentolite Ditch (Environmental Area A2300), revision 0, dated August 25, 2010 cc:
USNRC/C. J. Glenn (FSME)
USNRC/J. Webb (FSME)
USNRC/J. Tapp RIIL/DNMS/DB ODH/M. J. Rubadue
Plum Brook Reactor Facility Final Status Survey Report Revision 0 Pentolite Ditch (Environmental Area A2300)
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Document
Title:
Final Status Survey Report, Pentolite Ditch (Environmental Area A2300)
Revision Number: 0 ROUTING Prepared By
/R.
MassengiH Prepared By jN/A-
/0 Independent Technical Reviewer R. Case
"/2-"/1o Other Reviewer, QA Manager J. Thomas Other Reviewer k'-1iA FSS/Characterization Manager W. Stoner 7*
NASA Project Radiation Safety Officer W. Stoner ii
NASA PBRF DECOMMISSIONING PROJECT CHANGE/CANCELLATIONRECORD DOCUMENT TITLE: Final Status DOCUMENT NO: NA REVISION NO: 0 Survey
- Report, Attachment 4,
Pentolite Ditch (Environmental Area A2300)
Revision 0: Initial issue of Report Form AD-01/3 Rev I iii
Plum Brook Reactor Facility FSSR, Rev. 0 LIST OF EFFECTIVE PAGES REVISION NO: 0 DOCUMENT NO:
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Revision Level Cover Page 0
Routing & Approval 0
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Record LOEP TOC List of Tables & List of Figures 0
List of Acronyms &
0 Symbols, 2 pages Text, pages 1 through 0
33 Appendix A 25 pages Appendix B 45 pages Appendix C 20 pages 0
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Form AD-01/5 Rev 2
Plum Brook Reactor Facility FSSR, Rev. 0 TABLE OF CONTENTS 1.0 Introduction............................................................................................................
1 2.0 Pentolite Ditch Description....................................................................................
2 2.1 Pentolite Ditch Construction...................................................................................
3 2.2 Final Configuration and Scope of Remediation in Pentolite Ditch for Final Status Survey 3 3.0 Pentolite Ditch History and Operations with Radioactive Materials..................
6 3.1 Disposition of M aterials in the Post-Shutdown Period..........................................
7 3.2 Decommissioning...................................................................................................
8 4.0 Survey Design and Implementation for the Pentolite Ditch................................
9 4.1 FSS Plan Requirements...............................................................................................
9 4.1.1 Site-Specific DCGL Values for Soil................................................................
10 4.1.2 DCGL for Other M edia.....................................................................................
10 4.1.3 Radionuclide M ixture for FSS.........................................................................
10 4.1.4 Surrogate DCGL and the Unity Rule................................................................
11 4.1.4.1 Surrogate Equation.............................................................................................
12 4.1.4.2 Unity Rule Equation.........................................................................................
12 4.1.4.3 Area Factors....................................................................................................
12 4.1.4.4 Survey Unit Size..............................................................................................
13 4.1.4.5 Scan Coverage for Class 1 and Class 2 Areas.................................................
13 4.2 Area Classification and Survey Unit Breakdown...........................
14 4.3 Number of M easurements and Samples...............................................................
17 4.4 Instrumentation and Measurement Sensitivity........................
20 5.0 Pentolite Ditch Survey Results..............................................................................
21 5.1 Surveys and Investigations..................................................................................
22 5.1.1 Scan Surveys......................................................................................................
22 5.1.2 Static M easurements and Judgmental Soil Samples........................................
24 5.1.3 Systematic Soil Sampling................................................................................
25 5.1.3.1 Soil Sampling for Class 1 Areas......................................................................
25 5.1.3.2 Soil Sampling for Class 2 Areas......................................................................
25 5.1.3.3 Quality Control Sample Analysis....................................................................
26 5.2 ALARA Evaluation..............................................................................................
30 5.3 Comparison with EPA Trigger Levels..................................................................
30 5.4 Conclusions..........................................................................................................
31 6.0 References....................................................................................................................
32 7.0 Appendices..................................................................................................................
33 Appendix A - Exhibits......................................................................................................
33 Appendix B - Survey Unit Maps and Tables Showing Measurement Locations............ 33 Appendix C -Soil Sample Results...................................................................................
33 v
Plum Brook Reactor Facility FSSR, Rev. 0 LIST OF TABLES Table 1, DCGL Values for Surface Soil..................................................................................
10 Table 2, Surface Soil A rea Factors............................................................................................
13 Table 3, Recommended Survey Unit Area Size Requirements for FSS...................................
13 Table 4, Minimum Scan Survey Coverage..............................................................................
14 Table 5, Pentolite Ditch Survey Units for FSS.........................................................................
14 Table 6, Pentolite Ditch Survey Unit Breakdown by MARSSIM Classification.....................
17 Table 7, Pentolite Ditch Survey Design Summary..................................................................
18 Table 8, Sensitivity Analysis for OL-3-30 Design..................................................................
19 Table 9, Detection Sensitivities of 44-10 for Cs-137...............................................................
20 Table 10, Scan Survey R esults.................................................................................................
23 Table 11, Pentolite Ditch Systematic Soil Sample Results By Survey Unit...........................
28 LIST OF FIGURES Figure 1, Pentolite Ditch Final Status Survey Unit Breakdown.................................................
5 vi
A AEMC AEC ALARA bi BR BPL CFR CRB cm cpm A
dC DCGL DCGLEMc DCGLw DODT dpm Ei E,
Et EMC EPA ERB FPR FSS FSSP FSSR 7
IM in.
LBGR m2 MARSSIM Plum Brook Reactor Facility FSSR, Rev. 0 LIST OF ACRONYMS & SYMBOLS alpha; denotes alpha radiation, also type I error probability in hypothesis testing Area, also detector open area Area corresponding to the area factor calculated using the scan MDC Atomic Energy Commission As Low As Reasonable Achievable beta; denotes beta radiation, also type II error probability in hypothesis testing backgro~und counts in observation interval Background count rate Byproduct License Code of Federal Regulations Cold Retention Basin centimeters counts per Minute delta, DCGLw - LGBR Scan surveyor sensitivity index Derived Concentration Guideline Level DCGL for small areas of elevated activity, used with the Elevated Measurement Comparison test (EMC)
DCGL for average concentrations over a survey unit, used with statistical tests.
(the "W" suffix denotes "Wilcoxon)"
Direct Offsite Disposal Threshold disintegrations per minute Detector, or instrument efficiency Surface efficiency Total efficiency Elevated Measurement Comparison US Environmental Protection Agency Emergency Retention Basin Final Post Remediation Final Status Survey Final Status Survey Plan Final Status Survey Report gamma, denotes gamma radiation gram Hard To Detect Hot Retention Area observation counting interval during scan surveys Investigative Measurement inch Lower Bound of the Gray Region square meters Multi-Agency Radiation Survey and Site Investigation Manual vii
Plum Brook Reactor Facility FSSR, Rev. 0 LIST OF ACRONYMS & SYMBOLS, Continued MDC Minimum Detectable Concentration MDCsca Minimum Detectable Concentration for scanning surveys MDCsmttic Minimum Detectable Concentration for static surface activity measurements MDCR Minimum Detectable Count Rate mrem millirem MW Megawatt MWH Mongomery-Watson-Harza NASA National Aeronautics and Space Administration N
Number of FSS measurements or samples established in a survey design NA Not Applicable Nal Sodium Iodide ncpm net counts per minute NRC US Nuclear Regulatory Commission PBOW Plum Brook Ordinance Works PBRF Plum Brook Reactor Facility PBS Plum Brook Station PNL Pacific Northwest Laboratory (D
Standard normal distribution function p
surveyor efficiency for scan surveys pCi/g picocuries per gram percent QC Quality Control RAL Remediation Action Level (50% of the DCGL)
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 RESRAD-BUILD A companion code to RESRAD for evaluating indoor building contamination and developing site-specific DCGLs s
seconds a
generic symbol for standard deviation of a population S+
Sign Test statistic SNL Sandia National Laboratory SR Survey Request ts sample count time tb background count time TBD Technical Basis Document p
Mean activity concentration UL Upper limit of the confidence interval about the mean VSP Visual Sample Plan WEMS Waste Effluent Monitoring Station Z1_1 Proportion of standard normal distribution values less than 1 -a ZI-P Proportion of standard normal distribution values less than 1-3 00 Mathematical symbol for infinity viii
Plum Brook Reactor Facility FSSR, Rev. 0 1.0 Introduction This report presents the results of the final status radiological survey of the Plum Brook Reactor Facility (PBRF) Pentolite Ditch (Environmental Area A2300). This report is identified as Attachment 4 of the PBRF Final Status Survey Report (FSSR) 1. This attachment describes the Pentolite Ditch, its operational history and final condition for the final status survey (FSS). This attachment describes the methods used in the FSS and presents the results of the survey and sample measurements.
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 criteria in US NRC I0CFR20 Subpart E. The principal criterion is that the dose to future site occupants will be less than 25 mrem/y. 10CFR20 Subpart E also requires that residual contamination be reduced to levels as low as reasonably achievable (ALARA). A Derived Concentration Guideline Level (DCGL) for surface and sub-surface soils has been established for PBRF soils, per Table 3-1 of the FSSP
[NASA 2007] and Technical Basis Document (TBD) PBRF-TBD-09-001 [PBRF 2009]. In accordance with the FSSP and TBD-09-001 [PBRF 2009], the primary DCGLs for surface soils are as follows:
- Cs-137 is 14.7 pCi/g.
Furthermore, surrogate DCGLs for soil of the Pentolite Ditch were established in Table 5-2 of PBRF-TBD-09-001 [PBRF 2009]. The surrogate DCGL (based on Cs-137) is 13.34 pCi/g.
The survey measurement results and supporting information presented herein demonstrate that residual contamination levels in each survey unit of the Pentolite Ditch are well below the DCGL.
Additionally, it is shown that residual contamination has been reduced to levels that are consistent with the ALARA requirement. Therefore, the Pentolite Ditch meets the criteria for unrestricted release.
Section 2.0 of the report provides a description of the Pentolite Ditch. This includes the location of the ditch in relation to the Waste Effluent Monitoring Station (WEMS) and other PBRF buildings and facilities. This section also discusses the final configuration of the Pentolite Ditch for the FSS and scope of the FSS for this area.
A brief history of 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.
Section 4.0 presents the FSS design for the Pentolite Ditch. This section includes FSS Plan requirements applicable to the Pentolite Ditch, breakdown into survey units and assignment of 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, Rev. 0 MARSSIM [USNRC 2000] classification to each, the survey design approach, and instrumentation used for the FSS and measurement sensitivities.
Survey results are presented in Section 5.0. This section includes a summary of the FSS measurements performed in the Pentolite Ditch survey units, comparison to the DCGL, tests performed and an evaluation of residual contamination levels relative to the ALARA criterion.
Supporting information is contained in Appendices. Appendix A contains photos and schematics to supplement the text. Survey design maps and tables of coordinates for the measurement locations in each survey unit are provided in Appendix B. Soil sample results are provided in Appendix C.
2.0 Pentolite Ditch Description The Pentolite Ditch [PBRF 2010] is a drainage canal that is approximately one half mile long extending eastward from PBRF WEMS outfall to its confluence with Plum Brook. The Pentolite Ditch, identified as Environmental Area A2300, is shown on the map identified as Figure 1.
Photographic documentation of Pentolite Ditch, prior to remediation, is provided in Exhibits 2, 3 and 4 in Appendix A.
Liquid effluents (such as storm drainage, waste waters including man-made radioactive contamination, and processed lake dilution water) from the nuclear test facility were released into the Pentolite Ditch via the WEMS.
The WEMS [PBRF 2009c] had built-in capabilities for automatically closing the WEMS sluice gates when radioactivity levels exceeded pre-set limits. These limits were set to preclude the release of radioactivity level releases that would exceed the Federal licensing limits. During operation, the WEMS sluice gates closed numerous times for a variety of reasons ranging from detected high radioactivity levels, equipment malfunctions and weather related conditions like freezing and flooding conditions. When the WEMS sluice gates closed, planned radioactive discharges were terminated and the effluent waters were usually permitted to backup in the effluent trenches or were pumped into a 5 million gallon Emergency Retention Basin for temporary storage. See Exhibits 14 and 15 for views of the WEMS outfall into Pentolite Ditch.
2
Plum Brook Reactor Facility FSSR, Rev. 0 2.1 Pentolite Ditch Construction The Pentolite Ditch was constructed in the 1958-61 timeframe as part of PBRF site water management infrastructure. A 1958 vintage site map shows a small unnamed surface stream running west to east just south of Pentolite Road. During PBRF construction, the Pentolite ditch was created by straightening and extending the stream channel to run parallel to Pentolite Road from Garage Road on the west to the Plum Brook on the east. In about 1958, the ditch was excavated from a 4 foot bottom to a "V" profile, roughly 12-15 feet wide and 6 feet deep during the reactor construction period. The Ditch was designed to receive surface runoff from Plum Brook areas south of Pentolite Road and to drain the Pentolite Road right of way as well as receive liquid effluents from the PBRF. The ditch was designed to accommodate maximum expected WEMS outflow and surface runoff from the 100-year rainfall event [PBRF 2010].
The ditch lies within unconsolidated deposits comprised of glacial till, glacial lake deposits and soils derived from silt and shale, clay and mudstone beds which underlie the site. The soil in the vicinity of the Pentolite Ditch has been extensively disturbed by construction activities.
Depth to bedrock at the northern portion of the Plum Brook site is typically about 25 feet
[USACE 2003].
On several occasions since initial construction, the ditch bed has been dredged to remove accumulated sediment and debris and the banks graded to remove vegetation growth. Soil and sediment removed by these activities were spread on nearby land areas south of the ditch
[PBRF 2010].
Currently, Pentolite Ditch is approximately 2750 feet long and runs west to east just south of Pentolite Road from south of the WEMS at the west end and intersects with Plum Brook at the east end.
2.2 Final Configuration and Scope of Remediation in Pentolite Ditch for Final Status Survey Pentolite Ditch area was cleaned and grubbed of trees, brush and debris prior to surveys and remediation efforts commencing.
Pentolite Ditch was dammed (See Exhibit 11 of Appendix A) and the piping was installed to bypass Pentolite Ditch (See Exhibits 8 and 9 of Appendix A). Residual water from Pentolite Ditch was pumped to batch tanks, processed, sampled, analyzed and released.
The entire Pentolite Ditch proper, a portion of Plum Brook south of Pentolite Ditch and a small portion of Un-named Stream south of Pentolite Ditch was remediated by initially excavating the stream bed and banks in one 6" lift and then performing subsequent remediation of areas identified by radiological survey results. When surveys indicated that the action level was met, the area was remediated. When surveys indicated that the survey area was below the Remediation Action Level (RAL), no remediation was performed.
3
Plum Brook Reactor Facility FSSR, Rev. 0 Remediation continued until surveys indicated that the area was below the RAL. Surrounding Class 1 survey units and the Class 1 survey units south of Pentolite Ditch were remediated in the same manner as the Pentolite Ditch was remediated (See Exhibits 12 through 20 of Appendix A). Refer to Exhibits 22 and 23 of Appendix A for photographic documentation of the final configuration of Pentolite Ditch.
East of the Pentolite Ditch cross-over, Class 1 survey units not located within the stream proper were remediated based on surveys performed by Radiation Protection personnel, as stated above.
In accordance with Work Execution Packages (WEP), PBRF-WEP-09-003 and PBRF-WEP-09-004 the soil from Pentolite Ditch and Environs (A2300) was removed and staged in two piles. The first pile was greater than the DCGL and the second pile was >RAL but <DCGL.
See Section 3.2 for further details on the soil staging segregation and disposal process.
SR-170 was written to direct the performance of subsurface soil samples after remediation of Pentolite Ditch and the areas south of the ditch (Areas of Concern) was complete. The SR required collection of subsurface soil samples to a depth of 2 meters, below the first 0.15 meters (or 6 inches) of surface soil.
A total of 82 samples were collected at 41 sub-surface locations within Pentolite Ditch. Four of the 82 samples had Cs-137 activity above the MDA. No sample results were above the MDA for Co-60. The highest identified sample activity was from Sample Point #26, which was located in Pentolite Ditch approximately 100 feet west of the Plum Brook confluence, at a depth of 1-2 meters. The Cs-137 activity was 2.37 pCi/g for Cs-137 and <MDA for Co-60.
This activity is equivalent to 17% of unity.
4
Plum Brook Reactor Facility FSSR, Rev. 0 Figure 1, Pentolite Ditch Final Status Survey Unit Breakdown FEET 0 50 Ioo 200 B8 1192 wEMS J PBRF OL-3-34 BA 1
01-3-22 OL--39 DICHNTOUTEIF OL-3-10--
OL34 01-3-22-.
AY 0
0 0
00 OL 3.13 0
0 03 AX 30-37 0-3-14 17 0L-3-19 AW
- L0-3-20 1.
OL 3-42 OL3 29 1
AV AU A T 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 115 116 117 118 119 120 121 122 123 124 125 126 127 128 129 13x GRID IS 100' x 100" LEGEND
= CLASS I
= CLASS 2 OL-3 OPEN LAND SURVEY UNIT ID NUMBER WEMS
= WATER EFFLUENT MONITORING SYSTEM 5
Plum Brook Reactor Facility FSSR, Rev. 0 3.0 Pentolite Ditch History and Operations with Radioactive Materials The PBRF 60MW test reactor started up on June 14, 1961 and operated until January 5, 1973.
During this operations period, liquid effluent from all sources at the PBRF site, except sanitary sewage and settling basin waste, was released through the WEMS to Pentolite Ditch. Prior to startup of the reactor facility, the liquid effluent from the site, including groundwater and storm runoff, also primarily flowed through Pentolite Ditch and smaller ditches north of the site to the offsite environment.
The Atomic Energy Commission originally licensed the 60 MW PBRF for startup operations with a provisional license in March 1961 and a final license (TR-3) in December 1963. The Mock-up Reactor was licensed (R-93) in July 1964. These licenses, subsequently, fell under the current US Nuclear Regulatory Commission in 1975. The licenses prescribed the Federal limits for PBRF release of radionuclides to the environment.
As mentioned in Section 2.0 of this report, the WEMS continuously collected and discharged the effluent waters from PBRF sources to Pentolite Ditch. Typical flow rates from reactor operations were in the 400 to 1000 gallons per minute range; these rates varied depending on plant evolutions including controlled radioactively contaminated and clean water releases and dilution water flows and weather factors such as dry spells and heavy rains. Effluents consisted of the following:
- Excess lake water softened by the precipitator (400-800 gpm),
- Cooling tower blow-down,
- Ground water,
- Building clean sump outputs,
- Radioactively contaminated discharges, and
- Area runoff directly into the storm drains system.
An exception to the aforementioned effluent discharge system was the sanitary sewer discharge that was contained in separate piping to the PBS sanitary waste treatment plant.
The radioactively contaminated water sources were primarily from the HRA, the CRBs and ERB discharges (the normal collection systems for radioactively contaminated water), plus accidental spills and cross contamination of clean system discharges (for example, reactor primary cooling water leakage into the de-ionized water system that ended up in clean sumps).
Generally, controlled releases were made from the areas where radioactively contaminated (hot) waters were retained, such as the HRA, the CRBs and ERB mentioned previously. Dilution waters were supplied to the ditch with mixing prior to release off-site through the WEMS. There were two heavy rain events (one in 1966 and the other in 1969) that exceeded 9 inches per day and caused major problems on site such as a buildup of sludge (sand, mud and silt) in the HRA tanks from flooding in various building basement sumps including the hot waste sumps.
Releases to the Pentolite Ditch were controlled by PBRF procedures in accordance with AEC and NRC regulations. The WEMS gate was designed to close if there was an inadvertent release of contaminated liquid that exceeded regulatory limits or if the WEMS malfunctioned. These actions 6
Plum Brook Reactor Facility FSSR, Rev. 0 were designed to control the releases of radioactive contaminants to Pentolite Ditch to within Federal regulatory limits.
3.1 Disposition of Materials in the Post-Shutdown Period The radioactive contamination in Pentolite Ditch originated principally from PBRF operations. Atmospheric atomic bomb testing during the 1950s and 1960s contributed man-made radioisotopes to PBRF and Pentolite Ditch background levels.
Following termination of operations of the two PB reactors in early 1973, Pentolite Ditch remained active and was to be maintained in acceptable condition for effluent flows from the operable building groundwater sump pumps and storm drainage.
Following termination of operations of the reactor on January 5, 1973 and before June 3 0 th of 1973, the WEMS remained active and was to be maintained in that condition until there was no radiological release hazard.
Prior to deactivation, the following conditions were in place:
- No liquid radioactive waste discharges had occurred for two months prior to deactivation. A rainfall of 1" in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and an accumulated rainfall of 2" had occurred and the liquid effluent radioactively level had not exceeded 1x 10 7 pCi/ml beta-gamma and 3x 10-8 gCi/ml alpha since the beginning of the two month period.
Prior to shutting down the WEMS, the PBRF trenches, catch basins, settling basins and the WEMS inlet basin were flushed to remove silt and sand.
The end condition after the shutdown in 1973 was that the WEMS was deactivated and the gates left open to the Pentolite ditch.
Subsequent to July Is' 1973, the WEMS was controlled according to Nuclear Regulatory Commission Licenses TR-3, R-93 and Broad By-Product Material License BPL No.
34-06706-03. Periodic effluent sampling for radioactivity was conducted as part of the PBRF facility and environmental program to demonstrate compliance with AEC/NRC regulations. The annual reports to the AEC/NRC provide the details of significant events or changes in status during the period between 1973 and the approval of the PBRF Decommissioning Plan [NASA 2007a] in 2001.
In 1985, Teledyne Isotopes, Inc. conducted a radiological characterization study for decommissioning planning and in 1998 GTS Duratek conducted a confirmatory survey of radiological conditions at PBRF. The survey results indicated that the west end near the WEMS and the east end nearest Plum Brook were radioactively contaminated higher than the remainder of the ditch. Four shallow cores indicated that contamination was confined to depths less than 6 inches.
During the 1998 confirmatory survey, conducted by GTS Duratek, eight sediment samples were collected along the ditch. The analytical results showed that the total activity ranged 7
Plum Brook Reactor Facility FSSR, Rev. 0 from 10 to 30 pCi/g. The residual activity from Cs-137 ranged from 2 to 15 pCi/g and from Co-60 from 0 to 1 pCi/g.
In 2004, a comprehensive characterization survey of the area was conducted, by NASA subcontractor Mongomery-Watson-Harza (MWH). During the gamma scan surveys, the area of concern grew an additional 42,577 square meters, out from the bounds of Pentolite Ditch proper, in the north and south directions from the ditch. One hundred and twenty surface soil and sediment samples were selected for analysis. The results indicate that Co-60 and Cs-137 was present in 49 surface samples at activity levels above the action level (50% of the interim DCGL Unity Test for Co-60 and Cs-137). The results further indicated that Co-60 and Cs-137 was present in 40 samples at concentrations exceeding 90% of the interim DCGL Unity Test. The maximum Co-60 and Cs-137 activities, 16.65 pCi/g and 1,093 pCi/g respectively, were observed at a location just east of the WEMS outfall. Additionally, 86 subsurface soil samples from 24 locations were selected for analysis. The results indicate that Co-60 and Cs-137 were present in 15 subsurface soil samples at activity levels above the action level. The results further indicate that Co-60 and Cs-137 were present in 12 subsurface soil samples (10 at 1 foot, 1 at 3 feet and 1 at 7 feet) at activity levels exceeding 90% of the interim DCGL Unity Test. The maximum Co-60 and Cs-137 activities were 0.92 pCi/g and 65.16 pCi/g respectively.
3.2 Decommissioning The Pentolite Ditch Environmental Area (A2300) was remediated in the following manner:
- Brush, trees and debris removed from the Class 1 and Class 2 survey units.
- Pentolite bypass piping system installed, dams installed and tanks staged to control excavation water.
" Batched water was processed, sampled and discharged.
" Areas remediated based on contamination levels.
- Soil segregated into piles based on sample results. The excavated soil was staged into two piles, the first pile was > the DCGL (referred to as the Direct Off-Site Disposal Threshold or DODT) and the second pile was known to be > the RAL (50%
of the DCGL) but < the DCGL (referred to as "the contaminated stockpile").
- The soil from the first pile (>DCGL) was shipped to an approved waste disposal facility.
- Soil from the second pile (>RAL but <DCGL) was loaded into trucks and transported to the soil farming area, within the PBRF Restricted Area, for processing.
Suspect material was surveyed and sorted using the MACTEC Development Corporation SS-Series Conveyor Soil Sorting System. The criterion for soil rejection was established for small and large material volumes. The small volume action level was established at the DCGL. The large volume was 50% of the DCGL. Rejected materials were staged for shipment to an approved waste disposal facility.
The total estimated amount of soil removed from the Pentolite Ditch area was 35,472 tons.
8
Plum Brook Reactor Facility FSSR, Rev. 0 Subsurface sampling was performed for these areas during Final Post Remediation (FPR) survey efforts as delineated in SR-170. This FPR survey established that no further remediation was necessary prior to commencing Final Status Survey for the Pentolite Ditch or adjacent Class 1 Areas.
The development of the sample criterion in SR-170 utilized three scenarios:
(1) A non-parametric sample plan developed using VSP.
(2) A biased sample plan in the Pentolite Ditch. As the ditch had undergone extensive remediation at depth with significant removal of the ditch banks the biased sampling was as follows:
Pentolite Ditch's centerline was sampled at 200' intervals with the first sample point east of the WEMS outfall and the flow prevention ditch which are located at the west end of the impacted portions of Pentolite Ditch.
These biased samples include a sample from the Class 1 designated portion of the unnamed creek, and samples from the Class 1 designated portions of Plum Brook which are upstream and south of the Pentolite Ditch/Plum Brook confluence.
(3) A biased sample plan which acquires samples at seven sample locations determined from previous characterization efforts. These seven locations all contained Cs-137 activity levels above the remediation action level at depths greater than 6 inches.
The Pentolite Ditch Environmental Areas (A2300) were prepared for FSS and surveyed in accordance with the FSSP [NASA 2007].
4.0 Survey Design and Implementation for the Pentolite Ditch The survey design and implementation for Pentolite Ditch is as follows:
Section 4.1 discusses numerous factors relating to FSS plan design requirements including the site specific DCGL values for soil, DCGL values for other media, radionuclide mixtures expected, surrogate DCGL values, equations used, area factors, survey unit size requirements and scan coverage requirements for Class 1 and Class 2 areas.
Section 4.2 discusses the area classification and survey unit breakdowns.
Section 4.3 discusses the number of measurements and samples conducted in each survey unit.
Section 4.4 discusses the instrument and measurement sensitivities.
4.1 FSS Plan Requirements The goal of the PBRF decommissioning project is to release the site for unrestricted use in compliance with the NRC's annual dose limit of 25 mrem/yr plus ALARA. The NRC dose limits apply to residual radioactivity that is distinguishable from background. The DCGL 9
Plum Brook Reactor Facility FSSR, Rev. 0 values established within the FSSP [NASA 2007] will not be increased without prior NRC approval.
4.1.1 Site-Specific DCGL Values for Soil The surface soil DCGL values are provided in Table 3-1 of the FSSP [NASA 2007]
and listed in Table 1 of this report. The DCGL values are the volumetric activity of the first 6 inches of soil, in pCi/g, that will be used during FSS to determine compliance with the 25 mrem/yr unrestricted use criterion.
Table 1, DCGL Values for Surface Soil Radionuclide DCGL (pCi/g)
Co-60 3.8 Sr-90 5.4 Cs-137 14.7 To provide a consistent level of analysis for the contamination of surface soil, a site-specific analysis approach was used for the PBRF.
The dose model selected for analyzing residual soil contamination, RESRAD Version 6.0.
The dose assessments and DCGL calculations for surface soil, are described in detail in Attachment B, "Approach and Basis for Development of Site-Specific Derived Concentration Guideline Levels (DCGL)" of the FSSP [NASA 2007].
Model input parameters were developed and justified for each assessment and can be found in the FSSP, Attachment B, Tables B-1 through B-8.
4.1.2 DCGL for Other Media In accordance with the FSS Plan [NASA 2007], the DCGL for sediment (e.g., stream or ditch silt) is the same as the surface soil. The DCGL for subsurface soil is the same as surface soil.
4.1.3 Radionuclide Mixture for FSS The evaluations of radionuclide mixtures for soil are contained in Attachment A of the FSSP [NASA 2007], "Radionuclide Distribution Basis for DCGL Determination, 10
Plum Brook Reactor Facility FSSR, Rev. 0 and FSS of the PBRF". Current and representative sample data were used to determine the final radionuclide mixtures for FSS.
Per NUREG-1757 [USNRC 20061, the Nuclear Regulatory Commission (NRC) staff considers radionuclides and exposure pathways that contribute no greater than 10%
of the 25 mrem/yr dose criteria to be insignificant contributors. This 10% limit for insignificant contributors is an aggregate limitation only. That is, the sum of the dose contributions from all radionuclides and pathways considered insignificant was no greater than 10% of the dose criteria of 25 mrem/yr per 10 CFR Part 20, Subpart E.
For PBRF soil, the doses from all radionuclides other than Cs-137, Co-60, and Sr-90 totaled 0.5 mrem/yr. Because this dose is 2% of the 25 mrem/yr limit, all radionuclides other than Cs-137, Co-60, and Sr-90 were eliminated from further consideration. To ensure the 25 mrem/yr criterion is met, any open land survey unit where the mean of FSS soil sample results indicates that the dose may be greater than 24.5 mrem/yr is reviewed for compliance with the unrestricted use limit.
4.1.4 Surrogate DCGL and the Unity Rule Two surrogate DCGLs, one for scans and one for soil samples, were used during the FSS of Pentolite Ditch.
For scanning, the radionuclide mixture reported for Pentolite Ditch soils in TBD 001 [PBRF 2009], Table 5-2 is Cs-137 at 96.9 %, Sr-90 at 1.7%, and Co-60 at 1.4 %.
For PBRF soils, the dose from all radionuclides other than Cs-137, Sr-90, and Co-60 totaled 0.5 mrem/yr. Because this dose is only 2% of the 25 mrem/yr limit, all radionuclides, other than Cs-137, Sr-90, and Co-60, were eliminated from further consideration. To ensure the 25 mrem/yr criterion is met, Scans of the soil were performed with a gamma scintillation detector utilizing a Cs-137 window. Since the scan is for a single nuclide, a surrogate calculation was used to account for both Sr-90 and Co-60. Based on the evaluation of characterization soil sample data provided in TBD PBRF-TBD-09-001, "Radionuclide Distributions and Adjusted DCGLs for Site Soils" [PBRF 2009], a surrogate DCGL value (DCGLSUR) was determined for the hard-to-detect (HTD) radionuclide of concern, Sr-90, using Cs-137. The DCGLsUR value was determined to be 13.34 pCi/g for FSS gamma scans of the Pentolite Ditch.
Soil samples were analyzed by a gamma spectroscopy system, which is capable of detecting both Cs-137 and Co-60, therefore a surrogate calculation was performed to account for the Sr-90 component, utilizing Cs-137 as the surrogate nuclide. The result of this calculation is 14.02 pCi/g. The Co-60 DCGL as listed in the FSSP is 3.8 pCi/g. A unity rule calculation was performed on the sample results to quantify the total activity for each sample.
11
Plum Brook Reactor Facility FSSR, Rev. 0 4.1.4.1 Surrogate Equation The surrogate DCGL is computed based on the distribution ratio between the hard-to-detect radionuclides and the easy-to-detect radionuclides. The surrogate DCGL is calculated using the following equation:
Surrogate,,,,, =
1___
S DCGLs.
DCGL2 DCGL3)
DCGL,1j Where: DCGLSUR = Surrogate radionuclide DCGL DCGL 2, 3... n = DCGL for radionuclides to be represented by the surrogate R, = Ratio of concentration (or nuclide mixture fraction) of radionuclide "n" to surrogate radionuclide.
4.1.4.2 Unity Rule Equation The unity rule is typically used as the first test to evaluate compliance with radiological criteria for license termination when more than one radionuclide has been determined to be potentially present. In lieu of a single DCGL, a unity rule calculation is used to demonstrate compliance with the soil unrestricted use limit. A surrogate DCGL, if applicable, would be used in the unity rule calculation. The unity rule is:
C
+
C2 Cn
+
+.......
<1 DCGL, DCGL2 DCGLn Where:
Cn = concentration of radionuclide n and DCGLn = DCGL of radionuclide n.
4.1.4.3 Area Factors Area factor is a value that is used to adjust the DCGLw to estimate the DCGLEMC and the MDC for Class 1 survey units. The area factor is the magnitude by which the residual radioactivity in a small area of elevated activity can exceed the DCGLw and still be in compliance with the release criteria or DCGLEMC.
The area factor is the multiple of the DCGL that is permitted in the area of elevated residual radioactivity without requiring remediation. The area factor is related to the size of the area over which the elevated residual radioactivity is distributed. That area, denoted AEMC, is generally bordered by levels of residual radioactivity below the DCGL, and is determined by an investigation. The area factor is the ratio of dose per unit area or volume for the default surface area for the applicable dose modeling scenario to that generated using the area of elevated residual radioactivity, AEMCO Area factors for surface soil are provided in Table 3-4 of the FSSP [NASA 2007] and 12
Plum Brook Reactor Facility FSSR, Rev. 0 are shown in Table 2. Area factor assumptions and calculations are provided in Attachment B of the FSSP [NASA 2007].
Table 2, Surface Soil Area Factors Elevated Area 1
2 3
5 10 15 25 100 250 2,000 (m2)
Area Fa 10.4 6.2 4.7 3.4 2.3 1.9 1.6 1.2 1.1 1
Factor 4.1.4.4 Survey Unit Size Survey units are typically limited in size to ensure each area is assigned an adequate number of data points. The survey unit sizes for PBRF are provided in Table 4-1 of the FSSP [NASA 2007] and in Table 3. Note that the maximum survey unit size for Class 1 surface soils is 2,000 in2.
Table 3, Recommended Survey Unit Area Size Requirements for FSS Class Land 1
up to 2000 m 2 2
up to 10,000 m2 3
up to 100,000 m 2 4.1.4.5 Scan Coverage for Class I and Class 2 Areas The area covered by scan measurement is based on the survey unit classification. A 100% accessible area scan of Class 1 survey units is required. The emphasis is placed on scanning the higher risk areas of Class 2 survey units. The percentage of scan coverage in Class 2 areas is proportional to the potential for finding contamination that is close to the DCGL. No Class 3 survey units were identified within the Pentolite Ditch Environmental Area (A2300). Minimum scan survey coverage requirements for the PBRF are provided in Table 5-1 of the FSSP [NASA 2007] and Table 4 below.
13
Plum Brook Reactor Facility FSSR, Rev. 0 Table 4, Minimum Scan Survey Coverage By Classification 4.2 Area Classification and Survey Unit Breakdown At the time the FSSP [NASA 2007] was initially submitted to the NRC for review and approval, the Pentolite Ditch and its environs were still being characterized. The area classification is provided in Table 2-2 of the FSSP [NASA 2007], and states that Pentolite Ditch and Environs (A2300) contain 574,000 fte of Class 1 area. However, Attachment D, Figure D-33 contains a map of the PBRF Environmental Areas and depicts a small portion of Pentolite Ditch as having Class 1, Class 2 and Class 3 areas. This appears to be in disagreement with Table 2-2 of the FSSP [NASA 2007].
As stated in Section 3.1, a comprehensive characterization was conducted by NASA subcontractor MWH, in 2004 and the results indicated that the impacted Class 1 area extended south and north of the ditch proper. This increased the impacted area to a total of 36 Class 1 survey units, totaling 681,328 ft2 of surface area and 6 Class 2 survey units, totaling 560,421 ft2 of surface area were identified to buffer the Class 1 areas, per Section 2.1 of the FSSP [NASA 2007]. This is equivalent to a 19% increase in Class 1 surface area and a 100% increase in Class 2 surface area, since no Class 2 area was identified in Table 2-2 of the FSSP [NASA 2007]. Refer to Figure 1 for a map of the survey units and their classification. Table 5 provides the current classification of the area and the corresponding FSSP [NASA 2007] classification for the area.
Table 5 was reviewed to ensure that no areas were classified "downward" from classifications assigned in the FSS Plan [NASA 2007].
Table 5, Pentolite Ditch Survey Units for FSS Survey Unit Class Description(1)
FSSP Classification (2)
OL-3-1 1
Pentolite Ditch from 101 to 105.5 OL-3-2 1
Pentolite Ditch Adjacent Areas - AX-101 &
AY-101 OL-3-3 1
Pentolite Ditch Adjacent Areas - AX-102 &
1 AY-102 OL-3-4 1
Pentolite Ditch Adjacent Areas - AX-103 &
1 AY-103 OL-3-5 1
Pentolite Ditch Adjacent Areas - AX-104 &
1 AY-104 14
Plum Brook Reactor Facility FSSR, Rev. 0 Table 5, Pentolite Ditch Survey Units for FSS Survey Unit Class Description(1)
FSSP Classification (2)
OL-3-6 Pentolite Ditch Adjacent Areas - AX-105 &
AY-105 1 Pentolite Ditch Adjacent Areas - AW-104 &
New Class 1 SU that was OL-3-7 1not identified in Table 2-2 AW-105 of FSSP(')
OL-3-8 1
Pentolite Ditch from 105.5 to 109.7 OL-3-9 Pentolite Ditch Adjacent Areas - North of Ditch to Road Line 100 to 110 OL-3-10 1
Pentolite Ditch from 113 to 116.7 OL-3-11 1
Pentolite Ditch from 116.7 to 120.8 1
OL-3-12 1
Pentolite Ditch Adjacent Areas - AY-106 &
1 AY-107 Pentolite Ditch Adjacent Areas - AX-106 &
OL-3-13 IX10 AX-107 Pentolite Ditch Adjacent Areas - AW-106 &
New Class 1 SU that was not identified in Table 2-2 AW-107 of FSSP (3)
Pentolite Ditch Adjacent Areas - AX-108 &
OL-3-15 I1 AY-108 OL..3-16 Pentolite Ditch Adjacent Areas -AX-109 &
AY-109 Pentolite Ditch Adjacent Areas - AW-108 &
New Class 1 SU that was not identified in Table 2-2 AW-109 of FSSP (3)
Pentolite Ditch Adjacent Areas - AX-110 &
New Class 1 SU that was OL318 Pen e Dnot identified in Table 2-2 AY-110 ofFSSP(3 )
Pentolite Ditch Adjacent Areas - AW-1 10 &
OL-3-19 1
AW-1 Pentolite Ditch Adjacent Areas - AV-109 -AV-New Class 1 SU that was not identified in Table 2-2 OL 0111 North & AW-103 NE of FSSP (3)
Pentolite Ditch Adjacent Areas - AX-1 11 &
OL-3-21 1
A-1 AY-I111 Pentolite Ditch Adjacent Areas - AY-112, AY-OL-3-22 1
13A-1 113, AY-1 14 OL-3-23 1
Pentolite Ditch Adjacent Areas - AY-1 15 through AY-118 Pentolite Ditch from 120.8 to 124.4 OL-3-24 1I Pentolite Ditch from 124.4 to piling wall OL-3-25 1
OL-3-26 1
Pentolite Ditch Adjacent Areas - AY-1 19 through AY-123.8 OL-3-27 1
Pentolite Ditch from 100 to 101, AY-100, AX-100 North OL-3-28 1Pentolite Ditch Adjacent Areas - AY-123.8through AY-127 15
Plum Brook Reactor Facility FSSR, Rev. 0 Table 5, Pentolite Ditch Survey Units for FSS Survey Unit Class Descriptiont1 )
FSSP Classification (2)
OL3-29 Pentolite Ditch Adjacent Areas - AX-127, AX-128, AY-128 OL-3-30 I
Plum Brook from AV line to Pentolite Road culverts OL-3-31 1
Pentolite Ditch Adjacent Areas - AX-125, 126, 127 west of Plum Brook Pentolite Ditch Adjacent Areas - AW-126, AV-OL-3-32 1
126 west of PB ; AV-125, AW-125, AX-126, AX-127 east of PB OL-3-33 1
Pentolite Ditch Adjacent Areas - AW-125, AV-125 west of PB Pentolite Ditch from 109.7 to 113 OL-3-34 1l L-335 Pentolite Ditch Adjacent Areas - North of Ditch New Class I SU that was not identified in Table 2-2 to Pentolite Road from 113 line to 117 line of FSSP (3)
AU-124/125/ 126, AV-124/126/127, AW-New boundary Class 2 SU that were not OL-3-36 127/128N, AX-128/129N, AY-129, AZ-129 identified in Table 2-2 of South of Pentolite Road FSSP (3)
New boundary Class 2 SU OL-3-37 2
AX-116 to 124, AW-124 that were not identified in Table 2-2 of FSSP (3)
AU-108N to l12N,AV-109Sto lllS,AV-112, New boundary Class 2 SU OL-3-38 2
Athat were not identified in AW-1 12, AX-1 12 to 115 Table 2-2 of FSSP (3)
AW-100 to 102, AW-103SW, AV-102NE, AV-New boundary Class 2 SU that were not identified in 103-108 Table 2-2 of FSSP (3)
AW-99N, AX-99, AX-100N, AY-99, AZ-99 New boundary Class 2 SU OL-3-40 2
South of Pentolite Road, AZ-103 to 116 North of that were not identified in PentliteRoadTable 2-2 of FSSP (3)
Pentolite Road AZ-1 17 to 126 North and South of Pentolite New boundary Class 2 SU OL-3-41 2
that were not identified in Road, AZ-127 to 129 North of Pentolite Road Table 2-2 of FSSP (3)
AY-1 17 to AY-126 North of Pentolite Ditch OL-3-42 I
Table 5 Notes:
- 1. See Figure 1 for a map of Pentolite Ditch that identifies the survey unit locations and their corresponding grid coordinate designation.
- 2.
The FSS Plan [NASA 2007] classifications were based on area history and available characterization data. The specific Class 1 survey units were not defined, only a total surface area was identified.
- 3. Denotes a survey unit whose classification was changed from that listed in the FSSP Table 2-2
[NASA 2007] or one that was not specifically identified (and classified) in Table 2-2.
Table 6 provides the survey unit breakdown, by MARS SIM classification.
16
Plum Brook Reactor Facility FSSR, Rev. 0 Table 6, Pentolite Ditch Survey Unit Breakdown by MARSSIM Classification No. of Surface
% of Survey
% of Surface Average Area of Class Survey Units Area (m2)
Units Area Survey Units (m2) 1 36 65,277 85.7 55.4 1,813.3 2
6 52,555 14.3 44.6 9,759.2 Total 42 117,832 100.0 100 4.3 Number of Measurements and Samples The Final Status Survey for Pentolite Ditch was covered by several Survey Design and Survey Request (SR) documents. Survey Design number 30 covered the one (1) Class 1 survey unit immediately north of Pentolite Ditch (SU OL-3-42). Survey Design number 32 covered the thirty-five (35) Class 1 survey units that make-up Pentolite Ditch. Survey Design number 35 covered the six (6) Class 2 survey units that border the Class 1 Pentolite Ditch survey units. See Exhibit 5 of Appendix A for a view of surveys being performed in Pentolite Ditch.
The number of measurements and samples for each Pentolite Ditch survey unit was determined using the MARSSIM statistical hypothesis testing framework as outlined in the FSS Plan. The Sign Test was selected because background soil concentrations are small when compared to the applicable DCGLw. Decision error probabilities for the Sign Test are set at a = 0.05 (Type I error) and P3
= 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 each survey unit within the Pentolite Ditch.2 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:
N l.2 (ZI-a + ZI-6)2 ]
(Equation 1)
Where:
1.2 = adjustment factor to add 20% to the calculated number of samples, per a MARSSIM requirement to provide a margin for measurement sufficiency, 2 The FSS Plan (Section 5.2.4) states that a qualified software product, such as Visual Sample Plane [PNL 2010], may be used in the survey design process.
17
Plum Brook Reactor Facility FSSR, Rev. 0 N = Number of measurements or samples, a = the type I error probability, P3 = the type II error probability, Zl-, = proportion of standard normal distribution < 1 - a (1.6449 for a =
0.05),
ZI_- = proportion of standard normal distribution < 1 - 03 (1.2816 for f3 = 0.1),
(D (A/a) = value of cumulative standard normal distribution over the interval
-00, A/a, A = the "relative shift", defined as the DCGL - the Lower Bound of the Gray Region (LGBR), and a = 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: a, Y3, A, a and the DCGLw. The number of measurements, N, for the 42 Pentolite Ditch survey units were calculated in two survey designs. Table 7 summarizes the survey design calculations and lists the values of the key VSP input parameters.
Table 7, Pentolite Ditch Survey Design Summary Design LG BR/
Survey Units Class DCGL LGBR A
a A/a N
No.
DCGL OL-3-1 through OL-32 3-35 and OL-3-42 1
13.34 9
0.7 4.3 1.7 2.5 11 35 OL-3-36 through 2
13.34 13 0.98 0.3 0.2 1.3 11 OL-3-41 Table 7 Notes:
- 1. The data reported in Table 7 is taken from the Survey Design reports listed. They are maintained in the PBRF Document Control System.
- 2. Units are in pCi/g except for N which is unit-less.
- 3. Spreadsheet rounding and significant figures are the reason for small differences in the values provided in this Table and the values documented in the data contained in the Survey Design reports.
- 4. Values provided in Table are typical values for the survey units within that specific design.
Selection of design input parameters followed guidance in the FSS Plan. The Plan states that "the LGBR is initially set at 0.5 times the DCGLw, but may be adjusted to obtain a value for the relative shift (A/a) between 1 and 3".
The VSP software automatically performs an analysis to examine the sensitivity of the number of samples, N, to critical input parameter values. The following is obtained from the VSP report for survey unit OL-3-30 (with modifications). The sensitivity of N is explored by varying the standard deviation from 2.67 to 4 pCi/g (an increase of 50%) with the lower bound of gray region from ranging from 50 to 60 % of theDCGL. The value of beta, probability of mistakenly concluding that the survey units mean concentration is greater than the DCGL is varied from 0.05 to 0.15. While the VSP sensitivity analysis also varies the value of a, the sensitivity of N to changes in a is not evaluated here.
18
Plum Brook Reactor Facility FSSR, Rev. 0 Table 8 summarizes the results of this analysis. The region of most interest in the Table is for a = 0.05 (required to be fixed), P3
= 0.10 (may be adjusted) and the LBGR at 50% to 60%
of the DCGL. The sensitivity of N to expected measurement variability is examined first.
With the LBGR set to 60%, a = 0.05 and P3
= 0.10, a 50 % increase in aF increases N from 12 to 16. At this LBGR value, N is sensitive to measurement variability. With the LBGR set to 50% of the DCGL, the sensitivity is decreased; a 50 % increase in 7 increases N from 11 to 13.
However, in contrast, the sensitivity of N to an incorrect conclusion that the survey unit will pass (owner's risk) is low. When the LBGR is set at 60 %, of the DCGL (holding a and a constant) and 1P is increased from 0.10 to 0.15, the number of measurements is decreased from 12 to 10. When the LBGR set at 50 %, of the DCGL, (holding (Y and a constant) and f3 is increased from 0.10 to 0.15, the number of measurements is decreased from 11 to 9.
These results show that N = 11 represents a reasonable number of measurements for FSS of the Pentolite Ditch, in view of parameter values applied to the designs.
Table 8, Sensitivity Analysis for OL-3-30 Design Number of Samples Cs-137 DCGLsu=14.02 T=0.05 (2)
=0.10 a=0.15 Co-60 DCGLw=3.8 1) 4.0(1) (3) o= 2.67 a= 4.0 a= 2.67 a= 4.0 a= 2.67 LBGR=60% (1)(4)
B=0.05 20 15 16 12 13 10 B=0.10 16 12 12 9
10 8
B=0.15 13 10 10 8
8 6
LBGR=50%
B=0.05 16 14 13 11 11 9
B=0.10 13 11 10 9
8 7
B=0.15 11 9
8 7
7 6
LBGR=40%
B=0.05 15 14 12 11 10 9
B=0.10 12 11 9
8 8
7 B=0.15 10 9
8 7
6 6
Table 8 Notes:
- 1. Units of DCGL, o and LBGR are pCi/g.
- 2. a = alpha, probability of mistakenly concluding that p < DCGL.
- 3. a = Standard Deviation.
- 4. LBGR = Lower Bound of Gray Region (as % of DCGL)
= beta, probability of mistakenly concluding that p > 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 Pentolite Ditch survey unit.
The survey designs also specified scan survey coverage and action levels based on FSS plan requirements in Table 4. If the scan sensitivity of the detectors used in Class 1 survey units was below the DCGLw, the number of measurements in each survey unit is determined 19
Plum Brook Reactor Facility FSSR, Rev. 0 solely by the Sign Test. If the scan sensitivity was not below the DCGLw, the number of measurements was increased as determined by the Elevated Measurement Test. 3 4.4 Instrumentation and Measurement Sensitivity Instruments used in the FSS of each survey unit were selected and identified in the appropriate survey design. Their detection sensitivities were shown to be sufficient to meet the required action levels for the MARSSIM class of each survey unit.
In accordance with the FSSP [NASA 2007], gamma scanning was performed over land surfaces to identify locations of residual surface activity. Nal gamma scintillation detectors (typically 2" x 2") were used for these scans. Scanning was generally performed by moving the detector in a serpentine pattern within 10 cm (4 in) from the surface, while advancing at a rate not to exceed 0.5 m (20 in) per second. Technicians responded to indications of elevated areas, both audible and visual, while surveying. Upon detecting an increase in visual or audible response, the technician reduced the scan speed or paused and isolated the elevated area. If the elevated activity was verified to exceed the established investigation level, the area was bounded (e.g., marked or flagged and measured to obtain an estimated affected surface area).
A summary of the a priori detection sensitivities, for Ludlum model 44-10 (2" x 2" Nal detector) used to scan the open land survey units that constitute Pentolite Ditch, is provided in Table 9. Measurement sensitivities provided in this section relate both to the gamma scan sensitivities and the static measurement sensitivities.
Table 9, Detection Sensitivities of 44-10 for Cs-137
Background
MDCR121 MDCsan*1 *
(cpm)
(ncpm)(3)
(pCi/g) 25 50.3 2.21 50 71.2 3.13 100 100.6 4.43 150 123.2 5.42 200 142.3 6.26 250 159.1 7.00 300 174.3 7.67 350 188.3 8.28 400 201.3 8.85 450 213.5 9.39 500 225.0 9.90 Table 9 Notes:
- 1. MDC=Minimum Detectable Concentration, in pCi/g.
- 2. MDCR=Minimum Detectable Count Rate, in ncpm.
- 3. ncpm=net counts per minute=gross counts per minute - background counts per minute.
3 As discussed in the next section, the scan sensitivities of instruments used in the FSS of the Pentolite Ditch were below the DCGLw, and no increase in the number of measurements calculated using the Sign Test was required.
20
Plum Brook Reactor Facility FSSR, Rev. 0 5.0 Pentolite Ditch Survey Results Results of the Pentolite Ditch FSS are presented in this section. This section includes scan survey frequencies (% of areas covered) for each survey unit and occurrence of events where scan investigation levels were exceeded. Investigations performed and the results are summarized. Soil sample results, for each survey unit, along with comparison tests of survey unit maximum and average values with the DCGLw are provided. No statistical tests were required. It is shown that levels of residual contamination have been reduced to levels that are ALARA. Soil activity concentrations are compared to EPA trigger levels in accordance with the 2002 Memorandum of Understanding between the NRC and EPA [USEPA 2002]. This section closes with a summary which concludes that applicable criteria for release of the Pentolite Ditch for unrestricted use are satisfied and all FSS Plan requirements are met.
Additionally, Section 9.2 of the FSS plan states that measurements performed during characterization, turnover and investigation surveys can be used as FSS data if they are performed according to the same requirements as the final survey data. These requirements include:
(1) The survey data is representative of the as-left survey unit condition and is not impacted by further remediation; (2) The application of isolation measures to the survey unit to prevent re-contamination and to maintain final configuration; and (3) The data collection and design were in accordance with FSS methods (e.g., MDCscan, investigation levels, survey data point number and location, statistical tests, and EMC tests) [PBRF 2009a].
Therefore, in accordance with Survey Request 179 (SR-179), surveys of Pentolite Ditch by FSS personnel were conducted in concert with the demolition contractor in an effort to allow Pre-Remediation-Remediation-Post-Remediation phases to be performed more efficiently. All surveys conducted for this purpose were performed in accordance with the FSS plan requirements above.
See Exhibits 5, 6, 7, 11, 12 and 16 through 20 of Appendix A for photographic documentation of remediation and performance of surveys associated with the Pentolite Ditch FSS.
Five Survey Requests (SR's) directed the final status surveys and sampling that were conducted at Pentolite Ditch, SR-179, SR-180, SR-181, SR-189 and SR-192. Scanning, static measurements, pre-and post remediation surveys, judgmental sampling and systematic sampling were covered by these SR's.
SR-179 was written to direct the performance of final status surveys of the soil in the Class 1 areas that constitute Pentolite Ditch. The following Class 1 Survey Units were surveyed under this SR:
OL-3-1 through OL-3-29, OL-3-31 through OL-3-35 and OL-3-42. Compliance is demonstrated through the use of the unity rule.
SR-180 was written to direct the performance of systematic soil sampling in support of FSS for all Class 1 survey units that constitute Pentolite Ditch. Specifically, Survey Units OL-3-1 through OL-3-35 and OL-3-42 are covered by this SR. Compliance is demonstrated through the use of the unity rule.
21
Plum Brook Reactor Facility FSSR, Rev. 0 SR-181 was written to direct the performance of Final Post Remediation Surveys in the Pentolite Ditch Crossover Culvert Pipes and to verify completion of remediation activities. An overview of the results of surveys conducted in support of SR-181, but the crossover culvert pipes are considered buried piping and shall be addressed in Attachment 09 of the FSS Report. See Exhibits 12, 13 and 21 of Appendix A for photographic documentation.
SR-189 was written to direct the performance of Final Status Surveys of the soil in the Plum Brook area south of Pentolite Road. This SR directed the 100% scan of all soil surfaces in Survey Unit (SU) OL-3-30, this included both water covered and non-water covered soil areas.
SR-192 was written to direct the performance of FSS surveys for Class 2 Survey Units OL-3-36 through OL-3-41.
5.1 Surveys and Investigations 5.1.1 Scan Surveys In accordance with the requirements contained in SR-179, 100% of all Class 1 survey units were scanned with the Ludlum 2350-1 with the 44-10 detector setup with a window for Cs-137 energies. A scan action level of 250 ncpm, which corresponds to 7.85 pCi/g, was established, per the SR. Static measurements were conducted at each location that exceeded the action level and judgmental soil samples were collected at the discretion of the FSS/Characterization Supervisor or Engineer.
In accordance with the requirements contained in SR-180, 50% of all Class 2 survey unit land areas were scanned with the Ludlum 2350-1 with the 44-10 detector setup with a window for Cs-137 energies. A scan action level of 250 ncpm, which corresponds to 7.85 pCi/g, was established, per the SR. Static measurements were conducted at each location that exceeded the action level and judgmental soil samples were collected at the discretion of the FSS/Characterization Supervisor or Engineer.
Scan survey results were reviewed to confirm that the scan coverage requirement (as % of survey unit area) was satisfied for all survey units. QC scans were reviewed and analyzed by the FSS/Characterization Engineer while processing Survey Unit Release Records. The results of QC replicate surveys were also reviewed to confirm that the minimum coverage requirement of 5% was satisfied. Results of the Pentolite Ditch scan surveys are compiled in Table 10. See Exhibit 5 of Appendix A for a photograph of the Pentolite Ditch survey being conducted.
22
Plum Brook Reactor Facility FSSR, Rev. 0 Table 10, Scan Survey Results C
I Surface Area of QC Replicate Investigation Survey a
'SR #
SScan Survey Scan Coverage Level Unit(
s (in Square UniFeet)
Coverage (%) (2)
(%) (2)
Exceeded(3)
OL-3-1 1
179(l) 21,097 100 6.4 No OL-3-2 1
179(')
19,625 100 5.1 No OL-3-3 1
179")
19,844 100 6.0 No OL-3-4 I
179UT) 19,373 100 5.2 No OL-3-5 I
1797T 19,028 100 6.3 No OL-3-6 1
1797ý 18,076 100 5.3 No OL-3-7 1
179")
20,000 100 5.0 No OL-3-8 11 1791) 21,293 100 5.9 No OL-3-9 I
179(l) 20,296 100 5.1 No OL-3-10 1
179(')
21,312 100 5.2 No OL-3-11 1
179(l) 21,214 100 5.4 No OL-3-12 I
179(l) 17,874 100 5.6 No OL-3-13 1
179(')
20,000 100 5.0 No OL-3-14 1
17977}
20,000 100 5.0 No OL-3-15 1
179(')
19,152 100 5.2 No OL-3-16 1
179(')
19,322 100 5.2 No OL-3-17 I
1797T-20,000 100 5.0 No OL-3-18 1
179(l) 19,299 100 5.2 No OL-3-19 1
1797T 20,000 100 5.0 No OL-3-20 1
179(')
20,000 100 5.0 No OL-3-21 1
179(')
19,191 100 5.2 No OL-3-22 1
179 20,424 100 7.8 No OL-3-23 1
179(')
20,279 100 5.1 No OL-3-24 1
1797T 21,076 100 6.0 No OL-3-25 1
179(1) 18,835 100 5.8 No OL-3-26 1
1791T 21,435 100 5.0 No OL-3-27 1
1797T-19,595 100 7.1 No OL-3-28 1
179(')
17,842 100 5.6 No OL-3-29 1
179(')
18,290 100 5.5 No OL-3-30 1
189
'T 14,662 100 5.5 Yes"5 )
OL-3-31 1
179(')
19,608 100 5.1 No OL-3-32 1
1797TT 15,912 100 6.3 No OL-3-33 1
179(1) 18,671 100 5.4 No OL-3-34 1
17971T 16,241 100 6.4 No OL-3-35 1
179k1) 20,332 100 5.9 No OL-3-36 2
192(6) 104,123 51.6 5.6 No OL-3-37 2
192(i )
100,000 50.8 5.9 No OL-3-38 2
192(6) 100,000 51.1 5.4 No OL-3-39 2
1927T 100,000 51.2 6.0 No OL-3-40 2
1927T 73,692 50.2 6.5 No OL-3-41 2
192(6) 86,735 54.5 5.1 No OL-3-42 1
179`_)
2,130 100 8.5 No Table 10 Notes:
- 1. Except as noted, scan surveys performed under SR-179 and systematic soil sampling was performed under SR-180.
- 2.
The % scan coverage is given as the % of the area scanned in the initial survey.
23
Plum Brook Reactor Facility FSSR, Rev. 0 (Table 10 Notes continued)
- 3. From survey unit Release Record.
- 4. Scanning and Investigative surveys and sampling for IM-1 and IM-2 were performed under SR-189.
- 5. Underwater surveys performed under SR-189 establish a scan investigation level of 125 ncpm, which corresponds to an activity of 3.92 pCi/g. However, during initial post remediation surveys, two static measurements were taken. The first static measurement location, taken at IM-1, was 162 ncpm and the second static measurement location, taken at IM-2, was 119 ncpm. Soil samples were collected at both locations and the sample results indicated that all locations were less than the DCGL. No further action was taken. The 125 ncpm (3.92 pCi/g) scan investigation level was derived from PBRF-TBD-09-006, "An Evaluation of the 2350-1/44-10 NaI Detector Response in Water Covered Areas."
- 6.
Scan survey and systematic soil sampling were performed under SR-192.
The results provided in Table 10 show that scan coverage requirements were satisfied for all survey units. Table 10 results also shows that scan investigation level were exceeded in one survey unit, OL-3-30 (see note #5 above).
5.1.2 Static Measurements and Judgmental Soil Samples As discussed in Section 5.0, pre-remediation, remediation and post-remediation surveys for Class 1 survey units within Pentolite Ditch were performed in tandem with the demolition contractor's performance of soil remediation activities. Therefore, elevated scans or static measurements indicated that remediation was necessary. After the remediation was performed additional scans were conducted to ensure that the remediation was complete.
The final scan of each area became part of the FSS release record for that survey unit.
Survey unit OL-3-30, is located in Plum Brook at the confluence of Plum Brook and Pentolite Ditch. Refer to Figure 1 for the exact location of survey unit OL-3-30. See Exhibits 10 and 11 of Appendix A for photo of the Pentolite Ditch and Plum Brook confluence. Per SR-189, 100 % scans were performed underwater using the Ludlum 2350-1 with the 44-10 detector setup with a window for Cs-137 energies. During those initial pre and post remediation scans, two (2) IM locations were identified. However, only one of the two IM locations was above the scan action level, of 125 ncpm (3.92 pCi/g), established in SR-189.
NOTE: Technical Basis Document PBRF-TBD-09-006, "An Evaluation of the 2350/44-10 NaI Detector Response in Water Covered Areas" [PBRF 2009b] was written that determined the effectiveness of the aforementioned detector in water covered areas [PBRF 2009b]. The results of the TBD determined that a 2 inch covering of water decreases the detector response from between 20% to 32%. The aforementioned TBD provided several recommendations that would aid in minimizing the impact of scanning a water covered surface. These recommendations included the following:
Establish background in the water covered areas, Hold the detector tube in contact with the underwater soil instead of 4"
- above, Reduce the distance between the serpentine lines to 8",
24
Plum Brook Reactor Facility FSSR, Rev. 0
- Limit the scan speed to 4" per second, and
- Reduce the scan investigation level from 250 ncpm (7.85 pCi/g) to 125 ncpm (3.92 pCi/g).
Static measurements were conducted at the two locations, IM-1 and IM-2. However, only IM-1 was identified as being greater than the scan investigation level. IM-1 static measurement was 162 ncpm and IM-2 was 119 ncpm. Judgmental soil samples were collected at both locations and indicated the following:
TM-1 Cs-137 activity was 1.03 pCi/g and Co-60 was <MDA, and 0 IM-2 Cs-137 activity was 1.12 pCi/g and Co-60 was <MDA.
Since the sample activities were well below the DCGLsUR for Cs-137 (14.02 pCi/g), no further action was taken.
5.1.3 Systematic Soil Sampling 5.1.3.1 Soil Sampling for Class 1 Areas SR-180 was written to direct the performance of Final Status Survey soil sampling in the following Class 1 Survey Units: OL-3-1 through OL-3-35 and OL-3-42 located in Pentolite Ditch and the adjacent excavated areas. The directions contained in the SR were based upon requirements given by Final Status Survey Design # 32. The DCGLsUR for sampling is 14.02 pCi/g for Cs-137 and the DCGLw is 3.8 pCi/g for Co-60. Compliance with the DCGL is demonstrated through the use of the unity rule.
The results are as follows:
Three hundred and ninety-nine samples were collected, processed and analyzed.
Of the 399 samples collected and analyzed, 148 were > MDA for Cs-137 and no sample was >MDA for Co-60.
The highest activity was at OL-3-2 Sample Point (SP) 2. The activity at this location was 7.62E+00 pCi/g +/- 6.01E-01 pCi/g for Cs-137 and <MDA Co-60.
The average Cs-137 activity was 4.46E-01 pCi/g +/- 1.33E-01 pCi/g for Cs-137.
All 399 samples were <MDA for Co-60.
Table 11 provides a summary of soil sample results by survey unit. See Appendix C for a complete list of individual soil sample results.
5.1.3.2 Soil Sampling for Class 2 Areas SR-192 was written to direct the performance of Final Status Survey soil sampling in the following Class 2 Survey Units: OL-3-36 through OL-3-41 that surround the Class 1 survey units that constitute the Pentolite Ditch proper. The directions contained in the SR were based upon requirements given by Final Status Survey Design # 35. The DCGLsUR for sampling is 14.02 pCi/g for Cs-137 and the DCGLw 25
Plum Brook Reactor Facility FSSR, Rev. 0 is 3.8 pCi/g for Co-60. Compliance with the DCGL is demonstrated through the use of the unity rule. The results are as follows:
Sixty-six soil samples were collected, processed and analyzed.
" Of the 66 samples collected and analyzed, 46 were > MDA for Cs-137 and no sample was >MDA for Co-60.
The highest activity was at OL-3-37 Sample Point (SP) 7. The activity at this location was 3.35E+00 pCi/g +/- 4.1 IE-01 pCi/g for Cs-137 and <MDA Co-60.
The average Cs-137 activity was 4.12E-01 pCi/g +/- 1.31E-01 pCi/g for Cs-137.
All 66 samples were <MDA for Co-60.
Table 11 provides a summary of soil sample results by survey unit. See Appendix C for a complete list of individual soil sample results.
5.1.3.3 Quality Control Sample Analysis In accordance with Section 12.7 of the FSSP [NASA 2007], the objective of QA/QC implementation is to ensure that the survey data collected are of the type and quality required to demonstrate that the dose from residual contamination is below the 25 mrem/yr unrestricted use criteria and to support a decision to terminate the PBRF license. Proper application of QA/QC ensures that:
the elements of the FSS plan are implemented in accordance with the approved procedures; surveys are conducted by trained personnel using calibrated instrumentation; the quality of the data collected is adequate; all phases of survey package design and implementation are properly reviewed, and oversight is provided; and corrective actions, when identified, are implemented in a timely manner and are determined to be effective.
Section 12.7.2 oftheFSSP [NASA 2007] further states that replicate sample analyses will be used to monitor sample precision. A minimum of one out of every twenty (5%) FSS samples collected will be reanalyzed or homogenized, split and submitted for independent analyses. This evaluation is performed as follows:
- Determine the resolution for each known nuclide concentration by dividing the initial activity by its corresponding 1 a uncertainty.
- Determine the ratio of each nuclide concentration by dividing the duplicate sample result by the initial sample result.
- The results are acceptable if the agreement ratio falls within the values given in Table 12-1 of the FSSP [NASA 2007] for the corresponding resolution.
26
Plum Brook Reactor Facility FSSR, Rev. 0 For Pentolite Ditch Environmental Area (A2300), a total of 43 QC samples were collected, processed and analyzed (37 from Class 1 areas and 6 from Class 2 areas).
The results are as follows:
37 QC samples from Class 1 areas (399 total samples) constitutes a ratio of 9.3% QC samples to total sample population,
& 6 QC samples from Class 2 areas (66 total samples) constitutes a ratio of 9.1% QC samples to total sample population, and
- All 43 QC samples (37 from Class 1 areas and 6 from Class 2 areas) were analyzed and the resolution was determined and the ratios were all within the acceptable range provided in Table 12-1 of the FSSP [NASA 2007].
See Appendix C for QC Comparison results, per FSSP Section 12.7.2.
27
Plum Brook Reactor Facility FSSR, Rev. 0 Table 11, Pentolite Ditch Systematic Soil Sample Results By Survey Unit Cs-137, DCGLSUR = 14.02 pCi/g Co-60, DCGLw = 3.80 pCi/g Test Test Test Test Maximum Result:
Average Result:
Maximum Result:
Average(')
Result:
Average Survey No. of (pCi/g)
Maximum (pCi/g)
Average (pCi/g)
Maximum (pCi/g)
Average Unity Unit ID Measurements
< DCGLw Fraction DCGLSUR DCGLSUR DCGLw OL-3-1 11 0.220 Yes 0.096 Yes 0.139 Yes 0.121 Yes 0.039 OL-3-2 11 7.620 Yes 0.801 Yes 0.137 Yes 0.118 Yes 0.088 OL-3-3 11 0.506 Yes 0.160 Yes 0.149 Yes 0.129 Yes 0.045 OL-3-4 11 1.060 Yes 0.201 Yes 0.145 Yes 0.123 Yes 0.047 OL-3-5 11 0.550 Yes 0.153 Yes 0.140 Yes 0.119 Yes 0.042 OL-3-6 11 0.390 Yes 0.180 Yes 0.141 Yes 0.124 Yes 0.046 OL-3-7 11 0.325 Yes 0.202 Yes 0.148 Yes 0.128 Yes 0.048 OL-3-8 14 0.127 Yes 0.086 Yes 0.136 Yes 0.125 Yes 0.039 OL-3-9 11 0.569 Yes 0.157 Yes 0.140 Yes 0.118 Yes 0.042 OL-3-10 11 0.158 Yes 0.088 Yes 0.139 Yes 0.122 Yes 0.038 OL-3-11 11 0.098 Yes 0.085 Yes 0.144 Yes 0.129 Yes 0.040 OL-3-12 11 0.295 Yes 0.101 Yes 0.135 Yes 0.124 Yes 0.040 OL-3-13 11 0.614 Yes 0.149 Yes 0.149 Yes 0.126 Yes 0.044 OL-3-14 11 0.785 Yes 0.253 Yes 0.148 Yes 0.124 Yes 0.051 OL-3-15 11 1.650 Yes 0.220 Yes 0.132 Yes 0.114 Yes 0.046 OL-3-16 11 0.359 Yes 0.104 Yes 0.132 Yes 0.116 Yes 0.038 OL-3-17 11 0.247 Yes 0.111 Yes 0.139 Yes 0.120 Yes 0.040 OL-3-18 11 0.547 Yes 0.137 Yes 0.141 Yes 0.125 Yes 0.043 OL-3-19 11 0.414 Yes 0.195 Yes 0.140 Yes 0.124 Yes 0.046 OL-3-20 11 0.695 Yes 0.182 Yes 0.149 Yes 0.128 Yes 0.047 OL-3-21 11 0.606 Yes 0.267 Yes 0.148 Yes 0.126 Yes 0.052 OL-3-22 11 0.604 Yes 0.176 Yes 0.146 Yes 0.124 Yes 0.045 OL-3-23 11 0.471 Yes 0.204 Yes 0.143 Yes 0.128 Yes 0.048 OL-3-24 11 0.099 Yes 0.085 Yes 0.145 Yes 0.128 Yes 0.039 28
Plum Brook Reactor Facility FSSR, Rev. 0 Table 11, Pentolite Ditch Systematic Soil Sample Results By Survey Unit Cs-137, DCGLSUR = 14.02 pCi/g Co-60, DCGLw = 3.80 pCi/g Test Test Test Maximum Result:
Average(1)
Result:
Maximum Test Average Result:
Reut vrg~~Result:
Average Survey No. of (pCi/g)
Maximum (pCi/g)
Average (pCi/g)
Maximum (pCi/g)
Average Unity Unit ID Measurements
< DCGLw Fraction DCGLsuR DCGLsUR DCGLw OL-3-25 11 0.121 Yes 0.084 Yes 0.149 Yes 0.120 Yes 0.038 OL-3-26 11 0.777 Yes 0.253 Yes 0.140 Yes 0.125 Yes 0.051 OL-3-27 11 1.130 Yes 0.361 Yes 0.144 Yes 0.129 Yes 0.060 OL-3-28 11 1.270 Yes 0.491 Yes 0.140 Yes 0.129 Yes 0.069 OL-3-29 11 0.956 Yes 0.265 Yes 0.146 Yes 0.127 Yes 0.052 OL-3-30 11 0.340 Yes 0.207 Yes 0.145 Yes 0.130 Yes 0.049 OL-3-31 11 0.939 Yes 0.313 Yes 0.148 Yes 0.135 Yes 0.058 OL-3-32 11 0.387 Yes 0.259 Yes 0.149 Yes 0.140 Yes 0.055 OL-3-33 11 0.446 Yes 0.257 Yes 0.142 Yes 0.138 Yes 0.055 OL-3-34 11 0.243 Yes 0.082 Yes 0.145 Yes 0.123 Yes 0.038 OL-3-35 11 0.475 Yes 0.289 Yes 0.141 Yes 0.129 Yes 0.054 OL-3-36 11 0.350 Yes 0.234 Yes 0.145 Yes 0.127 Yes 0.050 OL-3-37 11 3.350 Yes 0.676 Yes 0.144 Yes 0.135 Yes 0.084 OL-3-38 11 0.720 Yes 0.292 Yes 0.131 Yes 0.118 Yes 0.052 OL-3-39 11 0.316 Yes 0.237 Yes 0.149 Yes 0.134 Yes 0.052 OL-3-40 11 0.366 Yes 0.200 Yes 0.146 Yes 0.123 Yes 0.047 OL-3-41 11 0.432 Yes 0.268 Yes 0.144 Yes 0.131 Yes 0.053 OL-3-42 11 0.382 Yes 0.192 Yes 0.149 Yes 0.126 Yes 0.047 Total 465 Maximum 7.62 0.801 0.149 0.14 0.088 Average 0.223 0.126 0.05 Table 11 Note:
- 1.
If actual value was less than the MDA, the MDA value was used to calculate the average value.
29
Plum Brook Reactor Facility FSSR, Rev. 0 5.2 ALARA Evaluation It is shown that residual contamination in the Pentolite Ditch 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, those 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."4 The applicable NRC surface soil screening values are: Co-60, 3.8; Sr-90, 1.7 and Cs-137, 11 (all in pCi/g). From Appendix C, the highest activity was at OL-3-2 Sample Point (SP) 2.
The activity at this location was 7.62E+00 pCi/g Cs-137 and <MDA Co-60. These values are well below the applicable NRC surface soil screening values stated above. Since Cs-137 is the surrogate for Sr-90 and the Sr-90: Cs-137 activity ratio is only 0.0 17, the activity concentration of Sr-90 is also well below the screening level. The average Cs-137 activity was 4.46E-01l1.33E-01 pCi/g for Class 1 areas and 4.12E-01l+/-.31E-01 pCi/g for Class 2 areas. All samples were <MDA for Co-60. Therefore, all soil sample results are below their respective screening level values. From these comparisons, it is concluded that the ALARA criterion is satisfied.
5.3 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.
The trigger levels applicable to the PBRF for residual soil concentrations of the radionuclides of concern are:
" Co-60, 4 pCi/g,
" Sr-90 (plus daughter activity), 23 pCi/g and
" Cs-137 (plus daughter activity), 6 pCi/g.
4 This guidance was initially published in Draft Regulatory Guide DG-4006, but has been reissued in NUREG-1757 Volume 2, Appendix N.
30
Plum Brook Reactor Facility FSSR, Rev. 0 From Appendix C, the average Cs-137 activity was 4.38E-01+/-l.32E-01 pCi/g for Class 1 areas and 4.12E-01+/-1.3 IE-01 pCi/g for Class 2 areas. All samples were <MDA for Co-60.
These average values are well below the applicable EPA Trigger Levels stated above. Since Cs-137 is the surrogate for Sr-90 and the Sr-90: Cs-137 activity fraction is only 0.0 175, the activity concentration of Sr-90 is also well below the trigger level.
5.4 Conclusions The results presented above demonstrate that the Pentolite Ditch satisfies all FSS Plan commitments and meets the release criteria in 1 OCFR20 Subpart E. The principal conclusions are:
- Scan surveys were performed in all 42 survey units with scan coverage equal to (for Class 1 areas) or in excess of (for Class 2 areas) the percentage requirements stated in the FSSP [NASA 2007].
- Residual surface soil contamination above investigation levels was detected in only one of 42 survey units. Soil sample results indicated that the activity present was well below the DCGLs.
- All 465 systematic soil sample results were less that the applicable DCGLw, values for Cs-137 and Co-60.
- Residual soil concentration measurement results are shown to be less than NRC screening level values - demonstrating that the ALARA criterion is satisfied.
- Residual activity concentrations measured in the soil survey unit were compared to, and found to be less than EPA trigger levels.
" No changes from what was proposed in the FSS Plan were made except that the Class 1 area was expanded based on characterization results, by 107,328 square feet (or a 19% increase) from the estimated impacted Class 1 area provided in the FSSP
[NASA 2007]. Additionally, six (6) Class 2 survey units, totaling 560,421 ft2 of surface area were established as a buffer zone around the Class 1 survey units.
31
Plum Brook Reactor Facility FSSR, Rev. 0 6.0 References NASA 2007 NASA 2007a PBRF 2009 PBRF 2009a PBRF 2009b PBRF 2009c PBRF 2010 USNRC 2000 USNRC 2006 PNL 2010 USEPA 2002 NASA Safety and Mission Assurance Directorate, Final Status Survey Plan for the Plum Brook Reactor Facility, Revision 1, February 2007.
NASA Safety and Mission Assurance Directorate, Decommissioning Plan for the Plum Brook Reactor Facility, Revision 6, July 2007.
Plum Brook Reactor Facility Technical Basis Document, Radionuclide Distributions and Adjusted DCGLsfor Site Soils, PBRF-TBD-09-001, June 2009.
Plum Brook Reactor Facility Technical Basis Document, 44-10 Detector MDCscan Values for Various Survey Conditions, PBRF-TBD-09-002, June 2009.
Plum Brook Reactor Facility Technical Basis Document, An Evaluation of the 2350-1/44-10 Nal Detector Response in Water Covered Areas, PBRF-TBD 006, October 2009.
Plum Brook Reactor Facility, Memorandum to Project File, J. L. Crooks, Don Young, FSS Final Report Background Information - WEMS, Waste Effluent Monitoring Station/System (1192), December 15, 2009.
Plum Brook Reactor Facility, Memorandum to Project File, J. L. Crooks, FSS Final Report Background Information - Pentolite Ditch, February 25, 2010.
US Nuclear Regulatory Commission, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM), NUREG-1575, Rev. 1, August 2000.
US Nuclear Regulatory Commission, Consolidated Decommissioning Guidance, NUREG-1757, Vol. 1, Rev.2, September 2006.
Battelle Pacific Northwest Laboratories (PNL), Visual sample Plan, Version 5.9, 2010.
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.
NASA PBRF Decommissioning Project Environmental Media Sampling and Analysis Cumulative Report November 2000-October 2002, by the U.S. Army Corps of Engineers, Engineering Division-Environmental Branch, Louisville District, dated March 2003.
USACE 2003 32
Plum Brook Reactor Facility FSSR, Rev. 0 7.0 Appendices Appendix A - Exhibits Appendix B - Survey Unit Maps and Tables Showing Measurement Locations Appendix C -Soil Sample Results 33
Plum Brook Reactor Facility Final Status Survey Report Pentolite Ditch (Environmental Area A2300)
Revision 0 Appendix A Exhibits
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix A Rev.0, Page 2 of 25 List of Exhibits Exhibit 1, Pentolite D itch Survey U nit Breakdow n...........................................................................
3 Exhibit 2, Pentolite D itch prior to Excavation..................................................................................
4 Exhibit 3, South of Pentolite D itch....................................................................................................
5 Exhibit 4, V iew s of Pentolite D itch..................................................................................................
6 Exhibit 5, Pentolite D itch Survey....................................................................................................
7 Exhibit 6, Pentolite D itch Excavation................................................................................................
8 Exhibit 7, Pentolite D itch Excavation................................................................................................
9 Exhibit 8, Installation of Bypass Piping for Pentolite D itch......... :.................................................
10 Exhibit 9, Installation of Bypass Line for Pentolite D itch...................................................................
11 Exhibit 10, Confluence of Pentolite D itch w ith Plum Brook..........................................................
12 Exhibit 11, Pentolite D itch and Plum Brook....................................................................................
13 Exhibit 12, Excavation W ork on Pentolite D itch.............................................................................
14 Exhibit 13, Pipe Culverts.....................................................................................................................
15 Exhibit 14, W EM S Outfall...................................................................................................................
16 Exhibit 15, Excavation of W EM S O utfall......................................................................................
17 Exhibit 16, V iew s of Pentolite D itch Excavations...........................................................................
18 Exhibit 17, V iew s of Pentolite D itch Excavations...........................................................................
19 Exhibit 18, V iew s of Pentolite D itch Excavations...........................................................................
20 Exhibit 19, V iew s of Pentolite D itch Excavation...........................................................................
21 Exhibit 20, V iew s of Pentolite D itch Excavation...........................................................................
22 Exhibit 21, Pipe Culverts.....................................................................................................................
23 Exhibit 22, Stone D am.........................................................................................................................
24 Exhibit 23, Com pleted Restoration of Pentolite D itch....................................................................
25 2
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Plum Brook Reactor Facility FSSR, Attachment 4 Appendix A Rev.0, Page 4 of 25 Exhibit 2, Pentolite Ditch prior to Excavation Ppntnlitp Thitrh I nnl-ino Wpcf 4
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix A Rev.0, Page 5 of 25 Exhibit 3, South of Pentolite Ditch Survey Units South of Pentolite Ditch, looking South 5
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix A Rev.0, Page 6 of 25 Exhibit 4, Views of Pentolite Ditch Pentolite Ditch South Bank Looking East 6
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix A Rev.0, Page 7 of 25 Exhibit 5, Pentolite Ditch Survey Survey of Ditch Lultcn 3urvey 7
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix A Rev.0, Page 8 of 25 Exhibit 6, Pentolite Ditch Excavation Load-out of Soil imxcavanon 1OOKing *outn 8
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix A Rev.0, Page 9 of 25 Exhibit 7, Pentolite Ditch Excavation Pentolite Ditch Excavation looking West Excavation South ot Pentolite Ditch 9
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix A Rev.0, Page 10 of 25 Exhibit 8, Installation of Bypass Piping for Pentolite Ditch Piimnz for Rvrnn' Pinino 10
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix A Rev.0, Page 11 of 25 Exhibit 9, Installation of Bypass Line for Pentolite Ditch Tnc*tahtitnn nfrnne T in iindir Pontnl;tP Pnni,'l 11
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix A Rev.0, Page 12 of 25 Exhibit 10, Confluence of Pentolite Ditch with Plum Brook Tlrni Thnuntremn, nfPPintnlitP Tlitohf/P1,,m Rrnnk InnfhiPnPP Dam LOoicrng Noutii 12
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix A Rev.0, Page 13 of 25 Exhibit 11, Pentolite Ditch and Plum Brook Dam Looking East with Sheet Pile Installed on Pentolite Ditch 13
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix A Rev.0, Page 14 of 25 Exhibit 12, Excavation Work on Pentolite Ditch Excavation of Pentolite Ditch 14
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix A Rev.0, Page 15 of 25 Exhibit 13, Pipe Culverts Close-up of Pipe Culverts 15
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix A Rev.0, Page 16 of 25 Exhibit 14, WEMS Outfall q.ediment at WF.Mq Ontfal Izxcavation 01 Ifle wLmN 01) 16
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix A Rev.0, Page 17 of 25 Exhibit 15, Excavation of WEMS Outfall I.nPi-niit nf rpdimpnt nt WPFvIO Oiitfnhll 17
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix A Rev.0, Page 18 of 25 Exhibit 16, Views of Pentolite Ditch Excavations Deeper Excavation South of Pentolite Road 18
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix A Rev.0, Page 19 of 25 Exhibit 17, Views of Pentolite Ditch Excavations 19
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix A Rev.0, Page 20 of 25 Exhibit 18, Views of Pentolite Ditch Excavations Excavation Looking East 20
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix A Rev.0, Page 21 of 25 Exhibit 19, Views of Pentolite Ditch Excavation Load-out of Soil 21
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix A Rev.0, Page 22 of 25 Exhibit 20, Views of Pentolite Ditch Excavation U
enioille uitcn LOOKIng ftast 22
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix A Rev.0, Page 23 of 25 Exhibit 21, Pipe Culverts ltion of Sleeve inside Pipe Culvei I - -11
ý M: -
--4 23
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix A Rev.0, Page 24 of 25 Exhibit 22, Stone Dam Stone Dam East End of Pentolite Ditch 24
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix A Rev.0, Page 25 of 25 Exhibit 23, Completed Restoration of Pentolite Ditch THvdrm--,i-i-incr nf thi-Ppntnlift-T~itn h Innt-ino gPnet ILVULU-ýUJlIItV 1 I LLF 1LIILUIILL I 25
Plum Brook Reactor Facility Final Status Survey Report Pentolite Ditch (Environmental Area A2300)
Revision 0 Appendix B Survey Unit Maps and Tables Showing Measurement Locations
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 2 of 45 Index of Pentolite Ditch (OL-3) Survey Unit Maps and Tables of Coordinates Survey Unit Description Page Number Number of Pages OL-3-1 Pentolite Ditch from 101 to 105.5 4
1 OL-3-2 Pentolite Ditch Adjacent Areas - AX-101 & AY-101 5
1 OL-3-3 Pentolite Ditch Adjacent Areas - AX-102 & AY-102 6
1 OL-3-4 Pentolite Ditch Adjacent Areas - AX-103 & AY-103 7
1 OL-3-5 Pentolite Ditch Adjacent Areas - AX-104 & AY-104 8
1 OL-3-6 Pentolite Ditch Adjacent Areas - AX-105 & AY-105 9
1 OL-3-7 Pentolite Ditch Adjacent Areas - AW-104 & AW-105 10 1
OL-3-8 Pentolite Ditch from 105.5 to 109.7 11 1
OL-3-9 Pentolite Ditch Adjacent Areas - North of Ditch to Road Line 100 to 110 12 1
OL-3-10 Pentolite Ditch from 113 to 116.7 13 1
OL-3-11 Pentolite Ditch from 116.7 to 120.8 14 1
OL-3-12 Pentolite Ditch Adjacent Areas - AY-106 & AY-107 15 1
OL-3-13 Pentolite Ditch Adjacent Areas - AX-106 & AX-107 16 1
OL-3-14 Pentolite Ditch Adjacent Areas - AW-106 & AW-107 17 1
OL-3-15 Pentolite Ditch Adjacent Areas - AX-108 & AY-108 18 1
OL-3-16 Pentolite Ditch Adjacent Areas - AX-109 & AY-109 19 1
OL-3-17 Pentolite Ditch Adjacent Areas - AW-108 & AW-109 20 1
OL-3-18 Pentolite Ditch Adjacent Areas - AX-110 & AY-1 10 21 1
OL-3-19 Pentolite Ditch Adjacent Areas - AW-1 10 & AW-1 11 22 1
OL-3-20 Pentolite Ditch Adjacent Areas - AV-109 -AV-1 11 North & AW-103 23 1
NE OL-3-21 Pentolite Ditch Adjacent Areas - AX-111 & AY-1 11 24 1
OL-3-22 Pentolite Ditch Adjacent Areas - AY-112, AY-113, AY-114 25 1
OL-3-23 Pentolite Ditch Adjacent Areas - AY-1 15 through AY-1 18 26 1
OL-3-24 Pentolite Ditch from 120.8 to 124.4 27 1
OL-3-25 Pentolite Ditch from 124.4 to piling wall 28 1
OL-3-26 Pentolite Ditch Adjacent Areas - AY-119 through AY-123.8 29 1
OL-3-27 Pentolite Ditch from 100 to 101, AY-100, AX-100 North 30 1
OL-3-28 Pentolite Ditch Adjacent Areas - AY-123.8through AY-127 31 1
OL-3-29 Pentolite Ditch Adjacent Areas - AX-127, AX-128, AY-128 32 1
OL-3-30 Plumbrook from AV line to Pentolite Road culverts 33 1
OL-3-31 Pentolite Ditch Adjacent Areas - AX-125, 126, 127 west of Plumbrook 34 1
OL-3-32 Pentolite Ditch Adjacent Areas - AW-126, AV-126 west of PB ; AV-35 125, AW-125, AX-126, AX-127 east of PB OL-3-33 Pentolite Ditch Adjacent Areas - AW-125, AV-125 west of PB 36 1
OL-3-34 Pentolite Ditch from 109.7 to 113 37 1
OL-3-35 Pentolite Ditch Adjacent Areas - North of Ditch to Pentolite Road from 38 1
113 line to 117 line OL-3-36 AU-124/125/126, AV-124/126/127, AW-127/128N, AX-128/129N, 39 1
AY-129, AZ-129 South of Pentolite Road OL-3-37 AX-116 to 124, AW-124 40 1
OL-3-38 AU-108N to 112N, AV-109S to 111S, AV-112, AW-112, AX-112 to 115 41 1
OL-3-39 AW-100 to 102, AW-103SW, AV-102NE, AV-103-108 42 1
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 3 of 45 Index of Pentolite Ditch (OL-3) Survey Unit Maps and Tables of Coordinates Survey Unit Description Page Number Number of Pages OL-3-40 AW-99N, AX-99, AX-100N, AY-99, AZ-99 South of Pentolite Road, 43 1
AZ-103 to 116 North of Pentolite Road OL-3-41 AZ-1 17 to 126 North and South of Pentolite Road, AZ-127 to 129 North 44 1
of Pentolite Road OL-3-42 AY-1 17 to AY-126 North of Pentolite Ditch 45 1
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 4 of 45 Survey Unit OL-3-1 X Coord Y Coord Label Type 394 1' from south edge of ditch VSP-1 Systematic 441 1' from south edge of ditch VSP-2 Systematic 41 15' from north edge of ditch VSP-3 Systematic 88.5 17' from north edge of ditch VSP-4 Systematic 135.5 17' from north edge of ditch VSP-5 Systematic 182.5 13' from north edge of ditch VSP-6 Systematic 229.5 9' from north edge of ditch VSP-7 Systematic 276.5 10' from north edge of ditch VSP-8 Systematic 324 8' from north edge of ditch VSP-9 Systematic 371 11' from north edge of ditch VSP-10 Systematic 418 6' from north edge of ditch VSP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are from the center of the ditch excavation on the grid 101 line
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 5 of 45 Survey Unit OL-3-2 X Coord Y Coord Label Type 25 38 SP-1 Systematic 70 38 SP-2 Systematic 2
77 SP-3 Systematic 48 77 SP-4 Systematic 93 77 SP-5 Systematic 25 116 SP-6 Systematic 70 116 SP-7 Systematic 2
156 SP-8 Systematic 48 156 SP-9 Systematic 93 156 SP-10 Systematic 25 195 SP-11 Systematic
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 6 of 45 Survey Unit OL-3-3 1b~g Ara Pentlit Ditch Adacn Ara XI0 Y
I 02 X Coord Y Coord Label Type 37.0 9.5 SP-1 Systematic 82.7 9.5 SP-2 Systematic 14.2 49.0 SP-3 Systematic 59.9 49.0 SP-4 Systematic 37.0 88.5 SP-5 Systematic 82.7 88.5 SP-6 Systematic 14.2 128.1 SP-7 Systematic 59.9 128.1 SP-8 Systematic 37.0 167.6 SP-9 Systematic 9.0 1.4' from top SP-10 Systematic 2.3 0.2' from top SP-1 1 Systematic
The X coordinate for samples SP-10 and SP-1 1 are from the point shown on the map.
I
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 7 of 45 Survey Unit OL-3-4 t
I.
I 1-SPA 1
% iP 4
+
X Coord Y Coord Label Type 23 37 SP-1 Systematic 68 37 SP-2 Systematic 0.2 76 SP-3 Systematic 45 76 SP-4 Systematic 90 76 SP-5 Systematic 23 115 SP-6 Systematic 68 115 SP-7 Systematic 0.2 154 SP-8 Systematic 45 154 SP-9 Systematic 90 154 SP-10 Systematic 23 193 SP-11 Systematic
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 8 of 45 Survey Unit OL-3-5
.1.
sP-1 Area: Petlt ic-Ajcn ra A-0~4
& AY-1 4 X Coord Y Coord Label Type 32 34 SP-1 Systematic 77 34 SP-2 Systematic 9
73 SP-3 Systematic 54 73 SP-4 Systematic 99 73 SP-5 Systematic 32 112 SP-6 Systematic 77 112 SP-7 Systematic 9
150 SP-8 Systematic 54 150 SP-9 Systematic 99 150 SP-10 Systematic 32 189 SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are from grid pin AX 104.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 9 of 45 Survey Unit OL-3-6 I I I
1%Pg X Coord Y Coord Label Type 25 33 SP-1 Systematic 70 33 SP-2 Systematic 3
72 SP-3 Systematic 47 72 SP-4 Systematic 92 72 SP-5 Systematic 25 110 SP-6 Systematic 70 110 SP-7 Systematic 3
148 SP-8 Systematic 47 148 SP-9 Systematic 92 148 SP-10 Systematic 70 187 SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are from grid pin AX 105.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 10 of 45 Survey Unit OL-3-7 "SP-1I I
t 1-Ara:PntlieDitch AdaetAes-A-4&AW-1 05 X Coord Y Coord Label Type 22 3
SP-1 Systematic 74 3
SP-2 Systematic 128 3
SP-3 Systematic 179 3
SP-4 Systematic 48 49 SP-5 Systematic 100 49 SP-6 Systematic 153 49 SP-7 Systematic 22 95 SP-8 Systematic 74 95 SP-9 Systematic 128 95 SP-10 Systematic 179 95 SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are from grid pin AW 104.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 11 of 45 Survey Unit OL-3-8 SP-6 1=
SP_
It
+1I~
X Coord Y Coord Label Type 37 2' from south edge of ditch VSP-1 Systematic 85 3' from south edge of ditch VSP-2 Systematic 134 4' from south edge of ditch VSP-3 Systematic 183 4' from south edge of ditch VSP-4 Systematic 232 2' from south edge of ditch VSP-5 Systematic 13 3' from north edge of ditch VSP-6 Systematic 61 1' from north edge of ditch VSP-7 Systematic 110 2.5' from north edge of ditch VSP-8 Systematic 159 7.5' from north edge of ditch VSP-9 Systematic 208 8' from north edge of ditch VSP-10 Systematic 256 9' from north edge of ditch VSP-1 1 Systematic 305 9' from north edge of ditch VSP-12 Systematic 354 12' from north edge of ditch VSP-13 Systematic 403 12' from north edge of ditch VSP-14 Systematic The X coordinate for samples SP-1 thru SP-14 are from the center of the ditch excavation on the grid 105.5 line.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 12 of 45 Survey Unit OL-3-9 I
I I I
I I
I I
I I
SP-I SF-SP SP SF SP SP-SFPFS-SF-Il X Coord Y Coord Label Type 98
-6 SP-1 Systematic 208
-6 SP-2 Systematic 317
-6 SP-3 Systematic 426
-6 SP-4 Systematic 535
-6 SP-5 Systematic 644
-6 SP-6 Systematic 753
-6 SP-7 Systematic 862
-6 SP-8 Systematic 971
-6 SP-9 Systematic 1080
-6 SP-1 0 Systematic 1189
-6 SP-11 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are from the northwest corner of Survey Unit 3-9 where the survey unit abuts Pentolite Road.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 13 of 45 Survey Unit OL-3-1 0 115 ii~~iArea Pentolit Ditchill fro 113!!i to 16.
X Coord Y Coord Label Type 105 77' from north edge of ditch VSP-1 Systematic 34 9' from south edge of ditch VSP-2 Systematic 82 15' from south edge of ditch VSP-3 Systematic 129 31' from north edge of ditch VSP-4 Systematic 176 Centerline of ditch VSP-5 Systematic 223 Centerline of ditch VSP-6 Systematic 271 Centerline of ditch VSP-7 Systematic 318 Centerline of ditch VSP-8 Systematic 365 Centerline of ditch VSP-9 Systematic 11 8' from north edge of ditch VSP-10 Systematic 58 2' from north edge of ditch VSP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are from the center of the ditch excavation on the grid 113 line.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 14 of 45 Survey Unit OL-3-11 X Coord Y Coord Label Type 22 9.5' from south edge of ditch VSP-1 Systematic 69 12' from south edge of ditch VSP-2 Systematic 116 12' from south edge of ditch VSP-3 Systematic 163 11' from south edge of ditch VSP-4 Systematic 210 11' from south edge of ditch VSP-5 Systematic 258 11' from south edge of ditch VSP-6 Systematic 305 13' from south edge of ditch VSP-7 Systematic 352 16' from south edge of ditch VSP-8 Systematic 399 18' from south edge of ditch VSP-9 Systematic 187 1' from north edge of ditch VSP-10 Systematic 234 1' from north edge of ditch VSP-1 1 Systematic The X coordinate for samples SP-1 thru SP-1 1 are from the center of the ditch excavation on the grid 116.7 line.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 15 of 45 Survey Unit OL-3-12 X Coord Y Coord Label Type 29 26 SP-1 Systematic 72 26 SP-2 Systematic 115 26 SP-3 Systematic 159 26 SP-4 Systematic 7
63 SP-5 Systematic 50 63 SP-6 Systematic 180 63 SP-7 Systematic 107 36 SP-8 Systematic 147 36 SP-9 Systematic 85 74 SP-10 Systematic 127 74 SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are from grid pin AY 106.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 16 of 45 Survey Unit OL-3-13
~AX-1 07 Tvoe 1.0 SP-1 Svstematic 65 1.0 SP-2 Systematic 120 1.0 SP-3 Systematic 176 1.0 SP-4 Systematic 37 49 SP-5 Systematic 92 49 SP-6 Systematic 148 49 SP-7 Systematic 9
97 SP-8 Systematic 65 97 SP-9 Systematic 120 97 SP-10 Systematic 176 97 SP-11 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are from grid pin AX 106.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 17 of 45 Survey Unit OL-3-14
+
+
- 1~-
4 imr-1 A 6, 0 u
.,oUrU VFU
- Ldua, I ypI 15 0.4 SP-1 Systematic 71 0.4 SP-2 Systematic 126 0.4 SP-3 Systematic 182 0.4 SP-4 Systematic 43 48 SP-5 Systematic 98 48 SP-6 Systematic 154 48 SP-7 Systematic 15 96 SP-8 Systematic 71 96 SP-9 Systematic 126 96 SP-10 Systematic 182 96 SP-11 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are from grid pin AW 106.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 18 of 45 Survey Unit OL-3-15
- tP9
- sp
- 11, 4
I.
X Coord Y Coord Label Type 3
37 SP-1 Systematic 48 37 SP-2 Systematic 93 37 SP-3 Systematic 26 75 SP-4 Systematic 70 75 SP-5 Systematic 3
114 SP-6 Systematic 48 114 SP-7 Systematic 93 114 SP-8 Systematic 26 153 SP-9 Systematic 70 153 SP-10 Systematic 93 3' south of ditch edge SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are from grid pin AX 108, (Y co-ordinate for SP-11 is as described).
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 19 of 45 Survey Unit OL-3-16
+
iSP-I1
- ff2g 4
+
Ar. ~
~
O 3-16AY1P Me.asuremenvt Loaiosandresuts X Coord Y Coord Label Type 29 37 SP-1 Systematic 74 37 SP-2 Systematic 7
76 SP-3 Systematic 52 76 SP-4 Systematic 97 76 SP-5 Systematic 29 115 SP-6 Systematic 74 115 SP-7 Systematic 7
154 SP-8 Systematic 52 154 SP-9 Systematic 97 154 SP-10 Systematic 74 3' south of ditch edge SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are from grid pin AX 109, (Y co-ordinate for SP-1 1 is as described).
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 20 of 45 Survey Unit OL-3-17 4
X Coord Y Coord Label Type 16 5
SP-1 Systematic 69 5
SP-2 Systematic 12 5
SP-3 Systematic 174 5
SP-4 Systematic 42 50 SP-5 Systematic 95 50 SP-6 Systematic 148 50 SP-7 Systematic 16 96 SP-8 Systematic 69 96 SP-9 Systematic 121 96 SP-10 Systematic 174 96 SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-11 are from grid pin AWl08.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 21 of 45 Survey Unit OL-3-18
,AY-.110 A voora T.oora Lapel I ype 30 37 SP-1 Systematic 75 37 SP-2 Systematic 7
76 SP-3 Systematic 52 76 SP-4 Systematic 97 76 SP-5 Systematic 30 115 SP-6 Systematic 75 115 SP-7 Systematic 7
154 SP-8 Systematic 52 154 SP-9 Systematic 97 154 SP-10 Systematic 75 2' south of ditch edge SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are from grid pin AX 110.( SP 11 Y coordinate as listed).
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 22 of 45 Survey Unit OL-3-19 i
LSP-11
[SFI-X Coord Y Coord Label Type 8
2 SP-1 Systematic 63 2
SP-2 Systematic 119 2
SP-3 Systematic 174 2
SP-4 Systematic 36 50 SP-5 Systematic 91 50 SP-6 Systematic 146 50 SP-7 Systematic 8
98 SP-8 Systematic 63 98 SP-9 Systematic 119 98 SP-10 Systematic 174 98 SP-11 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are from grid pin AW 110.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 23 of 45 Survey Unit OL-3-20 sP-¶l sva twý t--3 t-v S
NE X Coord Y Coord Label Type 35' east of grid pin AW 109 36'south of grid pin AW 109 SP-1 Systematic 79' east of grid pin AW 109 36'south of grid pin AW 109 SP-2 Systematic 123' east of grid pin AW 109 36'south of grid pin AW 109 SP-3 Systematic 167' east of grid pin AW 109 36'south of grid pin AW 109 SP-4 Systematic 211' east of grid pin AW 109 36'south of grid pin AW 109 SP-5 Systematic 255' east of grid pin AW 109 36'south of grid pin AW 109 SP-6 Systematic 299' east of grid pin AW 109 36'south of grid pin AW 109 SP-7 Systematic 2' west of grid pin AX 104 96' south of grid pin AX 104 SP-8 Systematic 25' west of grid pin AX 104 55' south of grid pin AX 104 SP-9 Systematic 48' west of grid pin AX 104 18' south of grid pin AX 104 SP-10 Systematic 2' west of grid pin AX 104 18' south of grid pin AX 104 SP-1 1 Systematic a The X, Y coordinates for samples SP-1 thru SP-7 are from grid pin AW 109.
b The X, Y coordinates for samples SP-8 thru SP-1 1 are from grid pin AX 104.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 24 of 45 Survey Unit OL-3-21
-4 4
X Coord Y Coord Label Type 6
37 SP-1 Systematic 51 37 SP-2 Systematic 96 37 SP-3 Systematic 29 76 SP-4 Systematic 74 76 SP-5 Systematic 6
115 SP-6 Systematic 51 115 SP-7 Systematic 96 115 SP-8 Systematic 29 154 SP-9 Systematic 74 154 SP-1O Systematic 51 2' south of ditch edge SP-1 1 Systematic
=The X, Y coordinates tor samples SP-1 thru SP-1 1 are from grid pin AY 111 or as directed.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 25 of 45 Survey Unit OL-3-22 A tloora Lapel Type Systematic 26 SP-1 72 118 SP-2 Systematic SP-3 Systematic SP-4 Systematic 164 257 26 SP-5 Systematic 3
66 SP-6 Systematic 49 66 SP-7 Systematic 95 5' south of ditch edge SP-8 Systematic 3
146 SP-9 Systematic 49 146 SP-10 Systematic 95 146 SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are from grid pin AY 112 or as directed.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 26 of 45 Survey Unit OL-3-23 I
SP-1 Systematic 75 3
SP-2 Systematic 130 3
SP-3 Systematic 185 3
SP-4 Systematic 240 3
SP-5 Systematic 295 3
SP-6 Systematic 350 3
SP-7 Systematic 103 1' south of ditch edge SP-8 Systematic 158 2' south of ditch edge SP-9 Systematic 323 2' south of ditch edge SP-1 0 Systematic 378 2' south of ditch edge SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are from grid pin AY 115 or as directed.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 27 of 45 Survey Unit OL-3-24 125 X Coord Y Coord Label Type 173.3048 1' from south edge of ditch SP-1 Systematic 220.3414 2' from south edge of ditch SP-2 Systematic 267.3779 1' from south edge of ditch SP-3 Systematic 8.6770 16' from north edge of ditch SP-4 Systematic 55.7135 16' from north edge of ditch SP-5 Systematic 102.7500 17' from north edge of ditch SP-6 Systematic 149.7866 17' from north edge of ditch SP-7 Systematic 196.8231 18' from north edge of ditch SP-8 Systematic 243.8596 17' from north edge of ditch SP-9 Systematic 290.8962 17' from north edge of ditch SP-10 Systematic 337.9327 18' from north edge of ditch SP-1 1 Systematic The X coordinate for samples SP-1 thru SP-1 1 are from the center of the ditch excavation on the grid 120.7 line
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 28 of 45 Survey Unit OL-3-25 125 A
X Coord Y Coord Label Type 22 1' from south edge of ditch VSP-1 Systematic 67 4' from south edge of ditch VSP-2 Systematic 111 2' from south edge of ditch VSP-3 Systematic 156 1'from south edge of ditch VSP-4 Systematic 45 16' from north edge of ditch VSP-5 Systematic 89 16' from north edge of ditch VSP-6 Systematic 134 17' from north edge of ditch VSP-7 Systematic 178 15' from north edge of ditch VSP-8 Systematic 223 18' from north edge of ditch VSP-9 Systematic 267 21' from north edge of ditch VSP-10 Systematic 312 29' from north edge of ditch VSP-1 1 Systematic I [e A coOrainate Tor samples -S-PI tnru SHr-I are Trom tne center OT tne ditcn excavation on the grid 124.4 line.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 29 of 45 Survey Unit OL-3-26 X Coord Y Coord Label Type 5
25......
SP-1 Systematic 52 25 sP-2 Systematic 99 25 sP-3 Systematic 146 25 SP-4 Systematic 193 25 SP-5 Systematic 240 25 SP-6 Systematic 287 25 SP-7 Systematic 334 25 SP-8 Systematic 381 25 SP-9 Systematic 428 25 SP-10 Systematic 475 25 SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are from grid pin AY 119.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 30 of 45 Survey Unit OL-3-27 I
1 I
TVDB 27 VSP-1 Svstematic
-I10 74
-118 VSP-2 Systematic 4
-77 VSP-3 Systematic 51
-77 VSP-4 Systematic 98
-77 VSP-5 Systematic 27
-36 VSP-6 Systematic 74
-36 VSP-7 Systematic 4
5 VSP-8 Systematic 51 5
VSP-9 Systematic 98 5
VSP-10 Systematic 27 45 VSP-1 1 Systematic
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 31 of 45 Survey Unit OL-3-28 X Coord Y Coord Label Type 7
10 SP-1 Systematic 50 10 SP-2 Systematic 93 10 SP-3 Systematic 137 10 SP-4 Systematic 180 10 SP-5 Systematic 223 10 SP-6 Systematic 266 10 SP-7 Systematic 309 10 SP-8 Systematic 245 1' south of ditch edge SP-9 Systematic 288 5' south of ditch edge SP-10 Systematic 331 12' south of ditch edge SP-11 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are from grid pin AY-124 or as directed.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 32 of 45 Survey Unit OL-3-29 Area: P l
D A
c A
2 X28, AY4 28 X Coord Y Coord Label Type
-86 29 SP-1 Systematic
-42 29 SP-2 Systematic
-64 67 SP-3 Systematic
-20 67 SP-4 Systematic
-174 1' north of ditch edge SP-5 Systematic
-42 105 SP-6 Systematic
-196 143 SP-7 Systematic
-152 143 SP-8 Systematic
-108 143 SP-9 Systematic
-64 143 SP-10 Systematic
-20 143 SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are from grid pin AY-129 or as directed.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 33 of 45 Survey Unit OL-3-30 125 V 1ý A
T.
2' from west edge of brook 81-1 6' from west edge of brook 115.
8' from west edge of brook 149.
8' from west edge of brook 183.
8' from west edge of brook 217.
9' from west edge of brook 251.
5' from west edge of brook 285.
1' from west edge of brook 319.
3' from steel dam wall 387.
43' from steel dam wall 387.
33' from west edge of brook 421.
/-
4 I
01ul
, yp SP-1 Systematic 2
SP-2 Systematic 5
SP-3 Systematic 3
SP-4 Systematic 1
SP-5 Systematic 5
SP-6 Systematic 3
SP-7 Systematic 1
SP-8 Systematic 7
SP-9 Systematic 7
SP-10 Systematic I
SP-1 1 Systematic 13 The Y coordinate for samples SP-1 thru the south boundary of the survey unit 11 are from the center of the Plum Brook on
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 34 of 45 Survey Unit OL-3-31 X Coord TvDe 50 SP-1 Svstematic 105 3
SP-2 Systematic 160 3
SP-3 Systematic 23 50 SP-4 Systematic 78 50 SP-5 Systematic 133 50 SP-6 Systematic 188 50 SP-7 Systematic 50 98 SP-8 Systematic 105 98 SP-9 Systematic 160 98 SP-10 Systematic 215 98 SP-11 Systematic 2150 9
SP-11 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are from grid pin AX 125 or as directed.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 35 of 45 Survey Unit OL-3-32
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 36 of 45 Survey Unit OL-3-33 X Coord Y Coord Label Type 35 3
SP-1 Systematic 13 41 SP-2 Systematic 57 41 SP-3 Systematic 35 80 SP-4 Systematic 80 80 SP-5 Systematic 13 118 SP-6 Systematic 57 118 SP-7 Systematic 35 156 SP-8 Systematic 80 156 SP-9 Systematic 13 195 SP-10 Systematic 57 195 SP-11 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are from grid pin AV-125 or as directed.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 37 of 45 Survey Unit OL-3-34 110 0p-X Coord Y Coord Label Type 129 1' from south edge of ditch SP-1 Systematic 253 5' from south edge of ditch SP-2 Systematic 294 12' from south edge of ditch SP-3 Systematic 26 32 SP-4 Systematic 67 32 SP-5 Systematic 108 32 SP-6 Systematic 149 32 SP-7 Systematic 273 5' from north edge of ditch SP-8 Systematic 314 2' from south edge of ditch SP-9 Systematic 1' from edge above culverts 10' from south edge of ditch SP-10 Systematic 2' above culverts 8' from south edge of ditch SP-11 Systematic 2
The X coordinate for samples SP-1 thru SP-9 are from the southeast corner of survey unit at top of ditch.
b The Y coordinate for samples SP-4 thru SP-7 are from the southeast corner of survey unit at top of ditch.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 38 of 45 Survey Unit OL-3-35 Are: Pntoit Dich djaen Aras Nothof itc toPe tolieRoad fom
_____Measurement Loc~ations and results~
X Coord Y Coord Label Type 207 2
SP-1 Systematic 265 2
SP-2 Systematic 323 2
SP-3 Systematic 381 2
SP-4 Systematic 3
53 SP-5 Systematic 61 53 SP-6 Systematic 119 53 SP-7 Systematic 177 53 SP-8 Systematic 235 53 SP-9 Systematic 293 53 SP-10 Systematic 351 53 SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are from grid pin AZ-133 or as directed.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 39 of 45 Survey Unit OL-3-36 Area: AU1212/16 V12/2127, AW-12/2N XI2819,A-9 MeasureImenft Loain run1 ra jilmA X Coord Y Coord Label Type 67 74 SP-1 Systematic 172 74 SP-2 Systematic 276 74 SP-3 Systematic 15 164 SP-4 Systematic 224 164 SP-5 Systematic 329 164 SP-6 Systematic 381 255 SP-7 Systematic 485 255 SP-8 Systematic 433 345 SP-9 Systematic 590 436 SP-1 0 Systematic 538 526 SP-1 1 Systematic The X,Y coordinates for samples SP-1 thru SP-1 1 are from grid pin #AU 124
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 40 of 45 Survey Unit OL-3-37 X Coord Y Coord Label Type 863
-92 SP-1 Systematic 810
-0.5 SP-2 Systematic 18 91 SP-3 Systematic 123 91 SP-4 Systematic 229 91 SP-5 Systematic 335 91 SP-6 Systematic 441 91 SP-7 Systematic 547 91 SP-8 Systematic 653 91 SP-9 Systematic 759 91 SP-10 Systematic 865 91 SP-1 1 Systematic The X,Y coordinates for samples SP-1 thru SP-1 1 are from grid pin #AX 116.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 41 of 45 Survey Unit OL-3-38 X Coord Y Coord Label Type 60
-18 SP-1 Systematic 162
-18 SP-2 Systematic 265
-18 SP-3 Systematic 367
-18 SP-4 Systematic 470
-18 SP-5 Systematic 419 70 SP-6 Systematic 470 159 SP-7 Systematic 419 248 SP-8 Systematic 521 248 SP-9 Systematic 623 248 SP-10 Systematic 726 248 SP-1 1 Systematic The X,Y coordinates for samples SP-1 thru SP-1 1 are from grid pin #AV 108.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 42 of 45 Survey Unit OL-3-39 AX ý100 4
-I.
4
.4--
X Coord Y Coord Label Type 269
-125 SP-1 Systematic 371
-125 SP-2 Systematic 474
-125 SP-3 Systematic 576
-125 SP-4 Systematic 679
-125 SP-5 Systematic 781
-125 SP-6 Systematic 884
-125 SP-7 Systematic 13
-36 SP-8 Systematic 115
-36 SP-9 Systematic 218
-36 SP-1 0 Systematic 320
-36 SP-1 1 Systematic The X,Y coordinates for samples SP-1 thru SP-1 1 are from grid pin #AX 100
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 43 of 45 Survey Unit OL-3-40 X Coord Y Coord Label Type 159 13 SP-1 Systematic 80 150 SP-2 Systematic 77
-12 SP-3 Systematic 236
-12 SP-4 Systematic 394
-12 SP-5 Systematic 554
-12 SP-6 Systematic 712
-12 SP-7 Systematic 871
-12 SP-8 Systematic 1029
-12 SP-9 Systematic 1188
-12 SP-10 Systematic 1347
-12 SP-11 Systematic The X,Y coordinates for samples SP-1 & SP-2 are from grid pin #AX 99.
The X,Y coordinates for samples SP-3 thru SP-1 1 are from grid pin #BA 103.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 44 of 45 Survey Unit OL-3-41 SP-E~SP-7~SP-8V' V
X Coord Y Coord Label Type 4
8 SP-1 Systematic 127 8
SP-2 Systematic 250 8
SP-3 Systematic 373 8
SP-4 Systematic 496 8
SP-5 Systematic 619 8
SP-6 Systematic 742 8
SP-7 Systematic 865 8
SP-8 Systematic 988 8
SP-9 Systematic 1111 8
SP-10 Systematic 1234 8
SP-1 1 Systematic The X,Y coordinates for samples SP-1 thru SP-1 1 are from grid pin #BA1 17.
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix B Rev. 0, Page 45 of 45 Survey Unit OL-3-42
- v.
A tuoora T toora LaDel I ype 60
-1.0 SP-1 Systematic 146
-1.0 SP-2 Systematic 232
-1.0 SP-3 Systematic 318
-1.0 SP-4 Systematic 404
-1.0 SP-5 Systematic 490
-1.0 SP-6 Systematic 576
-1.0 SP-7 Systematic 662
-1.0 SP-8 Systematic 748
-1.0 SP-9 Systematic 834
-1.0 SP-10 Systematic 920
-1.0 SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are from grid pin AZ-1 17 or as directed.
Plum Brook Reactor Facility Final Status Survey Report Pentolite Ditch (Environmental Area A2300)
Revision 0 Appendix C Soil Sample Results
Plum Brook Reactor Facility FSSR, Attachment 4 Appendix C, Rev. 0, Page 2 of 20 Table of Contents Description Page Number Number of Pages Class 1 (SR-180) Soil Sample Results 3
12 Class 1 (SR-180) Soil Sample Summary 15 1
Class 2 (SR-192) Soil Sample Results 16 2
Class 2 (SR-192) Soil Sample Summary 18 1
QC Soil Sample Comparison for Class 1 and Class 2 Areas 20 2
APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 4 Appendix C, Rev. 0, Page 3 of 20 CLASS 1 (SR-180) SOIL SAMPLE RESULTS Cs-137 Co-60 Cs-137 Co-60 DCGLI.M 14.02 DCGL 3.8 MDA MDA Location Sample Log #
Sample #
Weight (g) pCi/g G
pCi/g 9
Unity Fraction Cs:Co pCi/g pCilg OL-3-1 SP-1 PB09-03337 SR-180-1 350.4
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.14E-02 1.24E-01 OL-3-1 SP-2 PB09-03339 SR-180-3 379.5
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.85E-02 1.19E-01 OL-3-1 SP-3 PB09-03340 SR-180-4 320.0
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.91E-02 1.36E-01 OL-3-1 SP-4 PB09-03342 SR-180-5 369.5 2.20E-01 9.87E-02
<MDA
<MDA 0.0157 N/A 1.27E-01 OL-3-1 SP-5 PB09-03343 SR-180-6 399.2
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 1.16E-01 1.13E-01 OL-3-1 SP-6 PB09-03344 SR-180-7 430.9
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 6.62E-02 1.01E-01 OL-3-1 SP-7 PB09-03345 SR-180-8 382.9
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.83E-02 1.23E-01 OL-3-1 SP-8 PB09-03346 SR-180-9 388.6
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.34E-02 1.12E-01 OL-3-1 SP-9 PB09-03347 SR-180-10 337.0
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.90E-02 1.39E-01 OL-3-1 SP-10 PB09-03348 SR-180-11 403.7
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.03E-02 1.12E-01 OL-3-1 SP-11 PB09-03349 SR-180-12 350.8
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.13E-02 1.24E-01 OL-3-2 SP-1 PB09-04417 SR-180-100 328.9
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 1.69E-01 1.37E-01 OL-3-2 SP-2 PB09-04418 SR-180-101 398.2 7.62E+00 6.01E-01
<MDA
<MDA 0.5435 N/A 1.09E-01 OL-3-2 SP-3 PB09-04419 SR-180-102 345.8 2.12E-01 1.O0E-01
<MDA
<MDA 0.0151 N/A 1.36E-01 OL-3-2 SP-4 PB09-04423 SR-180-104 438.8
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.20E-02 9.91E-02 OL-3-2 SP-5 PB09-04424 SR-180-105 420.3
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.14E-02 1.12E-01 OL-3-2 SP-6 PB09-04425 SR-180-106 368.9
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 9.70E-02 1.22E-01 OL-3-2 SP-7 PB09-04426 SR-180-107 422.9
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 9.OOE-02 1.03E-01 OL-3-2 SP-8 PB09-04427 SR-180-108 384.0
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 1.80E-01 1.22E-01 OL-3-2 SP-9 PB09-04428 SR-180-109 392.1
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 1.29E-01 1.15E-01 OL-3-2 SP-10 PB09-04429 SR-180-110 395.8
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.21 E-02 1.10E-01 OL-3-2 SP-11 PB09-04430 SR-180-111 361.2
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.31E-02 1.30E-01 OL-3-3 SP-1 PB09-04715 SR-180-196 351.9
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.11E-02 1.24E-01 OL-3-3 SP-2 PB09-04716 SR-180-197 323.6 2.77E-01 1.18E-01
<MDA
<MDA 0.0197 N/A 1.45E-01 OL-3-3 SP-3 PB09-04717 SR-180-198 321.0
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 1.05E-01 1.41E-01 OL-3-3 SP-4 PB09-04718 SR-180-199 388.9
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.34E-02 1.12E-01 OL-3-3 SP-5 PB09-04719 SR-180-200 380.2 2.03E-01 9.35E-02
<MDA
<MDA 0.0145 N/A 1.24E-01 OL-3-3 SP-6 PB09-04720 SR-180-201 371.6
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.64E-02 1.21E-01 OL-3-3 SP-7 PB09-04723 SR-180-203 401.5 1.83E-01 8.62E-02
<MDA
<MDA 0.0130 N/A 1.17E-01 OL-3-3 SP-8 PB09-04724 SR-180-204 334.7
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.48E-02 1.48E-01 OL-3-3 SP-9 PB09-04725 SR-180-205 359.8 5.06E-01 1.48E-01
<MDA
<MDA 0.0361 N/A 1.21E-01 OL-3-3 SP-10 PB09-04726 SR-180-206 315.7
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 9.50E-02 1.49E-01 OL-3-3 SP-11 PB09-04727 SR-180-207 389.8
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.28E-02 I1.16E-01
APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 4 Appendix C, Rev. 0, Page 4 of 20 CLASS I (SR-180) SOIL SAMPLE RESULTS Cs-137 Co-60 Cs-137 Co-60 DCGL(eM 14.02 DCGL 3.8 MDA MDA Location Sample Log #
Sample #
Weight (g) pCilg
-2 pCilg 2*
Unity Fraction Cs:Co pCi/g pCilg OL-3-4 SP-1 PB09-04444 SR-180-124 394.0
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.24E-02 1.10E-01 OL-3-4 SP-2 PB09-04445 SR-180-125 431.0
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 6.96E-02 1.09E-01 OL-3-4 SP-3 PB09-04447 SR-180-127 322.9
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 9.29E-02 1.45E-01 OL-3-4 SP-4 PB09-04448 SR-180-128 362.8
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.82E-02 1.24E-01 OL-3-4 SP-5 PB09-04449 SR-180-129 370.8
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.69E-02 1.17E-01 OL-3-4 SP-6 PB09-04450 SR-180-130 325.9 2.12E-01 1.03E-01
<MDA
<MDA 0.0151 N/A 1.44E-01 OL-3-4 SP-7 PB09-04451 SR-180-131 327.0 1.06E+00 2.46E-01
<MDA
<MDA 0.0758 N/A 1.38E-01 OL-3-4 SP-8 PB09-04452 SR-180-132 334.4
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.53E-02 1.30E-01 OL-3-4 SP-9 PB09-04453 SR-180-133 431.2 2.74E-01 1.02E-01
<MDA
<MDA 0.0195 N/A 1.09E-01 OL-3-4 SP-10 PB09-04454 SR-180-134 407.1
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 6.97E-02 1.11E-01 OL-3-4 SP-11 PB09-04455 SR-180-135 373.7
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 1.14E-01 1.16E-01 OL-3-5 SP-1 PB09-04456 SR-180-136 316.5 5.50E-01 1.65E-01
<MDA
<MDA 0.0393 N/A 1.37E-01 OL-3-5 SP-2 PB09-04457 SR-180-137 339.2 3.74E-01 1.56E-01
<MDA
<MDA 0.0267 N/A 1.38E-01 OL-3-5 SP-3 PB09-04458 SR-180-138 439.6
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 6.45E-02 1.03E-01 OL-3-5 SP-4 PB09-04459 SR-180-139 444.7
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 1.01E-01 9.78E-02 OL-3-5 SP-5 PB09-04460 SR-180-140 335.4
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.94E-02 1.40E-01 OL-3-5 SP-6 PB09-04462 SR-180-141 412.1
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 6.88E-02 1.09E-01 OL-3-5 SP-7 PB09-04463 SR-180-142 398.5
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 1.24E-01 1.09E-01 OL-3-5 SP-8 PB09-04464 SR-180-143 414.0
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.25E-02 1.13E-01 OL-3-5 SP-9 PB09-04465 SR-180-144 363.9
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.80E-02 1.24E-01 OL-3-5 SP-10 PB09-04467 SR-180-146 351.0
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.55E-02 1.34E-01 OL-3-5 SP-11 PB09-04468 SR-180-147 401.9
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.10E-02 1.08E-01 OL-3-6 SP-1 PB09-04510 SR-180-148 392.4
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.65E-02 1.20E-01 OL-3-6 SP-2 PB09-04511 SR-180-149 363.9 2.01E-01 9.51E-02
<MDA
<MDA 0.0144 N/A 1.29E-01 OL-3-6 SP-3 PB09-04512 SR-180-150 332.4 2.57E-01 1.12E-01
<MDA
<MDA 0.0183 N/A 1.41E-01 OL-3-6 SP-4 PB09-04513 SR-180-151 333.9 3.90E-01 1.38E-01
<MDA
<MDA 0.0278 N/A 1.41E-01 OL-3-6 SP-5 PB09-04514 SR-180-152 332.7 3.36E-01 1.25E-01
<MDA
<MDA 0.0239 N/A 1.36E-01 OL-3-6 SP-6 PB09-04515 SR-180-153 386.4
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 9.80E-02 1.22E-01 OL-3-6 SP-7 PB09-04517 SR-180-155 368.0 2.66E-01 1.09E-01
<MDA
<MDA 0.0189 N/A 1.28E-01 OL-3-6 SP-8 PB09-04518 SR-180-156 351.4
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.07E-02 1.28E-01 OL-3-6 SP-9 PB09-04519 SR-180-157 352.5
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.51 E-02 1.33E-01 OL-3-6 SP-10 PB09-04520 SR-180-158 363.9
<MDA
<MDA I<MDA
<MDA 0.0000 N/A 1.04E-01 6.20E-02 OL-3-6 SP-11 PB09-04522 SR-180-159 355.7
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.98E-02 1.27E-01
APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 4 Appendix C, Rev. 0, Page 5 of 20 CLASS 1 (SR-180) SOIL SAMPLE RESULTS Cs-137 Co-60 Cs-137 Co-60 DCGL(.fo 14.02 DCGL 3.8 MDA MDA Location Sample Log #
Sample #
Weight (g) pCilg pCil/g 2
Unity Fraction Cs:Co pCi/g pCi/g OL-3-7 SP-1 PB09-04728 SR-180-208 362.0 2.35E-01 1.01E-01
<MDA
<MDA 0.0168 N/A 1.20E-01 OL-3-7 SP-2 PB09-04729 SR-180-209 353.2
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.49E-02 1.33E-01 OL-3-7 SP-3 PB09-04730 SR-180-210 332.2 2.03E-01 6.88E-02
<MDA
<MDA 0.0145 N/A 6.79E-02 OL-3-7 SP-4 PB09-04732 SR-180-212 312.7 3.25E-01 1.30E-01
<MDA
<MDA 0.0232 N/A 1.50E-01 OL-3-7 SP-5 PB09-04733 SR-180-213 357.5 3.23E-01 1.18E-01
<MDA
<MDA 0.0230 N/A 1.26E-01 OL-3-7 SP-6 PB09-04734 SR-180-214 341.3 2.16E-01 9.91 E-02
<MDA
<MDA 0.0154 N/A 1.28E-01 OL-3-7 SP-7 PB09-04735 SR-180-215 350.0 1.98E-01 9.61E-02
<MDA
<MDA 0.0141 N/A 1.34E-01 OL-3-7 SP-8 PB09-04736 SR-180-216 323.9
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.76E-02 1.39E-01 OL-3-7 SP-9 PB09-04737 SR-180-217 336.7 2.76E-01 1.13E-01
<MDA
<MDA 0.0197 N/A 1.29E-01 OL-3-7 SP-10 PB09-04738 SR-180-218 317.2
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 9.46E-02 1.48E-01 OL-3-7 SP-11 PB09-04739 SR-180-219 345.1
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.22E-02 1.31E-01 OL-3-8 SP-1 PB09-03476 SR-180-13 354.0
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.48E-02 1.33E-01 OL-3-8 SP-2 PB09-03478 SR-180-15 369.5
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 1.02E-01 1.27E-01 OL-3-8 SP-3 PB09-03479 SR-180-16 381.9
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.47E-02 1.14E-01 OL-3-8 SP-4 PB09-03480 SR-180-17 342.4
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.29E-02 1.32E-01 OL-3-8 SP-5 PB09-03482 SR-180-18 344.5
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 1.27E-01 1.36E-01 OL-3-8 SP-6 PB09-03483 SR-180-19 331.3
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.61E-02 1.31E-01 OL-3-8 SP-7 PB09-03484 SR-180-20 376.3
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.54E-02 1.20E-01 OL-3-8 SP-8 PB09-03485 SR-180-21 364.1
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 1.07E-01 1.29E-01 OL-3-8 SP-9 PB09-03486 SR-180-22 388.1
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.35E-02 1.12E-01 OL-3-8 SP-10 PB09-03487 SR-180-23 348.4
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.14E-02 1.30E-01 OL-3-8 SP-11 PB09-03488 SR-180-24 354.0
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.48E-02 1.33E-01 OL-3-8 SP-12 PB09-03489 SR-180-25 352.6
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.09E-02 1.23E-01 OL-3-8 SP-13 PB09-03490 SR-180-26 389.6
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.28E-02 1.16E-01 OL-3-8 SP-14 PB09-03491 SR-180-27 407.1
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.37E-02 1.15E-01 OL-3-9 SP-1 PB09-04984 SR-180-292 341.4
<MDA
<MDA
<MDA
<MDA 0.000 N/A 1.22E-01 1.27E-01 OL-3-9 SP-2 PB09-04985 SR-180-293 396.7 1.93E-01 6.63E-02
<MDA
<MDA 0.014 N/A 3.94E-02 OL-3-9 SP-3 PB09-04987 SR-180-295 379.4
<MDA
<MDA
<MDA
<MDA 0.000 N/A 9.49E-02 1.15E-01 OL-3-9 SP-4 PB09-04988 SR-180-296 375.5
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.99E-02 1.25E-01 OL-3-9 SP-5 PB09-04989 SR-180-297 391.2
<MDA
<MDA
<MDA
<MDA 0.000 N/A 9.20E-02 1.11E-01 OL-3-9 SP-6 PB09-04990 SR-180-298 335.9
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.93E-02 1.40E-01 OL-3-9 SP-7 PB09-04991 SR-180-299 345.7
<MDA
<MDA
<MDA
<MDA 0.000 N/A 1.09E-01 1.30E-01 OL-3-9 SP-8 PB09-04992 SR-180-300 334.6
<MDA
<MDA
<MDA
<MDA 0.000 N/A 1.25E-01 1.30E-01 OL-3-9 SP-9 PB09-04993 SR-180-301 371.6
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.63E-02 1.21E-01 OL-3-9 SP-10 PB09-04994 SR-180-302 347.8
<MDA
<MDA
<MDA
<MDA 0.000 N/A 1.72E-01 1.25E-01 OL-3-9 SP-11 PB09-04995 SR-180-303 351.7 5.69E-01 1.59E-01
<MDA
<MDA 0.041 N/A 1.28E-01
APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 4 Appendix C, Rev. 0, Page 6 of 20 CLASS 1 (SR-180) SOIL SAMPLE RESULTS Cs-137 Co-60 Cs-137 Co-60 DCGL(.m 14.02 DCGL 3.8 MDA MDA Location Sample Log #
Sample #
Weight (g) pCi/g 2_
pCi/g 2/
Unity Fraction Cs:Co pCi/g pCilg OL-3-10 SP-1 PB09-03571 SR-180-28 411.9 1.58E-01 7.92E-02
<MDA
<MDA 0.0113 N/A 1.14E-01 OL-3-10 SP-2 PB09-03573 SR-180-30 372.5
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.66E-02 1.17E-01 OL-3-10 SP-3 PB09-03574 SR-180-31 338.8
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.42E-02 1.28E-01 OL-3-10 SP-4 PB09-03575 SR-180-32 338.7
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.86E-02 1.39E-01 OL-3-10 SP-5 PB09-03576 SR-180-33 402.6
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 9.20E-02 1.08E-01 OL-3-10 SP-6 PB09-03577 SR-180-34 344.3
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.71E-02 1.36E-01 OL-3-10 SP-7 PB09-03578 SR-180-35 398.1
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.13E-02 1.13E-01 OL-3-10 SP-8 PB09-03579 SR-180-36 345.5
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.26E-02 1.26E-01 OL-3-10 SP-9 PB09-03580 SR-180-37 400.1
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.50E-02 1.17E-01 OL-3-10 SP-10 PB09-03582 SR-180-38 393.2
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.63E-02 1.20E-01 OL-3-10 SP-11 PB09-03583 SR-180-39 382.9
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.41E-02 1.18E-01 OL-3-11 SP-1 PB09-03622 SR-180-40 367.8
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.76E-02 1.18E-01 OL-3-11 SP-2 PB09-03624 SR-180-42 321.0
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 9.76E-02 1.35E-01 OL-3-11 SP-3 PB09-03625 SR-180-43 364.1
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.24E-02 1.29E-01 OL-3-11 SP-4 PB09-03626 SR-180-44 356.5
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.OOE-02 1.22E-01 OL-3-11 SP-5 PB09-03627 SR-180-45 361.0
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.31E-02 1.30E-01 OL-3-11 SP-6 PB09-03628 SR-180-46 340.7
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.37E-02 1.28E-01 OL-3-11 SP-7 PB09-03629 SR-180-47 327.0
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 9.17E-02 1.44E-01 OL-3-11 SP-8 PB09-03630 SR-180-48 315.7
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 9.04E-02 1.38E-01 OL-3-11 SP-9 PB09-03631 SR-180-49 382.6
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.84E-02 1.23E-01 OL-3-11 SP-10 PB09-03632 SR-180-50 367.9
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.75E-02 1.18E-01 OL-3-11 SP-11 PB09-03633 SR-180-51 338.7
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.86E-02 1.39E-01 OL-3-12 SP-1 PB09-04652 SR-180-172 337.2
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.46E-02 1.29E-01 OL-3-12 SP-2 PB09-04653 SR-180-173 358.3 2.95E-01 1.16E-01
<MDA
<MDA 0.0211 N/A 1.38E-01 OL-3-12 SP-3 PB09-04654 SR-180-174 354.7
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.OOE-02 1.27E-01 OL-3-12 SP-4 PB09-04655 SR-180-175 387.6
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.36E-02 1.12E-01 OL-3-12 SP-5 PB09-04657 SR-180-177 412.4
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.42E-02 1.09E-01 OL-3-12 SP-6 P§09-04658 SR-180-178 362.4
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 9.32E-02 1.20E-01 OL-3-12 SP-7 PB09-04659 SR-180-179 415.0
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.23E-02 1.13E-01 OL-3-12 SP-8 PB09-04660 SR-180-180 338.4
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.38E-02 1.33E-01 OL-3-12 SP-9 PB09-04662 SR-180-181 322.3
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.85E-02 1.35E-01 OL-3-12 SP-10 PB09-04663 SR-180-182 390.5
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.68E-02 1.20E-01 OL-3-12 SP-11 PB09-04664 SR-180-183 359.3
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.90E-02 1.25E-01
APPENbIX c FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 4 Appendix C, Rev. 0, Page 7 of 20 CLASS 1 (SR-180) SOIL SAMPLE RESULTS Cs-137 Co-60 Cs-137 Co-60 DCGL(0 ff) 14.02 DCGL 3.8 MDA MDA Location Sample Log #
Sample #
Weight (g) pCi/g TO pCi/g 2
Unity Fraction Cs:Co pCilg pCilg OL-3-13 SP-1 PB09-04740 SR-180-220 368.2
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.75E-02 1.18E-01 OL-3-13 SP-2 PB09-04742 SR-180-221 351.7 6.14E-01 1.69E-01
<MDA
<MDA 0.044 N/A 1.34E-01 OL-3-13 SP-3 PB09-04743 SR-180-222 403.0
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.04E-02 1.12E-01 OL-3-13 SP-4 PB09-04744 SR-180-223 406.4
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.02E-02 1.07E-01 OL-3-13 SP-5 PB09-04746 SR-180-225 377.3
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.52E-02 1.20E-01 OL-3-13 SP-6 PB09-04747 SR-180-226 320.9 3.02E-01 1.21E-01
<MDA
<MDA 0.022 N/A 1.36E-01 OL-3-13 SP-7 PB09-04748 SR-180-227 316.3
<MDA
<MDA
<MDA
<MDA 0.000 N/A 9.49E-02 1.49E-01 OL-3-13 SP-8 PB09-04749 SR-180-228 355.1
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.99E-02 1.27E-01 OL-3-13 SP-9 PB09-04750 SR-180-229 337.1
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.46E-02 1.29E-01 OL-3-13 SP-10 PB09-04751 SR-180-230 342.6
<MDA
<MDA
<MDA
<MDA 0.000 N/A 9.61E-02 1.37E-01 OL-3-13 SP-11 PB09-04752 SR-180-231 379.0
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.49E-02 1.19E-01 OL-3-14 SP-1 PB09-04756 SR-180-232 338.5 7.85E-01 2.10E-01
<MDA
<MDA 0.056 N/A 1.28E-01 OL-3-14 SP-2 PB09-04757 SR-180-233 317.7
<MDA
<MDA
<MDA
<MDA 0.000 N/A 1.23E-01 1.48E-01 OL-3-14 SP-3 PB09-04758 SR-180-234 331.2 2.91 E-01 1.16E-01
<MDA
<MDA 0.021 N/A 1.36E-01 OL-3-14 SP-4 PB09-04759 SR-180-235 327.5 2.19E-01 7.21E-02
<MDA
<MDA 0.016 N/A 6.64E-02 OL-3-14 SP-5 PB09-04762 SR-180-237 326.3 4.25E-01 1.42E-01
<MDA
<MDA 0.030 N/A 1.38E-01 OL-3-14 SP-6 PB09-04763 SR-180-238 364.7
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.82E-02 1.19E-01 OL-3-14 SP-7 PB09-04764 SR-180-239 398.2
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.92E-02 1.18E-01 OL-3-14 SP-8 PB09-04765 SR-180-240 342.7
<MDA
<MDA
<MDA
<MDA 0.000 N/A 1.07E-01 1.32E-01 OL-3-14 SP-9 PB09-04766 SR-180-241 352.6 3.75E-01 1.48E-01
<MDA
<MDA 0.027 N/A 1.23E-01 OL-3-14 SP-10 PB09-04767 SR-180-242 330.3
<MDA
<MDA
<MDA
<MDA 0.000 N/A 2.15E-01 1.42E-01 OL-3-14 SP-11 PB09-04768 SR-180-243 375.4
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.60E-02 1.16E-01 OL-3-15 SP-1 PB09-04769 SR-180-244 356.8
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.OOE-02 1.22E-01 OL-3-15 SP-2 PB09-04770 SR-180-245 385.3
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.79E-02 1.22E-01 OL-3-15 SP-3 PB09-04772 SR-180-247 422.9
<MDA
<MDA
<MDA
<MDA 0.000 N/A 6.75E-02 1.03E-01 OL-3-15 SP-4 PB09-04773 SR-180-248 355.9
<MDA
<MDA
<MDA
<MDA 0.000 N/A 1.06E-01 1.32E-01 OL-3-15 SP-5 PB09-04774 SR-180-249 372.4
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.62E-02 1.21E-01 OL-3-15 SP-6 PB09-04775 SR-180-250 374.2
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.62E-02 1.16E-01 OL-3-15 SP-7 PB09-04776 SR-180-251 363.7
<MDA
<MDA
<MDA
<MDA 0.000 N/A 6.03E-02 6.45E-02 OL-3-15 SP-8 PB09-04777 SR-180-252 386.3
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.34E-02 1.17E-01 OL-3-15 SP-9 PB09-04778 SR-180-253 408.7
<MDA
<MDA
<MDA
<MDA 0.000 N/A 6.98E-02 1.06E-01 OL-3-15 SP-10 PB09-04779 SR-180-254 380.5
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.88E-02 1.23E-01 OL-3-15SP-11 PB09-04780 SR-180-255 347.6 1.65E+00 2.74E-01
<MDA
<MDA 0.118 N/A 1.30E-01
APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 4 Appendix C, Rev. 0, Page 8 of 20 CLASS 1 (SR-180) SOIL SAMPLE RESULTS Cs-137 Co-60 Cs-137 Co-60 DCGL(.ff) 14.02 DCGL 3.8 MDA MDA Location Sample Log #
Sample #
Weight (g) pCilg 2
pCilg 2
Unity Fraction Cs:Co pCi/g pCilg OL-3-16 SP-1 PB09-04782 SR-180-256 388.1
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.35E-02 1.12E-01 OL-3-16 SP-2 PB09-04783 SR-180-257 421.9
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.11E-02 1.11E-01 OL-3-16 SP-3 PB09-04784 SR-180-258 376.2
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.54E-02 1.20E-01 OL-3-16 SP-4 PB09-04785 SR-180-259 389.4
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.33E-02 1.12E-01 OL-3-16 SP-5 PB09-04786 SR-180-260 354.7
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.46E-02 1.32E-01 OL-3-16 SP-6 PB09-04787 SR-180-261 395.1
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.18E-02 1.14E-01 OL-3-16 SP-7 PB09-04789 SR-180-263 393.3
<MDA
<MDA
<MDA
<MDA 0.000 N/A 9.62E-02 1.19E-01 OL-3-16 SP-8 PB09-04790 SR-180-264 439.2 3.59E-01 1.13E-01
<MDA
<MDA 0.026 N/A 1.03E-01 OL-3-16 SP-9 PB09-04791 SR-180-265 395.0
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.22E-02 1.10E-01 OL-3-16 SP-10 PB09-04792 SR-180-266 376.2
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.97E-02 1.25E-01 OL-3-16 SP-11 PB09-04793 SR-180-267 372.9
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.69E-02 1.21E-01 OL-3-17 SP-1 PB09-04803 SR-180-268 391.1
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.29E-02 1.11E-01 OL-3-17 SP-2 PB09-04804 SR-180-269 369.1
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.45E-02 6.36E-02 OL-3-17 SP-3 PB09-04805 SR-180-270 342.2
<MDA
<MDA
<MDA
<MDA 0.000 N/A 1.13E-01 1.32E-01 OL-3-17 SP-4 PB09-04806 SR-180-271 376.3 2.47E-01 1.01 E-01
<MDA
<MDA 0.018 N/A 1.16E-01 OL-3-17 SP-5 PB09-04807 SR-180-272 338.8
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.85E-02 1.39E-01 OL-3-17 SP-6 PB09-04809 SR-180-274 366.3
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.79E-02 1.19E-01 OL-3-17 SP-7 PB09-04810 SR-180-275 351.2
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.54E-02 1.34E-01 OL-3-17 SP-8 PB09-04811 SR-180-276 349.7
<MDA
<MDA
<MDA
<MDA 0.000 N/A 1.08E-01 1.29E-01 OL-3-17 SP-9 PB09-04812 SR-180-277 351.5
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.12E-02 1.24E-01 OL-3-17 SP-10 PB09-04813 SR-180-278 343.5
<MDA
<MDA
<MDA
<MDA 0.000 N/A 1.82E-01 1.37E-01 OL-3-17 SP-11 PB09-04814 SR-180-279 367.9
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.71E-02 1.23E-01 OL-3-18 SP-1 PB09-04815 SR-180-280 347.7 2.12E-01 9.72E-02
<MDA
<MDA 0.015 N/A 1.25E-01 OL-3-18 SP-2 PB09-04816 SR-180-281 357.2 5.47E-01 1.59E-01
<MDA
<MDA 0.039 N/A 1.31 E-01 OL-3-18 SP-3 PB09-04817 SR-180-282 380.4
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.46E-02 1.19E-01 OL-3-18 SP-4 PB09-04818 SR-180-283 361.3
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.90E-02 1.20E-01 OL-3-18 SP-5 PB09-04819 SR-180-284 382.6
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.84E-02 1.23E-01 OL-3-18 SP-6 P509-04820 SR-180-285 363.4
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.25E-02 1.29E-01 OL-3-18 SP-7 PB09-04822 SR-180-286 371.4
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.64E-02 1.21E-01 OL-3-18 SP-8 PB09-04823 SR-180-287 375.7
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.59E-02 1.16E-01 OL-3-18 SP-9 PB09-04824 SR-180-288 339.0
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.85E-02 1.38E-01 OL-3-18 SP-10 PB09-04826 SR-180-290 374.2
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.62E-02 1.16E-01 OL-3-18SP-11 PB09-04827 SR-180-291 332.9
<MDA
<MDA
<MDA
<MDA 0.000 N/A 1.20E-01 1.41E-01
APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 4 Appendix C, Rev. 0, Page 9 of 20 CLASS 1 (SR-180) SOIL SAMPLE RESULTS Cs-137 Co-60 Cs-137 Co-60 DCGL(eff 14.02 DCGL 3.8 MDA MDA Location Sample Log #
Sample #
Weight (g) pCilg 2-pCi/g 2T*
Unity Fraction Cs:Co pCi/g pCi/g OL-3-19 SP-1 PB09-05067 SR-180-328 366.6
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.19E-02 1.28E-01 OL-3-19 SP-2 PB09-05068 SR-180-329 400.0 4.14E-01 1.27E-01
<MDA
<MDA 0.030 N/A 1.13E-01 OL-3-19 SP-3 PB09-05069 SR-180-330 335.1 2.92E-01 1.33E-01
<MDA
<MDA 0.021 N/A 1.40E-01 OL-3-19 SP-4 PB09-05070 SR-180-331 330.4 3.73E-01 1.32E-01
<MDA
<MDA 0.027 N/A 1.37E-01 OL-3-19 SP-5 PB09-05071 SR-180-332 408.6
<MDA
<MDA
<MDA
<MDA 0.000 N/A 6.98E-02 1.07E-01 OL-3-19 SP-6 PB09-05072 SR-180-333 453.1
<MDA
<MDA
<MDA
<MDA 0.000 N/A 6.62E-02 1.04E-01 OL-3-19 SP-7 PB09-05073 SR-180-334 351.7 3.83E-01 1.30E-01
<MDA
<MDA 0.027 N/A 1.28E-01 OL-3-19 SP-8 PB09-05074 SR-180-335 397.8
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.87E-02 1.09E-01 OL-3-19 SP-9 PB09-05075 SR-180-336 352.9
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.50E-02 1.33E-01 OL-3-19 SP-10 PB09-05076 SR-180-337 360.3
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.88E-02 1.25E-01 OL-3-19 SP-11 PB09-05078 SR-180-339 340.2 2.27E-01 1.05E-01
<MDA
<MDA 0.016 N/A 1.38E-01 OL-3-20 SP-1 PB09-04191 SR-180-88 332.7
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.53E-02 1.36E-01 OL-3-20 SP-2 PB09-04192 SR-180-89 315.9
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 9.50E-02 1.49E-01 OL-3-20 SP-3 PB09-04193 SR-180-90 371.6
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.68E-02 1.17E-01 OL-3-20 SP-4 PB09-04194 SR-180-91 434.2
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 6.53E-02 1.04E-01 OL-3-20 SP-5 PB09-04196 SR-180-93 384.2 6.95E-01 1.68E-01
<MDA
<MDA 0.0496 N/A 1.13E-01 OL-3-20 SP-6 PB09-04197 SR-180-94 330.6
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.58E-02 1.36E-01 OL-3-20 SP-7 PB09-04198 SR-180-95 325.7
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 9.21E-02 1.44E-01 OL-3-20 SP-8 PB09-04199 SR-180-96 384.5
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.78E-02 1.13E-01 OL-3-20 SP-9 PB09-04200 SR-180-97 332.0 4.17E-01 1.40E-01
<MDA
<MDA 0.0298 N/A 1.36E-01 OL-3-20 SP-10 PB09-04202 SR-180-98 343.9
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 2.15E-01 1.37E-01 OL-3-20 SP-1 1 PB09-04203 SR-180-99 342.2
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.34E-02 1.27E-01 OL-3-21 SP-1 PB09-05106 SR-180-364 413.6 2.71E-01 1.01E-01
<MDA
<MDA 0.019 N/A 1.05E-01 OL-3-21 SP-2 PB09-05107 SR-180-365 316.8 2.96E-01 1.24E-01
<MDA
<MDA 0.021 N/A 1.48E-01 OL-3-21 SP-3 PB09-05108 SR-180-366 323.7
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.76E-02 1.39E-01 OL-3-21 SP-4 PB09-05109 SR-180-367 416.6
<MDA
<MDA
<MDA
<MDA 0.000 N/A 6.85E-02 1.05E-01 OL-3-21 SP-5 PB09-05111 SR-180-369 356.8
<MDA
<MDA
<MDA
<MDA 0.000 N/A 2.03E-01 1.27E-01 OL-3-21 SP-6 PB09-05112 SR-180-370 385.5
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.40E-02 1.13E-01 OL-3-21 SP-7 PB09-05113 SR-180-371 368.7 2.65E-01 1.08E-01
<MDA
<MDA 0.019 N/A 1.28E-01 OL-3-21 SP-8 PB09-05114 SR-180-372 332.9 2.54E-01 1.09E-01
<MDA
<MDA 0.018 N/A 1.36E-01 OL-3-21 SP-9 PB09-05115 SR-180-373 350.1 3.32E-01 1.21E-01
<MDA
<MDA 0.024 N/A 1.24E-01 OL-3-21 SP-10 PB09-05116 SR-180-374 369.6 3.64E-01 1.27E-01
<MDA
<MDA 0.026 N/A 1.27E-01 OL-3-21 SP-11 PB09-05117 SR-180-375 349.6 6.06E-01 1.64E-01
<MDA
<MDA 0.043 N/A 1.29E-01
APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 4 Appendix C, Rev. 0, Page 10 of 20 CLASS 1 (SR-180) SOIL SAMPLE RESULTS Cs-137 Co-60 Cs-137 Co-60 DCGL(ef 14.02 DCGL 3.8 MDA MDA Location Sample Log #
Sample #
Weight (g) pCi/g 2
pCilg 2
Unity Fraction Cs:Co pCi/g pCi/g OL-3-22 SP-1 PB09-05009 SR-180-316 382.5
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.46E-02 1.14E-01 OL-3-22 SP-2 PB09-05011 SR-180-318 374.6
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.57E-02 1.20E-01 OL-3-22 SP-3 PB09-05012 SR-180-319 330.9
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.62E-02 1.31E-01 OL-3-22 SP-4 PB09-05013 SR-180-320 353.2
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.49E-02 1.33E-01 OL-3-22 SP-5 PB09-05014 SR-180-321 404.5 2.09E-01 8.94E-02
<MDA
<MDA 0.015 N/A 1.11E-01 OL-3-22 SP-6 PB09-05015 SR-180-322 364.7
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.82E-02 1.19E-01 OL-3-22 SP-7 PB09-05016 SR-180-323 369.9
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.11E-02 1.27E-01 OL-3-22 SP-8 PB09-05017 SR-180-324 362.9
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.82E-02 1.24E-01 OL-3-22 SP-9 PB09-05018 SR-180-325 371.9 6.04E-01 1.59E-01
<MDA
<MDA 0.043 N/A 1.17E-01 OL-3-22 SP-10 PB09-05019 SR-180-326 321.4 2.41E-01 1.11E-01
<MDA
<MDA 0.017 N/A 1.46E-01 OL-3-22 SP-11 PB09-05020 SR-180-327 387.2 3.28E-01 1.15E-01
<MDA
<MDA 0.023 N/A 1.16E-01 OL-3-23 SP-1 PB09-05092 SR-180-352 348.1 4.56E-01 1.43E-01
<MDA
<MDA 0.033 N/A 1.25E-01 OL-3-23 SP-2 PB09-05093 SR-180-353 359.1 3.29E-01 1.22E-01
<MDA
<MDA 0.023 N/A 1.31E-01 OL-3-23 SP-3 PB09-05094 SR-180-354 316.6
<MDA
<MDA
<MDA
<MDA 0.000 N/A 3.20E-01 1.43E-01 OL-3-23 SP-4 PB09-05095 SR-180-355 324.0
<MDA
<MDA
<MDA
<MDA 0.000 N/A 1.51E-01 1.34E-01 OL-3-23 SP-5 PB09-05097 SR-180-357 335.5 4.71 E-01 1.47E-01
<MDA
<MDA 0.034 N/A 1.35E-01 OL-3-23 SP-6 PB09-05098 SR-180-358 360.9
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.91E-02 1.21E-01 OL-3-23 SP-7 PB09-05099 SR-180-359 375.1
<MDA
<MDA
<MDA
<MDA 0.000 N/A 1.24E-01 1.25E-01 OL-3-23 SP-8 PB09-05100 SR-180-360 352.2
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.06E-02 1.28E-01 OL-3-23 SP-9 PB09-05102 SR-180-361 371.4
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.08E-02 1.27E-01 OL-3-23 SP-10 PB09-05103 SR-180-362 371.7
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.68E-02 1.17E-01 OL-3-23 SP-11 PB09-05104 SR-180-363 384.6
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.38E-02 1.17E-01 OL-3-24 SP-1 PB09-03690 SR-180-52 407.2
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.01E-02 1.07E-01 OL-3-24 SP-2 PB09-03692 SR-180-54 355.5
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.98E-02 1.27E-01 OL-3-24 SP-3 PB09-03693 SR-180-55 401.5
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 9.95E-02 1.08E-01 OL-3-24 SP-4 PB09-03694 SR-180-56 341.5
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.78E-02 1.37E-01 OL-3-24 SP-5 PB09-03695 SR-180-57 353.6
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.02E-02 1.28E-01 OL-3-24 SP-6 PB09-03696 SR-180-58 352.5
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.09E-02 1.23E-01 OL-3-24 SP-7 PB09-03697 SR-180-59 324.3
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 9.25E-02 1.45E-01 OL-3-24 SP-8 PB09-03698 SR-180-60 320.9
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.84E-02 1.41 E-01 OL-3-24 SP-9 PB09-03699 SR-180-61 320.8
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.89E-02 1.36E-01 OL-3-24 SP-10 PB09-03702 SR-180-62 341.9
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.77E-02 1.37E-01 OL-3-24 SP-11 PB09-03703 SR-180-63 381.5
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.44E-02 1.18E-01
APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 4 Appendix C, Rev. 0, Page 11 of 20 CLASS 1 (SR-180) SOIL SAMPLE RESULTS Cs-1 37 Co-60 Cs-1 37 Co-60 DCGL(.fn 14.02 DCGL 3.8 MDA MDA Location Sample Log #
Sample #
Weight (g) pCi/g 27 pCi/g 21 Unity Fraction Cs:Co pCilg pCilg OL-3-25 SP-1 PB09-03704 SR-180-64 369.8
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.71E-02 1.18E-01 OL-3-25 SP-2 PB09-03706 SR-180-66 364.4
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.79E-02 1.24E-01 OL-3-25 SP-3 PB09-03707 SR-180-67 370.5
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 1.03E-01 1.17E-01 OL-3-25 SP-4 PB09-03708 SR-180-68 331.9
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 9.04E-02 1.41 E-01 OL-3-25 SP-5 PB09-03709 SR-180-69 417.6
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 6.79E-02 1.08E-01 OL-3-25 SP-6 PB09-03710 SR-180-70 402.1
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.09E-02 1.08E-01 OL-3-25 SP-7 PB09-03711 SR-180-71 427.7
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.01E-02 1.10E-01 OL-3-25 SP-8 PB09-03712 SR-180-72 348.5
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.14E-02 1.29E-01 OL-3-25 SP-9 PB09-03713 SR-180-73 383.9
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 1.21E-01 1.13E-01 OL-3-25 SP-10 PB09-03714 SR-180-74 314.6
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 9.54E-02 1.49E-01 OL-3-25 SP-11 PB09-03715 SR-180-75 429.9
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 6.60E-02 1.05E-01 OL-3-26 SP-1 PB09-05079 SR-180-340 342.5
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.33E-02 1.27E-01 OL-3-26 SP-2 PB09-05080 SR-180-341 431.8
<MDA
<MDA
<MDA
<MDA 0.000 N/A 6.95E-02 1.09E-01 OL-3-26 SP-3 PB09-05083 SR-180-343 344.7 2.70E-01 1.10E-01
<MDA
<MDA 0.019 N/A 1.26E-01 OL-3-26 SP-4 PB09-05084 SR-180-344 335.8
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.94E-02 1.40E-01 OL-3-26 SP-5 PB09-05085 SR-180-345 395.0
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.18E-02 1.14E-01 OL-3-26 SP-6 P809-05086 SR-180-346 327.5 4.37E-01 1.44E-01
<MDA
<MDA 0.031 N/A 1.33E-01 OL-3-26 SP-7 PB09-05087 SR-180-347 348.1
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.62E-02 1.35E-01 OL-3-26 SP-8 PB09-05088 SR-180-348 342.0 7.77E-01 1.88E-01
<MDA
<MDA 0.055 N/A 1.32E-01 OL-3-26 SP-9 PB09-05089 SR-180-349 362.5 6.52E-01 1.68E-01
<MDA
<MDA 0.046 N/A 1.20E-01 OL-3-26 SP-10 PB09-05090 SR-180-350 392.5
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.64E-02 1.20E-01 OL-3-26 SP-11 PB09-05091 SR-180-351 380.9
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.45E-02 1.19E-01 OL-3-27 SP-1 PB09-03717 SR-180-76 352.0 2.89E-01 1.16E-01
<MDA
<MDA 0.0206 N/A 1.33E-01 OL-3-27 SP-2 PB09-03719 SR-180-78 347.7 2.34E-01 1.05E-01
<MDA
<MDA 0.0167 N/A 1.35E-01 OL-3-27 SP-3 PB09-03720 SR-180-79 348.1 2.34E-01 1.05E-01
<MDA
<MDA 0.0167 N/A 1.35E-01 OL-3-27 SP-4 PB09-03722 SR-180-80 341.0 2.72E-01 1.11E-01
<MDA
<MDA 0.0194 N/A 1.28E-01 OL-3-27 SP-5 PB09-03723 SR-180-81 351.1 7.24E-01 1.79E-01
<MDA
<MDA 0.0516 N/A 1.28E-01 OL-3-27 SP-6 PB09-03724 SR-180-82 325.9
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 1.35E-01 1.44E-01 OL-3-27 SP-7 PB09-03725 SR-180-83 363.4 5.11E-01 1.48E-01
<MDA
<MDA 0.0365 N/A 1.20E-01 OL-3-27 SP-8 PB09-03726 SR-180-84 331.0 2.91E-01 1.17E-01
<MDA
<MDA 0.0207 N/A 1.36E-01 OL-3-27 SP-9 PB09-03727 SR-180-85 381.7
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.86E-02 1.23E-01 OL-3-27 SP-10 PB09-03728 SR-180-86 353.8 1.13E+00 2.24E-01
<MDA
<MDA 0.0804 N/A 1.23E-01 OL-3-27 SP-11 PB09-03729 SR-180-87 392.8
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.22E-02 1.15E-01
APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 4 Appendix C, Rev. 0, Page 12 of 20 CLASS 1 (SR-180) SOIL SAMPLE RESULTS Cs-137 Co-60 Cs-137 Co-60 DCGL(e*
14.02 DCGL 3.8 MDA MDA Location Sample Log #
Sample #
Weight (g) pCi/g 2
pCilg 2<*
Unity Fraction Cs:Co pCilg pCi/g OL-3-28 SP-1 PB09-05118 SR-180-376 312.3 5.62E-01 1.85E-01
<MDA
<MDA 0.040 N/A 1.39E-01 OL-3-28 SP-2 PB09-05119 SR-180-377 362.7 7.97E-01 1.90E-01
<MDA
<MDA 0.057 N/A 1.30E-01 OL-3-28 SP-3 PB09-05120 SR-180-378 322.0 4.19E-01 1.42E-01
<MDA
<MDA 0.030 N/A 1.40E-01 OL-3-28 SP-4 PB09-05122 SR-180-379 393.0 6.60E-01 1.62E-01
<MDA
<MDA 0.047 N/A 1.11 E-01 OL-3-28 SP-5 PB09-05124 SR-180-381 385.4 4.70E-01 1.38E-01
<MDA
<MDA 0.033 N/A 1.17E-01 OL-3-28 SP-6 PB09-05125 SR-180-382 347.3 4.35E-01 1.40E-01
<MDA
<MDA 0.031 N/A 1.25E-01 OL-3-28 SP-7 PB09-05126 SR-180-383 335.6 1.27E+00 2.51E-01
<MDA
<MDA 0.091 N/A 1.40E-01 OL-3-28 SP-8 PB09-05127 SR-180-384 359.6
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.89E-02 1.26E-01 OL-3-28 SP-9 PB09-05128 SR-180-385 318.2 3.29E-01 1.27E-01
<MDA
<MDA 0.023 N/A 1.37E-01 OL-3-28 SP-10 PB09-05129 SR-180-386 373.2
<MDA
<MDA
<MDA
<MDA 0.000 N/A 1.31E-01 1.26E-01 OL-3-28 SP-11 PB09-05130 SR-180-387 350.8 2.41E-01 1.03E-01
<MDA
<MDA 0.017 N/A 1.29E-01 OL-3-29 SP-1 PB09-05170 SR-180-412 321.0 3.98E-01 1.39E-01
<MDA
<MDA 0.0284 N/A 1.35E-01 OL-3-29 SP-2 PB09-05171 SR-180-413 359.5 3.74E-01 1.30E-01
<MDA
<MDA 0.0267 N/A 1.31E-01 OL-3-29 SP-3 PB09-05172 SR-180-414 317.6
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 4.47E-02 7.10E-02 OL-3-29 SP-4 PB09-05174 SR-180-416 321.3 9.56E-01 2.68E-01
<MDA
<MDA 0.0682 N/A 1.46E-01 OL-3-29 SP-5 PB09-05175 SR-180-417 370.9
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 9.06E-02 1.22E-01 OL-3-29 SP-6 PB09-05176 SR-180-418 336.7 2.66E-01 1.14E-01
<MDA
<MDA 0.0190 N/A 1.39E-01 OL-3-29 SP-7 PB09-05177 SR-180-419 354.5 2.50E-01 1.04E-01
<MDA
<MDA 0.0178 N/A 1.27E-01 OL-3-29 SP-8 PB09-05178 SR-180-420 349.6 2.55E-01 1.06E-01
<MDA
<MDA 0.0182 N/A 1.24E-01 OL-3-29 SP-9 PB09-05179 SR-180-421 344.1
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 1.03E-01 1.36E-01 OL-3-29 SP-10 PB09-05180 SR-180-422 346.6
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.19E-02 1.30E-01 OL-3-29 SP-11 PB09-05182 SR-180-423 314.2
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 9.08E-02 1.38E-01 OL-3-30 SP-1 PB09-04665 SR-180-184 321.2 2.65E-01 1.13E-01
<MDA
<MDA 0.0189 N/A 1.35E-01 OL-3-30 SP-2 PB09-04666 SR-180-185 343.3
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 1.64E-01 1.37E-01 OL-3-30 SP-3 PB09-04667 SR-180-186 322.0
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 1.61E-01 1.40E-01 OL-3-30 SP-4 PB09-04668 SR-180-187 314.0 2.84E-01 1.19E-01
<MDA
<MDA 0.0202 N/A 1.38E-01 OL-3-30 SP-5 PB09-04669 SR-180-188 331.9
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 9.04E-02 1.41E-01 OL-3-30 SP-6 PB09-04670 SR-180-189 350.1
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.1OE-02 1.29E-01 OL-3-30 SP-7 PB09-04671 SR-180-190 329.8 3.40E-01 1.27E-01
<MDA
<MDA 0.0243 N/A 1.32E-01 OL-3-30 SP-8 PB09-04672 SR-180-191 338.1 2.31E-01 8.86E-02
<MDA
<MDA 0.0165 N/A 6.94E-02 OL-3-30 SP-9 PB09-04674 SR-180-193 342.0 3.17E-01 1.20E-01
<MDA
<MDA 0.0226 N/A 1.27E-01 OL-3-30 SP-10 PB09-04675 SR-180-194 335.7
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.94E-02 1.40E-01 OL-3-30 SP-11 PB09-04676 SR-180-195 322.6
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 2.49E-01 1.45E-01
APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 4 Appendix C, Rev. 0, Page 13 of 20 CLASS 1 (SR-180) SOIL SAMPLE RESULTS Cs-137 Co-60 Cs-137 Co-60 DCGL(effl 14.02 DCGL 3.8 MDA MDA Location Sample Log #
Sample #
Weight (g) pCi/g 2W pCi/g 2
Unity Fraction Cs:Co pCi/g pCi/g OL-3-31 SP-1 PB09-05135 SR-180-388 337.1
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.90E-02 1.39E-01 OL-3-31 SP-2 PB09-05136 SR-180-389 328.3
<MDA
<MDA
<MDA
<MDA 0.000 N/A 1.90E-01 1.37E-01 OL-3-31 SP-3 PB09-05137 SR-180-390 352.3 3.OOE-01 1.18E-01
<MDA
<MDA 0.021 N/A 1.33E-01 OL-3-31 SP-4 PB09-05138 SR-180-391 401.5 2.59E-01 9.99E-02
<MDA
<MDA 0.018 N/A 1.12E-01 OL-3-31 SP-5 PB09-05140 SR-180-393 355.1 2.06E-01 9.47E-02
<MDA
<MDA 0.015 N/A 1.27E-01 OL-3-31 SP-6 PB09-05142 SR-180-394 328.5
<MDA
<MDA
<MDA
<MDA 0.000 N/A 9.13E-02 1.43E-01 OL-3-31 SP-7 PB09-05143 SR-180-395 312.1 3.21E-01 1.26E-01
<MDA
<MDA 0.023 N/A 1.44E-01 OL-3-31 SP-8 PB09-05144 SR-180-396 360.1 3.62E-01 1.28E-01
<MDA
<MDA 0.026 N/A 1.30E-01 OL-3-31 SP-9 PB09-05145 SR-180-397 344.8 4.02E-01 1.34E-01
<MDA
<MDA 0.029 N/A 1.31E-01 OL-3-31 SP-10 PB09-05146 SR-180-398 316.6 9.39E-01 2.21E-01
<MDA
<MDA 0.067 N/A 1.48E-01 OL-3-31 SP-11 PB09-05147 SR-180-399 325.6 2.84E-01 1.16E-01
<MDA
<MDA 0.020 N/A 1.38E-01 OL-3-32 SP-1 PB09-05184 SR-180-424 318.2
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 1.32E-01 1.48E-01 OL-3-32 SP-2 PB09-05185 SR-180-425 311.6 3.34E-01 1.29E-01
<MDA
<MDA 0.0238 N/A 1.45E-01 OL-3-32 SP-3 PB09-05186 SR-180-426 344.3
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.71E-02 1.36E-01 OL-3-32 SP-4 PB09-05188 SR-180-428 321.8 3.16E-01 1.27E-01
<MDA
<MDA 0.0225 N/A 1.46E-01 OL-3-32 SP-5 PB09-05189 SR-180-429 315.4 3.42E-01 1.29E-01
<MDA
<MDA 0.0244 N/A 1.43E-01 OL-3-32 SP-6 PB09-05190 SR-180-430 316.0 2.96E-01 1.24E-01
<MDA
<MDA 0.0211 N/A 1.49E-01 OL-3-32 SP-7 PB09-05191 SR-180-431 343.7 2.58E-01 1.08E-01
<MDA
<MDA 0.0184 N/A 1.31 E-01 OL-3-32 SP-8 PB09-05192 SR-180-432 348.8 3.55E-01 1.26E-01
<MDA
<MDA 0.0253 N/A 1.25E-01 OL-3-32 SP-9 PB09-05193 SR-180-433 327.2
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 1.05E-01 1.43E-01 OL-3-32 SP-10 PB09-05194 SR-180-434 327.6 2.32E-01 1.03E-01
<MDA
<MDA 0.0165 N/A 1.38E-01 OL-3-32 SP-11 PB09-05195 SR-180-435 319.7 3.87E-01 1.37E-01
<MDA
<MDA 0.0276 N/A 1.36E-01 OL-3-33 SP-1 PB09-05152 SR-180-400 322.8
<MDA
<MDA
<MDA
<MDA 0.000 N/A 2.09E-01 1.35E-01 OL-3-33 SP-2 PB09-05153 SR-180-401 344.9 2.48E-01 1.08E-01
<MDA
<MDA 0.018 N/A 1.36E-01 OL-3-33 SP-3 PB09-05154 SR-180-402 318.1 2.30E-01 1.06E-01
<MDA
<MDA 0.016 N/A 1.42E-01 OL-3-33 SP-4 PB09-05155 SR-180-403 321.1 4.46E-01 1.47E-01
<MDA
<MDA 0.032 N/A 1.35E-01 OL-3-33 SP-5 PB09-05157 SR-180-405 319.4
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.88E-02 1.41E-01 OL-3-33 SP-6 PB09-05158 SR-180-406 322.7 3.36E-01 1.27E-01
<MDA
<MDA 0.024 N/A 1.35E-01 OL-3-33 SP-7 PB09-05159 SR-180-407 313.0 3.51E-01 1.35E-01
<MDA
<MDA 0.025 N/A 1.50E-01 OL-3-33 SP-8 PB09-05160 SR-180-408 317.6 2.07E-01 1.01E-01
<MDA
<MDA 0.015 N/A 1.37E-01 OL-3-33 SP-9 PB09-05162 SR-180-409 319.4
<MDA
<MDA
<MDA
<MDA 0.000 N/A 1.92E-01 1.41E-01 OL-3-33 SP-10 PB09-05163 SR-180-410 351.9 3.24E-01 1.23E-01
<MDA
<MDA 0.023 N/A 1.33E-01 OL-3-33SP-11 PB09-05164 SR-180-411 353.2
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.03E-02 1.28E-01
APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 4 Appendix C, Rev. 0, Page 14 of 20 CLASS I (SR-180) SOIL SAMPLE RESULTS Cs-137 Co-60 Cs-137 Co-60 DCGL(eff 14.02 DCGL 3.8 MDA MDA Location Sample Log #
Sample #
Weight (g) pCi/g 2a pCi/g 2
Unity Fraction Cs:Co pCi/g pCilg OL-3-34 SP-1 PB09-04594 SR-180-160 427.4
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 6.67E-02 1.02E-01 OL-3-34 SP-2 PB09-04595 SR-180-161 381.1
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.87E-02 1.23E-01 OL-3-34 SP-3 PB09-04596 SR-180-162 341.4
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.31 E-02 1.32E-01 OL-3-34 SP-4 PB09-04597 SR-180-163 403.5
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.07E-02 1.08E-01 OL-3-34 SP-5 PB09-04598 SR-180-164 358.6
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.37E-02 1.31E-01 OL-3-34 SP-6 PB09-04599 SR-180-165 375.0.
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.57E-02 1.20E-01 OL-3-34 SP-7 PB09-04600 SR-180-166 375.0
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.61E-02 1.16E-01 OL-3-34 SP-8 PB09-04602 SR-180-167 322.6
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 9.30E-02 1.45E-01 OL-3-34 SP-9 PB09-04603 SR-180-168 350.2
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.10E-02 1.29E-01 OL-3-34 SP-10 PB09-04604 SR-180-169 396.1
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 1.10E-01 1.10E-01 OL-3-34 SP-11 PB09-04606 SR-180-171 343.3
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.26E-02 1.31 E-01 OL-3-35 SP-1 PB09-04996 SR-180-304 353.7
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.07E-02 1.23E-01 OL-3-35 SP-2 PB09-04997 SR-180-305 332.2
<MDA
<MDA
<MDA
<MDA 0.000 N/A 1.43E-01 1.41E-01 OL-3-35 SP-3 PB09-04998 SR-180-306 323.3 2.86E-01 1.17E-01
<MDA
<MDA 0.020 N/A 1.39E-01 OL-3-35 SP-4 PB09-04999 SR-180-307 343.5 3.27E-01 1.22E-01
<MDA
<MDA 0.023 N/A 1.27E-01 OL-3-35 SP-5 PB09-05000 SR-180-309 406.8
<MDA
<MDA
<MDA
<MDA 0.000 N/A 1.16E-01 1.15E-01 OL-3-35 SP-6 PB09-05003 SR-180-310 317.7 4.75E-01 1.53E-01
<MDA
<MDA 0.034 N/A 1.37E-01 OL-3-35 SP-7 PB09-05004 SR-180-311 361.6 3.83E-01 1.32E-01
<MDA
<MDA 0.027 N/A 1.30E-01 OL-3-35 P-8 PB09-05005 SR-180-312 339.0 2.61 E-01 1.09E-01
<MDA
<MDA 0.019 N/A
_1.33E-01 OL-3-35 SP-9 PB09-05006 SR-180-313 375.1 3.61E-01 1.23E-01
<MDA
<MDA 0.026 N/A 1.16E-01 OL-3-35 SP-10 PB09-05007 SR-180-314 368.1 3.76E-01 1.29E-01
<MDA
<MDA 0.027 N/A 1.28E-01 OL-3-35 SP-11 PB09-05008 SR-180-315 348.9 3.66E-01 1.28E-01
<MDA
<MDA 0.026 N/A 1.25E-01 OL-3-42 SP-1 PB09-05291 SR-180-436 314.6
<MDA
<MDA
<MDA
<MDA 0%
N/A 9.54E-02 1.49E-01 OL-3-42 SP-2 PB09-05292 SR-180-437 337.8 2.86E-01 1.15E-01
<MDA
<MDA 2%
N/A 1.29E-01 OL-3-42 SP-3 PB09-05294 SR-180-439 366.4
<MDA
<MDA
<MDA
<MDA 0%
N/A 1.79E-01 1.19E-01 OL-3-42 SP-4 PB09-05295 SR-180-440 337.6 2.29E-01 1.05E-01
<MDA
<MDA 2%
N/A 1.39E-01 OL-3-42 SP-5 PB09-05296 SR-180-441 333.3
<MDA
<MDA
<MDA
<MDA 0%
N/A 9.OOE-02 1.41 E-01 OL-3-42 SP-6 PB09-05297 SR-180-442 330.3 2.46E-01 1.10E-01
<MDA
<MDA 2%
N/A 1.42E-01 OL-3-42 SP-7 PB09-05298 SR-180-443 405.2
<MDA
<MDA
<MDA
<MDA 0%
N/A 1.54E-01 1.07E-01 OL-3-42 SP-8 PB09-05299 SR-180-444 337.8 2.29E-01 7.45E-02
<MDA
<MDA 2%
N/A 6.95E-02 OL-3-42 SP-9 PB09-05302 SR-180-445 357.7
<MDA
<MDA
<MDA
<MDA 0%
N/A 1.14E-01 1.22E-01 OL-3-42 SP-10 PB09-05303 SR-180-446 337.5 2.52E-01 1.08E-01
<MDA
<MDA 2%
N/A 1.29E-01 OL-3-42 SP-11 PB09-05304 SR-180-447 336.6 2.30E-01I 1.06E-01I
<MDA
<MDA 2%
N/A 1 1.39E-01
APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 4 Appendix C, Rev. 0, Page 15 of 20 CLASS 1 (SR-180) SOIL SAMPLE RESULTS Cs-137 Co-60 Cs-137 Co-60 DCGL(efq 14.02 DCGL 3.8 MDA MDA Location Sample Loa #
Sample #
Weight (g) pCilg 2y pCil/g 2a Unity Fraction Cs:Co pCl~g pCilg Total Number 399 130 130 0
0 399 0
269 399 Maximum Value 453.1 7.62E+00 6.01E-01
.000E+00 0.00E+00 0.5435 0.0 3.20E-01 1.50E-01 Average Value 359.2 4.38E-01 1.32E-01 0.OOE+00 0.OOE+00 0.0107 0.0 9.19E-02 1.25E-01 Standard Deviation 30.33 6.70E-01 5.50E-02 O.OE+00 0.OOE+00 0.0314 0.0 3.17E-02 1.47E-02
.APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR; Attachment 4 Appendix C, Rev. 0, Page 16 of 20 CLASS 2 (SR-1~2~ SOIL SAMPLE RESULTS Cs-137 Co-60 Cs-137 Co-60 DCGL(.,n 14.02 DCGL 3.8 MDA MDA Location Sample Log #
Sample #
Weight (g) pCi/g 2a pCi/g 2*
% Unity Cs:Co pCilg pCi/g OL-3-36 SP-1 PB09-04829 SR-192-1 349.5 2.66E-01 1.09E-01
<MDA
<MDA 2%
N/A 1.24E-01 OL-3-36 SP-2 PB09-04830 SR-192-2 322.7 3.03E-01 1.24E-01
<MDA
<MDA 2%
N/A 1.45E-01 OL-3-36 SP-3 PB09-04831 SR-192-3 339.7
<MDA
<MDA
<MDA
<MDA 0%
N/A 8.35E-02 1.33E-01 OL-3-36 SP-4 PB09-04832 SR-192-4 357.0 2.15E-01 8.83E-02
<MDA
<MDA 2%
N/A 6.09E-02 OL-3-36 SP-5 PB09-04834 SR-192-6 326.9 3.41E-01 1.27E-01
<MDA
<MDA 2%
N/A 1.38E-01 OL-3-36 SP-6 PB09-04835 SR-192-7 340.9 1.82E-01 9.1OE-02
<MDA
<MDA 1%
N/A 1.28E-01 OL-3-36 SP-7 PB09-04836 SR-192-8 336.4
<MDA
<MDA
<MDA
<MDA 0%
N/A 1.22E-01 1.40E-01 OL-3-36 SP-8 PB09-04837 SR-192-9 365.6 2.84E-01 1.10E-01
<MDA
<MDA 2%
N/A 1.23E-01 OL-3-36 SP-9 PB09-04838 SR-192-10 337.9 3.32E-01 1.24E-01
<MDA
<MDA 2%
N/A 1.29E-01 OL-3-36 SP-10 PB09-04839 SR-192-11 340.9 3.50E-01 1.26E-01
<MDA
<MDA 2%
N/A 1.32E-01 OL-3-36 SP-11 PB09-04840 SR-192-12 319.0
<MDA
<MDA
<MDA
<MDA 0%
N/A 9.76E-02 1.41 E-01 OL-3-37 SP-1 PB09-04955 SR-192-13 354.1
<MDA
<MDA
<MDA
<MDA 0%
N/A 8.47E-02 1.33E-01 OL-3-37 SP-2 PB09-04956 SR-192-14 349.6 2.31E-01 1.01E-01
<MDA
<MDA 2%
N/A 1.29E-01 OL-3-37 SP-3 PB09-04957 SR-192-15 345.6 7.66E-01 1.91E-01
<MDA
<MDA 5%
N/A 1.36E-01 OL-3-37 SP-4 PB09-04958 SR-192-16 336.1 4.58E-01 1.45E-01
<MDA
<MDA 3%
N/A 1.34E-01 OL-3-37 SP-5 PB09-04959 SR-192-17 378.0
<MDA
<MDA
<MDA
<MDA 0%
N/A 7.94E-02 1.24E-01 OL-3-37 SP-6 PB09-04960 SR-192-18 313.7 4.42E-01 1.48E-01
<MDA
<MDA 3%
N/A 1.44E-01 OL-3-37 SP-7 PB09-04962 SR-192-19 323.8 3.35E+00 4.11E-01
<MDA
<MDA 24%
N/A 1.34E-01 OL-3-37 SP-8 PB09-04963 SR-192-20 311.7 4.31E-01 1.50E-01
<MDA
<MDA 3%
N/A 1.51E-01 OL-3-37 SP-9 PB09-04964 SR-192-21 328.2 6.80E-01 1.80E-01
<MDA
<MDA 5%
N/A 1.38E-01 OL-3-37 SP-10 PB09-04965 SR-192-22 335.2 3.OOE-01 1.43E-01
<MDA
<MDA 2%
N/A 1.30E-01 OL-3-37 SP-11 PB09-04966 SR-192-23 356.7 6.16E-01 1.69E-01
<MDA
<MDA 4%
N/A 1.32E-01 OL-3-38 SP-1 PB09-05197 SR-192-37 383.1
<MDA
<MDA
<MDA
<MDA 0%
N/A 9.40E-02 1.14E-01 OL-3-38 SP-2 PB09-05199 SR-192-39 390.3 2.86E-01 1.06E-01
<MDA
<MDA 2%
N/A 1.16E-01 OL-3-38 SP-3 PB09-05200 SR-192-40 370.8 7.20E-01 1.75E-01
<MDA
<MDA 5%
N/A 1.17E-01 OL-3-38 SP-4 PB09-05202 SR-192-41 392.0 2.28E-01 9.76E-02
<MDA
<MDA 2%
N/A 1.20E-01 OL-3-38 SP-5 PB09-05203 SR-192-42 348.6
<MDA
<MDA
<MDA
<MDA 0%
N/A 6.64E-02 6.47E-02 OL-3-38 SP-6 PB09-05204 SR-192-43 324.6
<MDA
<MDA
<MDA
<MDA 0%
N/A 1.93E-01 1.34E-01 OL-3-38 SP-7 PB09-05205 SR-192-44 406.2
<MDA
<MDA
<MDA
<MDA 0%
N/A 7.39E-02 1.16E-01 OL-3-38 SP-8 PB09-05206 SR-192-45 338.6 4.12E-01 1.38E-01
<MDA
<MDA 3%
N/A 1.28E-01 OL-3-38 SP-9 PB09-05207 SR-192-46 358.9 4.37E-01 1.56E-01
<MDA
<MDA 3%
N/A 1.31E-01 OL-3-38 SP-10 PB09-05208 SR-192-47 351.1 3.07E-01 1.16E-01
<MDA
<MDA 2%
N/A 1.28E-01 OL-3-38 SP-11 PB09-05209 SR-192-48 350.0 3.98E-01 1.33E-01
<MDA
<MDA 3%
N/A 1.24E-01
APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 4 Appendix C, Rev. 0, Page 17 of 20 CLASS 2 (SR-92) SOIL SAMPLE RESULTS Cs-137 Co-60 Cs-137 Co-60 DCGL(.f) 14.02 DCGL 3.8 MDA MDA Location Sample Log #
Sample #
Weight (g) pCilg 2_ _
pCi/g 2o
% UnitE, Cs:Co pCi/g pCi/g OL-3-39 SP-1 PB09-05210 SR-192-49 318.2 3.16E-01 1.24E-01
<MDA
<MDA 2%
N/A 1.37E-01 OL-3-39 SP-2 PB09-05211 SR-192-50 380.8 2.89E-01 1-11E-01
<MDA
<MDA 2%
N/A 1.23E-01 OL-3-39 SP-3 PB09-05213 SR-192-52 324.7
<MDA
<MDA
<MDA
<MDA 0%
N/A 2.45E-01 1.45E-01 OL-3-39 SP-4 PB09-05214 SR-192-53 311.6 3.00E-01 1.26E-01
<MDA
<MDA 2%
N/A 1.51E-01 OL-3-39 SP-5 PB09-05215 SR-192-54 316.1 2.32E-01 1.09E-01
<MDA
<MDA 2%
N/A 1.49E-01 OL-3-39 SP-6 PB09-05216 SR-192-55 365.3
<MDA
<MDA
<MDA
<MDA 0%
N/A 1.04E-01 1.23E-01 OL-3-39 SP-7 PB09-05217 SR-192-56 360.0 2.47E-01 1.03E-01
<MDA
<MDA 2%
N/A 1.21 E-01 OL-3-39 SP-8 PB09-05218 SR-192-57 329.8 2.96E-01 1.21E-01
<MDA
<MDA 2%
N/A 1.42E-01 OL-3-39 SP-9 PB09-05219 SR-192-58 352.2
<MDA
<MDA
<MDA
<MDA 0%
N/A 8.06E-02 1.28E-01 OL-3-39 SP-10 PB09-05220 SR-192-59 390.4 2.28E-01 9.53E-02
<MDA
<MDA 2%
N/A 1.11E-01 OL-3-39 SP-11 PB09-05222 SR-192-60 336.9 2.66E-01 1.14E-01
<MDA
<MDA 2%
N/A 1.39E-01 OL-3-40 SP-1 PB09-05228 SR-192-61 398.2 2.82E-01 1.05E-01
<MDA
<MDA 2%
N/A 1.09E-01 OL-3-40 SP-2 PB09-05229 SR-192-62 322.5 3.66E-01 1.36E-01
<MDA
<MDA 3%
N/A 1.46E-01 OL-3-40 SP-3 PB09-05231 SR-192-64 339.5 2.28E-01 1.05E-01
<MDA
<MDA 2%
N/A 1.38E-01 OL-3-40 SP-4 PB09-05232 SR-192-65 380.6
<MDA
<MDA
<MDA
<MDA 0%
N/A 7.45E-02 1.18E-01 OL-3-40 SP-5 PB09-05233 SR-192-66 372.4 2.62E-01 1.07E-01
<MDA
<MDA 2%
N/A 1.26E-01 OL-3-40 SP-6 PB09-05234 SR-192-67 390.8
<MDA
<MDA
<MDA
<MDA 0%
N/A 7.26E-02 1.15E-01 OL-3-40 SP-7 PB09-05235 SR-192-68 358.5 3.41E-01 1.25E-01
<MDA
<MDA 2%
N/A 1.31E-01 OL-3-40 SP-8 PB09-05236 SR-192-69 387.3
<MDA
<MDA
<MDA
<MDA 0%
N/A 7.33E-02 1.16E-01 OL-3-40 SP-9 PB09-05237 SR-192-70 435.9
<MDA
<MDA
<MDA
<MDA 0%
N/A 6.88E-02 1.08E-01 OL-3-40 SP-10 PB09-05238 SR-192-71 360.6 3.20E-01 1.17E-01
<MDA
<MDA 2%
N/A 1.25E-01 OL-3-40 SP-11 PB09-05239 SR-192-72 399.0
<MDA
<MDA
<MDA
<MDA 0%
N/A 1.10E-01 1.18E-01 OL-3-41 SP-1 PB09-04968 SR-192-25 342.9 3.95E-01 1.34E-01
<MDA
<MDA 3%
N/A 1.27E-01 OL-3-41 SP-2 PB09-04970 SR-192-27 355.1 3.25E-01 1.19E-01
<MDA
<MDA 2%
N/A 1.27E-01 OL-3-41 SP-3 PB09-04971 SR-192-28 340.6 4.32E-01 1.41E-01
<MDA
<MDA 3%
N/A 1.28E-01 OL-3-41 SP-4 PB09-04972 SR-192-29 388.3 1.89E-01 8.91E-02
<MDA
<MDA 1%
N/A 1.21E-01 OL-3-41 SP-5 PB09-04973 SR-192-30 312.8 3.08E-01 1.23E-01
<MDA
<MDA 2%
N/A 1.44E-01 OL-3-41 SP-6 PB09-04974 SR-192-31 350.5
<MDA
<MDA
<MDA
<MDA 0%
N/A 1.19E-01 1.24E-01 OL-3-41 SP-7 PB09-04975 SR-192-32 326.5 2.99E-01 1.22E-01
<MDA
<MDA 2%
N/A 1.44E-01 OL-3-41 SP-8 PB09-04976 SR-192-33 379.9 4.26E-01 1.32E-01
<MDA
<MDA 3%
N/A 1.19E-01 OL-3-41 SP-9 PB09-04977 SR-192-34 325.9
<MDA
<MDA
<MDA
<MDA 0%
N/A 1.07E-01 1.34E-01 OL-3-41 SP-10 PB09-04978 SR-192-35 333.4
<MDA
<MDA
<MDA
<MDA 0%
N/A 9.OOE-02 1.41E-01 OL-3-41 SP-11 PB09-04979 SR-192-36 356.5 2.54E-01 1.23E-01
<MDA
<MDA 2%
N/A 1.27E-01
APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 4 Appendix C, Rev. 0, Page 18 of 20 CLASS 2 (SR-192) SOIL SAMPLE RESULTS Cs-137 Co-60 Cs-137 Co-60 DCGL,.fn 14.02 DCGL 3.8 MDA MDA Location Sample Log #
Sample #
Weight (g) pCi/g 2a pCil/g 2a
% Unity Cs:Co pCilg pCilg Total Number 66 46 46 0
0 66 0
20 66 Maximum Value 435.9 3.35E+00 4.11E-01 0.00E+00 0.OOE+00 24%
0.0 2.45E-01 1.51E-01 Average Value 351.9 4.12E-01 1.31E-01 0.00E+00 0.OOE+00 2%
0.0 1.02E-01 1.28E-01 Standard Deviation 27.13 4.61E-01 4.81E-02 0.00E+00 0.OOE+00 3%
0.0 4.40E-02 1.55E-02
APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE QC COMPARISON Plum Brook Reactor Facility FSSR, Attachment 4 Appendix C, Rev. 0, Page 19 of 20 QC SOIL SAMPLE
SUMMARY
DATA Location HPGe Log #
Sample #
(g)
Cs-137 Co-60 Fraction Cs:Co Cs-137 Co-60 MDA MDA pCi/g 2a pCi/g 2a pCi/g pCi/g OL-3-1 SP-1 QC PB09-03338 SR-180-2 368.2
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.15E-02 1.27E-01 OL-3-8 SP-1 QC PB09-03477 SR-180-14 402.2
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.05E-02 1.12E-01 OL-3-10 SP-1 QC PB09-03572 SR-180-29 388.2
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.31E-02 1.16E-01 OL-3-11 SP-1 QC PB09-03623 SR-180-41 351.4
<MDA
<MDA ZMDA
<MDA 0.0000 N/A 8.54E-02 1.34E-01 OL-3-24 SP-1 QC PB09-03691 SR-180-53 391.4
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.66E-02 1.20E-01 OL-3-25 SP-1 QC PB09-03705 SR-180-65 363.5
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 1.04E-01 1.29E-01 OL-3-27 SP-1 QC PB09-03718 SR-180-77 328.1 2.42E-01 9.34E-02
<MDA
<MDA 0.0173 NfA 6.87E-02 OL-3-20 SP-4 QC PB09-04195 SR-180-92 410.4
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 7.31E-02 1.14E-01 OL-3-2 SP-3 QC PB09-04422 SR-180-103 369.3 1.37E-01 6.27E-02
<MDA
<MDA 0.0098 N/A 6.10E-02 OL-3-3 SP-6 QC PB09-04720 SR-180-201 371.6
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 4.44E-02 6.22E-02 OL-3-4 SP-2 QC PB09-04446 SR-180-126 454.7
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 6.27E-02 9.56E-02 OL-3-5 SP-9 QC PB09-04466 SR-180-145 405.8
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 1.03E-01 1.07E-01 OL-3-6 SP-6 QC PB09-04516 SR-180-154 317.1
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 2.92E-01 1.42E-01 OL-3-34 SP-10 QC PB09-04605 SR-180-170 335.5 2.43E-01 1.09E-01
<MDA
<MDA 0.0173 N/A 1.40E-01 OL-3-12 SP-4 QC PB09-04656 SR-180-176 364
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.24E-02 1.29E-01 OL-3-30 SP-8 QC PB09-04673 SR-180-192 329.9 2.01E-01 8.29E-02
<MDA
<MDA 0.0144 N/A 6.83E-02 OL-3-3 SP-6 QC PB09-04722 SR-180-202 349
<MDA
<MDA
<MDA
<MDA 0.000 N/A 4.84E-02 6.24E-02 OL-3-7 SP-3 QC PB09-04731 SR-180-211 322.7 1.98E-01 6.91 E-02
<MDA
<MDA 0.014 N/A 6.74E-02 OL-3-13 SPA-QC PB09-04745 SR-180-224 395.7
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.58E-02 1.19E-01 OL-3-14 SP-4 QC PB09-04760 SR-180-236 344.5 2.66E-01 7.96E-02
<MDA
<MDA 0.019 N/A 6.81 E-02 OL-3-15 SP-2 QC PB09-04771 SR-180-246 369.6
<MDA
<MDA
<MDA
<MDA 0.000 N/A 1.31 E-01 1.22E-01 OL-3-16 SP-6 QC PB09-04788 SR-180-262 407.7
<MDA
<MDA
<MDA
<MDA 0.000 N/A 0.06997 0.10664 OL-3-17 SP-5 QC PB09-04808 SR-180-273 341.5
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.31 E-02 1.32E-01 OL-3-18 SP-9 QC PB09-04825 SR-180-289 350.3
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.10E-02 1.29E-01 OL-3-9 SP-2 QC PB09-04986 SR-180-294 351.9 1.74E-01 5.76E-02
<MDA
<MDA 0.012 N/A 4.27E-02 OL-3-35 SP-4 QC PB09-05002 SR-180-308 317.1 2.67E-01 1.14E-01
<MDA
<MDA 0.019 N/A 1.42E-01 OL-3-22 SP-1 Q0 PB09-05010 SR-180-317 420.3
<MDA
<MDA
<MDA
<MDA 0.000 N/A 7.14E-02 1.12E-01 OL-3-19 SP-10 QC PB09-05077 SR-180-338 356.5
<MDA
<MDA
<MDA
<MDA 0.000 N/A 8.00E-02 1.22E-01 OL-3-26 SP-2 QC PB09-05082 SR-180-342 406.4
<MDA
<MDA
<MDA
<MDA 0.000 N/A 6.98E-02 1.11E-01 OL-3-23 SP-4 QC PB09-05096 SR-180-356 319.9
<MDA
<MDA
<MDA
<MDA 0.000 N/A 1.28E-01 1.47E-01 OL-3-21 SP-4 QC PB09-05110 SR-180-368 375.4
<MDA
<MDA
<MDA
<MDA 0.000 N/A 1.12E-01 1.25E-01 OL-3-28 SP-4 QC PB09-05123 SR-180-380 353.3 6.20E-01 1.80E-01
<MDA
<MDA 0.044 N/A 1.33E-01 OL-3-31 SP-4 QC PB09-05139 SR-180-392 337.3 3.02E-01 1.21E-01
<MDA
<MDA 0.022 N/A 1.39E-01 OL-3-33 SPA QC PB09-05156 SR-180-404 327.2 2.11E-01 1.03E-01
<MDA
<MDA 0.015 N/A 1.43E-01 OL-3-29 SP-3QC PB09-05173 SR-180-415 405.6
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 4.16E-02 5.36E-02 OL-3-32 SP-3QC PB09-05187 SR-180-427 339.7
<MDA
<MDA
<MDA
<MDA 0.0000 N/A 8.35E-02 1.33E-01 OL-3-42 SP-2 QC PB09-05293 SR-180-438 334 3.82E-01 1.34E-01
<MDA
<MDA 3%
N/A 1.30E-01 OL-3-36 SP-4 QC PB09-04833 SR-192-5 349.5 1.77E-01 6.04E-02
<MDA
<MDA 1%
N/A 4.48E-02 OL-3-37 SP-11 QC PB09-04967 SR-192-24 325.6 6.27E-01 1.73E-01
<MDA
<MDA 4%
N/A 1.39E-01 OL-341 SP-1 00 P809-04969 SR-192-26 340.6 3.11E-01 1.22E-01
<MDA
<MDA 2%
N/A 1.38E-01 OL-3-38 SP-1 QC P809-05198 SR-192-38 381.5
<MDA
<MDA
<MDA
<MDA 0%
N/A 7.86E-02 1.23E-01 OL-3-39 SP-2 QC PB09-05212 SR-192-51 424.1 1.52E-01 5.91E-02
<MDA
<MDA 1%
N/A 5.32E-02 OL-340 SP-2 QC PB09-05230 SR-192-63 348.3 2.65E-01 1.09E-01
<MDA
<MDA 2%
N/A 1.29E-01 Total Number 43 17 17 0
0 43 0
26 43 Maximum Value 453.1 7.62E+00 6.01E-01 0.00E+00 0.OOE+00 0.5435 1 0.0 3.20E-01 1.50E-01 Average Value 359.5 4.46E-01 1.33E-01 0.00E+00000E+0 0107 00 919-02 1.25E-01 Standard Deviation 30.33 6.67E-01 5.60E-02 0.00E+00 0I.000E+00 00314 100 3.17E-02 1.47E-02
APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE QC COMPARISON Plum Brook Reactor Facility FSSR, Attachment 4 Appendix C, Rev. 0, Page 20 of 20 QC Comoarison (FSSP Section 12.7.21 Location HPGe Log #
Sample #
Original Replicate Original 2 Resolution Ratio Pass OL-3-1 SP-1 Q0 PB09-03338 SR-180-2
<MDA
<MDA YES OL-3-8 SP-1 QC PB09-03477 SR-180-14
<MDA
<MDA YES OL-3-10 SP-1 QC PB09-03572 SR-180-29 1.58E-01 7.31 E-02 7.92E-02 4
0.5 YES OL-3-11 SP-1 QC PB09-03623 SR-180-41
<MDA
<MDA YES OL-3-24 SP-1 QC PB09-03691 SR-180-53
<MDA
<MDA YES OL-3-25 SP-A QC PB09-03705 SR-180-65
<MDA
<MDA YES OL-3-27 SP-1 QC PB09-03718 SR-180-77 2.89E-01 2.42E-01 1.16E-01 5
0.8 YES OL-3-20 SP-4 QC PB09-04195 SR-180-92
<MDA
<MDA YES OL-3-2 SP-3 0C PB09-04422 SR-180-103 2.12E-01 1.37E-01 1.O0E-01 4
0.6 YES OL-3-3 SP-6 QC PB09-04720 SR-180-201
<MDA
<MDA YES OL-3-4 SP-2 QC PB09-04446 SR-180-126
<MDA
<MDA YES OL-3-5 SP-9 QC PB09-04466 SR-180-145
<MDA
<MDA YES OL-3-6 SP-6 QC PB09-04516 SR-180-154
<MDA
<MDA YES OL-3-34 SP-10 QC PB09-04605 SR-180-170 2.43E-01 1.10E-01 1.09E-01 4
0.5 YES OL-3-12 SP-4 QC PB09-04656 SR-180-176
<MDA
<MDA YES OL-3-30 SP-8 QC PB09-04673 SR-180-192 2.31E-01 2.01E-01 8.86E-02 5
0.9 YES OL-3-3 SP-6 QC PB09-04722 SR-180-202
<MDA
<MDA YES OL-3-7 SP-3 QC PB09-04731 SR-180-211 2.03E-01 1.98E-01 6.88E-02 6
1.0 YES ce Criteria Ratio OL-3-13 SP-4 QC I PB09-04745 SR-180-224
<MDA
<MDA YES
<4 0.4 - 2.5 OL-3-14 SP-4 QC PB09-04760 SR-180-236 2.19E-01 2.66E-01 7.21E-02 6
1.2 YES 4-7 0.5-2.0 OL-3-15 SP-2 QC PB09-04771 SR-180-246
<MDA
<MDA YES 8-15 0.6-1.66 OL-3-16 SP-6 QC PB09-04788 SR-180-262
<MDA
<MDA YES t6-50 0.75A-.33 OL-3-17 SP-5 QC PB09-04808 SR-180-273
<MDA
<MDA YES51-200 0.8-1.25 OL-3-18 SP-9 QC I PB09-04825 SR-180-289 I <MDA
<MDA YES
> 200 10.85 - 1.18 OL-3-9 SP-2 QC PB09-04986 SR-180-294 1.93E-01 1.74E-01 6.63E-02 6
0.9 YES I. If bath results are < MDA, they are in agreement.es OL-3-35 SP4 QC PB09-05002 SR-180-308 3.27E-01 2.67E-01 1.22E-01 5
0.8 YES
<MDA
<MDA YES assume that th vale result is positive at the MDA and OL-3-19 SPA10 QC P0-57 SR1-38
<MDA
<MDA-YES use the MDA-value to determine the ratio.
OL-3-26 SP-2 0C I PB09-05082 SR-180-342 I <MDA
<MDA YES OL-3-23 SP-4 QC PB09-05096 SR-180-356
<MDA
<MDA YES OL-3-21 SP-4 QC PB09-05110 SR-180-368
<MDA
<MDA YES OL-3-28 SP-4 QC PB09-05123 SR-180-380 6.60E-01 6.20E-01 1.62E-01 8
0.9 YES OL-3-31 SP-4 QC PB09-05139 SR-180-392 2.59E-01 3.02E-01 9.99E-02 5
1.2 YES OL-3-33 SP-4 QC PB09-05156 SR-180-404 4.46E-01 2.11E-01 1.47E-01 6
0.5 YES OL-3-29 SP-3QC PB09-05173 SR-180A15
<MDA
<MDA YES OL-3-32 SP-3QC PB09-05187 SR-180-427
<MDA
<MDA YES OL-3-42 SP-2 QC PB09-05293 SR-180-438 2.86E-01 3.82E-01 I1.06E-01 5
1.3 YES OL-3-36 SP-4 QC PB09-04833 SR-192-5 2.15E-01 1.77E-01 8.83E-02 5
0.8 YES OL-3-37 SP-11 QC PB09-04967 SR-192-24 6.16E-01 6.27E-01 1.69E-01 7
1.0 YES OL-3-41 SP-1 QC PB09-04969 SR-192-26 3.95E-01 3.11E-01 1.34E-01 6
0.8 YES OL-3-38 SP-1 QC PB09-05198 SR-192-38
<MDA
<MDA YES OL-3-39 SP-2 QC PB09-05212 SR-192-51 2.89E-01 1.52E-01 1.11E-01 5
0.5 YES OL-3-40 SP-2 QC PB09-05230 SR-192-63 3.66E-01 2.65E-01 1.36E-01 5
0.7 YES Total Number 1 8 18 18 18 18 N/A Maximum Value 453.1 7.62E+00 6 OlE-01 0.00E+00 0.00E+00 N/A Average Value 359.5 4.46E-01 1133E-01 0.00E+00 0 O0E+00 N/A Standard Deviation 30.33 6.67E-01 I 5.60E-02 I.00E+00 I.0E+00 N/A